Text

Revised Fire Protection Safe Shutdown Analysis:Compliance W/10CFR50,App R, Section Iii.G
	ML20039D634
Person / Time
Site:	Prairie Island
Issue date:	12/18/1981
From:	; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20039D631	List: ML20039D630; ML20039D634;
References
	TAC-11094, TAC-11095, NUDOCS 8201050290
	Download: ML20039D634 (110)
	v • d • e

{{#Wiki_filter:- l 9 NORTHERN STATES POWER COMPANY PRAIRIE ISIAND NUCLEAR GENERATING PIANT I UNITS 1 & 2 DOCKET NOS. 50-282 50-306 FIRE PROTECTION SAFE SHITfDOWN ANALYSIS COMPLIANCE WITH 10 CFR PART 50, APPENDIX R, SECTION III.C L L Prepared by: Gasser Associates Submitted: December 18, 1981 $$$1Sno! O b .F 1

r: IABLE OF CONTENTS Page 1.0 Introduction 1 2.0 Description of Functions and Equipment Required 2 for Hot and Cold Shutdown 3 2.1 General Description 2 2.2 Function 1 - Emergency Electrical Power Supply 3 2.3 Function 2 - Removsl of Decay Heat 4 2.4 _ Function 3 - Maintenance of the Reactor Coolant 6 Systen Inventory 2.5 Function 4 - Borate the Reactor Coolant System 8 to Cold Shutdown Xe Free Conditions 2.6 Function 5 - Cool the Reactor Coolant System to 8 Cold Shutdown Conditions 2.7 Function 6 - Monitor Critical System Parameters 8 ) 2.8 Support Functions 9 3.0 Description of Method of Analysis to 4.0 Results of Analysis 12 4.1 Primary Components and Equipment 12 4.2 Associated ~ Circuits 13 5.0 Corrective Actions 17 5.1 Hot Shutdown Functions 17 5.2 Cold Shutdown Functions 18 6.0 Plans and Schedules 19 e 7.0 Exemption Requests 20 ,o TABLE OF CONTENTS (cont) l i I TABLES ~ Page 1 Safe Shutdown Equipment List - Units 1 & 2 1-1 4 2 Safe Shutdown Equipment and Cable Matrices 2-1 3 3 Separation - Hot Shutdown Equipment 3-1 j in Conunon Fire Area 4 0 4 Separation - Cold Shutdown Equipment '4-1 1 in Conunon Fire Area 5 Valves Subject to Spurious Operation 5-1 FIGURES i 1 Cable Routing Tabulation - Example 22 i 2 Fire Hazards Sununary 23 i i l- ) -111- / ,, -,. - -, -. -... - ~. -..

1.0' INTRODUCTION This report was developed to describe the Safe Shutdown Analysis conducted for Prairie Island Nuclear Generating Plant, Units 1 1 and 2, in accordance with 10CFRSO Appendix R, Section III G, and the results of that analysis. Corrective actions, including plans and schedules for modifications, and exemption requests are also provided in this report. i f,. a 1 A l } i + e 4 I 1

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2.0 DESCRIPTION

OF FUNCTIONS AND EQUIPMENT REQUIRED FOR HOT AND (OLD , sg SHUTDOWN 2.1 General Description It has been demonstrated previously in the Prairie Island Final Safety Analysis Report that a loss of all a-c power to the station auxiliaries will not result in any adverse condition in the reactor e core as long as decay heat is transfered from the reactor coolant system. Additionally,.the analysis shows that there will be no loss of reactor coolant from the pressurizer relief valves. With this being the case, then the analysis must demonstrate that the fire will~ not affect the ability of the operator to (1) provide emergency electrical power, (2) maintain heat transfer from the reactor coolant system to the environment, (3) maintain reactor coolant inventory, (4) borate the reactor. coolant system to cold shutdown, Xe free (5) continue to cool the reactor coolant system to cold shutdown conditions, and (6) monitor critical reactor coolant system parameters. The systems which will be used to ( l fulfill the functions for safe shutdown are as follows. q) Function 1 - Provide emergency electrical power - emergency diesel generators, batteries, safeguards power buses, and associated distribution equipment Function 2 - Maintain heat transfer from the reactor coolant system to the environment - condensate storage tank, auxiliary feedwater, steam safety relief valves, power operated relief valves, cooling water system. Function 3 - Maintain reactor coolant inventory - charging system, safety injection system, RWST, component cooling system, cooling water system. Function 4 - Borate the reactor coolant to cold shutdown. Xe free - charging system, safety injection system, RWST, component cooling system, cooling water system. (3 [) Function 5 - Cool the reactor coolant system to cold shutdown \\~ / conditions - residual heat removal system,. component cooling system, cooling water system. Function 6 - Monitor critical system parameters - process instru-ments and sample system. The following is a description of the plant systems required to perform the desired functions listed above. The systems described are for one unit of this two unit plant. The description applies to both units. Two trains of equipment are designated for each function. A detailed equipment list is provided in Table 1 2.2 Function 1 - EMERGENCY ELECTRICAL POWER SUPPLY Instrument and Control Power Non-interruptible loads are automatically transferred to the battery-inverter sources of power. These include: a. The four safeguards instrument buses for both Units (Panels 112, 111, 114, and 113 for Unit 1 and Panels 211, 213, 214, fN and 212 for Unit 2). t') b. Control room annunciators. c. Computer buses (Panels 116 and 216). d. Public address and telephone systems. e. Emergency lighting, f. In general, any instrumentation needed for operation of safe shutdown equipment or for personnel safety. Emergency (Safeguards) A-C Power Two emergency diesel generators are provided which serve both units. The emergency diesel generatore will start automatically on loss of offsite power. Aloadrejectionandvoltaghrestor-ation scheme assures that the diesel generators are not overloaded. The diesel engines themselves are started using air reservoirs which need no external services except control signals powered from non-interruptible power. Fuel for the diesels is via gravity feed for the initial hours of operation. Fuel for subsequent op-(v) eration is supplied from the dedicated emergency diesel frol i

= (*g storage tank. The fuel transfer pump is powered from a safe-1x, guards bus. Cooling water inlet to the engine is via an air-operated inlet valve which' fails open. 4 Power Distribution In addition to the generation of emergency power, the appropriate power distribution equipment (safeguards buses and motor control centers) must remain free of fire damage to assure that safe shutdown equipment will function. Two independent trains of safeguards buses, DC panels and motor control centers, and cabling are provided. 2.3 Function 2 - REMOVAL OF DECAY HEAT Removal of decay heat after reactor trip is maintained by natural circulation within the reactor coolant loops. Feedwater must be supplied to the steam generators, where it absorbs heat and is -discharged as steam. Feedwater is supplied by the auxiliary feed-water system, and steam is discharged via the steam safety relief m ) vdives and the power operated relief valves. Auxiliary Feedwater Two auxiliary feedwater pumps are provided; one steam driven turbine pump and one motor driven pump. The steam driven aux-iliary feedwater pump starts automatically on a. loss of main feedwater pumps, and it will operate without additional electrical' power. It is driven by steam from the steam generators. The turbine auxiliary feedpump can be supplied with driving steam from either steam generator associated with that unit. The two steam isolation valves are motor operated valves powered from a safeguards bus and are maintained in the open position. The air operated steam inlet valve fails open on loss of air. A governor throttle valve is provided to prevent turbine overspeed. This valve is normally open. The driving steam exhausts to atmosphere. The turbine bearings are charged with oil once each 24 hours to assure sufficient lubrication will be available for turbine start-up. Once started, a shaft driven oil pump supplies lub-f-* rication for continued operation. U / The motor driven auxiliary feedwater pump is powered from the diesel generator and is automatically loaded according to the voltage restoration scheme. The oil pump which supplies lubri-cation for pump operation is powered from a safeguards power source. There are two sc. trees of water supplying the auxiliary feedpump. suction header. The first is the condensate storage system via a header which is normally supplied by both Unit 1 and 2 condensate storage tanks. The suction valves are kept in an open~ position to assure condensate will be available for the pumps. The second source of auxiliary feedwater suction is from the cooling water system. Supply valves to the punp suction are motor operated and powered from safeguards buses. The cooling water system also supplies water for turbine casing cooling and for lube oil cooling for both pumps. - The inlet valves are air operated fail open. The auxiliary feedwater pump discharge valves are maintained in an open position to assure auxiliary feedwater will be supplied to O da steam generators. Power Operated Relief Valves and Steam Safety Relief Valves Power operated relief valves are available for controlled release of steam from the steam generators thereby controlling cooldown. rate. These valves are air operated and have handwheels avail-able for manual operation. The power to these valves is supplied from safeguards buses. In addition, each steam generator is equipped with five self-actuating safety relief valves to assure a heat transfer path to the environment. These valves open at a pre-set pressure automatically and require no external actuation. Cooling Water System The diesel driven cooling water pumps start automatically on a loss of normal power to the motor driven cooling pumps. The engines themselves are started using air reservoirs which need no external services except control signals powered from the g non-interruptible power source. The receivers can be recharged from air compressors provided for each diesel cooling pump. Fuel for the diesels is provided via gravity feed initially. OV Fuel for subsequent operation is supplied from dedicated emer-gency diesel fuel storage tanks. Two tanks are provided with one normally aligned to each diesel, but with a manual cross-tie available for either tank to supply either diesel. Fuel transfer pumps are powered from safeguards buses. The cooling water pumps supply their own requirements for engine . jacket cooling and lubrication and gear oil cooling. An air op-erated' valve admits cooling water to the engine jacket cooling heat exchanger. The air supply is provided from the diesel starting reservoirs, and fails open (cooling water inlet open) on loss of air. No valves are required to change position to admit cooling water to the gear oil cooler. Cooling water pumps are sized so that one pump can supply the cooling requirements of both units. The pump discharges are manifolded so that either pump may supply either unit. !L) 2.4 Function 3 - MAINTENANCE OF THE REACTOR COOLANT SYSTEM INVENTORY Addition of wat'er to the reactor coolant system will be accomplished by using either charging system Train A or the safety injection system Train B. The Train A charging system utilizes a charging pump which is powered from_a safeguards power supply. The pump normally takes suction from the volume control tank. An alternate source of water provided for the charging pump is the refueling water storage tank (RWST) The RWST is maintained at a specified level of boron concentration. Water discharged from the charging pump enters the reactor coolant system through two normal flow paths. The first is the seal injection line which contains normally open manual valves and will be in service whenever the plant is in operation. The second path is via the normal charging line which will also be in service during plant operation. This line contains one air operated valve which fails open and one air operated valve which / ~~g) i fails closed with an open bypass line around it. x_,, i [) Seal leak-off from the reactor coolant pumps will return to the volume control tank. Component cooling water will be supplied to the seal leak-off return heat' exchanger to cool the water prior' to entering the volume control' tank. The Train B safety injection system utilizes a safety injection. pump which11s powered from a safeguards power supply.- The pump a will take water from the RWST through a normally closed motor valve powered from a safeguards power supply. The flow path from the pump to the reactor coolant system is maintained open. The valves are motor operated valves which are open and the: motor breakers are locked in the open position.. When the safety in-jection pump is used for adding water to the reactor coolant system, the component ' cooling system is required to cool the safety injection pumps. and to prevent damage to the reactor coolant pump seals. Component Cooling Water System ( Cooling for the seal water heat exchanger,' safety injection' pump, reactor coolant pump thermal barriers.and residual heat removal system will be provided by A and B trains of=the component cooling water system. The component cooling water system is~ designed to provide a closed cooling water loop which transfers heat from systems containing highly radioactive fluids to the cooling water system which uses i water from the river. Each train is provided with a pump, heat. exchanger.necessary piping and valves and a shared surge tank. The component. cooling pumps are powered from independent safeguards buses. The system is equiped.with motor operated valves to allow f either train of pump and heat exchanger to serve all safeguards cooling loads. These valves are powered from safeguards power sources. The cooling water system which cools the component cooling system has been previously described. 1

^N 2.5 Function 4 - BORATE THE REACTOR COOLANT SYSTEM TO COLD SHUTDOWN C' Xe FREE CONDITIONS Boration of the reactor core to cold shutdown conditions will be accomplished using the same systems as described above in Section 2.4. For boration, the charging system will use only the RWST as a source of water. 2.6 Function 5 - COOL THE REACTOR COOLANT SYSTEM TO COLD SHUTDOWN e CONDI".9NS The auxiliary feedwater system and the power cperated relief valves will be used as described in Section 2.3 to cool the reactor coolant system and reduce pressure until the coolant pressure is below 500 PSIG. Once below 500 PSIG the residual heat removal system will continue the cooling process to cold shutdown and then maintain those con-ditions as long as necessary. '~" The residual heat removal (RHR) system is designed to transfer decay heat from the reactor coolant system to the component cool-ing water system, and thereby eventually to the environment. It further has the ability to transfer water from the refueling water storage tank to the reactor for make-up. Two RHR trains are provided which each consist of suction piping to remove water from the reactor coolant system, an RHR pump, discharge piping to an RHR heat exchanger, and return piping for returning cooled reactor coolant to the reactor coolant system. Cross-over lines with manual valves are provided to allow either pump to operate with either heat exchanger. Power for pumps and motor valves for the two trains of RHR is provided by independent safeguards power sources. 2.7 Function 6 - MONITOR CRITICAL SYSTEM PARAMETERS Process Instrumentation System Decay heat removal, via natural circulation, and availability [' ' of a heat sink are observable by monitoring reactor coolant s system pressure' and temperature and steam generator level in at l least one steam generator. _ Maintenance of reactor. coolant system t inventory is monitored by pre ~ssurizer level. When cooldown has. progressed to the point of using the residual heat removal = system, monitoring of steam generator level is not necessary. The only 1 parameter needed to monitor maintenance of cold shutdown is reactor-coolant system temperature. Redundant process instrumentation channels are available for each of the above parameters. Sample System The process sample system is provided to allow a sample of reactor ) coolant to be drawn for chemical analysis. Reactor coolant chem-istry and in particular, boron concentration, will be monitored in this way. The system is equipped with series isolation valves and a sample cooler'for each sample point. The coolers are served by the component cooling system. 2.8 SUPPORT FUNCTIONS Station and Incerument Air System Three station air compressors powered from safeguards buses are provided which can supply filtered dehumidified air to control valves throughout the plant. The system also provides unfiltered air to the station air distribution system for maintenance and other service use. Isolation valves are provided which are capable of isolating the supply to the station air system in the event of a loss of pressure in that portion of the system which may threaten the supply for vital instrument use. One compressor only is required for instrument support. Two compressors, one from each train, were evaluated in chis analysis. O m -

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3.0 DESCRIPTION

OF METHOD OF ANALYSIS k J Appendix R requires that one of the two alternate systems intended to. ~ provide a hot shutdown function, must remain free of damage in the event of a fire in any single fire area, and that thi.a be demonstrated by analysis. The analysis was accomplished by identifying the' functions-required for hot and cold shutdown, and identifying the systems which could-perform those functions. Two alternate. systems or trains'of a single system were chosen which were then analyzed in detail. Within the chosen systems the portions of the system required to operate were identified, and the individual active components listed. The flow paths and circuits required were identified on P.& ID's, electrical drawings and circuit diagrams. A tabulation.of equipment, which *--in it belonged to, the time period in.which it was required to operate, control and power cabling serving the equipment, associated remote devices, and other information was assembled. Using NSP computer printout (NC-40099, 5-12-81, Cable Identification and Routing List) each cable identified-as required for safe shutdown was listed by system and then by function, i.e., from 125V distribution panel 26 to terminal box 2480, from terminal box 2480 to hot shutdown panel, etc. Also, the cable trays or conduit thru which each cable-passed were listed. This tabulation of information was set up so that A train ard B train functions were shown opposite each other. An example of the form of this tabulation is shown in Figure 1. Physical equipment arrangement drawings and cable tray arrangement drawings were obtained which also depicted fire area boundaries. Using' ~ i the previously prepared flow sheets and the drawings, each item of safe shutdown equipment was located and each cable tray or conduit serving s that equipment was traced to the fire areas in which the active comp-- .onents were found. A second tabulation was compiled similar to the c f first which indicated fire areas for each piece of equipment or cabling, j A column was provided in this tabulation for recording spatial separ-ation of trays carrying cables serving similar functions in redundant ~ trains. - lo -

These tables were then used to perform an area by area physical review \\ of the plant. The physical review was conducted on cable trays, equipment location, fire area characteristics, etc., on a two (2) part basis. 1. Where A & B trains were located and routed in separate fire areas, a visual inspection was made to assure that components were in the proper designated area. 2. Where system components or redundant trains were located in the same fire area, physical measurements were made to determine horizontal separation. If distance between cable trays or equipment serving redundant functions did not meet the minimum 20' separation criteria, the measurement was conservatively rounded to the lower whole figure. (Example - distance between trays LAG-TA24 and 1AG-TBS was measured at 7'-8", recorded as 7'.) In determining horizontal distance between cable trays or equipment in redundant divisions, no intervening combustible material or fire ~ hazards were permitted. Cables in cable trays or conduit were not considered to be combustible material for this purpose. e E 4.0 RESULTS OF ANALYSIS m ,,) 4.1 Primary Components and Equipment-The analysis. determined that areas exist within 'the plant where redundant components or cables for a hot or cold shutdown function are located within tna same fire area. Table 2 provides the results of the equipment and cable survey ~ in detail, giving each required component and the cabling for all primary and associated circuits which could affect component operation. This table is structured so that each train of equipment is shown on a separate page with redundant components arranged to fall on the same lines. The fire areas in which-the components and their cabling are located are indicated by X's. Spatial separation (SEP) refers to the minimum separation between any A Train and B Train component for. the same shutdown function. Table 3 lists, by fire area, the redundant hot shutdown components ( ) which fall within the same' fire area. Table 4 lists, by fire -area, the redundant cold shutdown components (not listed on Table 3) which fall'within the same fire area. Separation dictances are-also given. Tables 3 and 4 are simplifications of the.information in Table 2 and include only those safe shutdown components and cables not meeting the acceptance criteria of Appendix R, Section III.G. O t i v 4 f 4.2 Associated Circuits The definition of associated circuits is that given in Enclosure 2 to Generic Letter 81-12 dated February 20, 1981. Item (1) of this enclosure provides the following clarification: i - Safety related and non-safety related. cables that are associated. with the equipment and cables of the alternative, or dedicated method of shutdown are those that have a separation from the fire area less than that required by Section III.C.2 of Appendix R to 10 CFR 50 and have either (1) a common power source with the al-ternate shutdown equipment and the power source is not electrically protected from the post-fire shutdown circuit of concern by. coor-dinated circuit breakers, fuses or similar devices, (2) a connection to circuits of equipment whose spurious operation will adversely- ~ affect the shutdown capability, e.g., RHR/RCS Isolation Valves,' or (3) a common enclosure, e.g., raceway, panel, junction box, with alternative shutdown cables and are not electrically protected- ,_,) fc om the post-fire shutdown circuits of concern by circuit break-ers, fuses or similar devices. Associated circuits, included in categories (1) and.(3) of the above definition were evaluated as follows: All safety related, safe shutdown electrical loads are groupsd-together on a series of safeguards AC buses and motor control centers. During normal station operation and whenever of f-site electrical supply is 'available, the safeguards and normal loads are powered from common trans formers and buses. In the event of a loss of off-site power safeguard buses will automatically be disconnected form normal buses and will.be sequentially loaded onto the diesel generator units according to a load res toration scheme which assures the ui *el will not be overloaded. 4 \\

The safeguards loads are strictly separated into A train and p) ( B train loads providing redundancy for each function and com-ponent. Color coding is used throughout the plant to denote A train versus B train cables and cable trays serving the respective electrical loads. For plant system components, the coding scheme is orange denoting A train and green denoting B train. For plant safety related instrumentation the same division of redundancy ~ is observed and the colors white and blue denote A train instru-mentation and red and yellow denote B train. All cables and trays serving the various A and B train instrumentation and components are idelibly marked with the appropriate colors. No A train and B train cables are allowed to share the same cable trays. (The analysis uncovered one exception and it is addressed in section 5 of this report.) No safeguard cables are allowed to run in non-safeguards cable trays, and all cables within safeguards trays are color coded and treated as safeguards cables. This division and isolation of safeguards cabling not only covers O) safeguards power and control circuits, but also includes position ( indication circuits and all non-safety circuits connected to safeguards equipment; for example, a safeguards DC panel may power another ncn-safeguards instrument panel. The cable that connects the two is color coded and routed in safeguards cable trays all the way to the non-safety panel. Such cabling is also electrically protected by fuses or circuit breakers. In the course of the analysis all such associated circuits, not only primary power and control circuits, were identified and subject to the same separation criteria check. Additionally, the analysis verified that protective fuses or breakers were provided. Where problems were found, these have been listed in Tables 3 and 4 and corrective actions specified in section 5 of this report.

f%v) Associated circuits included in category (2) of the above definition were evaluated as follows: A number of valves were identified in this analysis, whose spurious operation could potentially affect proper function of a, . safe shutdown system. These valves fall into two categories. The first category includes passive motor operated valves in a safe shutdown system which are either open or closed in normal operation and do not have to change position for the system to function to achieve shutdown. The second category includes air operated control valves which fail safe if either power or air supply is cut off to the valve. The fail safe ~ position is one which does not hamper the ability of the system to function to-achieve shutdown. It has been postulated in the development of the Appendix R criteria that in certain circumstances fire damage to cables within the same tray could cause a hot short between power cables ~' causing a passive valve to change position or a fail safe valve-N' to remain in an uncontrolled and unsafe position. This is extremely unlikely at the Prairie Island facility since all AC and DC power is. carried in armored cable or conduit. The cable armor or conduit is grounded and the. cable trays carrying the. armored cable are-also-grounded. All power cables are connected to their power. sources through ci n it breakers or fuses. It is inconceivable that fire damage could occur to adjacent armored cables'where power conductors would short to each other without shorting to ground and opening the breaker or fuse. For safeguards valves whose spurious operation could affect shutdown, all power and control cables are trained with the associated safeguards train. These cable trays will be protected by fire' barriers, distance, automatic suppression systems, and automatic detection i systems provided for the associated safeguards shutdown system. 4 v

P .i 4 + s i-4 4 For non-safeguards valves whose spurious operation could affect shutdown, it has been determined that sufficient warning -of improper function will be available for -the plant.' operators to take corrective action and-manually position the valve or take

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some other compensating action. We believe this is permissible j since manual operation of normally remote or automatically operated safe shutdown equipment is permitted by the Appendix } R acceptance criteria. i. 6 All valves identifed in our analysis are lis.ted'in. Table 5. 4-l Plant safe shutdown procedures will identify each of these j valves, symptoms of improper function, and preventive or corrective 4 i action. 4 4 'f l. T i i i f-1 } } F p I + 1 i 1 4 i j t t 4, 1-

'5.0 Corrective Actions 5.1 Hot Shutdown Functions 5.1.1 Fire Areas #1 and #71 - Reactor Building, Units 1 and 2 { i No corrective action is required inside the containment j buildings. -All. safe shutdown cables are separated by at'.least 20 feet. 5.1.2 Fire Area #18 - Relay and Cable Spreading Room See exemption request 7.1. Control cables for. redundant power operated relief valves routed within the same tray in this area will-be're-routed to provide separation of at least.20 feet. 5.1.3 Fire Areas #31 and #32 - A and B-Train Hot Shutdown Panel and Instrument Air Rooms One train of power cables within these fire areas will be protected with an accepted one-hour fire barrier. The existing installed fire suppression systems will be expanded to. provide additional coverage to areas that are not currently. protected. These are spaces above- [ } adjacent fire areas. Fire detection equipment is already installed ~ ~ ' ' in this area. For control circuits from the hot -shutdown panels see exemption request 7.2. 5.1.4 Fire Area #41 - Screenhouse No corrective actions are required since all redundant cabling is separated by > 20', and automatic fire suppression system is pro-vided, and fire detection equipment is installed. 5.1.5 Fire' Areas #58 and #73 - Auxiliary Building Ground Floor, Units 1&2 One train of redundant cablingLin these fire areas will be protected-with.an accepted one hour fire barrier where those cables are < 20' feet apart. Automatic fire suppression systems will be installed in these areas to provide full area coverage. Fire detection equip-ment is already installed in this area. v .m

('~'g 5.1.6 Fire Areas #59 and #74 - Auxiliary Building Mezzanine Floor, ~ (,) Units i and 2 One train of redundant cabling in the'se fire areas will be protected with an accepted one hour fire barrier where those cables are < 20 feet apart. Automatic fire suppression systems will be installed in' these areas to provide full area coverage. Fire detection equip- -ment is already installed in this area. ~ 5.1.7 Fire Areas #60 and #75 - Auxiliary Building Operating Floor, Units 1 and 2 Control cables for redundant power operated relief valves' routed within the same tray in this area vill be re-routed to achieve adequate separation. If > 20' separation cannot be attained throughout the new route, then accepted one-hour fire barriers will be applied to non-complying segments. Automatic fire' suppression systems will be installed in these areas to provide' full area coverage. Fire detection equipment is already installed in this area. 5.1.8 Spurious Valve Operation - Preventive or Corrective Action j Written safe shutdown procedures will contain provisions -/ for operator action to prevent or compensate for spurious operation of valves located in, or having power or control cables routed through, each fire area. 5.2 Cold Shutdown Functions Procedures will be developed which address the checkout and repair of cold shutdown functions that may be damaged in a fire. Materials will be stocked on site which will be required to make repairs or replacements. O 4 n< s_- !- _. _. - ~. -. _,. - -, _ -. _ _.. - _. -.

6.0 Plans and Schedules Corrective actions described.in Section 5 will be scheduled for completion in accordance with-the following schedule: Description Completion Date a. .One-hour fire barriers August 17, 1981-ou one train of redundant cables in fire areas 31, 32, 58, 59, 73, 74, and possibly 60 and 75. b.- Extension of fire suppres-January 1, 1983 sion systems for fire areas 31 and 32. c. Procedures for hot shut-August 17, 1981 down.(including spurious valve operation) and cold shutdown (including necessary repairs). d. Stocking of materials on August 17, 1982 site required to make repairs to postulated g fire damaged cold shut-( down equipment. e. New automatic fire suppres-January 1, 1983-sion. systems for fire areas 58, 59, 60, 73, 74, and 75 e 7.0 Exemption-Requests i s' 7.1 Fire Area #18 - Relav and Cable Spreadine Room s Exemption - Relief is requested from the requirement to provide a one-hour barrier around DC distribution panels 15, 16, 26, and 26 and cables to _ panels 151, 161, 251, and 261. Relief is requested from the requirement to provide a one-hour barrier around auxiliary feedwater pump control circuits. Basis - Providing an effective barrier around these panels, cables, and control circuits is judged to be virtually impossible. No ignition sources are located in this area. The fire loading consists entirely' of low flammability cable insulation. The area is protected by ionization detectors and an automatic heat actuated Cardox total flooding system which will achieve a minimum carbon dioxide concentration of 50%. The system is sized to allow a second flooding action of the same volume which will achieve a concentration of about 70% carbon dioxide. Local manual control of-the auxiliary feedwater pumps can be taken in the g-g event of damage to the normal control circuits. Safe shutdown procedures (_,) will provide for this possibility. 7.2 Fire Areas #31 and #32 - A and B Train Hot Shutdown Panels and Instrument Air Rooms Exemption - Relief is requested from the requirement to provide a one-hour fire barrier around control circuits from the shutdown panels to the auxiliary feedwater pumps located in the opposite hot shutdown areas (the s area containing A hot shutdown panel contains B turbine auxiliary feedwater pump and vice versa). Basis - Providing an effective barrier around these control circuits is judged to be' impractical. These circuits are now enclosed in conduit which provides physical protection and some fire resistance. The areas in question have a light fire loading. The turbine auxiliary feedwater pumps are designed to run AC free and require no outside control once started. They are provided with mechanical governor valves. Motor operated auxiliary feedwater pumps s s,/ can be started locally from the motor starters and cross connected to the other unit's_ steam generators. Safe shutdown procedures will provide i for these' options. t

7.3 Schedule for Installing Additional Suppression Svsters Exemption - Iteus (b) and (c) of the corrective actions described in Section 6 of this report require an exemption from the implementation date in paragraph (c) (2) of 10 CFR PArt.50, Section 50.48 in addition to the schedule relief requested in our March 13, 1981 exemption request. Basis - Design and installation of the required automatic suppression systecs cannot be accomplished in less than ten to twelve months. We expe ct the installation to be complicated by clearance problets with installed equipaent near the ceiling in the areas to be protected and the need to carefully schedule and control work in critical plant areas Additional time to complete these suppression systems will not compromise the health and safety of the public. These areas now have automatic fire detection systems, hose stations for manual fire fighting, and portable extinguishers. ' A fire brigade of five trained individuals is available Ib) on site at all times to respond to a fire. The plant is within the municipal boundary of Red Wing, Minnesota. This city has an exception-ally well qualified and equipped fire department. 4 v)

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SUMMARY

sOR TM E.R P. S.T.A T E.S.PO.W..E.R C.oa.P AfdV FIGL'RE 2

.m. 23 - b

y TABLE 1 SAFE SHUTDGJN EQUIPMENT LIST - UNITS 1 & 2 6 4 e O l i 1 O 1-1

i ) t I t I t j .~,t e 1 I g g-l t I i 4 i 44 k, O E ,f4 \\1 I ~. ~ N ( u s ~ ~ a h [ fi' k T d g \\ M d ) e N k A w A 2 b ( k d d h. U I 4 01 N W g h 4 1 ' { l A d [ ( s n t ( '4 > I i t % { s 4 3 1 t s n s } 9 d } d d 4 4 I l 4 4 (d t 2' 5 $,s tc, i. d s-e n t 2 d a e a e ~ ~ s <s ,n o s. m 'e 4 g g c b "y ,_.. =_ c4 g m n 5 ~ ~d O n w Il p. t d I L M, 1 f +l y ,,' I (f) $(i t '4< s) 4 + e Al 1 I /l D i i i =-.._ 41 s, $a O W i g 1 s s c ~ n + gl 'J M \\ N 4 4 4 y ) q g p% ) e Q h d ( d h i d ( k d R /,l t c c U v .e v i s v 3. v x s O 4 t q N'_- . n ei d, Y 'a \\-. y ej SJ N u O s \\- N E s.,N N M [ k % D = h g L') 4. c - + - g ~ i + = w *= ae a a

s-O R

S 4 w = r s .r 1._,4-h w g s = = q = s _q _, C S ~ e ,,\\~ \\ a V E d t .A t i -,s, l* .D .i e l 11 ,'- x W .'>1

[-

l l / yJ t y .J i, l i ~ a, < { i v i O ft l j 1-2

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o. 9 n

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r m

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"1 U

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a M.

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P7

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r. 3+g a

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4. a. e n,d c

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6 i -4 e ~ l { g ? i ti. t [ C y g v. a n \\ r ( 'k g$ g N../ w w y( t 0 0 }y. L, u t s

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4 g

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s U

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a qE O d

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l 1 ~L i t l .A/ t.,u 1 v t t e 0 .= s e 6 1 M 4 ;- 3, L [ Q 4 + a e n a y e C o y F N N C o 9 T N ft 6' ) 2 i n n a m r ~ n a e m. i d s e m m a e 7) .d q Cf h, 9 A h A a i h ( k '3 h Q a i a v v E 3E t N 4 + ,e 'Ab s a C / g ( L. M-. [ T J %,}. i M 4 ,N Y 4 Q d i 3g 4 4 1 e. ( j s- -4: Cr i 4 K,/ 6j o .2

p 3.

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TABLE 3 Sepsrction - Hot Shutdown Equipmint in Common Fire Arso 01 Table 3 lists by fire area the redundant hot shutdown systems which fall within that fire J area, and the separation distance. 4 i Unit 1 Fire Area #1 - Reactor Building Ionization and Smoke Detectcrs Provided Manual Suppression Equipment Provided i Minimum Train Comoonent or Cable Separation l A 125V DC Power from Containment Penetration C-3 to DC Panel 153 B 125V DC Power from Containment Penetration D-?.:o DC Panel 163 >21' A Pressurizer level instrument ILT-427 and cable i B Pressurizer level instrument ILT-426 and cable >21 ' A ' Steam generator l'evel instrument ILT-487 and. cable B Steam generator level instrument ILT-488 >21' ~ A RCS temperature instrument ITE-450A and " f cable (T ) h \\. B RCS temperature instrument ITE-451A and j cable (Tp,) >21' A RCS temperature instrument ITE-450B and cable (Te) B RCS temperature ins trument ITE-451B and cable (T ) >21' e A RCS pressure instrument IPT-709 and cable i. B RCS pressure instrument IPT-710 and cable >21' t E a l i e O 3-1
Fire Ares #18 - Relay and Cable Spreading Room (Serves Unit 1 & 2) 'g . Ionization and Thermal Detectors Provided Automatic CArdox Flooding System gehieves Mit'imum 50% Co., Concentration) Manual Suppression Equipment Provided Minimum Train Comoonent or Cable Separation A 125V DC Panel 15 and Cables to Pnl 151 B 125V DC Panel 16 and Cables to Pal 152 8' l A Control Cables for CV-31084 Power Operated Relief Valve B Control Cables for CV-31089 Power Operated Within Relief Valve Same Tray A Control Circuits for 11 Auxiliary Feed-water Pump B Control Circuits for 12 Auxiliary Feed- ~ water Pump 3' A Control Cables for D-1 Emergency Diesel p Generator s. B Control Cables for D-2 Emergency Diesel Generator >21' A Control Cables for Charging Pump B Control Cables for Safety Injection Pump >21' A Control Cables for CV-31300" Hot Sample Valve B Control Cables for CV-31301 Hot Sample Valve >21' j. A Cable for pressurizer level ins trument ILT-427 m l B Cable for pressurizer level instrument ILT-426' >21' 1 l A Control cable for CV-31798 s team inlet valve to 11 turbine auxiliary feedwater pump B Control cable for 12 motor driven auxiliary feedwater pump T21' f et s f sL
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~ t 4 .y i~ 1' Fire Area #31 "A" Train Hot Shutdown Panel and Instrument Air Room 4 Ionization and Thermal Detectors Provided Wet Pipe Sprinkjer System Provided 3 Manual Suppression Equipment Provided 3j Minimum g Train' Component of Cable Separation ^ A ' Circuits from A Hot Shutdown Panel to 11 s Auxiliary Feedwater Pump a A. ~ 3 Circuits from B Hot Shutdown Panel to 12 _ Auxiliary Feedwater Pump 3' Fire Area #32 "B" Train Hot Shutdown Panel and Instrument Air Room ? ~ Ionizction and Thermal Detectors Provided i Wet Pipe Sprinkler System Provided i. Manual Suppression Equipment Provided I i Minimum [ Train. Component of Cable ' Separation D. A 125V DC Cable from Panel 11 to 4KV Bua 15 B' 125V DC Cable from Panel 12 to 4KV Bus'16 S' l A 125V DC Cable from Panel.ll to Panel 15 s B 125V DC Cable from Panel 12 to Panel 16 8' f' A DC Cable from Panel 11 to Diesel Generator
+
D-1 4 B DC Cable from Panel 12 to Diesel Generator D-2 8' e 3 A 125V DC Cable from Panel 11 to Bus 110 f' B 125V DC Cable from Panel 12 to Bus 120 7' -i A Power Cable from-MCC 1A1 to MCC 1ACl 3 .Pcver Cable from MCC 1A2 to MCC 1AC2 8' B 1 A Circuits from'A Hot Shutdown Panel to 11 Aux'iliary Feedwater Pump B Circuits from B Hot shutdo"n Panel to 12 p- ' Auxiliary Feedwater Pump 3' ~\\ t 4- '* W A- ,MCC,1Al g i B
~~~~MCC TA2~~~~
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i 4 8 i. l Fire Area 432 - continued j r i 1 r. i Minimum i-Train-Component of Cable Separation i: .A Cable for steam generator level instrument ILT-487 l t . B Cable for steam generator level instrument > 21 ' .ILT-488 A Controlland-power cables for CV-31998 steam j-inlet valve to 11. turbine auxiliary i feedwater pump B Control and power cables for '12 motor driven. j-auxiliary feedwater pump i 1 h l<- g i f t k t 1 l - l e f-k I 3-4 .__.,____....-~...m,-__.-_,,_.m.
_ [ Fire Area #41 - Screenhouse \\ _-i Ioniza' tion and Thermal Detectors Provided Automatic Pre-Action Sprinkler System, Manual Fire Suppression Equipment Provided Minimum Train-Component of Cable Separation A 12 Diesel Cooling Water Pump B 22 Di+sel Cooling Water Pump >21' A 12 Diesel Cooling Water Pump Oil Transfer Pumps and. Cabling B 22 Diesel Cooling Water Pump 011 Transfer Pumps and Cabling >21' U Fire Area #58 - Auxiliary Building Ground Floor Ionization and Smoke Detectors Provided Automatic Wet Pipe Sprinklers in Stairwells Manual Suppression Equipment Provided Minimum [ l-Train Component of Cable Separation \\- / A Refueling Water Storage Tank (RWST) to Charging Pump Inlet Valve and Cables, MV-32060 B RWST to Safety Injection Pump Inlet Valve and l Cables, MV-32080 10' A Cooling Water to 11 Component Cooling Heat Exchanger, Inlet Valve, MV-32145 B Cooling Water to 12 Component Cooling Heat Exchanger, Inlet Valve, MV-32146 6' A Cables from Diesel Generator D-1 to Bus 15 B Cables from Diesel Generator D-2 to Bus 16 (Via Bus 25) >21' 'A MCC 1K1 L MCC 1K2 >21' A 125V DC Cables from Panel 11 to Diesel Generator D-1 3 B 125V DC Cables from Panel 12 to Diesel Generator D-2 >21' %/ '3-5
Fire Areas # 58 - continued Minimum Train Component or Cable Separation t'~ A Diesel Generator D-1 Control Cables B Diesel Generator D-2 Control Cables .>21 A Power Cable to Charging Pump B Power Cable to Safety Injection Pump >21' A Charging Pump B Safety Injection Pump >21' A il Component Cooling Water Pump and Power Cable B 12 Component Cooling Water Pump and Power ' Cable (see note 1) >21' Fire Area #59 - Auxiliary Building Mezzanins Floor Ionization Detectors Frovided Automatic. Wet Pipe Sprinklers in Stairwells Manual Suppression Equipment Provided Minimum { Train Component or Cable Separation A 125V DC Cables from Panel 11 to Bus 110 B 125V DC Cables from Panel 12.to Bus 120 7' A Power Cable from Bus 15 to Transformer 101 B Power Cable from Bus 16 to Transformer 102 7' A Power Cable from Bus 110 to MCC lAl B Power Cable from Bus 120 to MCC 1A2 7' A Power Cable from Bus 110 to MCC 1K1 B Power Cable from Bus 120 to MCC 1K2 A Power Cable from Bus 110 to MCC IL1 B Power Cable from Bus 120 to MCC IL2 10' A Power Cable from Bus 110 to MCC ILAl-B Power Cable trom Bus 120 to MCC lLA2 18' A 125V DC Cable from Panel 15 to Panel 151 B 125V DC Cable from Panel 16 to Panel 161 >21' o 3-6
Fire Area #59-- continued Minimum f' Train-Component or Cable Separation A 125V DC Cable from Panel 15 to Penetration C-3 B 125V DC Cable from Panel 16 to Penetration D-3 >21' A Control Cable for Hot Sample Valve CV-31300 B Control Cable for Het Sample Valve CV-31301 >21' ~A Cable for pressurizar level instrument ILT-247 B Cable for pressurizer level instrument ILT-426 7' A Cable for steam generator level instrument ILT-487 ^ B Cable for steam generator level instrument ILT-488 6' A Cable for RCS temperature instrument ITE-450A (Th) B Cable for RCS temperature instrument ITE-451A (Th) 6' A Cable for RCS temperature instrument ITE-450B (T ) c B Cable for RCS temperature instrument ITE-451B (T ) 6' c A Cable for RCS pressure instrument IPT-709 B Cable for RCS pressure instrument IPT-710 6' t e - O 3-7
i J Fire Area #60 - Auxiliary Building Operating Floor. s Ionization Detectors Provided Automatic Wet Pipe Sprinklers in Stairwells Manual Suppression Equipment Provided Minicun Train Componcnt or Cable Separation A Control Cables for CV-31084 Power Operated i Relief Valve i B Control Cables for CV-31089 Power Operated Within Relief Vavle Same Tray _ i A MCC ILAl [ B MCC ILA2 >21' a i NOTE 1: Component cooling water pumps 11 and 12 are physically located in fire areas 58 and 73 respectively. These two areas are divided by an imaginary ' barrier which indicates the division between Unit 1 and Unit 2. This ima-3- ginary barrier has been used in all previous fire analysis and is main-tained herein to eliminate confusion from a change of fire area designa-tion. The pumps are physically separated by >60'. The component cool-ing water pumps are the only compo- + nents which are separated by this imaginary barrier. No credit was taken in the analysis for the existence of a real barrier. d i O }L 3-8 4 m-....- m. e,~. ..,_r_. .,..,...g.,,..- ,-,,.,m...-vc.,,y_. ..e.- .mf ,1--. , e
Unit 2 U Fire Area #18 - Relay and Cable Spreading Room for Protection Features See Unit 1 Minimum-Train Component or Cable Separation A 125V.DC Panel.25 and Cables to Panel 251 B -125V DC-Panel 26 and Cables to Panel 261 8' A Control Cables for Powcce Operated Relief Valve CV-31102 B Control Cables for Power Operated Relief Within Vavle CV-31107 Same Tray A Centrol Circuits for 21 Auxiliary Feed-water Pump B Control Circuits for 22 Auxiliary Feed-water Pump' 3' A Control Cables for D-2 Emergency Diesel-Generator B Control Cables for D-1 Emergency Diesel Generator- >21'- m) ~ A Control Cables for Charging Pump B Control Cables for Safety Injection Pump >21' A Control Cables for CV-31307 Hot Sample Valve-B Control Cables for.CV-31308 Hot Sample Valve >21' A Cable for pressurizer level instrument ILT-427 B Cable for pressurizer level instrt4 ment 2LT-426 >21' A Control cable for 21 motor auxiliary feedwater Pump B Control cable for CV-31418 steam inlet valve to 22 turbine auxiliary feedwater pump Y 3-9
Fire Area - #31 "A" Train Hot Shutdown' Panel and Instrucent Air Room For Protection Features See Unit 1 Minimum ex Train Cocoonent or Cable Seoaration A 125V DC Cable from Panel 21 to Penel 25 B 125V DC Cable from Panel 22 to Panel 26 8' -A 125V DC Cable from Panel 21 to Panel 210 B 125V DC Cable from Panel 22 to Bus 220 8' A Power Cable from MCC 2Al to MCC 2ACl B Power Cable from MCC 2A2 to MCC 2AC2 8' A Circuits from A Hot Shutdown Panel to 21 Auxiliary Feedwater Pump B Circuits from B Hot Shutdown Panel to 22 Auxiliary Feedwater Pump 3' A 125V DC Cable from Panel 21 to 4KV Bus 26 B 125V DC Cable from Panel 22 to 4KV Bus 25 8' A MCC 2Al B MCC 2A2 >21' A Control and power cable for 21 motor auxiliary Feedwater Pump B Control and power cable for CV-31418 steam inlet valve to 22 turbine auxiliary feedwater pump Fire Area #32 "B" Train Hot shutdown Panel and Instrument Air Room For Protection Features See Unit 1 Minimum Train Component or Cable Separation A Circuits from A Hot Shutdown Panel to 21 Auxiliary Feedwater Pump B Circuits from B Hot Shutdown canel to 22 Auxiliary Feedwater Pump 3' ] (d' 3-10 j
Fire Arc. #59 - Auxiliary Building Mezzanine Floor Ionization Detectors Provided .p Automatic Wet Pipe Sprinklers in Stairvells Manual Suppression Equipment Provided Minimum Train Component or Cable Separation A-Cable for RCS temperature instrument 2TE-450A (T ) h B Cable for RCS temperature instrument 2TE-451A (T ) 0' h A Cable for RCS temperature instrument 2TE-450B (T ) c B Cable for RCS temperature instrument 2TE-451B (T } 0' c Fire Area #71 - Reactor Building Ionization Detectors Provided Manual Suppression Equipment Provided Minimum Train Component or Cable Separation A Pressurizer level instrument 2LT-427 and cable B Pressurizer level instrument 2LT-426 and cable >21' A Steam generator level instrument 2LT-487 and cable B Steam generator level instrument 2LT-488 and cable >21' A RCS temperature instrument 2TE-450A and cable (T ) h B RCS temperature instrument 2TE-451A and cable (T )
~~~~21' h~~~~
~ A RCS temperature instrument 2TE-450B and cable (Te) B RCS temperature instrument 2TE-451B and cable (T ) > 21' c A BCS pressure instrument 2PT-709 and cable B RCS pressure instrument 2PT-710 and cable > 21 ' A 125V DC Power from Penetration C-1 to Panel 253 B 125V DC Power from Penetration C-3 to Panel >21' 263 3-11
J Fire Area #73 - Auxiliary Building Ground Floor Ionization Detectors Provided Automatic Wet Pipe Sprinklers in Stairwells Manual Suppression Equipment Provided Minimum Train Component or Cable Separation A RWST to Charging Pump Inlet Valve and Cables, MV-32062 B RWST to Safety Injection Pump Inlet Valve and Cables, MV MV-32183 10' A-Cooling Water to 21 Component Cooling Heat Exchanger, Inlet Valve MV-32160 B Cooling Water to 22 Component Cooling Heat Exchanger, Inlet Valve MV-32161 6' A Power Cable from Bus 210 to MCC 2K1 B Power Cable from Bus 220 to MCC 2K2 >21' ('y (,/ A Charging Pump and Power Supply Cable B Safety Injection Pump and Power Supply Cable >21' A 21 Component Cooling Water Pump and Power Cable B 22 Component Cooling Water Pump and Power Cable (see note 2) >21' Fire Area #74 - Auxiliary Building Mezzanine Floor Ionization Detectors Provided Automatic Wet Pipe Sprinklers in Stairwells Manual Suppression Equipment Provided Minimum Train Component or Cable Separation A Power Cable from Bus 26 to Transformer 201 B Power Cable from Bus 25 to Transformer 202 8' A 125V DC Cable from Panel 25 to Panel 251 B 125V DC Cable fran Panel 26 to Panel 261 8' fs A 123V DC Cable from Panel 21 to Bus 210 - \\- ') I B 125V DC Cable from Panel 22 to Bus 220 8' 3-12
Fire Area d 74 - continued 4 -Minimum Train Component or Ceble Separation A-Power Cable from Bus 210 to MCC 2Al 3 Power Cable from Bus 220 to EC 2A2 8' A Power Cable from Bus 210 to MCC 2K1 B Power Cable from Bus 220 to MCC 2K2 9' A Power Cable fr'om Bus 210 to EC 2L1 B ' Power Cable from Bus 220 to EC 2L2 9' ~ A Power Cable from Bus 210 to EC 2IA1 B Power Cable from Bus 220 to EC 2IA2 9' A 125V DC Cable from' Panel 25 to Penetration C-1 B 125V DC Cable from Panel 26 > 21' to Penetration C-1 A Control Cable for Hot Sample Valve CV-31307 B Control Cable for Hot Sample Valve > 21' CV-31308 l l A. Cable for Pressurizer Level Inst 2LT-427 j B Cable for Pressurizer Level Inst 2LT-426 7' A Cable for Steam Gen Level Inst 2LT-487 B Cable for Steam Gen Level Inst 2LT-488 6' ~ A Cable for RCS Temperature Inst 2TE-450A Th B Cable for RCS Temperature Inst 2TE-451A T 0' h A Cable for RCS Temperature Inst 2TE-450B Tc B Cable for RCS Temperature Inst 2TE-451B T 6' e A Cable for RCS Pressure Inst 2PT-709 B Cable for RCS Pressure Inst 2PT-710 6' 'Q) i 3-13
4 Fire Area #75 - Auxiliary Building Operating Floor rs lonization Detectors Provided f g ( ) Automatic Wet Pipe Sprinklers in Stairwells 1 Manual Suppression Equipment Provided ) Minimum Train Component or Cable Separation A Control Cables for CV-31102, Power Operated Relief Valve B Control Cables for CV-31107 Pouer Operated Within Relief Valve Same Tray A MCC 2LAl 8 McG 2LA2 221' ,- s tb' Note 2: Component cooling water pumps 21 and 22 are physically located in fire areas 58 and 73 respectively. These two areas are divided by an imaginary barrier which indicates the division between Unit 1 and Unit 2. This imaginary barrier has been used in all previous fire analysis and is maintained herein to eliminate confusion from a change of fire area designation. The pumps are physically separated by 60'. The component cooling water pumps are the only components which are separated by this imaginary barrier. No credit was taken in the analysis for the existence of a real barrier. \\ / sm-3-14
m TABLE;4 ' Separation - Cold Shutdown Equipment in Conunon Fire Areas } f-- . Table 4 lists by fire area the Tedundant cold k shutdown systems which fall within ASat' fire area, and the separation distance. Where a- _. system or ' component previously listed in: Table 3 for.how shutdown, it is not repeated here. j TABLE 4-i Unit 1~ Fire Area #1 Reactor Building See Table 3, Unit 1 for Protection Features i Minimum Train Component or Cable - Separation i A Power and Control Cables to RHR Suction. Valves. MV 32164 and MV 32165 l .B-Power and Control. Cables to RHR Suction Valve, 1. MV 32230 and MV 32231 >21' r A Power and Control Cables to l'10t Injection Valve, MV-32064 4 f B Power and Control Cables to RHR Injection s-m Valve MV-32065 >21' f ' Fire Area #58 - Auxiliary Building Ground Floor - See Table _3, Unit 1 For Protection Features. l ~ Minimum Table Component or Cable-Separation A Power Cable from Bus 15 to 11 RHR Pump B Power Cable from Bus 16 to' 12 RER Pump >21' A 11 RER Pump >21' and installed - in separate con-3 12 RER Pump crete. pits 1 Fire Area #59 - Auxiliary Building Mezzanine Floor See Table 3, Unit 1 for Prot.ection Features Minimum ~ Table Component or Cable Separation 4 i d-A Power and Control Cables to RRR Suction Valves, MV-32164 and MV-32165 B Power and Control Cables to RRR Suction Valves, MV 32230 and MV 32231 >21' ) \\,,. i i-4-1 1 2 --..._, _ -..._ _. _ - _. ~ ..4 -, -. - - -,,,.., -,,., - -, -. - -. ~. -. -
Minimum Train Component or Cable Separation A-Power and Control Cables to RHR Injection Valve MV-32064 B Power and Control Cables to RHR Injection Va'lve NV 32065. >21' Fire Area #60 - Auxiliary ' Building Operating Floor See-Table 3, Unit 1 for Protection Features Minimum Train ' Component or Cable ' Separation- ? A Power and Control' Cables to RHR Suction Valves, MV-32164 and MV-32165 B Power and Control Cables to RHR Suction Valves, MV-32230 and MV 32231 >21' A Power and Control Cables to RRR Injection Valve MV-32064-B Power and Control Cables to RHR Injection-Valve MV_32065- >21' \\. F i .a 4-2
t Unit 2 Fire / ea #18 - Relay and. Cable Spreading Room .See Table ~3, Unit 1 for Protection Features Minimum Tabli Component or Cable Separation A Control Cable for RHR Suction Valves i MV-32192 and MV-32193 i B Control Cable fo-RER Suction Valves ~MV-32232 and MV-32233 >21' A Control Cable for RER Injection Valve 1 MV-32167 B Control Cable for RHR Injection Valve MV-32168 >21' i l Fire Area #71 - Reactor Building See Table 3, Unit 2 for Protection Features Minimum s Train Component or Cable Separation A _ Power and Control Cables for RHR Suction ( Valves MV-32192 and MV-32193 4 B Power and Control Cables for RHR Suction Valves MV-32230 and MV-32231 >21' A Power and Control Cables for RHR Injection . Valve MV 32167 B Power and Control Cables for RHR Injection Valve MV-32168 >21' Fire Area #73 - Auxiliary Building Ground Floor l' See Table 3, Unit 2 for Protection Features i Minimum j Train Component or Cable Separation i A Power Cable from Bus 26 to 21 RHR ramp o B Power Cable from Bus 25 to 22 RHR Pump 6' i A 21 RHR Pump ~ >21' and installed in Separate con-B 22 RHR Pump crete pits l '\\ ~ ~~ > 4-3 i
4 1 Fire Area _#74 - Auxiliary Building Mezzanine Floor N- 'See Table 3, Unit 2 for Protection Features Minimum Train Component or Cable Separation A Power and Control Cables.for RHR Suction Valves MV-32192 and MV-32193' B Power and Control Cables for RHR Suction Valves MV-32230 and MV-32231 >21' A Power and Control Cables for RHR Injection valve MV 32167 B Power and Control Cables for RHR Injection Valve MV-32168 >21' 4 4 ~ i Fire Area #75 - Auxiliary Building Operating Floor See Table 3, Unit 2:for Protection Features 4 Minimum Train Component or Cable Separation A Power and Control Cables for RHR Suction Valves MV-32192 and MV-32193 B Power and Control Cables for RHR Suction p) { Valves MV-32230 and MV-32231 ->21' A ' Power and Control Cables for RHR-Injection Valve MV-32167 B Power and Control Cables for RHR Injection f Valve MV-32168 ~ >21' 4 i I-(. o r (. ,) 44 y -,,,- -. ~ ,e,---- --y,...%,,,*,,,--.<.,.mw.-,m,.+,,,-g% y.,-. y.n,.,,, w -m ,,-3.,, ---,--~w-, e<-yc-- p -,w- ,-w, - -, - -, - - - + e ,--m-
s TABLE 5 Valves Subject to Spurious Operation s j PASSIVE MOTOR OPERATED VALVES SYSTEM VALVE POSITION NORMAL FUNCTION Condensate Supply MV32333 LO Supplies condensate to auxili-MV32335 LO ary feedwater pumps (see note 1) MV32336 LO MV32345 LO MV32041 NC Fills hot well from condensate MV32042 NC storage tank t Auxiliary MV32246 LO Supplies auxiliary feedwater Feedwater MV32249 ID to the steam generators (see MV32237 LO note 1) MV32238 LO MV 32381 LO MV 32382 LO MV 32243 LO MV 32242 LO MV 32283 LO MV32384 LO MV32247 LO V MV32246 ID Cooling Water MV32332 NO Discharges cooling water MV 32334 NO to circulating water system Main Steam MV32016 LO Supplies steam to turbine MV32017 LO auxiliary feedwater pun-- (see. i MV32019 LO note 1) i. MV32020 L0 Charging System MV32199 NO Containment isolation for MV32166 NO-return flow from reactor coolant pump seal leak off MV32061 NO Provides flow from volume (Alternate source control tank to charging pump is RWST which is protected) l. Safety Injection MV32163 LO Provides flow from RWST to MV32191 Lo safety injection pump (see \\ note 1) %/ 5-1 i
SYSTEM VALVE-POSITION NORMAL FUNCTION Safety Injection MV32074 NO Containment isolation for (con'f.) MV32177 NO safety injection discharge to reactor coulant system (see note 1) Component MV32200 NO Isolates component cooling Cooling MV32201 NO. surge tank from pumps MV32211 NO MV32212 NO MV32121 NO Certain combinations allow MV32267 NO isolation of various branches MV32266 N0 for alternate pump operation MV32120 NO MV32122 NO MV32269 NO MV32123 NO MV32268 NO MV32093 NO Isolates component cooling MV32094 NO to RHR heat exchanger O MV32128 NO Q MV32129 NO MV32126 NO Containment isolation for MV32124 NO component cooling to reactor MV32089 NO coolant pump seals MV32091 NO i FAIL SAFE CONTROL VALVES Auxiliary CV31681 F0 Supplies cooling to turbine Feedwater CV31684 F0 auxiliary feedwater pumps and oil coolers l CV32682 F0 Supplies cooling to motor O CV31683 FO auxiliary feedwater pump and oil cooler i Cooling Water CV31423 F0 Provides cooling for diesel CV31457 F0 ' cooling pump engine jacket cooling heat exchanger LO 5-2
_-m SYSTEM VALVE POSITION NORMAL FUNCTION N Cooling wate-CV31506 F0 Provides cooling water to (con't.) CV31505 F0 diesel generator engine jacket coolers Charging CV31336 F0 Reactor coolant pump seal CV31335 FO leakoff isolation (see note 2) CV31426 F0 CV31427 F0 CV31328 F0 Normal charging flow path: CV31420 FO an open bypass is provided Residual Heat CV31235 F0 Control of flow from RHR-heat Removal CV31236 FO exchanger to reactor coolant CV31238 F0 . sys *:em CV31239 F0 Le gend: F0 = fails open LO = locked open FC = fails closed NC = normally closed NO = normally open Note 1: All these valves are maintained open with their power supply breakers locked. Note 2: These valves would be open during plant operation. Open is the desired position for use of the charging system to maintain reactor coolant in-t ventory. If safety injection is used to maintain coolant inventory the valves may remain open or be closed. In the open position component cooling water is required to prevent damage to the reactor coolant pump seals. Componelt cooling water will be provided. In the closed position no pump seal damage can occur. o l l 9 l e l' r I O_ 5-3 I - - - -.,. -}}

v t e Letter Sequence Other
TAC:11094, (Approved, Closed) TAC:11095, (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance... Administration Meeting Questions Answers Results Approval, Approval, Approval, Approval Other: ML17258A414, ML19246B009, ML19250A369, ML19250A773, ML19250A775, ML19253C848, ML19256E014, ML19256E601, ML19259D337, ML19290C267, ML19309C144, ML19309G864, ML19329F778, ML19330C398, ML19338C429, ML19338G617, ML19338G621, ML19339C823, ML19339D007, ML19340D872, ML19343C482, ML19345G356, ML19351D490, ML19351F917, ML20003C307, ML20003C310, ML20003C413, ML20039D630, ML20039D634, ML20053C136, ML20063M137, ML20070C704, ML20070G223, ML20125B981
MONTHYEAR1980-08-08 [Table View]

ML20039D634

Text

2.0 DESCRIPTION

3.0 DESCRIPTION

SUMMARY

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