ML20235Q724

Forwards Overview of Sys Testing Planned to Be Performed for Restart of Facility,Including Select Sys Integrated Test Matrix,Sys Functional Test Overviews & Sys Functional Testing Abstracts,Per Discussions at 870825 Meeting

ML20235Q724
Person / Time
Site:	Rancho Seco
Issue date:	09/08/1987
From:	Andognini G SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
GCA-87-554, NUDOCS 8710070679
Download: ML20235Q724 (103)

Text

{{#Wiki_filter:- RECEIVED SACRAMENTO MUNICIPAL UTILITY OtSTRICT c3 P, O, Box 15830, Sacramento CA 95852MB80, (916) 452 3211 AN ELECTRIC SYSTEM SERVING THOEG}ONT'@F CALIFORNIA - @ '8 E R81 SEP 10 A O 3s GCA 87-554 i U. S. Nuclear Regulatory Commission Attn: J. B. Martin, Regional Administrator Region V Office of Inspection and Enforcement 1450 Maria Lane, Suite 210 Halnut Creek, CA 94596 DOCKET NO. 50-312 RANCHO SECO NUCLEAR GENERATING STATION LICENSE NO. DPR-54 SYSTEM FUNCTIONAL TESTING OVERVIEW l k

Dear Mr. Martin:

As was discussed at our August 25, 1987 meeting, please find attached, the following items for your. information: l l Select System Integrated Test Matrix System Functional Test Overviews j System Functional Testing Abstracts l These documents provide an overview of the system testing that is planned to be performed for the restart of Rancho Seco. The Select System Integrated Test Matrix provides a correlation between the integrated tests and the select systems that will have all or a portion of their functions tested by the integrated test. The System Functional Test Overviews summarize the system functions (test requirement), component testing, system integrated functional testing, and plant integrated functional. testing. Lastly, the System Functional Testing Abstracts provide a slightly'more detailed review of each of the select (System Status Report-SSR) systems which will: l 8710070679 870908 " PDR ADOCK 05000322-P PDR \\\\ f-o( l,, RANCHO SECO NUCLEAR GENERATING STATION D 14440 Twin Cities Road, Herald, CA 95638 9799;(2o9) 333-2935 E - -- _ - - j

GCA 87-554 J.B. Martin Define the system functions (from SSR). List those system functions that are affected by or affect other systems. List those functions that require verification for restart. List those functions that do not require verification for Restart with a justification. Provide a summary of the system functional tests to be performed with a a brief description of the test objectives. j If you have any questions please contact Mr. Jim Shetler of my staff at (916) 452-3211, extension 4154. Sincerely, 3 1 1% G. Car Andog ni Chief Executive Officer, Nuclear Attachment cc: F. J. Miraglia, NRR, Bethesda (w/atch) A. D'Angelo, NRC, Rancho Seco ( ) G. Kalman, NRC, Bethesda ( )

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y,. ATTAQMENT 2' HP3464B/D-0005B SYSTEM FUNCTIONAL TESTING ABSTRACT-120 VAC VITAL POWfdFSYSTEH A. SYSTEM FUNCTIONS (' The function of the 120 VAC ' vital power ' system is 'to pro' vide rated voltage and frequency under all. operating condition:s for essential power,jnstrumentationandcontrolloads. The following subfunctions require testing prior to restart to ensure'that all major functions are / verified:5 1. - Static inverters provide a regulated 120 VAC source for essential M. power, instrument and control loads. 2. Static transfer switches provide an automatic transfer from the normal.to the alternate 120 VAC supply on loss of normal source. 3. Manual Bypass Switch isolates the static inverters from the alternate power source while directing alternate power to the, loads. \\ 4. Regulating transformers provide an alternate 120 VAC source'for-- essential. power instrumentation and control loads. B. [.Ujg.70NS CO'VERED BY'OTHER SYSTEMS 1. . Testha of the abnormal operation characteristics will be provided by the Emerg:ncy Diesel Generator System tests.- C. FUNCTIONS REOUIRING VERIFICATION The following functionspf 120 VAC Vital Power System are considered' important'to the safe operation of the plant'and therefore require ( testing prior to restart: s 1. Static inverters provide a regulated 120 VAC source.for essential power, instrumentation and control loads. 2. Static transfer switches provide an automatic transfer from.the normal to the alternate source on loss of normal source. l 3. Mantpl Bypass switches isolate the static inverters from the-l- altirnate power source while directing alter'nate power to the loads. f l,' i e-gi _i_ o Odd b Cf l \\ L._ I _2___

ATTACHMENT.2 ~ e,, v, b, 4. Regulating transformers provide'an alternate 120 VAC source for essential power, instrumentation and control'.' loads.: I g O. FUNCTIONS NOT REOUIRING' VERIFICATION 1. System Component functions (C.1-4) will be tested during component testing. E.

SUMMARY

OF' SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. . Overall system operation will. be verifled during STP.961,." Loss of Offsite Power Test," and STP.1124, "120'VAC Vital and Non-Vital. / Power System Functional Test." t-e,'. '1 ; >r ,) V 4-n 4, '~ s, ,i f l \\ l 1; 1 .e '..I ' le. v'r l l i st L ~ f'- p . ~. ,f - J 3' t - { -) ~ l ,m PAGE 9 0F 18 T 3 .h

09-01-87 HP3462B i D-0151B SYSTEM FUNCTIONAL TESTING ABSTRACT 125VDC NON-VITAL POWER SYSTEM ru., s,. ) A. SYSTEM FUNCTIONS o

s. d The major function of the 125VDC Non-Vital Power System is to provide

[,y reliable DC power to equipment required for normal plant operation. The following sub-functions require testing prior'to restart to ensure that the major function of the system has been verified: E 1. Power supplied from battery chargers. 2. Power supplied from batteries. 3. Distribution protection. 4. System condition indication. B. FUNCTION COVERED BY OTHER SYSTEMS The system condition indications provided in the control room are covered by the Plant Annunciator. System and the Flant Computer System tests. C. FUNCTIONS REOUIRING VERIFICATION 1. Power supplied from battery chargers. 2. Power supplied from batteries. 3. Distribution protection. j ~ 4. System condition indication. D. FUNCTIONS NOT REOUIRING VERIFICATION i 1. None 1 ) l' AGE 10 OF 18

1 ' ATTACllMENT '2 ; I E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PECFORMED 1. STP.1127,."125 VDC Vital and Non-Vital Power System Functional Test," verifies system sub-functions C.1-4. 2.. STP.961, " Loss of Offsite Power Test," verifies operation'of the. ~ system during. loss of offsite power.- t 1 l 1 J ( \\ l \\ n .1 I i -2 i i, Or_18 c _--____.__.____-_______-__m __.-m____

l 1 ATTACHMENT 2-09-01-87' j HP34678 D-0145B SYSTEM FUNCTIONAL TESTING ABSTRACT 125VDC VITAL-POWER SYSTEM. 1 A. SYSTEM FUNCTIONS The major function.of the 125VDC Vital Power System is to. support safe plant operation and safe shutdown by.providing a continuous supply of DC power for safety-related equipment under normal and abnormal operating l conditions. The following. sub-functions require testing prior to restart' to ensure - that the major function of the system has been verified:. 1. Power supplied from battery ~ chargers. 2. Power supplied from batteries. j 3. Distribution protection. 4. System condition. indication. B. FUNCTIONS COVERED BY OTHER SYSTEMS The system condition indications provided in the Control Room are covered by the Plant Annunciator System and the Plant Computer System-Tests. C. FUNCTIONS REOUIRING VERIFICATION 1. Power supplied from battery chargers, j 2. Power. supplied from batteries. I 3. Distribution protection. i 4. System condition indication (outside of control room). D. FUNCTIONS NOT REOUIRING VERIFICATION 1. None E.

SUMMARY

OF SYSTEM FUNCTIONAL' TESTING TO'BE PERFORMED 1. STP.1127, "125 VDC Vital'and Non-Vital Power System Functional Test," verifies system subfunctions C.1-4. 2. STP 961, " Loss'of Offsite Power Test," verifies operation of the system during loss of offsite power. .., pat;F.12 OF ls

R ATTACIWENT 2' i 09/01/87 HP34498 D-00988 ) l SYSTEM FUNCTIONAL TESTING ABSTRACT l 480 VAC POWER SYSTEM i j A. SYSTEM FUNCTIONS i The two major functions of the 480 Volt system are:

1) during normal plant operation the 480 Volt system provides power to Nuclear Service and Non-Nuclear Service 480 Volt loads; and 2) during abnormal operation, the 480 Volt system provides power to Nuclear Service 480 Volt loads to promote safe plant operation.

The following sub-functions require testing prior to restart to ensure that the two major functions of the system are verified: 1. Provide control of the 480V Switchgear buses by opening and closing i cn remote, local and automatic signal commands, i 2. Provide protection for 480 Volt buses against electrical fault i and/or overload conditions. 3. Provide Control Room annunciation for overload, fault, and abnormal voltage conditions by monitoring selected 480 Volt circuit breakers. 4. Convert 4.160 Volts to 480 Volts using the station service l trans fo'rmers. 4 5. Provide isolation switches for isolating Control Room circuitry, on 3A and 3A2 Switchgear, in accordance with 10CFR50 Appendix R l requirements. B. FUNCTIONS COVERED BY OTHER SYSTEMS 1. During abnormal operation, the 480 Volt system provides power to Nuclear Service 480 Volt loads to promote safe plant operation. 2. During abnormal operation, the 480 volt system provides power to nuclear Service 480 volt loads to promote safe plant operation. a. Testing of the abnormal operation will be provided by the Emergency Diesel Generator System Testing. 3. During a fire event in the Control Room, the system provides l isolation switches on the 3A and 3A2 switchgear to promote safe shutdown of the plant. a. Testing of the isolation switch on the 4A204 circuit breaker will be done under the 4160 VAC system (See STP.978). l I W ' PMI 11r' lx . - _ - _ _ _ _ _ - _ ~

ATTACIDIEhT 2 FUNCTIONS REOUIRING VERIFICATION (Continued) C. FUNCTIONS REOUIRING VERIFICATION 1. Provide control of the 480V Switchgear buses by opening and closing 480 Volt switchgear bus supply breakers on remote, local and automatic signal commands. 2. Provide protection for 480 Volt buses against electrical fault and/or overload conditions. 3. Provide Control Room annunciation for overload, fault, and abnormal voltage conditions by monitoring' selected 480 volt circuit breakers. 4. Convert 4,160 volts to 480 Volts using the station service transformers. D. FUNCTIONS NOT REOUIRING VERIFICATION 1. None E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. Individual system subfunctions C.1-4 are tested by STP.1129, "480 VAC System Functional Test." 2. Overall system function is tested by STP.961, " Loss of Offsite Power Test." l l l l l I PAGE 14 OE 18

ATTACHMENT 2 09-01-87 HP34378 0-00048 SYSTEM FUNCTIONAL TESTING ABSTRACT 4160V AC P0HER SYSTEM A. SYSTEM FUNCTIONS The 4160V AC System provides electrical power from the 220KV switchyard to the Nuclear Service and Auxiliary 4160V AC-loads for the station. This system, in conjunction with other systems, provides the required power sources and equipment to ensure continued operation of essential l reactor and station auxiliary equipment under all conditions as specified in the design basis. The following subfunctions of the 4160V AC System require testing to maintain a reliable soorce of power to the 4160V AC vital components, promoting safe plant operation: 1. Automatic and manual control of breakers is provided for the control of electrical power on 4160V switchgear. 2. Current and voltage indications are provided at the 4160V switchgear to provide indication and alarms for operations. 3. Isolation switches are provided for isolating the Control Room circuit (y in accordance with Appendix R requirements during.an event requiring evacuation of the Control Room. Si 4. Undervoltage protective relays monitor 4160V supply to assure Technical Specifications are met. Overvoltage alarms are also provided on the Nuclear Service buses. 5. The Nuclear Service buses will unload upon loss of offsite power, the diesel Generators will supply the buses and the loads will be prioritized on the Nuclear Service buses. 6. The Nuclear Service Buses will unload upon SFAS initiation, the diesel generators will start and the loads essential for safe plant operation will be resequenced on the Nuclear Service buses. 7. During an electrical fault or overload, protective relay circuitry will trip the associated breaker on S4A, S48, S4A2, S4B2, S4El, S4E2, S4C and S40. - PAGE li OF 18

NITACINENT 2 B. FUNCTIONS COVERED BY OTHER SYSTEMS 1. None I C. FUNCTIONS REOUIRING VERIFICATION ] 1. Verify that automatic and manual control of breakers is provided for the control of electrical power on 4160V switchgear S4A, S48, S4A2, S482, S4El, S4E2, S4C and S4D. -1 2. Verify that current and voltage indications are provided at the 4160V switchgear to provide indication and alarms:for Operations on l S4A, S4B, S4A2, S482, S4El, S4E2, S4C and S40. 3. Verify that isolation switches are provided for isolating the Control Room circuitry in accordance with Appendix R requirements i during an event requiring evacuation'of the Control Room on S4A and S4A2. 4. Verify that undervoltage protective relays monitor 4160V supply to assure Technical Specifications are met. Overvoltage alarms are also provided on S4A, S48, S4A2, S4B2. 5. Verify that the Nuclear Service Buses will unload upon loss of offsite power. The Diesel Generators will supply the buses and the loads will be prioritized on S4A, S48, S4A2 and S482. 6. Verify khat the Nuclear Service Buses will unload upon SFAS initiation. The diesel generators will start and the loads j essential for safe plant operation will be resequenced'on S4A, S48, S4A2 and S482. 7. Verify that during an electrical fault or overload, protective relay circuitry trips the associated breaker on S4A, S48, S4A2, S482, S4El, S4E2, S4C and S40. ] D. FUNCTIONS NOT REOUIRING VERIFICATION 1. None E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. System functions C.1-4 and C.7 are tested in STP.ll26, "4160 VAC System Functional Test," which verifies operation of system 1 controls, logic and component functions. ) 2. System functions C.5 and C.6 will be tested by STP.961, " Loss of Offsite Power Test." i 4 PAGE 16 M 18 i

o' ATTACINENT 2 09/01/87 WP34488 D-00978 SYSTEM FUNCTIONAL TESTING ABSTRACT 6900 VAC SYSTEM

.A. SYSTEM FUNCTIONS The 6900 VAC system is designed for the four. (4) each 10,000. horsepower' Reactor Coolant ' Pump (RCP) motors. This system is arranged-into two bus sections, each feeding two RCP motors. The following subfunctions require testing prior to restart to ensure that the two major functions of the system are verified. 1. .The current and potential transformers provide signals to the l metering and relaying circuits. 2. Four breakers provide control of.the reactor coolant pumps by. opening and closing on demand and four breakers provide' control of l the normal and alternate bus feeds. The 6900 VAC busses provide reliable power to the reactor coolanft 3. pumps. 4. The system provides for bus protection.on overcurrent and bus different(alaswellasrapid'transfertothealternatebusfeedon bus undervoltage. 1 i B. FUNCTIONS COVERED BY OTHER SYSTEMS The 6900 VAC system boundary for each interfacing system is defined as follows: 1. 4160 VAC system The system boundary is the AUX Transformer #1 side of the 6.9kv breakers feeding buses 6A and 68. Testing of the breakers and. associated control circuits are included. The transformer and associated bus work is covered by the 4160 VAC system testing. 2. Main Generator System The system boundary is the AUX Transformer #1-side of the 6.9kv i breakers feeding buses 6A and 68. Testing of the breakers and associated control circuits'are included. The transformer and associated bus work is covered by the Main Generator System (MGS) testing. _1 PAGl; 17 OF 18

I I ATTACHMENT 2-- -i I l l 3. Reactor Coolant: System The system boundary.is the load side of each 6900 VAC breaker. Testing of the breakers is included. -Testing of the breaker ~ 3 control circuits is covered by the Reactor Coolant System (RCS) testing. 3-C. FUNCTIONS REQUIRING VERIFICATION j l 1. The. potential and current transformers provide signals to the metering.and relaying circuits. 2. -Four breakers provide control.of the reactor coolant pumps.by. 3 opening and closing.on demand and four~ breakers-provide control of 1 the normal and alternate bus feeds. l 3. The bus. provides reliable power to the reactor coolant. pumps. ~ The l system provides for bus protection on overcurrent and bus dif ferential as well as rapid transfer to the alternate bus feed on= bus undervoltage. D. FUNCTIONS NOT REQUIRING VERIFICATION l 1. None \\ s 1 E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED l 1. The system rapid transfer function will be tested by RT-E05-009, "6900 VAC Rapid Transfer Test," which will be performed in the cold shutdown condition. 2. STP.ll28, "6900 VAC System' Functional. Test," verifies overall system functional performance. i i 1 u <1 PAGE 18 0F 18 ) i i

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ATTACHMENT 3' 08-31-87 WP3465B D-01S1B SYSTEM FUNCTIONAL TESTING ABSTRACT- . AUXILIARY FEE 0 WATER SYSTEM-l A. SYSTEM FUNCTIONS 1. The Auxiliary Feedwater System supplies an auxiliary' source of I cooling water to the steam generators sufficient to remove core-decay heat 'af ter a reactor trip. j 2. Provide an alternate source of makeup water to the NSCW Surge Tanks. 3. Provide an alternate source of water f rom the. site. reservoir. i 4. Allow pump testing via the AFW test line. l S. Limit AFW to OTSG~ flow to below'the 0TSG nozzle' flow limit. ] 6. Provide automatic initiation of'AFW to OTSG fill upon an EFIC initiation. 7. Provide flow initiation to the OTSGs within design response time. \\ 8. Provide flow to the OTSGs during a loss of off-site power. c] 'B. FUNCTIONS COVERED BY OTHER SYSTEMS 1. Automatic EFIC initiation ~will:be performed'in the EFIC test ~ p rog ram. ,'i 2. AFW control logic testing will be performed in the EFIC test ] program. l C. FUNCTIONS REQUIRING VERIFICATION-i ~ 1. Required flow to the OTSGs.using motor operation with the OTSGs at atmospheric pressure and.using motor and turbine operation with the OTSGs at operating pressure. 2. ~ Makeup to the NSCW system from'AFW. 3. Capability of the site reservoir suction source piping and valves j l to provide adequate NPSH requirements for the AFW pumps. PA(;E 7 OF 15 C

ATTACHMENT 3 4. Capability of the AFW test line to provide flow indication for AFW pump testing with the condenser at atmospheric pressure. i 5. The AFW flow limiters limit flow with the OTSGs at atmospheric pressure and at normal operating pressure. D. FUNCTIONS NOT REQUIRING VERIFICATION 1. None E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. Functions A.2-8 will be verified during component testing. l 2. STP.1105, "AFW Cold Functional Test", will verify overall system performance prior to plant heatup. 3. AFW system operations during heatup and reactor operations will be tested as part of system integrated tests. \\ s 1 1 [ , PAGE 8 0F 15 L

ATTACHMENT 3 .0 RAFT DATE I 09-01-87 i WP3459B D-0164 B ' . SYSTEM FUNCTIONAL TESTING ABSTRACT' AUXILIARY STEAM SYSTEM A. ' SYSTEM FUNCTIONS 1. Provide saturated steam ~ at 250. psig by use of two. auxiliary boilers ' -f and/or main steam through a pressure reducing station. 2. Transport steam to loads to support -required. plant operations. 3. Control the flow'of condensate to meet system operating requirements. i l 4. Store and supply sufficient fu'el oil to support. auxiliary boiler operations. B. FUNCTIONS COVERED BY OTHER SYSTEMS 1. None C. FUNCTIONS REQUIRING VERIFICAT10'N 1. Provide saturated steam at 250 psig by use of'the auxiliary boiler and by main steam. 2. Transport steam'to loads to support required plant operations. 3. Control the flow of condensate to meet system operating requirements. 4. Store and supply sufficient fuel oil to support auxiliary boiler operations. 1 0. FUNCTIONS NOT REQUIRING VERIFICATION 1. None E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1, Functions A.1-4 will be individually tested during component testing. i i 2. STP.1103, " Auxiliary Steam System Functional" Test," will verifyi l system logic, controls and interlocks and normal and off-normal-operation. I ; PAGE 9 OF 15 l

ATTACINENT 3. 1 HP34828/D-0060B SYSTEM FUNCTIONAL TESTING ABSTRACT MAIN FEEDHATER SYSTEM A. SYSTEM FUNCTIONS 1. Provides feedwater flow to each steam generator following a reactor trip for other than a loss of both main feed pumps. 2. Provides feedwater flow to each steam generator to prevent a ' reactor trip at less.than 207. reacto power following a turbine- . trip. l 3. Provides feedwater flow to each steam generator to prevent a reactor trip following a loss 'of a single main feed pump. l 4. Provides feedwater flow to each steam generator in the event of a 3 feedwater heater or feedwater heater train malfunction. ) l l l l 5. Isolates main feedwater from.a steam generator affected by either a' postulated main steam line failure or high steam generator water wheel. j .y 6. Provides inputs to ARTS, NNI, and the Control Room for indication and feedwater control. \\ 7. Provides preheated feedwater to eat.h steam generator.during startup, normal and shutdown modes of operation. i 8. Provides feedwater flow of 6.12 X 106 lbm/hr to each steam generator. 9. Controls feedwater pressure to each steam generator. B. FUNCTIONS COVERED BY OTHER SYSTEMS 1. The ability to provide feedwater flow to each steam generator following a turbine trip will be verified by performing STP.210.05 " Turbine Mechanical Overspeed Trip Surveillance Test" during HPT system functional testing (function 2). 2. STP.660 "ICS Tuning" will be performed during ICS system functional . testing and will aid in verifying functions 2 and 3. 3. The capability of isolating the MFH syster from a steam generator will be demonstrated in STP.666 "EFIC Cold Functional Test" during EFIC system functional testing as well as in Item E.I. (function 5) -l' AGE 10 i 15

ATTACllMENT 3 FUNCTIONS COVERED BY OTHER SYSTEMS (Continued) 4. Providing inputs to ARTS, NNI and the Control. Room will be verified by performing I.111 and SP.200.14 during RPS and NNI system functional testing respectively '(function 6). 5. Verification that feedwater can be supplied to each steam generator at rated flowrate will be demonstrated utilizing I.011 during NNI System functional testing (function 8). C. FUNCTIONS REOUIRING VERIFICATION 1. Verify that the system: Provides feedwater flow to each s' team generator following a a. reactor trip for other than a loss of both main feed pumps. b. Provides feedwater flow to each steam generator to prevent a reactor trip following a loss of a single main feed pump. c. Provides feedwater flow to each steam generator in the event of a feedwater heater of feedwater heater train malfunction. d. Isolates main feedwater from a steam generator affected by a postulated main steam line failure or high steam generator wa,ter level. e. Provides preheated feedwater to each steam generator during L. startup, normal, and shutdown modes of operation. f. Controls feedwater pressure to each steam generator. I D. FUNCTIONS NOT REQUIRING VERIFICATION 1. None l l E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED l 1. Individual system functions (A.1,.4,.7,.9) will be tested during component testing. 2. STP.1097 "Feedwater System Cold Functional Testing." 3. STP.1098 "Feedwater System Hot Functional Testing." a 'I I J PAE 11 OF 1 'i l l L-_____-.____

1 ATTACHMENT 3 { i 1 WP3463B/0-00058 SYSTEM FUNCTIONAL TESTING ABSTRACT l MAIN STEAM SYSTEM A. SYSTEM FUNCTIONS 1. The primary purpose of the MSS is to provide for removal of Reactor Cooling System (RCS) Heat which has been transferred to feedwater j in the steam generators. The majority of the steam generated in the steam generators provides the driving force for the turbine / generator assembly, which produces the electrical output of ) the plant. l l 2. Pressure relief for the Main Steam Headers and the Once-Through 1 Steam Generators (OTSGs). 3. Provide a steam supply to drive the Auxiliary Feedwater Pump P-318 ) Turbine. j l 4. Provide for OTSG Isolation in order to mitigate tube rupture and l l steamline break accidents. 1 5. Supply steam to the High Pressure Turbine. 6. Supply steam to the Moisture Separator Reheaters (MSRs). \\ l 7. Supply steam to the Main Feedwater Pump Turbines and the Auxiliary Steam System (ASC). 8. Supply steam to the second and fourth point feedwater heaters. 9. Provide a heat sink for the RCS during startup, shutdown, and transient mitigation. l 10. Serve as a pressure boundary for the secondary plant. B. FUNCTIONS COVERED BY OTHER SYSTEMS 1. The Atmospheric Dump Valve control logic is to be tested under the EFIC system testing program. 2. The Turbine Bypass Valve control logic is to be tested under the ICS system testing program. 3. The ability to supply steam to the Auxiliary Steam System will be tested under the ASC system testing program. Page 1 l PAGE 12 0F 15 ) i

. ATTACHMENT 3 C. FUNCTIONS RE001 RING VERIFICATION 1. Provide for removal of RCS heat to steam gener'ator feedwater and transf er generated steam to the main turbine generator. i 0. FUNCTIONS NOT RE0VIRING VERIFICATION 1. Functions A.2,-3,-4 and -10 are verified during component testing. 2. The ability to supply steam to the High' Pressure Turbine is' adequately demonstrated by normal plant operation. (Function A.5) j 3. The ability to supply steam to the MSRs is adequately demonstrated by normal plant. operations. (Function A.6) 4. Steam supply to the Main Feedwater Pump Turbines is. adequately demonstrated by normal plant operations. (Function'A.7) 5. Steam supply to the Main Feedwater Heaters is adequately demonstrated by normal operations. (Function A.8) 6. Provision of a heat sink for the RCS during startup, shutdown, and transient mitigation is demonstrated during normal plant operati'ons and integrated system testing. (Function A.9) E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE' PERFORMED 1. The following testing is scheduled to be performed. t-a. STP.1018A, " Main Steam System Cold Functional Test," will verify system functions, controls, interlocks and logic prior. to plant heatup. b. STP.1018-B, Main Steam Systr.m Hot Functional Test," will verify system functions and performance at hot shutdown I conditions prior to reactor startup. t Page 2 PAGE 13 0F 15 ) e-

' ATTACHMENT'3 1 -j i 09-01-87. l WP34818 l D-00988 l SYSTEM FUNCTIONAL TEST ABSTRACT. l ONCE THROUGH STEAM GENERATORS I 1 A. SYSTEM FUNCTIONS 1. During normal power operation, the Once Through Steam Generators serve to transfer heat from the Reactor Coolant System (RCS) to the water supplied by.the Feedwater System (FHS), producing.superheated-steam which. is distributed by the Main Steam. System (MSS).. Following either a manual or an automatic initiation of! Auxiliary Feedwater,'the OTSGs transfer RCS heat to the Auxiliary Feedwater. The OTSGs must provide decay heat removal and cooldown capability by the transfer of heat to the Main or Auxiliary.Feedwater.. System by natural circulation. B. FUNCTIONS VERIFIED BY OTHER SYSTEMS 1. The Once Through Steam Generators (OTSGs) directly. interface with the following systems: a. Ve,rify that the primtry side of the steam generator (upper j head, tubes, lower head) just act as a barrier to the release of radioactive material. This function is verified with the i Main Steam Supply (MSS) System Testing. q b. Assure that the steam generator recirculation system provides j a means of recirculating the wet lay up water, of sampling .I that water, and of adding chemicals as required in order to maintain proper chemistry. C. FUNCTIONS REOUIRING VERIFICATION 1. None 1 The OTSGs function as components of.the Reactor Coolant and Main Steam Systems. Overall system functions are tested as part of those systems' tests. i j PM;E [4 0F 13 C__ _ _

ATTACID1ENT 3 l D. FUNCTIONS'NOT RE0VIRING VERIFICATION I 1. None E.

SUMMARY

OF TESTS TO BE PERFORMED 1. None (See C.1) l -1 l l '1 1 l l l I l l \\ l l l 1 l -2 PAGF,15 0F 15 l

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'ATTACIDIENT-4 WP34k18/0-01818 SYSTEM FUNCTIONAL TESTING ABSTRACT-EMERGENCY FEEDWATER INITIATION AND CONTROL 3 A. SYSTEM FUNCTIONS 1. Initiation of AFW for: '] a) Safety Features Actuation System (SFAS). ) b) Loss of all four Reactor. Coolant Pumps. 1 i c) Loss of both~MFW pumps at >20 percent' power. l d) Manual Initiation and Control of AFW. e) OTSG Level. -1 ij f) OTSG Pressure, 2. EFIC provides an automatic control signal to the AFW flow contral valves to maintain OTSG level at the appropriate setpoints-. 3. EFIC sends close signals'to the MFW main and startup flow control valves, the MFW main block valve, and the OTSG MFW isolation valve j if the corresponding OTSG pressure falls below 600 psig or level N exceeds th'e main feedwater overfill setpoint (to be determined after startup). 4. EFIC provides main steam overpressure protection by sending control i signals to the ADVs on each main steam line. { 5. Based on OTSG pressure. signals,-EFIC provides the necessary signals to isolate AFW flow. 6. EFIC provides H/A control of: a) AFW flow control valves, b) Atmospheric Dump valves (ADVs). i 1%Gl', b T.i 2j l L

ATTACHMENT 4 . s. f SYSTEM FUNCTIONS (Continued) i 7. EFIC System Bypass Features: a) Maintenance Bypass. b) Shutdown Bypass i -The EFIC system also provides analog and/or ' digital signals to: 8. a) Safety Parameter. Display System (SPDS). b) Interim Data Acquisition and Display System (IDADS). 9. EFIC is initiated when SFAS is manually / automatically initiated. 10. EFIC provides manual isolate switching'for' Appendix "R" isolation of EFIC Control Room' commands which transfers some controls to the Remote Shutdown Panel. 11. EFIC provides rate of level increase control when filling the OTSG to the natural circulation or ECCS' level setpoint. B. FUNCTIONS COVERED BY OTHER SYSTEMS. 1. None \\\\ C. FUNCTIONS REQUIRING VERIFICATION' 1. Initiation of AFW for: a) Safety Features Actuation System (SFAS). b) Loss of all four Reactor Coolant Pumps. l c) Loss of both MFW pumps at >20 percent power. l d) Manual Initiation and Control of AFW, e) OTSG Level. f) 0TSG Pressure. t l W.1, j' L

ATTACIBtENT 4 l 4 l I FUNCTIONS REQUIRING VERIFICATION (Continued) j l 2. EFIC provides an automatic control signal to the AFW flow control I valves to maintain OTSG level at the appropriate setpoints. 3. EFIC sends close signals to the MFW main and startup flow control valves, the MFW main block valve, and the OTSG MFW isolation valve if the corresponding OTSG pressure falls below 600 psig or level j exceeds the main feedwater overfill setpoint (to be determined i after startup). 1 4. EFIC provides main steam overpressure protection by sending control j signals to the ADVs on each main steam line. d 5. Based on OTSG pressure signals, EFIC provides the necessary signals to isolate AFW flow. l 6. EFIC provides H/A control of: q a) AFW flow control valves. b) Atmospheric Demp valves (A0Vs). 7. EFIC System Bypass Features: a) Maintenance Bypass, b) Shutdown Bypass 8. The EFIC system also provides analog and/or digital signals to: i a) Safety Parameter Display System (SPOS). b) Interim Data Acquisition and Display System (10A05). 9. EFIC is initiated when SFAS is manually / automatically initiated. 10. EFIC provides manual isolate switching for Appendix "R" isolation of EFIC Control Room commands which transfers some controls to the j Remote Shutdown Panel. I l 11. EFIC provides rate of level increase control when filling the OTSG to the natural circulation or ECCS level setpoint. l l D. FUNCTIONS NOT REQUIRING VERIFICATION l I 1. None l l ' 6i L 1___

i ATTACHMENT 4 A ] E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. Individual system f unctions ( A.1-11) are verified during component testing. l i 2. STP.665, "EFIC Cabinet Functional Test," to functionally verify the I EFIC System internal logic and cabinet interconnections as l installed by ECN A-5415E. 3. STP.666, "EFIC Cold Functional Test," to functionally demonstrate l the orsioL;lity of the EFIC system including the interfacing and ancillary systems which make up the MOD 1 design package. 4. STP.667, "EFIC Cold Preoperational Test," to functionally I demon' strate the operability of the EFIC system controls and indication under dynamic conditions at cold shutdown. i 1 1 5. STP.668, "EFIC Post-Startup Test," to functionally demonstrate the i operability of the EFIC system controls and indications under l moderate and high decay heat conditions in conjunction with a l planned reactor shutdown. 6. STP.1113, "EFIC Hot Functional Test," to functionally demonstrate the operability of the EFIC system controls and indications unda'r dynamic conditions of hct shutdown. 1 \\ l i l l l l l PAGE 110F 23 e

ATTAC&1ENT 4 09-01-87 WP-34528 D-0098B i SYSTEM FUNCTIONAL TESTING ABSTRACT 4 INTEGRATED CONTROL SYSTEM (ICS) t A. SYSTEM FUNCTIONS I 1. The Integrated Control System (ICS) coordinates the reactor, steam generator, feedwater and turbine controls for stable-operation of the plant. The ICS also provides control actions to runback and limit the plant load demand whenever a condition exists-which limits generating capacity, or requires an orderly shutdown. The functions of the ICS can'be divided'into the five subsystems within the ICS, and functions related to ICS power. The five subsystems are: a. Unit load demand subsystem (master control) b. Integrated master subsystem (turbine control) c. Steam generator /feedwater subsystem d. Reactor control subsystem e. Borate control subsystem B. FUNCTIONS VERIFIED BY OTHER SYSTEMS 1. None C. FUNCTIONS RE0VIRING VERIFICATION-1. The testing recommended to verify functions of the Integrated Control System (ICS) that are important to safe plant operations (per STP.778 and STP.664) are: a. The Unit Load Demand subsystem shall be tested to verify manual and tracking operation, runbacks, load change rates, and load demand limits. b. The Integrating Master subsystem shall be t'sted to verify e that it' provides manual / automatic _ controls for steam / reactor demand and turbine bypass valves. i . PAGE 12 0F 23 L_______________

NITACHMENT'4 .] y \\ l c. The Steam Generator /Feedwater subsystem shall be tested to verify manual / automatic control for feedwater demand,esteam generator BTU. limits, min. and max. steam generator level, cross-limit, re-ratio ~feedwater on. loss of reactor coolant i pumps. d. Reactor Control subsystem shall be tested to verify manual / auto control for reactor demand, reactor power limits, cross-limits, Neutron Power Blocks Restart of Reactor Coolant. Pump, Neutron Error Blocks: Transfer of Rod Control to.. Automatic and Asymmetric Rod Condition Blocks Rod Hithdrawal. e. The Borate Control subsystem shall be tested ~to verify Annunciation of Rod Position Error and Operation of the Feed and Bleed Permissive. 1 f. Verify Loss of. NNI/ICS Power, Control' Actions are provided to place the plant in safe condition. g. NOTE: STP.660." Integrated Control System Tuning at Power" will be performed during power escalation.. The objective is to verify the ICS provides the best load respoase to load demands during steady state and transient conditions. D. filNCTIONS NOT REOUIRING VERIFICAITON 1. None \\ g E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. The testing detailed on Attachments I through 3 is _ scheduled to be performed: _] a. STP.778, " Integrated Control. System Functional Test", verifies t the Integrated Control System (ICS) can perform the functions necessary to control the Reactor, the Once-Through Steam Generators, and the Turbine over the plant's full range of power, by simulating inputs to the ICS and observing the system's reactions. b. STP.664, " Loss of ICS/NNI Power",' demonstrates that on a loss of ICS/NNI power, the plant can be controlled-in a Hot Shutdown condition. c. STP.660, " Integrated Control System Tuning at Power". verifies. the integrated Control System.(ICS) provides the load response to the unit load demand during ;teady-state and transient conditions by inducing transients, adjusting tuning parameters, observing power escalation, and verifying-the calibration of the feedforward function generators. -2 l 6' S

ATTACHMENT 4 09-01-87 WP3445B D-01458-SYSTEM FUNCTIONAL TESTING ABSTRACT NON-NUCLEAR INSTRUMENTATION SYSTEM A. SYSTEM FUNCTIONS 1. The Non-Nuclear Instrumentation (NNI) provides input signals of process variables for the reactor protection, system regulating, l and auxiliary system. 1 2. Provides inputs to the Integrated Control' System (ICS) for critical control functions. 3. The NNI System provides measurements used to indicate, record, alarm, provide for control and interlock functions based on the following five basic process variables. a. Pressure b. Temperature C. Flow d. Lehel e. Component position. 4. The NNI provides indications of measurement and control of process '1 variables necessary for proper system operation. a. Reactor Coolant System I b. Secondary Plant System l l c. Makeup and Purification System d. Core Flood System e. Decay Heat Removal System 5. Provides inputs to the Annunciator Systems. i 1 6. Provides the operator with a variety of' indication channel j selections. j ' Pact: 1/4 OF 23 i L

ATI'ACfMENT 4 - s \\ .1 'B. FUNCTIONS COVERED BY OTHER SYSTEMS 1. The NNI supports a number of operational and safety interlocks to' .i permit or to prevent equipment operation under predetermined 1 process conditions..The contacts associated with the interlocks are tested during NNI. testing ensuring loop continuity and proper I setpoints. The NNI System directly interfaces with the following systems a. Reactor Coolant System j b. Makeup and Purification System c. Decay Heat Removal System d. Secondary Plant System (OTSG, MFH, Turbine) e. Core Flood System I f. Integrated Control System i g. Annunciator System 1 2. The NNI System interfaces. indirectly with the Safety Features j Actuation System (SFAS) and the RPS. The temperature', pressure, 1 l and flow signals are used in these systems and are then sent to the.l NNI Sys, tem. ] 3. The systems required to support the NNI System are the Vital s Electrical Distribution System-and the Non-Vital Electrical Distribution System. 4. Instrument loop calibrations will be performed on all instrument q loops associated with the NNI System. The interlocks described in I the functional description will be tested. ( l C. FUNCTIONS REOUIRING VERIFICATION l. Provides indications for many parameters in the Control Room. 2. Provides input to the ICS System. 3. Provides inputs to the Annunciator System. l 4. Suppcrts a number of operational and safety interlocks. 5. Provides the operator with a variety of redundant' interfaces which are mainly selector type switches. i PAGE Ii 0F 3

/ ATTACHMENT 4 D. FUNCTIONS NOT REOUIRING VERIFICATION 1. None ~j E.

SUMMARY

OF SYSTEM FUNCTIONAL' TESTING TO BE PERFORNED 1. ~ STP.1115 - NNI Functional test. to facilitate and document the system' testing required.to verify, that the NNI system is capable of performing its design function. q 4 e a l 1 a l \\ l ',i l%GE M OF 23 l t

ATTACHMENT 4 HP34688/D01848 SYSTEM FUNCTIONAL TESTING ABSTRACT' RADIATION MONITORING SYSTEM A. -SYSTEM FUNCTIONS 1. The Radiation Monitoring System measures, indicates, annunciated, and records the radiation _ level at selected areas within'and on the perimeter of the plant verifying compliance with 10CFR20 and 40CFR190 limits, and detecting abnormal conditions within the plant: a. Provide indication of area radiation levels and process activity levels. b. Provide alarm and annunciato'r actuation for abnormal indication. c. Terminate or redirect flow of activity in process streams on alarm actuation. d. Collect grab samples for' particulate and iodine in gaseobs I effluents during an emergency. B. FUNCTIONS VERIFIED BY OTHER SYSTEM 1. Radiation Monitoring System inputs'to SPDS will be tested as part ) of the PCS system under STP 789 (Functions la. and b.). 2. Centrol Room Emergency HVAC actuation will be tested as'part of the-CN TSC HVAC System (SP.485A and B). C. FUNCTIONS REOUIRING VERIFICATION 1. Provide indication of area radiation levels and process activity l levels. l l 2. Provide alarm and annunciator actuation for abnormal indication. 3. Terminate or redirect flow of activity in process streams on alarm i annunciation. 4. Collect grab samples for particulate and iodine in gaseous I effluents during an emergency using RT-RDH-001.

iw;E 17 or a

. ATTACIDIENT 4 D. FUNCTIONS NOT REOUIRING VERIFICATION The fol'owing will not be tested: l 1. 4 a. R-15021 Gland Seal Exhaust Monitor (this monitor is tagged out

l and will be removed under ECN R-1380.)

i b. R-15018 Spent Fuel Coolant Monitor (This monitor is tagged out 1 and will be replaced under ECN R-1420).. 2. Individual system functions will be tested during component testing. E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED l 1. STP.lll2, " Functional Test of Radiation Monitoring System" will be-i performed to verify proper indication of radiation or activity level for all installed radiation monitors, proper alarm and annunciator actuation for all installed radiation monitors, that control functions are performed (termination of process activity flow) on alarm signal, and-the ability la collect grab samples of gaseous effluents during an emergency. 4 \\ 1 l s:. PAGE 18 Ui' M

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NITACHMENT 4.' 4 09-01-87 HP3442B 0-01518 SYSTEM FUNCTIONAL TESTING ABSTRACT REACTOR PROTECTION SYSTEM H A '. ' SYSTEM FUNCTIONS 1. The Reactor Protection System (RPS) fulfills the following safety-design. basis functions by tripping the Control Rod Drive-(CRD)- j' . breakers when system monitored parameters exceed their Limiting Safety System Settings: a. To protect the Reactor Coolant System.(RCS) against an over-pressurization condition.

l b.

To protect the reactor core against fuel rod cladding damage caused by a departure from nucleate boiling. c. To mitigate the consequences (i.e., challenging the _ EHOV)' of a Turbine Trip or Main.Feedwater Pump (MFP) Trip. B. FUNCTIONS VERIFIED BY OTHER SYSTEMS -l 1. To protect the Reactor Coolant System (RCS) against an over-pressurization condition. a. The portions of the instrument channels which supply the RCS-t pressure signal to the EMOV and Pressurizer Heater control . logic-and are outside the RPS cabinet are tested as part of the Non-Nuclear _ Instrumentation (NNI) System. .j C. FUNCTIONS REOUIRING VERIFICATION 1. To protect the Reactor Coolant System (RCS) against an over-pressurization condition. 2. To protect the reactor core against fuel rod. cladding' damage caused by a departure from nucleate boiling. ) 3. _ To mitigate the consequences (i.e., challenging the EMOV) of a Turbine Trip or Main Feedwater _ Pump (MFP) Trip. D. FUNCTIONS NOT REOUIRING VERIFICATION 1. None 1-PAGE 19 OF M

ATTACiDIENT 4 j l l 1 3 E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORHED i 1. STP.790, "RPS Module Removal Interlock Verification," functionally verifies operability of the critical module interlocks in the RPS cabinets. 2. STP.lill, "RPS Functional Testing," facilitates the system testing required to verify that the RPS is capable of performing its design function of tripping the Control Rod Drive (CRD) breakers when system monitored parameters exceed their Limiting Safety System Setting. 3. STP.795, "RPS Time Response Test," verifies the time response of q each RPS Channel. L I 4. RT-RCS.002, " Refueling Outage Reactor Coolant Pump Failure (Undercurrent) Relay Test," a. Verifies that the Reactor Coolant Pump (RCP) failure (motor i undercurrent) relays provide pump trip inputs to the RPS, b. That the RCP failure (motor undercurrent) relays provide pump trip inputs to the Integrated Control System (ICS) and, c. That the RCP/ Safety Injection and Hakeup/ Component Cooling Hater valve interlocks by checking that the auxiliary relays ) 637XA, XB, XC and XD will energize only if all four RCP motors are not running. l l 1 l l I i } l l 2 q -m~n

ATTAC101ENT 4 09-01-87 HP-3443D D-0151B i SYSTEM FUNCTIONAL TESTING ABSTRACT SAFETY FEATURES ACTUATION SYSTEMS j i A. SYSTEM FUNCTION 1. The plant Safety Features Actuation System (SFAS) monitors Reactor Coolant System (RCS) pressure and Reactor Building (RB) pressure in order to detect a loss in RCS pressure boundary integrity or. loss of coolant accident (LOCA). The SFAS initiates actuation signals to the following safety features systems to minimize the severity i and mitigate the consequences of a LOCA: a. Emergency Core Cooling to ensure fuel integrity. b. Reactor Building Cooling, Isolation and spray systems to ensure RB integrity, reduce the driving force for building i leakage and remove fission products from the RB atmosphere. c. Emergency Diesel Generators to provide redundant power sources ] to the nuclear service bu:es. 2. Provides actuation or indication on module withdrawal. 3. Bypass SFAS actuation on low RCS pressure. 4. Provides RCS pressure signals to various plant equipment. I B. FUNCTIONS COVERED BY OTHER SYSTEMS l I 1. The Safety Features Actuation System directly interfaces with the following systems: a. High Pressure Injection b. Low Pressure Injection c. Core Flood d. Reactor Building Emergency Cooling e. Nuclear Service Raw Hater f. Nuclear Service Cooling Hater g. Auxiliary Feedwater (EFIC Initiate) h. Reactor Building Spray i. CR/TSC Emergencv HVAC j. NSEB Emergency HVAC k. Emergency Diesel Generators 1. Reactor Plant Sampling P.u;i; 2 i o, .. t

g ATTACHMENT 4 I B. FUNCTIONS COVERED BY OTHER SYSTEMS (Continued) m. Purification and ' Letdown - n. Seal' Inject and Hakeup: o. Reactor Building. Purge p. Borated Hater. 2. The Safety Features Actuation System provides RCS pressure signals j to the.following systems: .I 1 a. Non-Nuclear Instrumentation 1. EH0V interlock l J 2. CFT outlet valve interlock 3. Control Room wide range recorder.- b. Reactor Coolant System - Tsat Calculators 1 i c. Decay Heat System - Drop Line. Valve Interlock d. Various Plant Meters l 1. Technical Support Center 2. Control Room - boron panel \\ C. FUNCTIONS REOUIRING VERIFICATION 1. MonitorReactorCoolantSystem(RCS)pressureandlReactorBuilding' 1 1 (RB) pressure. 2. Process the pressure signals and actuate safety-features-components as required. 3. Initiate Nuclear Service Bus unloading. 4. Provide RCS pressure signals to various plant equipment. 5. Bypass SFAS actuation on low RCS pressure. l 6. Provide system status indications. 1 1 7. Provide actuation or indication on module-withdrawal. j l . PAGE 22 0F 21 i C-

ATTACHMENT 4 L.' ' B. FUNCTIONS REQUIRING VERIFICATION '(Continued) l ~ 8. Provide the capability to manually initiate individual digital channels. 9. Provide the capability for manual control of safety features components:following an SFAS actuation. .D. FUNCTIONS NOT REQUIRING VERIFICATION i 1. Functions A.2-4 will be tested during Component Testing, E. SUMMA.RY OF SYSTEM FUNCTIONAL TESTING TO'BE PERFORMED 1. STP-1110, "SFAS Functional Testing," facilitates the system. testing required to verify that the SFS is capable of performing its design functions. I \\ 3 4 t 'j PAGE 23 0F 23

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r 1 NITACIDIENT 5 3 o .09-01 WP3479B l t D-0060B SYSTEM FUNCTIONAL TESTING ABSTRACT DECAY HEAT REMOVAL' SYSTEM A. SYSTEM FUNCTIONS i' The Decay Heat Removal System (DHS) provides the.following safety'and non-safety functions: 1. Low Pressure Injection (ECCS) to the Reactor Coolant System 2. Long Term Cooling _ of.the Reactor Coolant System 3. Long Term Boron Control ~ 4. -Normal Decay Heat Removal 5. Backup to Fuel Pool Cooling 6. Containment Isolation j q B. FUNCTIONS VERIFIED BY OTHER SYSTEMS

)

1. The Decay Heat System directly. interfaces with the-following j systems. .] a. Safety Features Actuation System (SFAS) j i b. Emergency Diesel Generator System j 1 c. Borated Water System C. FUNCTIONS REOUIRING VERIFICATION -l 1. All functions listed in "A." D. EMNCIIONS NOT REOUIRING VERIFICATIDH 1. Long Term Cooling of the RCS will riot be tested since an adequate test of this function requires discharge into an unloaded, uncapped-reactor vessel. An engineering analysis of the Reactor Building Sump Suction NPSH_is being performed. ld PAGE 6 OF 13

E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. STP.1087, " Decay Heat System Logic Functional Test," will verify the operation of the controls, interlocks and indications for the system functions. 2. STP.1088, "DHS Cold Functional Test," will verify the performance of the Decay Heat System functions prior to heatup. i ) i h 1 l i b \\ ,9 l } f

ATTACHMENT 5 ' 08/31/87 j WP3453B t D-00038 SYSTEM FUNCTIONAL TEST ABSTRACT i PURIFICATION AND LETDOWN SYSTEM l A. SYS}pj_[ UNCTIONS i i 1. The functions of the Purification and Letdown System (PLS) that are 1 important to safety are as follows. 7, 1 a. Provide RCS pressure boundary. l I e. Provide containment isolation on SFAS signal, j i c., Regulate (in conjunction with SIM) RCS inventory. ) l d. Regulate boric acid concentration in RC5 to accommodate reactivity changes in core. e. Detect failed fuel using installed Radiation Monitor. 4 i J f. Remove impurities from RCS. l g. Maintain proper concentration of hydrogen and corrosion l inhibiting chemicals in the RCS. q h, Provide makeup water to SIM during normal 09erption \\ s B. FilNCTIONS COVERED BY OTHER SYSTEMS 1. Detection of failed fuel using the installed Radiation Monitor will be performed by ROM. 2. Regulation of RCS inventory is covered by testing in RCS, SIM and PLS. j 1 3. Containment isola, tion provided by SFAS actuation is covered in,$FS; i .C. FUNCTIONS REQUIRING VERIFICATION j j 1. Provide RCS pressure boundary, 1 2. Provide containment isolation.on SFAS signal. 3. Remove impurities from the R'.S. ] f t k 31 \\ i 9 itu L 8 l:

v ATIACfDIENT 5 g'

g y FUNCTIONS REQUlHING VERIFICATION (Continued) 4. Regulate boric acid co9 centration in the RCS to accommodate ~ reactivity ?.5pnges in the core. t ~ 5. Maintain pr9per concentration of hydrogen and corrosion inhibitive ] chemicals in the RCS. s 6. Provide makeup water to SIM during normal operation. D. FUNCTIONS NOT REQUIRING VERIFICATION j 1. None. E.

SUMMARY

OF SYSTEM FUNCTIGNAL TESTING TO BE PERFORMED t 1. STP.1089, "PL5' Logic Functional Test," will test system logic, controls and interlocks for the functions listed in Section C. 1 2. STP.1090, PLS Cold Functional Test," will ' test the overall performance of the system. 3. STP.1093, "NSSS Integrated Functional Test," which will verify integrated operation of the PLS, SIM and RCS. i s _1 _ 10.G l'. '! s 13

1..

. ATTACHMENT 5, m 08-29 -HP-3472B-D-0054B ' SYSTEM FUNCTIONAL TESTING ABSTRACT REACTOR COOLANT SYSTEM A. SYSTEM FUNCTIONS 1. The Reactor Coolant Syst'em removes heat'from the core. The-following subfunctions require verification: a. 'The Reactor. Coolant System circulates reactor coolant for heat removal during steady. state operation-and for' any anticipated transient. b. .The RCS shall remove decay heat from the core via redundant heat removal paths. c. Provide a refloodable volume to cool the reactor core. following a LOCA. 2. The RCS pressure boundary is a barrier to'the release of radionuclides's to the Reactor Building atmosphere and to the secondary fluid in the steam generators. The following subfunctions require verification: a. Provide overpressure protection for the pressure boundary at normal operating conditions and at low temperatures.(Reactor Vessel Brittle Fracture Limits). -l i -l b. Leakage rate limits and detection, c. Coolant activity level limits. d. Containment isolation. 3. Reactor Coolant serves as a neutron moderator and as a solvent for acid used in chemical shim reactivity control. B. FUNCTIONS VERIFIED BY OTHER SYSTEMS 1. Reactor. Coolant System inventory control will be verified in SIM, PLS, DHS and CFS Testing. 2. Decay Heat Removal via redundant heat removal paths will be-verified in DHS testing. j i

PwF.10 N 11

?ATTACNMENT'5 C. FUNCTIONS'REOUIRING VEF.iFICATION j 1. The Reactor Coolant System removes heat from the core. 2. The RCS pressure boundary.is a barrier to the release of radionuclides to the reactor building atmosphere and to the secondary fluid'in the steam generators. ] 3. Coolant serves as a neutron moderator and as a solvent for boric. acid used in chemical shim. reactivity control. D. FUNCTIONS NOT REOUIRING VERIFICATION 1. BASIS FOR FUNCTIONS NOT VERIFIE_Q-a. Heat transfer from natural circulation..(Function A.l.a) Basis: Heat transfer.from natural' circulation is.a' function of steam generator' thermal center. This test has not' 1 been tested specifically' at SMUD, however, it needs'.to H be performed only once at an NSS of the same design .) because_it tests a passive function which is not r . The significantly affected..by time and. wear. subfunctions.that are required for, proper natural circulation are Emergency Pressurizer Heater, Operable Vent Paths (High Point),-and Hot Leg Level Indication. These subfunctions will,be discussed in i their proper sections. b. Reactor vessel internal vent valves. (Function A.l~c). H Basis:.SP.203.10, " Refueling Interval' Reactor Internal Vent Valves Surveillance and Inspection Test,"~ exercises the internal vent valves every refueling by applying.a force of 400 lbs vertically upward.on an exercise-lug. This demonstrates the vent' valves will be open when exposed to the pressure differential expected during a cold leg break. The reactor vessel head must be removed'for testing. There is no reason to. suspect that the valves have deteriorated such that their' functionality.is in question.- Relief from the test requirement has been requested since the head will not i be removed this outage. Proposed Amendment.145 would waive head removal until May 1989. 'A favorable response has been, verbally indicated from the NRC. j i 2. Individual system functions are verified during component testing. l P M 11 oE 13

ATTACIIMENT 5 q l E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. STP.1085, " Reactor Coolant System Logic Functional Test", will test RCS controls, interlocks and indications prior to plant heatup. 2. STP.1086, " Reactor Coolant System Cold Functional Test", will verify overall RCS performance prior to plant heatup. 3. STP.1093, "NSSS Integrated Functional Testing," will verify integrated operation of the RCS, SIM and PLS systems. 1 i ) s' i 1 l P u;i: l'! or 11

ATTACHMENT 5 ~ '~ 09-01-87 HP-3485B 0-0054B' SYSTEM FUNCTIONAL TESTING ABSTRACT SEAL INJECTION AND MAKEUP SYSTEM 1 A. SYSTEM FUNCTIONS 1. Provide makeup to RCS for volume and chemistry control. l 2. Provide seal injection to RCPs-for cooling and lubrication. 3. Provide injection of borated water to RCS for emergency core ' cooling on SFAS signal. 4. Provide containment isolation on SFAS signal. 5. Provide RCS pressure boundary. i i 6. Provide alternate pressurizer spray for cooldown and mitigation of boron precipitation. 7. Provide fill for Core Flood Tanks. I i B. FUNCTIONS COVERED BY OTHER SYSTEM l l 1. STP.773,xRCP Seal Injection and Seal Return Isolation Valves Interlock Functional Test, part of function 2 and is covered by PLS. 4 2. SP.203.01A/B, SFAS Digital Channel lA/B Refueling Test, is part of-functions 3 and A, covered by SFS. l C. FUNCTIONS REOUIRING VERIFICATION 1. All functions listed in section A will be verified prior to Startup. D. FUNCTIONS NOT REOUIRING VERIFICATION 1. None l E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. STP.1091, "SIM Logic Functional Test," vill test controls, interlocks and indications for system functions. l 2. STP.1092, "SIM Cold Functional Test," will test overall system performance. 3. STP.1093, "NSSS Integrated Functional Test," which will' test integrated operation of the SIM, PLS and RCS systems. / AGE 13 0F' 13

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T %"_0" ) !e;39(.<[< ATTAClEIENT 6 \\ HP34768/D-00413; SYSTEM FUNCTIONAL' TESTING ABSTRACT-H . COMPONENT COOLING HATER. SYSTEM A. SYSTEM FUNCTIONS 1. Heat sink provision for components.that'are. required for safe plant operation. 2. CCH containment isolation. I 3 Interlock from RCPs to CCH containment isolation valves. 4. CCH surge tank level indication. 5. CCH flow and pressure : signals used for interlocks and. annunciators. 6. Control Room indication' for CCW system flow, pressure and temperature. 7. CCH system barrier between the RCS and the PCH. B. FUNCTIONS VERIFIED BY OTHER SYSTEMS 1. CCW Containment Isolation Valves are included in SP.422A, and will undergo the LLRT with the PBS System (function 2). s 2. SP.205.07C includes all remotely operated Reactor Building i Isolation Valves, and will be_ inspected.and stroked with the PBS i System, (function 2). 3. Leakage into the CCH System from the RCS System will_be detected by 1 performing SP.200.03 and 200.07, covered in the RDH system [ (function 7). j C. FUNCTIONS RE0VIRING VERIFICATION 1. Verify that a heat sink is provided for components which are required to function continuously during plant operation. 2. CCH Containment isolation valves shall be operable.(SFV-46014, SFV-46203 and SFV-46204). 3. Valve interlock from RCP to CCH containment isolation. q l : PAGE 9 OF 21 1

ATTACHMENT 6 C.

FUNCTIONS REOUIRING VERIFICATION (Continued) 4. Accurate surge tank level. indication, automatic makeup control ~. 5. CCH flow and pressure signals used for interlocks and annunciators operate. 6. Control Room indication for CCH System flow, pressure.and' temperature must be' operable. 7. 'The CCH. System is a barrier between.the potentially radioactive Reactor Coolant System.(RCS) and the Plant Cooling Hater System-(PCH). D. FUNCTIONS NOT REQUIRING VERIFICATION 1. Individual System functions (C.1-7) will be tested'during component testing. E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTS TO BE PERFORMED-1. STP.1106, "CCW System Cold Functional Test,". will verify system interlocks, controls' and performance prior to plant heatup. ; 1 2. STP.1053, " Component Cooling Hater Component Flow Verification " .) will verify that flow rates to all CCH components are adequate. s R f '\\ . PAGE Hi 0F 21

ATTACHMENT 6'

]

f 09-01-87 HP-347.4B' 3 0-01748 J 'I SYSTEM FUNCTIONAL TESTING ABSTRACT EMERGENCY D!,ESEL GENERATOR SYSTEM A. SYSTEM FUNCTION 1. The Emergency Diesel Generator system provides an auto-fast' start ~ standby electrical power suppiy for the Nuclear Service-Buses. The emergency diesel generators and support systems.can be maintained l in a standby condition such that on a Safety Features Actuation Signal (SFAS) or Loss of Offsite Power (LOOP) initiation signal, the diesel generator can come up to speed and voltage within 10 seconds. B. FUNCTIONS COVERED BY~0THER SYSTEMS l The Emergency Diesel' Geiie'rator System directly interfaces.with the. ) following systems. ) 1 1. Nuclear Service Raw. Hater System 2. Fire Protection System \\ 3. Instrument Air System l ji 4. Diesel fuel oil system 5. Safety Features Actuation System 6. Plant Annunciator System l 7. Plant Computer System 8. 125 VDC (battery) system 9. 480 VAC Nuclear Service system 10. 4160 VAC Nuclear Service system-11. 220 KV system \\ PE E 11 oF 21 i' __________.1__

ATTACllMENT-6 l,. C. . FUNCTIONS REOUIRING VERIFICATION 1. SFAS initiation causes the diesels.to automatically. start and accelerate to speed and voltage. 2. Nuclear Service buses remain energized with offsite power on a SFAS initiation and SFAS automatic-load: sequencing. circuitry operates properly. 3. On a loss of Offsite Power in conjunction with a simulated SFAS initiation, the Nuclear-Service busses are de-energized.by proper operation of the load. shedding circuitry and the diesel generators load through the. sequencing circuitry. 4. All automatic diesel generator output breaker trips, except ground: 1 overcurrent and generator differential, are automatically blocked' with an SFAS initiation signal. .2 5. On a LOOP and SFAS, Diesel. Room C02 actuation, fuel oil transfer -) pump and ventilation. fan trip automatic blocking relays'are -{ energized. 1 6. Diesel Generator system, support'and interfacing system controls -I and instrumentation function properly. 'j ) D. FUNCTIONS NOT REOUIRING VERIFICATION None E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED-1. STP.961 " Loss of Offsite' Power," (LOOP) will verify required functions of the Emergency Diesel Generator Systems for both the Bruce GH and TDI units. l 2. STP.1009A and B, "TDI' Diesel Generator Preoperational. Test," will j test the logic, controls,-interlocks, starting reliability and-operation of the TDI Diesel Generators. 4 4 l'AGF 12 0: 'J 1 '

' ATTACHMENT 6 .] 't 1 .l WP34808/0-0060B ,] SYSTEM FUNCTIONAL TESTING ABSTRACT FIRE PROTECTION SYSTEM A. SYSTEM FUNCTIONS The Fire Protection: System includes-active,' passive and, administrative features to reduce the: likelihood of.f. ire occurrence; prompt detection i and extinguishment of fires if'they do occur; ability to maintain' safe shut down if a fire occurs;1and prevent the release of a significant amount of' radioactive material if a fire occurs. The Active Fire Protection System features are as-follows: I 1. Automatic water suppression ~ systems supplied by. (2) 100% fi; e pumps and an underground main header. 2. Manual sunnression provided by fire extinguishers and f. ire; hose. Standpipet 'or use by the plant Fire Brigade. 3. Automatic gas suppression, systems consisting of low pressure.C;02 and Halon 1301 total flooding systems. 4. Automatic fire detection.is provided by heat detectors, smoke detectors, flame detectors and duct smoke detectors. \\ 5. The station Automatic Fire Alarm system provides the required interfaces between detection systems and suppression' system m actuation and annunciation to the Main Control Room. System I supervision is also provided_by the Alarm system. .j l The Passive Fire Protection System features are as follows:

l l '.

Rated fire doors in fire barrier walls between redundant safety related cables and equipment. I 2. Rated fire dampers in fire barrier walls between redundant safety related cables and equipment. 3. Rated penetration seals in fire barrier walls between redundant safety related' cables and equipment. 1-4. 'l hour and 3 hour' rated fire wrap protecting redundant safety related cable trays and conduits. FUNCTIONS VERIFIED BY OTHER SYSTEMS B. 4 None 1 1 1 PEE 13 W 21 i ___m_________.___________._____.___.i_______

m ] -: ATTACHMENT.6 ~ a l J C; FUNCTIONS REQUIRING VERIFICATION The Active Fire Protection System features described in Section A 1. (above) are verified on-a system or component basis by-functional 1 operation of the' equipment per approved Surveillance Procedures _and Fire Protection' inspection Procedures. Past Modification _ testing will utilize existing approved procedures.where practicable, or. special test procedures as'necessary. The Passive Fire Protection System features -described in Section A 2. ~l '(above).are verified acceptable by visual. inspection and/or, functional. test as applicable-per approved Surveillance' Procedures. D. FUNCTIONS NOT REQUIRING VERIFICATION FireProtectionsystemfeatures:areall; subject'toperiodic 1. testing. In addition, modifications affecting_ fire protection of a certain: zone.have been tested onla zone basis. No overall system functional test is planned, due to the nature of the system j configuration (zones _and individual l components). O E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED The Fire Protection System is verified and/or' tested per_ approved 1, procedures as required'by Technical Specifications. \\. . PAGE 1'4 0F $1

ATTACllMENT 6 - 1 HP3477B/D-0041B l SYSTEM FUNCTIONAL TESTING ABSTRACT INSTRUMENT AIR SYSTEM A. SYSTEM FUNCTIONS 1. Emergency Diesel Driven Air Compressor (DDAC) and support equipment i provide a full capacity backup source of instrument quality air. ) i 2. Component Level Bottle Backup Air Supply automatically provides instrument quality air for critical valves upon a loss or degradation of instrument air pressure. i 3. Upon closure of the priority valve (PV-90508), all air delivered from the plant air compressors is directed to the IAS. This occurs { when low header pressure is detected. q 4. Normal Air Compressor Safeguards / Auto-Start operate. B. EUNCTIONS COVERED BY OTHER SYSTEMS j 1. None C. FUNCTIONS REOUIRING VERIFICATION 1. Emergency Diesel Driven Air Compressor 2. Component Level Bottle Backup Air Supply to Critical Valves 3. IAS to SAS Priority Valve Operation 4. Normal Air Compressor Auto-Start D. FUNCTIONS NOT RE0VIRING VERIFICATION 1. Individual component functions are verified during component testing. E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. STP.1107, "IAS Functional Test," will verify overall operation system functions prior to and during plant heatup. PAGE 15 of _'I

I . ATTACHMENT 6 .09-01-87 HP34698 D-0145B SYSTEM FUNCTIONAL. TEST ABSTRACT NUCLEAR SERVICE RAH HATER SYSTEM A. SYSTEM FUNCTIONS 1. During normal-plant shutdown and emergency conditions, the NRH system provides a heat sink for the.DHR System, via the NSH-system. This is. accomplished by supplying 15000.gpm of NRH to the tube side of the NSH. Heat Exchanger..The system also provides the i required flows to the following components: a. NSW Heat.Exchangers, b. Emergency Diesel Generators.- qq

c..HPI and HU Pumps.

)l d

Decay Heat Removal Pumps. e. Emergency Pump Room Air Coolers. i B. FUNCTIONS VERIFIED BY OTHER' SYSTEMS \\ 1. None C. FUNCTIONS REOUIRING VERIFICATION 1. The following specific functions performed by the.NRH system during both normal shutdown and emergency conditions, require verification for safe plant operation-1 a. Required flowrates are provided by the NRH system,' loops A and 8 to the components cooled by this system. D. FUNCTIONS NOT RE0VIRING VERIFICATION 1. None l' AGE 16 0F 21

'l ~ ATTACGIENT:6 E.

SUMMARY

OF ' SYSTEM FUNCTIONAL' TESTfNG TO BE PERFORMED - 1. STP.1031.A/8, " Nuclear Service Raw Hater (NRH) Component Flow Verification," verifies required flow to each component served by the NRH system. .j 2. STP.1108, "NRW Cold Functional Test," verifies overall. system performance prior to heatup.. .{ l 4 l -{ .{ l I ) I \\ I 4 -2 PAGl: I7 Of ji

ATTACfDIENT 6 HP34708/D-0181B SYSTEM FUNCTIONAL TEST ABSTRACT NUCLEAR SERVICE COOLING HATER A. SYSTEM FUNCTION 1. Provide required flows to components of the NSW System including: a. NSW Pumps, b. RB Emergency Coolers', c. Decay Heat Coolers. 2. Start on SFAS initiation signal, j 3. Contain primary coolant in the event of leakage into the NSH. l B. FUNCTIONS VERIFIED BY OTHER SYSTEMS l. Actuation of all SFAS devices on SFAS' digital channels lA and;IB will be verified during SFS testing. l 2. Functional tect of unloading and loading of Nuclear Service Bus A, A2, B and Diesel Generators A & B start for SFAS conditions and' loss of yoitage conditions will be performed during EGS 1 Surveillance Testing. i C. FUNCTIONS REQMIRING VERIFICATION 1. Provide required flows to components'of the NSW system. 2. System integrity is verified by periodic' surveillance and maintenance testing. D [MNCTIONS NOT RE0VIRING VERIFICATION 1. None PAGE b 0F J1

ATTACIIMENT 6 l E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED l 1. STP.1032, " Nuclear Service Cooling Hater (NSW) Component Flow I Verification," will verify required flows to components of the NSW ] System. j l 2. STP.1109, "NSH Cold Functional Test," will verify system performance prior to plant heatup. 1 I i l l l 2 PM;E pi ol' a

ATl'ACINENT 6 f 09-01-87 WP3486B 0-0054B i SYSTEH FUNCTIONAL TESTING ABSTRACT REACTOR SAMPLING SYSTEM i A. ESTEM FUNCTION 1. The normal RSS is used to collect fluid samples from the Reactor Coolant System and auxiliary systems for analysis under normal and abnormal conditions. The normal RSS collects fluid samples from the following locations: a. Core Flood Tanks b. Pressurizer c. Purification demineralized outlet d. Letdown cooler outlet e. Makeup tank f. Decay heat removal cooler outlet g. Miscellaneous nter hold-up tank h. Letdown filter outlet i. Makeup filter outlet 2. The Post Accident Sampling System (PASS), a subsystem of the RSS, is used to collect and analyze samples from the reactor coolant system, decay heat removal system, and the Reactor Building atmosphere following an accident. B. FUNCTIONS COVERED BY OTHER SYSTEMS 1. The Reactor Sampling System directly interfaces with the following systems: a. Reactor Coolant System b. Pressurizer Relief Tank c. Haste Gas System d. Purification and Letdown System PEF 20 0F a

.~ ATTACID1ENT. 6 l.I a 1 B. FUNCTIONS COVERED BY OTHER SYSTEMS (Continued) e. Decay Heat Removal System j f. -Core Flood System g. Heating and Ventilation System h. Plant Air System 1. Component Cooling Hater System j. Demineralized Water System k. Reactor Coolant Drain System ~ 1. 480 VAC. Vital Electrical Distribution System C. FUNCTIONS REOUIRING VERIFICATION 1. Post Accident Sampling System 4 Collection and analysis of a Reactor Building _ atmosphere! a. sample. o. Collection and analysis of a Reactor Coolant System sample. c. Collection and analysis of a Decay Heat Removal _ System sample. I D. FUNCTIONS NOT REOUIRING VERIFICATION 1. Normal Reactor Sampling System functions a. The normal functions are part of the original system design, are all manual functions, and are.used on a routine basis. l E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. STP.430. " Post Accident Sampling System (PASS) Decay Heat System Sample functional Test" 2. STP.432, " Post Accident Sampling System Gaseous Functional Test"' 3. STP.433, " Post Accident Sampling System RCS Sample Functional Test" 4. STP.793, " Hydrogen Monitoring and Post-Accident Sampling. System Heat Tracing Functional Test" PM;F 210F 21 1 ____-_.__-____-_O

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ATTACHMENT 7 l 08-31-87 ) WP3478B D-0003B SYST M FUNCTIONAL TESTING ABSTRACT CONTROL ROOM / TECHNICAL SUPPORT CENTER A. SYSTEM FUNCTIONS 1. The Control Room / Technical Support Center (CR/TSC) essential air conditioning system is designed to provide a suitable environment i for equipment and to enhance station operator comfort and safety. l The CR/TSC essential air conditioning system is comprised of two j 100% capacity redundant trains, with.the following functions: a. Isolate the CR/TSC during a radiological event. i b. Isolate the CR/TSC during a toxic event. c: Provide cooling for the CR/TSC during radiological, toxic gas. CR high temperature or loss of offsite power events. ^ d. Pressurization. of CR/TSC to prevent infiltration of contaminated air. e. Provide fresh, filtered, conditioned supply air for.CR/TSC j during\\ radiological or loss of offsite power events. 1 B. FUNCTIONS VERIFIED BY OTHER SYSTEMS v n 1. SFAS start of the units on loss of offsite power. C. FUNCTIONS REQUIRING VERIFICATION 1. Control Room / Technical Support Center isolation during a radiological event. 2. Control Room / Technical Support Center isol.ation during a toxic event. 3. Cooling for the CR/TSC during radiological, toxic gas, CR high / . temperature or loss of offsite power events. 4. Pressurizing of CR/TSC to prevent infiltration of contaminated air during radiological events by pressurizing Control Room relative to outside atmosphere. 1 r 1_ PAGE 5 T 9

7. ATTACHMENT 7 S. Provide f resh, filtered, conditioned supply air for CR/TSC during radiological and loss of power events by maintaining a flow of 3200 CFM through the essential filtration units. D. FUNCTIONS NOT REQUIRING VERIFICATION i i 1. I'idividual component functions are tested during component testing. E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. STP.1059, "CR/TSC Ref rigeration Operational Verification (Train A)" and STP.1061, "CR/TSC Ref rigeration Operational Verification (Train B)", verify provision of ventilation and cooling for radiological, toxic gas, Control Room High Temperature or Loss of Offsite Power conditions. 2. STP.1104, "CR/TSC HVAC Composite Functional Test"., verifies system I functional performance, interlocks, controls and abnormal operations. ) 3. STP.961 A/B, " Loss of uf fsite Power", will also test the units in an emergency operation mode. h e \\ R n I W A e PAGE 6 0F 9

1 KITACHMENT 7 l 08/31/87 i HP3483B l 0-0184B j i SYSTEM FUNCTIONAL TESTING ABSTRACT j NUCLEAR SERVICE ELECTRICAL BUILDING HVAC 1 A. SYSTEM FUNCTIONS 1 The Nuclear Service Electrical Building (NSEB) Heating, Ventilating and Air Conditioning.(HVAC) Systems, both normal and essential, are designed to: 1. Provide a suitable environment for the electrical equipment and operators during normal and abnormal conditions. 2. Provide required environment and battery room exhaust for the NSEB. B. FUNCTIONS VERIFIED BY OTHER SYSTEMS 1. Instrument Air 2. 480 VAC 3. Interim Data Acquisition And Display (IDADS) S C. FUNCTIONS REOUIRING VERIFICATION 1. Heating, ventilating and air conditioning in NSEB. l D. FUNCTIONS NOT REOUIRING VERIFICATION l 1. None ] E.

SUMMARY

OF SYSTEM FUNCTIONAL TESTS TO BE PERFORMED 1. STP.1066 and STP.1067, " Operational Verification of the Refrigeration System for the Nuclear Service Electrical Building (NSEB) Essential HVAC System, Train A &'B," to functionally verify., operability of the refrigeration system when energizing Train A or B of the NSEB Essential HVAC System. L/ 2. STP.1096, " Functional Test of the Nuclear Services Electrical Building HVAC System," to verify overall system performance in both normal and off-normal operating modes. 1 PAGE 7 0F 9

1 i ?'* ATTAC10!ENT 7 HP34758/0-01448 i SYSTEM FUNCTIONAL TESTING ABSTRACT' i REACTOR BUILDING. VENTILATION' SYSTEM A. SYSTEM FUNCTIONS 1. Provide sufficient heat removal capability to maintain environmental control, human comfort and equipment protection during plant operation. 2. Provide sufficient heat removal capability' to' maintain the post-accident reactor building pressure below the design value. 3. Air filtration and circulation. 4. Reactor building purge. 5. Monitor and limit the hydrogen concentration. 1 6. Provide post accident filtering of inorganic' radioactive iodine and l organic methyl iodine in the combined air-stream form. i B. FUNCTIONS COVERED BY OTHER SYSTEMS 1. SP.422A " Refueling Internal Local Component Leak Rate Testing" t, (functionsof the Reactor Building purge valves) is covered by,the " PBS System. C. FUNCTIONS REOUIRING VERIFICATION + 1. The following functions need verification to assure a safe s operating plant. The emergency cooling system circulates the Reactor Buildkng.. a. air and provides for removal of heat released during accident conditions. b. The RB ventilation system provides, air circulation, filtration and cooling for normal operations. c. The hydrogen recombiners maintain. hydrogen concentrations below 4.0 percent.of the Reactor Building total air volume. d. Reactor Bis 11 ding purge system provides outside air circulation while providing control of radioactive particulate and gaseous releases. _1 PAGE 8 0F 9 t____________.________ m

NITACHMENT 7 d D. FUNCTIONS NOT REQUIRING VERIFICATION 1. Filter efficiency is verified by individual component testing (SP.211.03A/B, "RB Emergency Filter System Loop A and B"). 2. Purge functions are verified by SP.621, "RB Purge Exhaust Filter System." E.

SUMMARY

OF' SYSTEM FUNCTIONAL TESTING TO BE PERFORMED 1. STP.1099,'" Reactor Building Emergency Ventilation Functional Test": a. To demonstrate control.' logic / interlocks response to varying conditions in both manual and automatic modes. b. To verify design. flow' capacity through the cooling coils of. each A500 (A-D) unit. ~ c. Tn verify delta T's across cooling coils. 2. STP.1100, " Reactor Building Normal Ventilation Functional Test": a. To demonstrate and verify temperature distribution during normal operation of the plant. 'Q \\ a i i 1 v 4 b . PAGE 9 OF 9 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. _ _ _ _ _ _ _. -. _ _____:_______}}