ML20045D878

Forwards Markups Addressing RPV Water Level Instrumentation, Issue Number 15.Matl Will Be Included in Amend 30 Scheduled for Transmittal to NRC on 930708

ML20045D878
Person / Time
Site:	05200001
Issue date:	06/24/1993
From:	Fox J GENERAL ELECTRIC CO.
To:	Poslusny C Office of Nuclear Reactor Regulation
References
NUDOCS 9306300163
Download: ML20045D878 (15)

Text

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a' GENuclearEnergy GeneralDectoc Cumany 173 Curtner Avenue, San Jose CA 95125 June 24,1993 Docket No. STN 52-001 Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation

Subject:

Submittal Supporting Accelerated ABWR Schedule - RPV Water Level ,

Instrumentation (Issue #15)

Dear Chet:

Enclosed is a SSAR markup addressing the RPV Water Level Instrumentation Issue # 15. This information will be included in Amendment 30, scheduled for transmittal to the NRC on July 8, 1993.

Please provide a copy of this transmittal to George Thomas.

Sincerely, bVf Jack Fox Advanced Reactor Programs cc: Alan Beard (GE)

Norman Fletcher (DOE)

Bernie Genetti (GE) b j Maryann IIerzog(GE) I Jim Sawabe (GE) g jdfg p f$Y:l]Y k!"? i JI91209 2800G5 l v306300163 930624 I PDR ADOCK 05200001 A PDR

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23.UNLESS OTHERZlSE INDICATED, ALL REFERENCED Wrt ARE PREFlXE0 BY lt. B21.

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6. AN EXPANSION LE" SHALL DE PJ.OVtCID IN THE INSTRUMENT LINE ' p g BETCEEN THE CONDENSING POT 0011/.ND THE t*ATER TICHT 24.SEE t'A;N STEAM PPING OESICN SPECIFICATION M21-C00tl PENETRATION IN THE REFUEttNG t ELLOTS.

AND P! PING INST;.LLATION SHALL BE DES!GNED TO ALLOW FOR THE EXPANSTON LEG FOR THE SPECIAL DESiCN REOUIREMENTS OHICH AKE APPLICABLEtl FEED _ A THE WAX! MUM CHANGE OF YESSEL LENCTH WITH TEMPERATURE CONTANWENT TO ISOLATION VALVES.TO THE PtPING TE1?EEN 12* FEEDWA' T

AVOiO OVERSTRESSNG THE THE INSULAT!ON AROUNO THE VESSEL. ELEVATION PIPING OR A SHALL BE THE SEAL Of "OAMACE TO 25.SEE FEEDWATER PIP:NC DESrCN SPECJFICATION (021-COtO! 13. REWOTE AT OR ADOVE THE INSTRUWENT THE LINE FROM CENTERUNE OF THE tf*PPV HEAD VENT ELEV AllONA* TO ELEVATION .

FOR LIN:.

THE SPECIAL OLSiCN REOUIREMENTS WHICH ARE APPLICABLE SHALL BE SLOPED CONTINUOUSLY UPWARD 21/24 AND BE KEPT CONTA;NMENT ISOLATION VALVES.TO THE PIPING BETWEEN THE FEE 0REACTON 14. WATE AS SHORT INSULATED AS PRACTICAL. THE INSTRUMENT LINE SHALL BE KEPT 15. ItECIRCtA FROM THE CONNECTION WITH THE RPV HEAD VENT LINE 26. OPERATION OF 2 OF 2 WANUAL SWITCHES IS REQUIRED FOR18.CANCE LL HAVE A WAXIWUM TO THE CONDENSING POT. THE INSUL ATIONOPERATION CONDUCTANCE OF O.000098 KCAL/HR-CW 2 . SHA.COF THE 8 SRV'S USED FOR THE AOS. RECIRCUL

17. RES!00At

7. PROVISIONS FOR INSTUUWENT LINE ISOLATION SHALL 27.SEE SUPPORTING DOCUMENT 1 FOR SYSTEM IDENTriCATION AT INTEftCONNECTIONS.

BE lH ACCORDANCE WITH SUPPORTING DOCUWENTS 3 & 4. 18. RESIDUAL ONE ORflCE SHALL DE INSTALLED IN EACH NSTRUWENT 25. PNEUMATIC SUPPLY FROM REFERENCE DOCUWENT 33.

3 19. HICH PRE

• IN RY RC BI OR ICE SIE 15 0 A 3 MAXtWUM NUMUER OF ORE!CES PER LINE iS ONE. 20. LEAK DET T 29. THE CONDENSING CHAMBER SHALL CONSIST OF A 25A X 25A PIPE ELBOW WHICH t$ CLOSE-COUPLED TO THE MAIN STLAW LINE FLOW 2L LEAK D y

6. OPERATED VALVE WOTOR OPERATORS Ak0 PLUT SOLENOIDS ARE AC RESTRICTCR INSTRUMENT LtNE TAPS. THE RUN OF 25A INS 1RUWENT Lt UNLESS OTHERWISE SPECIFIED, FROM THE TAP ON THE WAIN STEAM LINE FLOW RESTRICTOR22. TO THE MACTM

/ SHALL BE LEVEL IN THE HORIZONTAL PLANE WITHN 0.50 CM FOR ALL 94Th'E (ONOjNS!NG CHAWBER SHALL CONSIST OF A 40A X 25AHAVE BE LOCATEDCONDITIONS. THE 25A LNSTROWENT LINE COMECTION 23. REACTORTO P!PE TEE A DOWNWARD SLOPEVERTICALLY CCN T A;NMEN T AND EXTEND OOWNWARD. 24*

21/20 PRIOR TO PENETRAriNC THE THE 2SA REAC TOR AND LX1 ENS 10N PIPE WITH CAP WHICH IS CLOSE '

COUPLED TO SOA REACTOR VESSEL INSTRUMENT NO22LE BY A

'lLDING 50A TO 40A REDUCER. THE RUN OF THE " TEE" SHALL BE LEVEL

!N THE HORtIONTAL PLANE FOR ALL CONDtTIONS WITHIN JWW SHALL HE PROVf0ED IN THE 25A AND 20A PtPE SUCH CHAWBER WOVES WITH THE RPV AS IT THERMALLY EXPANDS 28.

25.LIOUD W^o AND T

LOWCONT CONO THE 25A BRANCH CONNECTION TO THE " TEE" SHALL BE LOCATED VERTlCALLY A DOWNWARD SLOPE ANDhEXTEND 1/2%, WITH DOWNWARD.

A TOTAL VERitCALTHE OROP25ATO PtP2 SHALL t

30. HAVEINSULATE WITH INSULATION THAT HAS A WAXtuuM CONDUCTANCE 0.000098 OF 27.TURB;NE D THE CONTAINVENT WALL NOT TO EXCEED O.9 WETERS. }

PRIORTHE TO WSTRUMENT LINE *C. THETAPINSULTOKCAL/HR-Cu ATION SHALL EXTENOa FROM ENDING INSTRUMENT UNE ITHIN 5.1 CM OF THE DOWN 28.CONDENSC NNt Q BE REDUCED TO 20A. FLEXtBLITY SHALL t% i BE PROViDED m v m a APPL INPENETR V LR THE JUN HE MIZON ATING THE CONTA!NUENT IHLELBO be Mg 29, TURBWAL NE @

THE 25A AND 20A PtPE SUCH THAT THE CONDENSING CHAWDER MOVES WITH THE REACTOR VESSEL AS IT THERMALLYVOtt. E. LINE EXPANDS i

= NKECTION m ei THE DOWNWARO EXTEN0'NG"Wr IM T 30. TURB!NE C' i r a- HUUM m m .tv.Y W 3 APPLI LU AND CONTRACTS. THERWAL EXPANSION SHALL NOT CHANGE THESHOUL Ltw iMAN ONE (iFuu tn.

ELEVATION OF THE 40A X 25A TEE WITH RESPECT TO THE RPV 3L STEAM BYr INSTRUWENT NOZZLE SY WORE THAN 3mm. THE CONDENSING CHAMBER TEES AND THE 25A AND 20A PIPES FROM IT TO THE 3L THE WOTOR-OPERATED val.VES fuCVS) WPL D21-F007A&9 IN THE (;ti4N-UP NSTRUWENTION SHALL NOT BE INSULATE 0*

BE DELETED IF THE RPV FEECWATER NOZZLE FATICU THE CUW SYS FEEDWATER LLNE SELECT!ON FEATURE. 1.0 Wiff f00T 33,3NS TRuuEg AN ACCEPTABLE ALTERNATE 19 TO USE A CONVENTIONAL 34.HICH PRES:

CONDENSING NO EXT POT IN PL ACE OF THE 40A X 25A PIPE TEE 32.THE THERMAL SLEEVE SHOWN WAY BE DELETED IF THE STRESS 35. VALVE CLA ANALYSIS SHOWS THAT IT IS NOT REOutRED.

10. LOCATE THE TEE AS CLOSE AS POS$!BLE TO REACTOR VESSEL.

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38. SAMPLING 5 431 L h 33.SEE REFERENCE DOCUMENT 3 FOR THE INSTRUWENT SETPOINT REOUIREMENTS. 37.NoT USED 1LTHE MAXIWUM OPERATING PRESSURE AND TEuPERATURE IvuCd 3S.NOT USED A

FOR THE PORT!ON OF THE WAIN STEAM LINE ORAIN LINE /7 34.FOR INTERFACE CONNECTIONS, SEE THE WStV EQUIPVENT REQUIREMENTS.

HEADER DOWNSTREAM OF THE WOTOR OPERATED VALVES SPECIFICATION SUPPORT ORAWING MPL FOOB AND F009.

(WOVS) F014 AND FOIS AND THE RESTRICTING ORIFICE 39* ATWOSPHEF DOOS AND 0007 10 DE DETERMINED BY THE CESIGNERS INOUgg B 40' MAIN STEAh OF THE MA!N CONDENSER STSTEM. 33.FOR VENT AND ORAIN LINES OPEN TO THE ATMOSPHERE, 3PECtFICA T' DOWNSTREAM OF THE OUTBOARD SHUT-OFF VALVE. THE FOLLOWING SOUNDARY CONDITIONS APPLY

12. LOCA TE Tile DRAIN LINE 204-NG-342 ANO ASSOCIATED EQUIPMENT FOR DETECTNG THE LEAKAGE AS CLO$E AS PRACTICAL TO THE RPV.

MAXfWUM OPERATING PRESSURE - O otg ~

13. FOR DETAILS, SEE 811-0021 & 0025.

WAX:WUM OPERATING TEWPERATURE - Sa C DES!CN CLASS AND OA CLASS - 7G S S AR. F g w*

• oEm SEISMIC CLASS - C COMOD 38.PiPtNG OESIGN SPECTICATION AS FOLLOWS:

5.I- 3 STREAWS.

T E R C C D EE ATER A.

Es REQUIREWENTS WAY BE USED.OTHER METHODS WHICH WEETMAXWUM APPLICABLE OPERAllNG CODE PRESSURE - SEE SPECtFIC OOUNDARIES ON D9 AWI SHOP B. WAXML%f CPERATNG C. MATERfAL - SEE TABLE S TEMPERATURE - SEE SPECttrC BOUNDARIES ON D

15. SPRING CLOSING CHECM VALVE SPRtNG ACTUATOR HELD IN0. PIPING TH!CKNESS - SEE TABLE S E.OPEN POSITION BY AIR PRESSURE DURtNO NORMAL OPERATION. F NOF. Mlil CLASS - SEE SPEC FIC BOUNDARIES ON DRAWING S IGNE CL S PR OR ^ OC CLASS - SEE SPECIFIC DOUNCARIES ON ORAWING APPRE BL FL W REVERSAL, FOO3 SHOULD DE INTERLOCKED TO OUWP AIR PRESSURE C. SEISMIC CLASS - SEE SPECflC BOUNDARIES ON ORAWING AUTOWATICALLY IN THE EVENT ALL FEEDWATER PUWPS TRIP. H. FLUID - SEE TABLE 3 IO* [Y T A T N g TOJ0g PIPING _TO BE DETERuNrn i p v . - ~"

3

- Date: June 17,1993 INSERT A

9. The condensing chamber shall be close coupled to the 50A RPV instrument-line nozzle by a 50A pipe. The SOA pipe from the reactor vessel instrument line nozzle shall be level in the horizontal plane for all conditions within 3 mm.

The instrument line connected to the bottom of the condensing chamber shall have a downward slope 21/25. Inside the primary containment, the total vertical drop from the condensing chamber to the containment wall, shall not exceed 0.9 meters. At the bottom connection to the condensing chamber, the instrument line shall be 25A pipe, but prior to penetrating the primary containment, shall be reduced to 20A pipe.

In addition, the condensing chamber has a 25A drain line which drains the excess condensate or water to the variable leg instrument lines for the RPV wide range water level instrumentation.

Flexibility shall be provided in the instrument line and condensing chamber drain line such that the condensing chamber is free to move with the reactor vessel as it thermally expands and contracts. Thermal expansion shall not change the elevation of the condensing chamber with respect to the RPV instrument line nozzle by more than 3 mm.

Insulate the 50A pipe which attaches the RPV instrument line nozzle to the condensing chamber with insulation which has a maximum conductance of 0.000098 kcal / hr-cm2- C. The insulation shall' extend from the RPV instrument line nozzle to the condensing chamber. The condensing chamber and the instrument line from the condensing chamber to the containment penetration shall not be insulated. The 25A drain line shall be insulated.

I N SE RT B 41 THE FLOW CONTROL STATION CONTAINS THE EQUIPMENT NECESSARY FOR LOCAL FLOW INDICATION AND LOCAL FLOW CON T ROL.

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ABWR nuime Standard Plant nev c drywell monitoring are provided by the residual heat removal systems are fitted with nuclear boiler system. A pressure rise drain lines from the valve stems, from above the normally indicated values will between the two sets of valve steam packing.

indicate a possible leak or loss of reactor Leakage through the inner packing is carried coolant within the drywell. Pressure to the drywell equipment drain sump. Leakage exceeding preset values will be alarmed in during hydro-testing may be observed in drain the main control room and required safety line sight glasses installed in each drain action will be automatically initiated. line. Also, each drainline is equipped with temperature sensors for detecting leakage. A i (7) Reactor Vessel Head F!ance Seal Monitorinc remote operated solenoid valve on each line may be closed to shut off the leakage flow A single channel of pressure monitoring is through the first seal in order to take provided for measurement and control room adyantage of the second seal, and may be used indication of pressure between the inre and during plant operation, in conjunction with outer reactor head flange seals. 3igh the sump instrumentation, to identify the ,

pressure will indicate a leak in the inner specific process valve which is leaking.

O-ring seal. This high pressure is annunciated in the main control room (no (11) Mai.. Steamline Hich Flow Monitorine (for isolation). A pressure tap for this leaks downstream of flow elements) measurement is provided by the nuclear boiler system. Leakage through both inner High flow in each main steamline is monitored and outer seals will be detected by other by four differential pressure transmitters drywel! Icak detection instrumentation. Any that sense the pressure difference across a leakage through the inner seal can be flow restrictor in the RPV main steam outlet directed to the drywell equipment draia nozzle. The pressure taps are part of the sump. nuclear boiler system. Two sets ef aps t are provided, each set includes a nozzle en and (8) Reactor Recirculation Pumo Motor Leakace vessel tap. High flow rate in the noin Monitorine steamlines during plant operation could indicate a MSL break. High flow exceeding Excess leakage from the RIP motor casing the preset value in any of the four main will be detected by the drywell floor drain steamlines will result in trip of the MSIV sump monitors described in (1) above. isolation logic to close all the MSIVs and the MSL drain valves, and annunciate the high (9) Safetv/ Relief Valve Leakace Monitoring flow in the main control room. Each moni-toring channel includes inputs to the process SRV leakage is detected by temperature computer.

sensors located on each relief valve discharge line such as to detect any valve (12) Esastor Vessel tow water tevel Monitorine outlet port flow. Each of the temperature channels includes contro! room recording and The nuclear boiler system provides reactor alarm capabilities. The temperature sensors water level monitoring for the LDS functions are mounted using thermowells in the and for safety functions of other systems.

discharge piping about half of a meter from Sixteen channels of monitoring (four in each the valve body to prevent false indication. division to provide trip signals at four The monitoring of this leakage is provided different water levels, i.e., levels 3, 2, by the nuclear boiler system. 1.5 and 1) are provided for the LDS functions, e.g., RHR, CUW, MSL and isolations (10) Valve Stem Packine Leakace Monitorine of other portions of the plant. The safety related performance requirements of the level Large (two inch or larger) remote monitoring channels are a function of the power-operated valves located in the drywell nuclear boiler system. For owibcnal,drm/ ion for the nuclear boiler, reactor water

[on Mr Vesse/ 4dev /Ne/ astemcehh,]se cleanup, reactor core isolation cooling, and (13) itCIC Steamline Flow Monitorine (for leaks downstream of flow elements) l n 7.7./.4 Amendment 27 5.2-22

ABM mA61oorr -

REV B Standard Plant only the nonsafety-related sensors for l 7.7 CONTROL SYSTEMS NOT those systems are described in this REQUIRED FOR SAFETY subsection.

7.7.1 Description j (1) System Identification This subsection provides discussion (or provides references to other chapter discussions)

The purpose of the nuclear boiler system for instrumentation and controls of systems which instrumentation is to monitor and provide are not essential for the safety of the plant, control input for operation variables and permits an understar. ding of the way the during plant operation, reactor and important subsystems are controlled, and why failure of these systems does not impair The nonsafety-related instruments and safety functions. The systems include the systems are used to provide the operator with information during normal plant following:

operation, or provide control input for e Nuclear boiler system - reactor vessel nonsafety-related functions.

instrumentation, (2) Classification e Rod control and information system, The systems and instruments discussed in Recirculation flow control system, this subsection are designed to operate e

under normal and peak operating conditions e Feedwater control system, of system pressures and ambient pressures and temperatures and are classified as non-e Process computer system, safety-related. However, mechanical inter-face of nonsafety-related instruments with Neutron monitoring system - ATIP safety-related instrument piping is either e

classified as essential passive to avoid subsystem, compromise of the Class 1E sensing capabi-Fire protection system (Chapter 9),

lity (e.g., a pressure-containing body of a e

non 1E transmitter on a Class 1 instrument line is classified as essential passive and e Drywell cooling system (Chapter 9),

is environmentally qualified), or redundant Instrument air systems (Chapter 9), sensing lines (four total) are provided e

with 2/4 safety system logic to show com-Makeup water system (Chapter 9), pliance with USNRC Regulatory Guide 1.151.

e e Atmospheric control system (Chapter 9), (3) Power Sources and The nonsafety-related instruments discussed Fuel Pool Cooling and Cleanup System in this subsection are powered from the e

(Chapter 9). non-Class 1E instrument buses.

7.7.1.1 Nuclear Boller System - Reactor Vessel (4) Equipment Design -

Instrumentation For instruments which are located below the Figure 5.1-3 (Nuclear Boiler System P&ID) process tap, the sensing lines will slope l

shows the instrument numbers, arrangements of the downward from the process tap to the sensors, and sensing equipment used to monitor instrument, so that air traps are not l

the reactor vessel conditions. The NBS interlock formed.

I l block diagram (IBD) is found in Figure 7.3 2. Where it is impractical to locate the in-Because the nuclear boiler system sensors used struments below the process tap, the for safety-related systems, engineered safe-sensing lines descend below the process guards, and control systems are described and evaluated in other portions of this document, 7.7-1 l Amendment 27 l

.MM Standard Plant 23Assoorr any g connection before sloping upward to a high point vent located at an accessible loca-tion.

7.7-1.1 Amendment 27

M 23A6100AF Standard Plant P1V B The purpose of this is to permit ~ venting of (b) Narrow Water Level Range noncondensable gases from the sensing line during calibration procedures. This range uses the RPV taps at the el-evation near the top of the steam out.

(5) Reactor Vessel Temperature let nozzle and the taps at an elevation near the bottom of the dryer skirt.

The reactor pressure vessel (RPV) coolant The zero of the instrument is at the temperatures are determined by measuring top of the active fuel and the in-saturation pressure (which gives saturation struments are calibrated to be accurate temperature), outlet flow temperature to the at the normal operating point. The wa-reactor water cleanup unit (RWCU), and ter level measurement design is the con.

bottom head drain temperature. Reactor densate reference chamber type and uses l vessel outside surface temperatures are differential pressure devices as its measured at the head flange and bottom head primary elements. The feedwater locations. Temperatures needed for control system uses this range for its operation and for compliance with the water level control and indication technical specification operating limits are inputs. For more information on the obtained from these measurements. During feedwater control system, see normal operation, either reactor steam S u b s e ction 7.7.1.4.

saturation temperature and/or the inlet temperatures of the reactor coolant to the (c) Wide Water Level Range RWCU and the RPV bottom drain can be used to determine the vessel temperature. This range uses the RPV safety related taps at the elevation near the top of (6) Reactor Vessel Water Level the steam outlet nozzle and the taps at an elevation below the top of the ac.

Figure 7.7-1 shows the water level range and tive fuel. The zero of the instrument the vessel penetration for each water level is the top of the active fuel and the range. The instruments that sense the water instruments are calibrated to be accu.

l level are strictly differential pressure de- rate at the normal power operating i

vices calibrated for a specific vessel pres- point. The water level measurement sure (and corresponding liquid temperature) design is the condensate reference type conditions. The following is a description and uses differential pressure devices of each water level range shown on Figure as its primary elements.

7.71.

(d) Fuel Zone Water Level R e (a) Shutdown Water Level Range bfb h hyr Md This range uses the RPV taps at the el.

This range is used to monitor the reac- evation near the(top of the steam duT_[

tor water level during the shutdown con- %and the taps below the top l dition when the reactor system is flood- of the active fuel (above the pump i ed for maintenance and head removal. deck). The zero of the instrument is l l The water level measurement design is the top of the active fuel and the the condensate reference chamber leg instruments are cylibrated to be type. Tb amim;o.m .od e.mu.s sou- accurate at 0 kg/cm g and saturated l

! di:!ca thati =d fu. iip uiib.rt+sa-, condition. The water level measurement

( Pirr 0 kg/cm g and 48.9 C water in design is the condensate reference type the vessel. The two vessel instrument and uses differential pressure devices l penetrations elevations used for this as its primary element.

water level measurement are located at the top of the RPV head and the (e) Reactor Well Water Level Range instrument tap just below the bottom of the dryer skirt. This range uses the RPV tap below the i top of the active fuel. The zero of g g o p -fAe. hufruMcW-Amendment 27 bk 7.7-2 Mi ad #s Mstrw,.sds ue calikated to be sawk d l

ABM 2346io04,

. Standard Plant nev n the instrument is the top of the active fuel. The temperature and pressure condition that is psed for the calibra-tion is 0 kg/cm g and 48.9 C water in the vessel. The water level measure-ment design is the pressure device which measures statie water pressure inside vessel and converts to a water level indication. This range is used to monitor the reactor water level when the reactor vessel head is removed and the reactor system is flooded during the refueling outage.

N The narrow condensate rang wide range /and reference fuel zone chamber for the[

water level range is commoo as discussed in Section 7.3.

i The concem that non-condensable gasses may build-up in the water column in the reactor vessel reference leg water level instrument lines, i.e. the reactor vessel instrument lines at the elevation near the main steam line nozzles, has been addressed by continually flushing these instrument lines with water supplied by the Control Rod Drive (CRD) System.

Amendment 27 7 7'I I

23xsicose ABWR Standard Plant REV B Reactor water level instrumentation that (b) Pressure transmitters and trip actua-initiates safety systems and engineered tors used for RCIC and LPFL are '

safeguards systems is discussed in discussed in Subsection 7.3.1.1.

Subsections 7.2.1 and 7.3.1. Reactor water level instrumentation that is used (c) Pressure transmitters and recorders as part of the feedwater control system used for feedwater control are discus-is discussed in Subsection 7.7.1.4. sed in Subsection 7.7.1.4.

(7) Reactor Core Hydraulics (d) Pressure transmitters that are used for pressure recording are discussed in A differential pressure transmitter indi- Section 7.5.

cates core plate pressure drop by measuring the core inlet plenum and the space just (9) Pressure between the inner and outer reac-above the core support assembly. The in- tor vessel head seal ring is sensed by a strument sensing line used to determine the pressure transmitter. If the inner seal t pressure below the core support assembly fails, the pressure at the pressure attaches to the same reactor vessel tap that transmitter is the vessel pressure and the is used for the injection of the liquid from associated trip actuator will trip and the standby liquid control system. An actuate an alarm. The plant will continue instrument sensing line is provided for to operate with the outer seal as a backup, measuring pressure above the core support and the inner seal can be repaired at the assembly. The differential pressure of the next outage when the head is removed. If core plate is indicated locally and recorded both the inner and outer head seals fail, in the main control room. the leak will be detected by an increase in drywell temperature and pressure.

Another differential pressure device indicates the reactor internal pump (10) Safety / Relief Valve Scal teak Detection developed head by measuring the pressure difference between the pressure above and Thermocouples are located in the discharge below the pump deck. exhaust pipe of the safety / relief valve.

The temperature signal goes to a multipoint recorder with an alarm and will be activat-(8) Reactor Vessel Pressure ed by any temperature in excess of a set Pressure indicators and transmitters detect temperature signaling that one of the safe-reactor vessel internal pressure from the ty/ relief valve seats has started to leak, same instrument lines used for measuring reactor vessel water level. (11) OtherInstruments The following list shows the subsection in The feedwater temperature is measured and which the reactor vessel pressure measuring transmitted to the main control room.

instruments are discussed.

The feedwater turbidity is monitored and (a) Pressure transmitters and trip actuators the signal is transmitted to the main for initiating scram, and pressure control room for recording.

transmitters and trip actuators for bypassing the main steam line isolation (12) Testability valve closure scram are discussed in Subsection 7.2.1.1.

Pressure, differential pressure, water 7.7-3 Amendment 27

u-MI@Y par n Standard Plant 16 vel, and flow instruments are located the control room and turns on an outside the drywell and are piped so that annunciator if the inner reactor head calibration and test signals can be applied seal fails.

during reactor operation, if desired.

(f) The discharge temperatures of all the safety / relief valves are shown on a (13) Environmenta! Considerations multipoint recorder in the control There is no tpecial environmental conside- room. Any temperature point that has exceeded the trip setting will turn on ration for the instruments described in this an annunciator indicating that a subsection except as discussed in (2) above for pressure containing parts of sensors safety / relief valve seat has started to leak, sharing instrument lines with safety.related instruments.

(g) Feedwater turbidity is recorded in the (14) OperationalConsiderations main control room. The recorder will turn on annunciator in the main control room for either a high or low signal.

The reactor vesselinstrumentation discussed in this subsection is designed to augment the existing information from the engineered (16) Setpoints safeguards systems instrumentation and safe-The annunciator alarm setpoints for the ry system such that the operator can start reactor head seal Icak detection, safety /

up, operate at power, shut down, and service relief valve seat leak detection, and the reactor vessel in an efficient manner. feedwater corrosion product (turbidity)

None of this instrumentation is required to monitor are set so the sensitivity to the initiate any engineered safeguard or safety-related system and its failure will not variable being measured will provide disable any ESF or safety related system. adequate information.

Table 2 and 3 of Figure 5.2-5 show the re-(15) Reactor Operator Information lative indicated water levels at which va-rious automatic alarms and safety actions The information that the operator has at his are initiated. The followig list tells disposal from the instrumentation discussed where various level measuring functions are in this subsection is discussed below: discussed and their setpoints are (a) The shutdown range water level, narrow referenced.

range water level, wide range water level, fuel zone water level, and (a) Level transmitters and trip actuators for initiating scram are discussed in reactor well water level are indicated Subsection 7.2.1.1.

in the main control room.

(b) Level transmitters and trip actuators (b) The core plate differential pressure for initiating containment or vessel provides a signal to the process Isolation are discussed in Subsection computer. -

- 7.3.1.2.

(c) The reactor internal pump differential pressure is indicated in the main (c) Level transmitters and trip actuators ,

i used for initiating HPCF, RCIC, LPFL control room. and ADS 'and the Icvel actuators used to shut down the HPCF pump and RCIC tur-(d) The reactor pressure is indicated in the main control room and at two local racks bine are discussed in Subsection in the containment by a pressure gage. 7.3.1.1.

l (d) Level trips to initiate various alarms (c) The reactor head seal leak detection and trip the main turbine and the system provides pressure indication in l

7.7-4 Amendment 27 l

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• feedpumps are discussed in Subsection 7.7.1.4 l

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