Text

Amends 203 & 206 to Licenses DPR-44 & DPR-56,respectively, Extending Surveillance Test Intervals & Allowable out-of Svc Times for Testing & or Repair of Instrumentation That Actuate Reactor Protection Sys
	ML20086B514
Person / Time
Site:	Peach Bottom ; (DPR-044, DPR-056)
Issue date:	06/06/1995
From:	Stolz J; Office of Nuclear Reactor Regulation
To:	; Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co
Shared Package
ML20086B515	List: ML20086B514; ML20086B525;
References
	DPR-44-A-203, DPR-56-A-206 NUDOCS 9507050425
	Download: ML20086B514 (126)
	v • d • e

{{#Wiki_filter:p. a"Ru .p +4 UNITED STATES s g NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066M001 49.....,d PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY 1 DOCKET NO. 50-277 i PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE l Amendment No. 203 License No. DPR-44 i 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by PECO Energy company, et al. (the licensee) dated September 26, 1994, as supplemented by letters dated January 5, and March 23, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I. l B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; r D. The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of. the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. DPR-44 is hereby amended to read as follows: i b 9507050425 950606 PDR ADOCK 05000277 p PDR I

(2) Itchnical Specifications The Technical Specifications contained in Appendices A and B, as ~ revised through Amendment No. 203 .are hereby incorporated in the license. PECO shall operate the facility in accordance with the Technical Specifications. 3. This 31 cense amendment is effective as of its date of issuance and is to be implemented within 30 days. i FOR THE NUCLEAR REGULATORY COMMISSION I 'en.<E. I. 4 ddw.,- John F. Stolz, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 6, 1995 k

ATTACHMENT TO LICENSE AMENDMENT NO. 203 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 t Replace the following pages of the Appendix A Technical Specifications with i the enclosed pages. The revised areas are indicated by marginal _ lines. Remove Insert 35 35 36 36 36a 36a 37 37 38 38 39 39 41 41 42 42 43 43 44 44 45 45 46 46 47 47 51 51 52 52 53 53 53a 53a 55 55 57 57 57a 58 58 59 59 59a 60 60 61 61 62 62 63 63 64 64 65 65 66 66 67 67 68 68 69 69 70 70 4 71 71 71a 71a 71b 71b 72 72 72a 73 73 74 74 i

'I .l ^," --2'- ATTACHMENT TO LICENSE AMENDMENT NO.203 . FACILITY OPERATING LICENSE NO. DPR-44' ' DOCKET NO. 50-277 Remove Insert l 74a 74a j 75' 75 7 9 -- 79 80 80 81 81- .i 81a 81a 83 83 84 84 85 85 87 87 83 88 i 89 89 i 89a. 91 91 94 94 05 95 96 96 98 98 i i i' t

.~. PBAPS' ,f UNIT 2.. .r 5 'UMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.1 Reactor Protection System (RPS) - 4.1 Reactor Pie 6 cue, System T i A.. The RPS instrumentation for each trip function A. Each RPS instrument channel shall be f in Table 3.1.1 shall be Operable; and, there demonstrated Operable by performance of a i shan be two Operable or tripped trip systems channel functional test and channel cabbration 'i for each Trip Function. at the Frequencies shown in Tables 4.1.1 and 5 4.1.2, respectively. I The designed system response times from the Response time measurements (from the - i opening of the sensor contact up to and opening of the sensor contact up to and ' j ' including the uponing of the trip actuator including the opening of the trip actuator contacts shall not exceed 50 miNiseconds contacts) are not part of the normal instrument test. The RPS response time of each reactor Apohcatzhty trip function shall be demonstrated to be within t its Emits once per operating cycle. { According to Table 3.1.1. b Conditions and Readred A@ns: (1)(2) _1. ' Wth one or more channel (s) required by Table 3.1.1 inoperable in one or more trip functions, place the inoperable channel or associated trip system in trip within 12 hours .}' 2. Wth one or more trip functions with one or more channels required by Table 3.1.1 inoperable in both trip systems, place channel in one trip system in trip or piece one trip system in trip within 6 hours 3. Wth one or more automatic trip functions or ? two or more manual trip functions (Mode Switch in Shutdown, Manual Scram and RPS Channel Test Switches) with RPS trip capabikty not maintained, restore RPS trip capability within one hour. 4. If the required actions and associated i completion time of Action 1 or 2 or 3 are not i' met, take the action required by Table 3.1.1 for the Trip Function. j (1) When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated trip function maintains RPS trip f capability. I c (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the trip function to occur. In these cases, if the inoperable channelis not restored to Operable status witHn the ' ] required time, the Action required by Table 3.1.1 for that trip function shall be taken immediately, t - as - Amendment No. 65. 70, 71, 76, 192, 203 i t I

PBAPS UNIT 2 1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS l 3.1 Reactor Protection System (continued) 4.1 Reactor Protection System (continued) i B. N/A B. Deleted C. N/A C. Deleted [ D. Reactor Protection System D. Reactor Protection System Power Supolv Power Sunoiv D.1 Reactor Protection System Power Supply: D.1 The following RPS power supply (MG set) protective devices shall be functionally One trip train

par RPS MG set may be in tested at least once every six months and the bypassed or lacperative condition for a caNbrated once each refuehng outage.

period of 72 houm. If this condition cannot be satisfied, or if both trip trains are Acceptable inoperative, the RPS bus shall be Device Settma transferred to the alternate source or de-energized within 30 mim.tes. Undervoltage 113

2 Volts Overvoltage 13112 Volts Underfrequency 57 Hz t.2 Hz Underfrequency Time Delay 6 see t 1 see D.2 One trip train
of the RPS alternate power D.2.

The following RPS alternate power supply supply may,be in the bypassed or protective devices shall be functionally inoperative con:iitson for a period of 72 tested at least once every six months and hours. If this condition cannot be satisfied, caNbrated once each refuehng outage, or if both trip trains are inoperative, the RPS bus shall be transferred to the RPS Acceptable MG set or de-energized within 30 minutes. Device Settina Undervoltage 11312 Volts Overvoltage 131 t 2 Volts Underfrequency 57 Hz t.2 Hz Undervoltage Time Delay Max. 4 secs. A trip train consists of one breaker, one undervoltage relay, one overvoltage relay, one underfrequency relay, one time delay relay (MG set only), and the associated logic. Amendment No. 75, 00, 203..

PBAPS UNIT 2 Intentionally Blank l J 1 l -36a. Amendment No. 99 M, 203

= ~..h. + PBAPS Unit 2 Table 3.1.1 IEACTOR PROTECTION SYSTEM ESCRMS NSTim_WATION N % g,,, Modes h which Funceon Operable Instrument h Be W Number of Instrument Channele per Chennais Provided Acuan l Item Trip System Trip Function Trip Level Seeing Refuel (F) Stereup Run .by Design - (1) 1 1 Mode Switch h x' x x 1 Mode W .A-Shutdown (4 W 2 1 Manuel Scram x x x 2 Instrument Channels A 3 3 IRM 14gh Fkst s120/125 of Full Scale x x M 8 hatrument Channele A 4 3 IFN inopereelve x x (5l 8 instrument Channele A 5 2 APfW High Flux (0.8814+88%4.88dW) x-S Instrument Chennois ' A or 8 - (csemp e 120%) (1 4 (139 h h 6 2 APfW Inopereelve (11) .x x x 6 heerument Chennois A or B g u) 7 2 APfW Downeoele 22.5 W (10) 8 heerument Channels A or B en Seele 8 2 APRM High Flux in 515% Power x x 6 instrument Channets A k n, E 9 2 High Reactor Pressure 51085 pois - xM x x 4 Instrument Channele A s 10 2 Hgh Drywell Preeeure 52 peig

xM xM x

4 Instrument Channels A' 11 2 Reactor Low Weser Level toin. W x x x 4 Instrument Channels A .h Level m C ],. m ,_...-.____.~__.__....._-~.2,_..___._.-,.

u ^% 'PBAPS , Unit 2 Table 3.1.1 (connnued) REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No. of Modes in which Function Operable instrumer Must Be Operable Channele per Her of hN i Channele Provided Action item Trip System ' Trip Function Trip Level Setting Refuel (7) Startup Run. by Deelen (1) 12 2 High Water Levelin i 50 Geilone X (2) X X 4 instrument Channele A-Scram D6scharge Volume 13 2 Turbine Condenser low 2 23 IN. Hg. Vacuum X 4 Instrument Chennele A or C Vacuum 14 2 Main Steam Line High i 15 X Normal X-X X 4 Instrument Chennels A Rediellon Full Power Background 15 8 Mein Steam Line i 10% Velve Closure g X (6) 16 Instrument A- ), a. Isolation Velve Closure Channele 16 2 Turbine Control Velve 500t P t 850 peig X (4) 4 instrument Channele A or D ' - 1 Feet Closure control Oil Pressure Between Feet Claeure Solenoid and Disc Dump Velve 17 4 Turbine Stop Velve i 10% Velve Closure X(4) 8 :...;~.. ;a Channene _ A or D g Closure 18 2 RPS Channel Test X X X 4 Instrument Channele A-g Switchee

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l UnR2-PBAPS NOTES FOR' TABLE 3.1.1 l'. If thelrequired actions and associated completion time of-Specification 3.1.A,-Actions'l or 2 or 3-are not' met, take the action listed below for.the affected trip function as required by Table 3.1.1. A.- Initiate insertion of operable rods and complete insertion of all operable rods within 12 hours. B. Reduc'e power. level to IRM range and place mode switch in the start up position-within 6 hours. c. Reduce turbine load and close main steam line isolation valves within 6 hours. D. Reduce power to less than 30% rated within 4 hours. 2. Permissible to bypass, in refuel and shutdown positions of the reactor mode switch. 3. Deleted. 4. Bypassed when turbine first stage press 6re is less than that which is equivalent to 30% of rated thermal power. 5. IRM's are bypassed when APRM's are onscale and the reactor l mode switch is in the run position. 6. The design permits closure of any two lines without a scram being' initiated. i l 7. When the reactor is subcritical and the reactor water i temperature is less than 212 degrees F, only the following trip functions need to be operable: A. Mode switch in shutdown B. Manual scram c. High flux IRM D. Scram discharge instrument volume high level 8. Not required to be operable when primary containment integrity is not required. 9. Not required to be operable when the reactor pressure vessel head is not bolted to the vessel. 2 4 i ! Amendment No. 23, 10', !!7, ISS, 190, 203 l

Unit 2 TABLE 4.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Group (2) Functional Test Minimum Frequency (3) Mode Switch in Ghutdown A Place Mode Switch Each refueing outage. In Shutdown Manual Scram A Trip Channel and Alarm Every 3 months. l RPS Channel Test Switch .A Trip Channel and Alarm Oncehveek or after channel maintenance. IRM High Flux C Trip Channel and Alarm (4) One per week during refueing or i b startup and before each startup. m inoperative C Trip Channel and Alarm (4) One per week during refuelng or startup and before each startup. APRM g High Flux B1 Trip Output Relays (4) Once/3 months k inoperative B1 Trip Output Relays (4) Once/3 months Downscale B1 Trip Output Relays.(4) Once/3 rwiths Flow Bias B1' Colbrate Flow Bias Signal (4) Once/ month High Flux in Startup or Refuel C Trip Output Relays (4) One per week during refuelng or sta: tup and before each startup. l g High Reactor Pressure (6) B2 Trip Channel and Alarm (4) Once/3 months High Drywel Pressure (6) B2 Trip Channel and Alarm. (4) Once/3 months Reactor Low Water Level (5)(6) B2 Trip Channel and Alarm (4) Once/3 months Z - C -4. N 4 -s m. .,,.-i r .-e. e m.

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~ Unit 2 TABLE 4.1.1 (Continued) REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Group (2) Functional Test Minimum Frequency (3) High Water Levelin Scram A Trip Channel and Alarm Once/3 months Discharge Instrument Volume Turbine Condenser Low Vacuum (6) B2. Trip Channel and Alarm (4) Once/3 months h. Main Steam Une High Radiation B1 Trip Channel and Alarm (4) Once/3 months J i Main Steam Line Isolation A Trip Channel and Alarm Once/3 months in .- 3 Valve Closure Turbine Control Valve A Trip Channel and Alarm Once/3 months { EHC Oil Pressure E. Turbine First Stage Pressure A Trip Channel and Alarm Once/3 months 5 Permissive 5 Turbine Stop Valve Closure A Trip Channel and Alarm Once/3 months z O c C ~ u ow .. _, - -...... - - -, -. ~. - e- ~ ~ - -, ,--,-,.---~,,.----.4 -.r. ..,w~,.-. .---.-,_rr.

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PBAP3 y UNrr 2 NOTES FOR TABLE 4.1.1 1. Deleted. -2. A description of each of the groups is included in the Bases of this Specification. 3. Functional tests are not required.on the part of the system that is not required to be operable or are tripped. If-tests are missed on parts not required to be operable or are tripped, then they shall be performed prior to returning the system to an operable status. 4. This instrumentation is exempted from the instrument channel test definition. This instrument channel functional test will consist of injecting a simulated electrical signal into-the measurement channels. 5. The water level in the reactor vessel will be perturbed and the corresponding level indicator changes will be monitored. This perturbation test will be performed every month after completion of the functional test program. 6. These channels consist of analog transmitters, indicators and electronic trip units. Instrument checks shall be performed once per day. AmendmentNo.30;203 -43

nit 2- ~ TABLE 4.1.2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CALIBRATION MINIMUM CAllBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS l Instrument Channel Group (1) Calibration Minimum Frequency (2) IRM liigh Flux C Comparison to APRM on Maximum frequency once-Controlled shutdown per week. APRM liigh Flux Output Signal B1 Heat Balance Twice per week. Flow Bias Signal B1 With Standard Pressure Every eighteen manths. Source LPRM Signal B1 TIP System Traverse Every 6 weeks 7 liigh Reactor Pressure B2 Standard Pressure Source Once per operating. cycle. liigh Drywell Pressure B2 Standard Pressure Source Once'per operating k cycle. h Reactor low Water Level B2 Pressure Standard Once per operating g cycle. c+ liigh Water Level in Scram A Water Column Every refueling outage. z ? Discharge Instrument Volume h Turbine Condenser low Vacuum B2 Standard Vacuum Source Once per operating cycle. Main Steam Line Isolation Valve A Note (5) Note (5) g Closure ? Main Steam Line liigh Radiation B1 ' Standard Current Source (3) Every 3 months. b Turbine first State Pressure A Standard Pressure Source Every 6 months. Permissive I s _~ .., - + ..-.m r ,.,,m

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==. 9 m C M W e C w C K i fJ >K E w us a. E a 2- .C. e N mE i., e o a s. a Z w ag; v .c - w in W a-= a w W. uE e sc a a e C ~K u .a e \\ a 8 o a e zb a z W>m i to W i > me mu 2 2W w o= t em o g, + W. = E C aC Wb w O 2 so S. - b aI o o E ac w M g,. IE bb h WK y g zu a .= >e u E u e c = Z c

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s a z -e oi z wm M. a E' c c-e C =n a a uo e a e i. e a. cw c -= c .c = wo w = >u e AmendmentNo.(4-H4,203 i

i ~ t t Unit 2 i NOTES FOR TABLE 4.1.2 1.. A description of.these groups is included in the bases of this Specification. 2. ' Calibration test is not required on the part.of the system that are-not required to be operable or are tripped but is required prior to return to service. i 3. The current source provides an instrument channel alignment. Calibration using a radiation source shall be made each refueling outage. 4. Deleted. 5. Physical inspection and actuation of these position switches will be performed during the refueling outages. i i 1 .l 1 l Amendment No. 203 l 1

Unit 2 PBAPS

BASIS The reactor protection system automatically initiates a reactor scram to:

1. Preserve the integrity of the fuel cladding. 2. Preserve the. integrity of the reactor coolant system. 3. Minimize the energy which must be absorbed following a loss of l-coolant accident, and prevent inadvertent-criticality. When there is not fuel in the reactor, the scram serves no function; therefore, the reactor protection system is not required-to be operable Allowed out of service times for repair and surveillance testing for Reactor Protection System Instrumentation have been determined in accordance with General Electric report NEDC-30851P-A, " Technical I. Specification Improvement Analyses for BWR Reactor Protection System," l General Slectric Company, March 1988. \\. The reactor protection system is of the dual channel type (Reference subsection 7.2 FSAR). The system is made up of two independent trip systems, each having two subchannels of tripping devices. Each subchannel has an input from at least one instrument channel which . monitors a critical parameter. The outputs of the subchannels are combined in a 1 out of 2 logic; i.e., an input signal on either one or both the subchannels will cause a trip system trip. The outputs of the trip systems are arranged so that a trip on both systems is required to produce a reactor scram. This system meets the intent of IEEE - 279 for Nuclear Power Plant Protection Systems..The system has a reliability greater than that of a 2 out of 3 system and somewhat less than that of a 1 out of 2 system. With the exception of the Average Power Range Monitor (APRM) channels, the Intermediate Range Monitor (IRM) channels, the Main Steam Isolation Valve closure and the Turbine stop valve closure, each subchannel has one instrument channel. When the minimum condition for operation on the number of operable-instrument channels per untripped protection trip system is met or if it cannot be met and the affected protection trip system is placed in a tripped condition, the effectiveness of the protection system is preserved. ] Three APRM instrument channels are provided for each protection trip system. APRM's A and E operate contacts in one subchannel and APRM's C and E operate contacts in the other subchannel. APRM's B, D and F I-are arranged similarly in Amendment No. E, 203 f-l (

PBAPS UNIT 2 4.1 Bases A Channel functional test frequencies for Reactor Protection System instrumentation have been determined in accordance with General Electric report NEDC-30851P-A, " Technical Specification improvement Analyses for BWR Reactor Protection System," General Electric Company, March 1988.

p.. 4gy - - -- - n s ty, 3,. PBAP@- ~ L UNIT 2 l, ' 4.1. Sangt ' (Con'td.)- 1. ~ I Intentionally Left Blank l.' l I Amendment No. 30, 203

_t <;l- -1 + t I P!AP3'- [ H UNIT 2 4 t k .'t -d..' 4.1 Saggi (Con'td.) t '- t t + i i 6 3 Intentionally Left Blank ij t t. I 1 l: ~ i i, I h L I:) r i l.. e 3 i 't ?

r i

r l F [ i Amendment No. 30, 203 53-t

i i PJAPS UNIT 2 ~ .j I 4.1 Rases (Con'td.)- t .i I i I i e l Calibration frequency of the instrument channel is divided into two groups. - These are t as follows: i 1. Passive type indicating devices that can be compared with like units on a continuous basis. 2. Vacuum tube or semi-conductor devices and detectors that drift or lose sensitivity. i h i i t i t i ? ? t l r -53a-Amendment No. 30, 203 -)

PBAP3 UNIT 2 4.1 Bases (Con'td.) P l Intentionally Left Blank 1 Amendment No. 203

6.' PBAPS UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS T !.2 Protectwe instrumentabon 4.2 Protectwo Instrumentshon 3 - A. Primary Containment isolabon Funchons A. Pnmary Contenment laolabon Funchons The primary containment isolation' - Instrumentabon shall be funchonally tested and instrumentation for each function in Table 3.2.A caibrated as indmated in Table 4.2.A.' shaN be Operable;: and, there shall be two Operable or tripped trip systems for each trip ' System logic shsN be funcbonally tested as function. Indicated in Table 4.2.A. bochcabiNtv Whenever Primary Containment Integrity is required.' Conditions and Required Achons. .(1)(2) 1. With one or more chanr'90s required by Table 3.2.A inoperable, place channel in trip within 12 hours for items 1,4, and 5; and, place channel b in trip within 24 hours for items other than 1,4, and5.

2. With one or more automatic functions with -

primary containment isolation function not maintained, restore primary containment isolation capabitty within one hour.(3) 3. If the required action and associated completion - time of Action 1 or 2 are not met, take the action required by Table 3.2.A for the function. (1) When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation - of these Actions may be deleyed for up to 6 hours provided the associated Function maintains primary - containment isolation capabitty. (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the. trip function to occur, in these cases, if the inoperable channelis not restored to Operable status within the required time, the Action required by Table 3.2.A for that trip function shall be taken. (3) This Action not appucable to item 11, Reactor Cleanup System High Temperature. l - 57 Amendment No. 203

q .i _m pgApg i l UNIT 2 UMITING CONDITIONS FOR OPERATION LIMITING CONDITIONS FOR OPERATION-t. l - 3.2 Pmtechve instrumentabon (Conbnued) 4.2 Protecbve Instrumentabon (Continued) - t i - B. Core and containment CMno S.r;.Te - B.~ Core and containment cMna Systems - initation and Control Irybabon and Control Core and containment cooling system initiation. ~ Instrumentation shall be functionally tested, f and control instrumentation for each Trip caNbrated and checked as indicated in j Function in Table 3.2.5 shall be Operable; and, Table 4.2.5. a there shall be two Operable or tripped trip systems for each Trip Function except as noted ' System logic shall be functionally tested as l in Table 3.2.B. Indicated in Table 4.2.B. i Mcability Each Trip Function listed in Table 3.2.5 shall be Operable whenever the system (s)it initiates or controls are required to be Operable as specified in Section 3.5. i Conditions and Raadred Actions: With one or more channel (s) required by Table q 3.2.5 inoperable in one or more Trip Functions, 1 take the Action required by Table 3.2.B. ';t f I 6 Y i I r - 57a - Amendment No. 203

? 1 PBAPS UNIT 2 UMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2 Protechve instrumentabon (Continued)- 4.2 Protectve instrumentation (Continued) f ..r C. Control Rod Block (CRB) Actumbon C. Control Rod Block (CRB) Actumbon j ' The Control Rod Block Actumbon Instrumentation shall be functionally tested, i instrumentation for each function in Table 3.2.C calibrated and checked as indicated in - shall be Operable; and, there shall be two Table 4.2.C. -l Operable or tripped trip systems for each i function except as noted in Table 3.2.C. System logic shall be functionally tested as [ indicated in Table 4.2.C. Acohcotzhty; (1) ' The Rod Block Monitor (RBM) shall be i Operable with setpoints as required by Table 3.2.C and the Core Operating Umits Report ' (COLR). 4 i i The APRM, IRM and SRM Control Rod Block (CRB) functions shall be Operable whenever [ the Reactor Mode Switch is in the Startup or i Run positions except as follows; i The SRM and IRM functions are not 5 . required when the Reactor Mode Switch is in Run. f I The APRM wxi RBM functions are not -i required to be Operable when the Reactor ] Mode Switch is in Startup except for the APRM Upscale (Startup Mode) which is not required to be Operable when the Reactor Mode Switch is in Run. l The scram discharge instrument volume high i level rod block is required to be Operable I whenever the Reactor Mode Switch is in the Startup or Run positions or in the Refuel position whenever more than one control rod is .{ withdrawn. l Conditions and Reatired Actions: With one or more channel (s) required by Table { 3.2.C inoperable in one or more trip functions,

j take the Action required by Table 3.2.C.

~ (1) Section 3.3.B.5 is Applicable during operation with a limiting control rod pattem. - 58 Amendment No. MB, 203

PBAPS UNIT 2 W.lRTING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS i 3.2 Protecbve Instrumentabon 4.2 Protective Instrumentation (Continued). (Continued)

D. Radiation Meeshi Systems-Isolation and D. Radiation Morntorino ' Systems-lW~1 and inibaban Funcbons initisbon Functons D.1.

Reactor 5tildino isolation and Standby Gas D.1. Reactor Buildina isolation and Standbv Gas Treatment System Treatment System The Reactor Building isolation and Standby Instrumentation shall be functionally tested, Gas Treatment System instrumentation for calibrated and checked as indicated in - l each trip function in Table 3.2.D shall be Table 4.2.D. Operable; and, there shall be two Operable or tripped trip systems for each trip System logic shall be functionally tested as i function. Indicated in Table 4.2.D. 6 Applicability Refuel Area Exhaust Morstors and Reactor I Building Area Exhaust Monitors shall be Operable whenever the associated systems are required to be Operable. i Main Stack Monitor shall be Operable whenever the containment is purging and primary containment integrity is required. I h Conditions and Reauired Actions:(1)(2) 1. With one or more channels required by Table 3.2.D inoperable in one or more trip functions, place channel in trip within 24 hours i 2. With one or more automatic Functions with containment isciation capability not maintained, restore containment isolation capability within one hour. 3. If the required actions and associated completion times of Action 1 or 2 are not met, take the Action required by Table 3.2.D. 1 (1) When a channelis piaced in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated Trip Function maintains isolation l capability. (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the Trip Function to occur. In there cases,if the inoperable channelis not restored to Operable status within the required tirpe. the Action required by Table 3.2.D for that trip Function shall be taken. Amendment No. 102, 150, IS', 203 59 - t i 4

p PBAPS . UNIT 3 - 1 LIMITING CONDITIONS FOR OPERATION SURVE!LLANCE REQUIREMENTS 3.2. Protective instrumentabon (Continued) 4.2 Protectwe Instrumentabon (Continued) D. - Radiation Monitorina Systems-isolabon and D. Radiation Mor*~ino S=5ms-Isolation and Inikation Funchons inihabon Funchons (Continued). (Continued) i D.2 - Main Control Room D.2 Main Control Room [. The limiting condibons for operation are given in Table 3.2.D. Instrumentabon shan be functionaHy tested, cabbrated and checked as indicated in Table 4.2.D. 3 i E. Drvwell Leak Detection E. Drvwell Leak Detection i The Emiting condibons of operation for the instrumentation shall be ceNbrated and f instrumentabon that monitors drywell leak checked as indicated in Table 4.2.E. detochon are given in Section 3.6.C.- i " Coolant Leakage". t F. SurveiNance frArir=R-ri R==daL@ F. Survelhance Informahon Readouts 'I The Erniting conditions for the instrumentabon shah be co8brated and h instrumentation that provides surveillence checked as indicated in Table 4.2.F. l information readouts are given in Table 3.2.F. ' f! I'I l I 1 - 59a - Amendraent.No. 203 I i

t PSAPS. i UNIT 2 i iUMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2 Protechve instrumentabon (Continued). 4.2 Protechve Instrumentaban (Continued) ' ( ' G. Altomate Rod insarbon (ARl) and G. Altemate Rod inserbon (ARis and l Rearculmbon Pump Tno (RPT) Recirculaban Pumo Trio (RPT) ) Two trip systems consisting of two channels per' Each RPT and ARI instrumentation channel' trip system for each instrumentation function ~ shall be demonstrated Operable by the - that initlates an Altemate Rod Insertion (ARI) performance of the instrument Check, scram and trips the reactor recirculebon pumps instrument Functional Test, Channel Calibration, l (RPT)in Table 3.2.G shall be Operable; and, - and Logic System Functional Test at the + the manual and automatic actuation logic and Frequencies shown in Table 4.2.G, actumbon devices of both trip systems shall be. Operable i Apohcatality 1 Whenever the Reactor Mode Switch is in the i Startup or Run positions. t Conditions and Raashed A@is:(1)(2) 1. With one or more channels required by Table 3.2.G inoperable, restore channel to Operable status or place channelin trip within 14 days.(3)

2. With one instrument function with trip capabiity not maintained, restore trip
I capability within 72 hours 3.

With both instrument functions or an actuation device with trip capability not j maintained, restore trip capability for one i function within 1 hour. 4. If the required actions and associated completion times of Action 1,2 or 3 are not l met, place the reactor in shutdown or refue! mode Wthin 8 hours. 'i-! (1) When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated Trip Function maintains ARl/RPT trip capability, t i (2). An inoperable channel or trip system need not be placed in the tripped condition where this would l cause the Trip Function to occur. In these cases, if the inoperable channelis not restored to Operable status Wthin the required time, the Action required by Condition 4 for that trip Function shall be taken. i (3) The action of placing the channelin trip is not applicable if the inoperable channelis the result of an inoperable breaker. I i - so. Amendment No. 441, 203 l i i

m Table 3.2.A INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION Minimum No. of Operable Instrument Channels per Number of instrument Action l Item Trip System Instrument Trip Level Setting Channels Provided by Design (2) 1 2 (6) Reactor Low Water Level = 0" indicated Level (3) 4 Inst. Channels A 2 1 Reactor High Pressure s 75 psig 2 Inst. Channels D (Shutdown Cooing isolation) 3 2 Reactor Low-Low-Low at or above -160" indicated 4 inst. Channels A Water Level level (4) 4 2 (6) High Drywell Pressure s 2 psig '4 Inst. Channels A Y 5 2 High Radiation s 15 X Normal Rated fun 4 inst. Channels B m Main Steam Une Tunnel Power Background (8) N m 6 2 Low Pressure a 850 psig (7) 4 Inst. Channels B E Main Steam Une h 7 2 (5) High Flow s 140% of Rated Steam Flow 4 Inst. Channels B Main Steam Une ? 8 2 Main Steam Une Tunnel s 200 Deg. F (9) 4 Inst. Channels B B Exhaust Duct High Temperature / r? "e zx u e y-w-r te -v qy.- .+ g9w-v vgg+-r,a-ww-g-, - -+gri--e.---g--wsw-e g-- s-mg-- ww +-w w -w-um e- -+.w w -*h- - - 3= y~'- e-- -.a um ,+m-mud

Table 3.2.A INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION Minimum No. of Operable instrument Channels per l Item Trip System Instrument Trip Level Setting Channels Provided by C;4-. (2) Number of Instrument Action 9 2 Main Steam Une - s 200 Deg. F 4 Inst. Channels - B Leak Detection High Temperature 10 1 Reactor Cleanup System s 300% of Rated Flow. 2 Inst. Channels '. C High Flow 11 1 Reactor Cleanup System s 200 Deg. F 1 Inst. Channels E High Temperature - y 12 2 Reactor Pressure s 600 psig 4 Inst. Channels F g IB (Feedwater Flush to System Interlock) - I% S~ 0 .? ra? Z R^ ro W e-g-e,e&he e mweeas--ww-40-P T- '*Av-T-h- L+ee-'sL'" fed & -e Ma***ww-D-' tem'- erWe-f'*e4-9hef'b==t-4*-W-r"- -e-+ -wh---# "P--?=*e-*:-m-set

^MwW-t's-e

-+mw n'M 9+ D=- w"-=r"'t-w-"w ev e - aT-

r-P-ew*uf-e-

= - 'f e t en-r e.ev'T-*'me=r+4eW+- dem-to---m-s 'wm -mw-1

l PBAPS NOTES FOR TABLE 3.2.A 1. Deleted 2. If the required actions and associated completion time of Specification 3.2.A, Actions 1 or 2 are not met, take the action listed below for the'affected Trip Function as required by Table 3.2.A. A. Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24 hours. B. Initiate an orderly load reduction and have Main Steam Lines isolated within 12 hours. 1 C. Isolate Reactor Water Cleanup System within 1 hour. l D. Isolate Shutdown Cooling within 1 hour. I E. Isolate Reactor Water Cleanup Filter Demineralizers unless the following provision is satisfied. The RWCU Filter Demineralizer may be used (the isolation overridden) to route the reactor water to the main condenser or waste surge tank, with the high temperature trip inoperable for up to 48 hours, provided the water inlet temperature is monitored once per hour and confirmed to be below 180 degrees F. F. Isolate Feedwater Flush System within 1 hour. 3. Instrument setpoint corresponds to 538 inches above vessel zero. 4. Instrument setpoint corresponds to 378 inches above vessel Zero. 5. Two required for each steam line. 6. These signals also start SBGTS and initiate secondary containment isolation. '1 7. Only required in Run Mode (Interlocked with Mode Switch). 8. An alarm will be tripped in the control room to alert the control room operators to an increase in the main steam line tunnel radiation level. Amendment No. 82, 101, Ill, 117, M9, 203

UNIT 2 TABLE 3.2.B INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of Number of Operable Instrument instrument Channels per Trip Channels Provided System (ACTION) Trip Function Trip Level Setting by Design - Remarks l2 (14) (15) Reactor Low-Low 2-48 in, indicated level 4 HPCI & RCIC Initiates HPCI & RCIC. Water Level Inst. Channels g 2 (8) (11) (15) Reactos ' ow-Low-Low a-100 in. Indicated level 4 Core Spray & 1. In conjunction with Low Reactor Water Level (4) RHR instrument Pressure initiates Core Spray. j Channels and LPCI. 4 ADS Instrument 2. In conjunction with conRrmatory Channels lowlevel Ffgh Drywell Pressure. R .2 120 second time delay, and LPCI f. or Core Spray pump interlock Initiates Auto Blowdown (ADS). 5 ~ 3. Initiates starting of Diesel Generators. l 5 -4 N saery

==.T wyew-- .w --__._.y -s-- +-vry-,-,w% ly-y v va F e w-4'We 9=' M-w-- e' e 73='T' T* e-m w e,es w m

UNIT 2 TABLE 3.2.B (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of Number of Operable Instrument instrument Channels per Trip Channels Provided System (ACTION) Trip Function Trip Level Setting by Design Remarks 2 (9) (16) Reactor High Water s +45 in. Indicated level 2 Inst. Channels Trips HPCI & RCIC turbines. Level 6l1 (8) (15) Reactor Low Level z+312 in above vessel 2 Inst. Channels Prevents inadvertent opera 6cn of .i (inside shroud) zero (2/3 core height) containment spray during acddent y V' conditions. j 2 (8) (15) Containment 1 (P (2 psig 4 Inst Channels Prevents inadvertent operation of High Pressure contenment spray during accident conditions. t l 1 (11)(15) Confirmatory Low Level a +6 in. Indicated level 2 Inst. Channels ADS Permissive. e 5 l 2 (8) (11)(14)(15) High Drywell Pressure s2 psig 4 Inst. Channels

1.. initiates Core Spray; LPCl; z

-HPCI.-~

2. Initiates starting of Diesel m

Generators 3. Initiates Auto Blowdown (ADS)in c2 conjunction with Low-Low-Low Reactor water level,120 second g time delay, and LPCI or Core w Spray pump running. i n ,--a --n.r... -- c,- n-..,, - ..w v- ..n. - - - ~, - - e n., ,,,-a, -n.

n UNIT 2 TABLE 3.2.B (continued) t INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Mirimum No. of Operable Instrument Number of Channels per Trip Instrument l System (ACTION) Trip Function Trip Level Setting Channels Provided Remarks by 0+ l 2 (9) (15) Reactor Low Pressure 400 - 500 psig 4 inst. Channels Permissive for opening Core Spray and LPCI Admission velves. Comcident with high drywell pressure, starts LPCI and Core g Spray pumps. g l2 (9) (15) Reactor Low Pressure 200 - 250 psig 4 Inst. Channels Permissive for closing Recirculation ll Pump Discharge Velve. ,i l1 (13) (16) ~ Reactor Low Pressure 50 s P s 75 psig 2 Inst. Channels in conjunction with PCI signal-c.j permits closure of RHR (LPCI) inbetion valves. r w t

^ UNIT 2 - TABLE 3.2.B (Continued) INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of OpereNe instrument Number of Charmels per Tdp Instrument Channels l System (ACTION) Trtp Functon Tdp Level Seteng Provided by Design Remarks 2 (9) (15) Core Spray Pump 6

1 sec.

4 Emers M pumps -loss of allhlte power only. l Start Timer 13 sec.

7% of seteng 2 Smers A & C pumps - oWelte power eveReWe.

23 sec. t 7% of settng 2 Smers B & D pumps - ellhtte power eveHeble. 1 per 4kV bus (7) 480V Emergency Load 310.5 sec. 4 9mers M Emers -loss of oWelle power only. - Center Timer 2 (9) (15) LPCI Pump Start Timer 2 sec.

7% of settng 4 9mers LPCI pumps A & B.

4l y (Four Pumps) 8 sec. i 7% of seting 4 9mers LPCI pumps C & D. {- .(n 1 (12) (15) ADS Actuolon Timer 90 st s120 seconds 2 Emers in cor@mcGon wigi Low Reactor Water Fl Level, High Drywen Pressure and LPCI or Core Spray Pump rurwing inledock, i inisates ADS. l2 (12) (15) ADS Bypass Timer 8 st s10 minutes 4 Emers in conjuncGon vdth Low Reactor Water Level, bypasses high dryweR pressure 2 .o inisolon of ADS. l 0l 2 (12) (15) RHR (LPCI) Pump 50 i 10 poig 4 channels Defers ADS actuolon peming w-Discharge Pressure contrmelon of Low Pressure Core Intedock CooRng system operaton (LPCI Pump . g running inledock). o-Ul2 (12) (15) Core Spray Pump 185 t to peig 4 channels Defers ADS actuoson pem5ng l Discharge Pressure conermelon of Low Pressure Core Intedock ' Cooling system opereGon (Core Spray Pump running inledock). E4 o N l l m ., ___,,_.,m.., m . ~ _.. _, _ _ _.,, _. __ ,,s._ ..m_.,. ,,..um.,.-,_. m m.m.

UNIT 2 TABLE 3.2.8 (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of Operable Instrument Channels per Number of Instrument l Trip System (ACTION) Trip Function Trip Level Setting C+s;gn Remarks Channels Provided by l 1 (8) (16) RHR (LPCl) Trip System NA-2 Inst. Channels Monitors availabilty of bus power monitor power to logic systems. l 1 (8) (16) Core Spray Trip System NA 2 Inst. Channels Monitors availabilty of bus power monitor b 9' power to logic systems. o l 1 (8) (16) ADS Trip System NA 3 Inst. Channels Monitors availability of o bus power monitor 0' power to logic systems. l 1 (8) (16) HPCI Trip System NA 2 Inst. Channels Monitors availability of bus power monitor power to logic systems. { 1 (8) (16) RCIC Trip System NA 2 Inst. Channels Monitors availabilty of a bus power monitor power to logic systems.- a P w m \\ ~. -..-

UNIT 2 TABLE 3.2.B (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of Operable Number ofinstrument

instrument Channels per Channels Provided by 1 Trip System (ACTION)

Trip Function Trip Level Setting Design Remarks 1 (8) (16) Core Spray Sparger 1 (plus or minus 1.5) psid 2 Inst. Channels Alarm to detect core to Reactor Pressure spray sparger pipe break. Vessel d/p 2 (10) (15) Condensate Storage Greater than or equal to 2 Inst. Channels Provides interlock to 6> Tank Low Level 5' above tank bottom HPCI pump suction y 3 P valves. J-2 (10) (15) - Suppression Chamber Less than or equal to 5" 2 Inst. Channels Transfers HPCI pump f High Level above torus midpoint suction to suppression g chamber. S 5 2 (10) (15) Condensate Storage Greater than or equal to 2 Inst. Channels Transfers RCIC pump g Tank Low Level 5' above tank bottom suction to suppression chamber. 53 l' ~e zw n = m--

i--

m

7 - UNIT 2 TABLE 3.2.8 (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS-THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of Operable Number of Instrument instrument Chanrels per Channels Provided by : l Trip System (ACTION) Trip Function Trip Level Setting Dessgn Remarks l 1 (13) (15) RCIC Turbine High Flow s 450" H O (2) 2 Inst. Channels 2 l 1 (13) (15) RCIC Turbine High Flow 3 i i seconds 2 Inst. Channels Time Delay l 2 (13) (15) RCIC Turbine s 200 deg. F (2) 4 Inst. ) y Compartment Well ) 16 Inst.- ,g l 6 (13) (15) RCIC Steam Line s 200 deg. F (2) ) 13 Area Temp. - 12 Inst.' ) l 2 (13) (15) RCiC Steam Line ~ 100 ) p ) 50 psig - (2) 4 Inst. Low Pressure Egl 1 (13) (15) HPCI Turbine Steam Line s 225" H O (3) 2 Inst. Channels 2 g-High Flow .5l 1 (13) (15) HPCI Turbine High Flow 3 i 1 seconds 2 Inst. Channels z Time Delay w m t s _.+,.E.- w -,* awe.,

v.~+ww-s,**e*-+.-a

- w ww.w e. .e----w-=- 'we,.=*= w.,w+ - + vv---*w+vw ww---+-w. +',.r-~w 3-,-rw-.eer.,-- e r+~- * - +.e.- - - h w + ~ w e-e.=w e em w r eva ++ e<= we ,w-m

TABLE 3.2.B (continued) - UNIT 2 INSTRUMENTATION THAT INITIATES OR CONTROLS' THE CORE AND CONTAINMENT COOLING SYSTEMS Mirimum No. of Operable ~ Number of Instrument inst - Channels per Channels Provided by Trip System (ACTION) Trip Function Trip Level Setting: Design Remarks l4 (5) (13) (15) HPCI Steam Une 100 )p )50 peig (3). 4 Inst Low Pressure. l2 (13) (15) HPCI Turbine s200 deg.-F - (3) 4 Inst ) Compartment ) Temperature ) 4 (13) (15) HPCI Steam Une s200 deg. F (3) 8 Inst.' ) - 16 Inst Area Temperature ) i' N 2 (13) (15) HPCl/RHR Valve Station s200 deg. F (3) 4 Inst.. ) 3 Area Temperature )- ]- 1 (1) LPCl Cross-Connect NA 1 Inst initiates annunciation Position when valve is not closed. 1 per 4 kV bus (1) 4 kV Emergency Bus 25% (iS%)

1. ~ Trips 'all loaded g

Undervoltage Relay of Rated Voltage breakers. (HGA) 2. Fast transfer Q-permissive. 3. Dead bus start of ' '+ dieselJ i z ? I per 4 kV bus (1) 4 kV Emergency Bus 95% (+0%, -10%) Pernuts sequential g Sequential Loadng Relay of Rated Voltage starting of vitalloads (SV) B w- . C_ w b -w-w 9 Ei+r -*c-

h.a e,

mN e-Ft.mm 4 e-.Ne+t----mir vTP-m. e YWw'ms-1 -=r ""+e

--tr'-*IFW w

T4r-e de' 'LTN9 Ts.--e e

4

stNi-' -7 '-*Eurd-" SW eW e Ty L w e*- -zu e w'41'T=9'- 7 WFim'- vm e

a UNIT 2 TABLE 3.2.B. _ (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Mirimum No. of Operable Number of Instrument instrument Channels per Channels Provided by l Trip System (ACTION) Trip Function Trip Level Setting Design Remarks l 2 per 4 kV bus (1) Emergency Transformer 80% (iS%) 1. Trips emergency I Undervoltage (IAV) of rated voltage. transfer feed to 4kV (Inverse time-voltage) Test at zero volts in. emergency bus. 1.8 seconds (i10%). 2. Fast transfer permissve b9 l 2 per 4 kV bus (1) Degraded voltage (27N) 98% of rated voltage

1. Trips emergency 5'

("non-LOCA" relay) 10.3% of setting transformer feed to (4077 volts i 12 volts) 4kV emergency bus. 0.9 - 1.1 second internal 2. Fast transfer time delay permissive. 80 second i 5% (13 sec.) { time delay 5. l l 2 per 4 kV bus (1) Degraded voltage (27N) 89% of rated voltage 1. Trips emergency ("LOCA" relay) 10.3% of setting. transformer feed to g (3702 volts i 11 volts) 4kV emergency bus. 0.9 - 1.1 second intemal 2. Fast transfer 3 time delay permissive. i 3. Safety injection signal l g 9 second i 7%(10.6 sec.) required. l y time delay - E$ i. -r t0 I i i. _-__m___._______.__________________.___,.m_____z.._..-<i--.._.,2_._ _.,c.,--_.,-____-.m_ . m

.g UNIT 2 TABLE 3.2.8 (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS j. THE CORE AND CONTAINMENT COOLING SYSTEMS 1 k Minimum No. of Operable Instrument Channels per Number of Instrument l Trip System (ACTION) Channels Provided by Trip Function Trip Level Setting Design Remarks l 2 per 4 kV bus (1) Emergency Transformer 87% (15%) of Rated

1. Trips emergency Degraded voRage VoRage.

transformer feed to (Inverse time - voRage). Tests at 2940 voRs in 30 4kV emergency bus. (CV4) seconds (110%) 2. Fast transfer permissive. Y G it c+ F ? "o 63 m

.. 7 .. ~. "t. i Unit 2 PBAP3 1 NOTES FOR TABLE 3.2.B i - 1. With one or more required channel (s) inoperable in one or more Trip Funcbons, place channel j in trip within one hour or the reactor shall be placed in the Cold Shutdown Condibon within -l 24 hours. l + l ' 2. Close isolabon valves in RCIC subsystem.' 'ft 3.' Close isolabon valves in HPCI subsystem. - 4. Instrument setpoint corresponds to 378 inches above vessel zero. i l Si HPCI has onh one trip system for these sensors. Sc Deleted l 7. The failure of a 480V Emergency Load Center timer could result in the failure of a 480V ] Emergency Load Center to re-energize following the loss of one or both offsite sources. Therefore, Technical Specification 3.9.B.7 will apply when a 480V Emergency Load Center l timer is not Operable. } 8. With one or more required channel (s) inoperable in one or more Trip Funcbons: 1. Within 24 hours, place inoperable channel in trip; and, 2. Within one hour from chscovery of loss of feature initiation capability in both trip systems l l for feature (s) supported by this trip funcbon, declare supported feature (s) inoperable l (See Footnote (1)); j 3. If required schons and assocated complebon times of Action 1 or 2 are not met, l deciere assoasted supported features inoperable immediately. ( i 9. With one or more required channel (s) inoperable in one or more Trip Funcbons i' 1. Within 24 hours, restore channel to Operable status; and, i 2. Within one hour from decovery of loss of initiation capabitty in both trip systems for ~l i feature (s) supported by this trip function, declare supported feature (s) inoperable (See Footnote (2)). i 3. If required actions and assometed completion times of Action 1 or 2 are not rnet, { ^ declare associated supported features inoperable immediately. i . 10. With one or more required channel (s) inoperable in one or more Trip Functions: 1. Within 24 hours, place inoperable channelin trip or align affected (HPCI or RCIC) pump i suction to suppression pool; and,- { 2. Within one hour of decovery of loss of initiation capability, declare affected system l (HPCI or RCIC) iraperable if associated pump suction is not aligned to suppression i pool. i 3. If required actions and associated complebon times of Action 1 or 2 are nct met, declare assocasted system inoperable immediately. i 1 (1) Only applicable to the High Drywell Pressure and Reactor Low-Low-Low Water Level functions. l (2) Not applicable to Reactor High Water level Function. I i i t

Amendment No. Ill, 113, 173, 203 l

l.;

i t .p .PBAPS i l t 11. With one or more required channel (s) inoperable in one or more Trip Functions: l 1. ' Within one hour from decovery of loss of ADS initiation capability in both trip systems,. ~! declare ADS valves inoperable; and, 2. Within 96 hours from descovery of inoperable channel concurrent with HPCI or RCIC i inoperable, place inoperable channel in trip; and, j 3. Within 8 days from decovery of inoperable channelif both HPCI and RCIC are -i Operable, place inoperable channelin trip. t 4. If required schons and associated completion times of Action 1 or 2 or 3 are not met, declare ADS inoperable immodately, j 12. With one or more required channel (s) inoperable in one or more Trip Functions: 'f 1. Within one hour from decovery of loss of ADS inibabon capability in both trip systems, declare ADS valves inoperable; and, 2. Within 96 hours from discovery of inoperable channel concurrent with HPCI or RCIC j inoperable, restore channel to Operable status; and, i 3. Within 8 days from decovery of inoperable channelif both HPCI and RCIC are Operable, restore channel to Operable status. { 4. If required actions and assocated complebon times of Action 1 or 2 or 3 are not met, declare ADS inoperable immodately. i 13. With one or more required channel (s) inoperable in one or more Trip Functions: l 1. Within 24 hours, piece channelin trip; and, i 2. Within one hour from dscovery of one or more automatic functions with primary i containment isolation capability not maintained, restore primary isolation capability. 3. If required schons and associated complebon times of Action 1 or 2 are not met, isolate affected penetration flow path (s) within one hour. [ i 14. With one or more required channel (s) inoperable in one or more Trip Funcbons-1. Within 24 hours, place inoperable channel in trip; and, 2. Within one hour from descovery of loss of system (HPCI or RCIC) initiation capability, declare affected system (HPCI or RCIC) inoperable. 3. If required actions and associated completion times of Action 1 or 2 are not met. declare affected system (HPCl or RC)C) inoperable immediately. 15. When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of required Actions may be delayed for up to 6 hours provided j associated Trip Function maintains trip capability. 16. When a channelis placed in an inoperable status solely for performance of required f Surveillances, initiation of required Actions may be delayed for up to 6 hours. j I !j 1 l i i - 72a - Amendment No. 203 )

Unit 2 TABLE 3.2.C INSTRUMENTATION THAT INITIATES CONTROL ROD BLOCKS Minwnum No. of Operable Number of Instrument Channels instrument Channels Per Trip System Instrument Trip Level Setting Provioed by Design Action l 4 (2) APFtM Upscale (Flow Biased) (0.66W+S4%-0.6thW) 6 Inst. Channels (10) (14) (Clamp at 108% max) 4 APRM Upscale (Startup Mode) s 12% 6 Inst. Channels (10) (14) 4 APRM Downscale = 2.5 indicated on scale 6 Inst. Channels (10) (14) 1 (7) (11) (13) Rod Block Monitor (RTP a85%), S sHTSP 2 inst. Channels (12) (14) pa (Power Biased) (65% sRTP <85%), Sag slTSP 4 (30% sRTP <65%), Sgg sLTSP Wl 1 (7) (11) (13) Rod Block Monitor Downscale aDTSP 2 inst. Channels (12) (14) ] 6 IRM Downscale (3) a 2.5 indicated on scale 8 Inst. Channels (10) Fg 6 IRN Detector not in Startup Position (8) 8 Inst. Channels (10) k 6 lRM Upscale s 108 indicated on scale 8 Inst. Channels (10) E g 2 (5) SRM Detector not in Startup (4) 4 Inst. Channels (1) Posmon 5 2 (5)(6) SRM Upscale s 10 counts /sec. 4 Inst. Channels (1) ? "."i 1 (15) Scram Dacharge Instrument s 25 gallons 1 Inst. Channel (9) Volume High Level 8~0 c ow ro -.- a--

1 PBAPS UNR 2 i l NOTES FOR TABE 3.2.C [ 1. If the first column cannot be met for one of the two trip systems, this condklon may exist for up to seven days provided that during that time the operable system is functionally tested immediately and daily thereafter; if this condtion lasts longer than seven days, the system shall be tripped if the first column cannot be met for both trip systems, the systems shall be tripped. W = Loop Recir' ulation flow in percent of design. 2. c Trip level setting is in percent of rated power (3458 MWt). aW is the difference between two loop and single loop offective recirculation drive flow rate at the same core flow. During single loop operation, the reduction in trip setting is accomplished by correcting the flow input of the flow biased rod block to preserve the original (two loop) relationship between the rod block setpoint and recirculation drive flow. 4W = 0 for two loop operation. 3. IRM downscale is bypassed when k is on its lowest range. t 4. This function is bypassed when the count rate is 2: 100 cps. 5. One of the four SRM inputs may be bypassed. 6. This SRM function is bypassed when the IRM range swkches are on range 8 or above. 7. The trip is bypassed when the reactor power is s 30% 8. This function is bypassed when the mode swkch is placed in Run. I i P i l Amendment No. 23, is, 79, 73, ,74 -123, 150, 102, 190, 203 t

q 1 PBAPS UNIT 2 ' NOTES FOR TABLE 3.2.C (Cont.) i 9. If the number of operable channels is less than required by the minimum operable channels per trip function requirement, place the inoperable channel in the tripped condition within twelve hours.- 1 1

10. -

For the Startup (for IRM rod block) and the Run (for APRM rod block) positions of the Reactor Mode Selector Switch and with the number of OPERABLE channels: One less than required by the Minimum OPERABLE Channels per Trip a. Function requirement, restore the inoperable channel to OPERABLE status - within 7 days or place the inoperable channel in the tripped condition within the next hour, i .1 b. Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped . condition within one hour. l 11. The values of HTSP, ITSP, LTSP and DTSP are specified in the CORE OPERATING LIMITS REPORT. 12. With one or more required Rod Block Monitor channel (s) inoperable: a. With one rod block monitor (RBM) channel inoperable, restore RBM channel to l Operable status within 24 hours. i b. If the required action and associated completion time in Action a above are not met, place one RBM channel in trip within 1 hour. [ With 2 RBM channels inoperable, place one RBM channel in trip within 1 hour. .l c. 13. Section 3.3.B.5 is Applicable during operation with a limiting control rod pattem. l 14. When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated function maintains control rod block capability. 15. The scram discharge instrument volume has only one trip system. i l 1 l i -74a-03' OI. T, 102, 203 i - -.. _ _ - -. - _ _ _ -. _ _. _ _. _ _ _ _ - - _. _. + -, ~

t TABLE 3.2.D Unit 2 RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE SYSTEMS Minimum No. of - l Operable Instrument Number of Instrument Action Channels l Per Trip System Trip Function Trip Level Setting by Design Channels Provided (1) 2 Refuel Area Exhaust Monitor Upscale, <16 mr/hr 4 Inst. Channels A or B 2 Reactor Building Exhaust Upscale, <16 mr/hr 4 Inst. Channels B l Monitors 1 Main Stack Monitor Upscale, s 10' cps. 2 Inst. Channels .C 2 (2) Main Control Room Upscale, <400 cpm 4 Inst. Channels D 4 Notes for Table 3.2.D E V' rn

1. Action 2-8 A. Cease operation of the refueling equipment.

5. B. Isolate secondary containment and start the standby gas treatment system. g C. Cease purging of primary containment, and close vent and purge valves greater than 2 inches in diameter. ] D.. As described in LCO 3.11.A.5. l %N 1 j

2. The trip function is required to be operable whenever secondary containment is required on either unit.

a l s' <? C I O~ n 1 l

2 TABLE 3.2.G Unit 2 INSTRUMENTATION THAT INITIATES ALTERNATE ROD INSERTION AND RECIRCULATION PUMP TRIP Minimum No. of Number of Operable Instrument Instrument Channels Channels Provided by Design ' Per Trip System Instrument Trip Level Setting per Trip System 2 Reactor High Pressure s 1120 psig 2 2 Reactor Low-Low Water Level 2 -48 in. indicated level 2 m$x lir - g. an bd b O C E w. M

- =-. p . r. s 1 + Unit 2 < TACLE 4 2.A. MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS Instrument Channel (5) Instrument Functonal Test ' Cairbraton Freauency Melmment Check

1) Reactor High Pressure Once/ 3 months Once/3 months None:

' (Shutdown Cooling Permissive)

2) Reector Low-Low-Low once/3 months - (3)

Once/opereeng cycle Once/ der Water Level (7)

3) Main Steam High Temp.

Once/3 months (3). Once/operstng cycle OnceMey o

4) Main Steam High Flow (7)

Once/3 months (3) Oncoloperelmg cycle OnceMoy

5) Main Steam Low Pressure Once/3 months Once/3 months None

6) Reactor Water Cleanup Once/3 months Once/3 months OnceMey High Flow

7) Reactor Water Cleanup Once/3 months Once/3 months None

- High Temp.

8) Reactor Pressure Once/3 months

~(3) Once/bperetng cycle - OnceMey (Feedwater Flush Perneseve) 1 . on . 9 Loaic System Functonal Test (4) f6) Freauency ] }

1) Main Steam Line isoleton Vvs.

Once/operetng cycle Main Steam Line Drain Vvs. O-Reactor Water Sample Vvs: 5 N

2) RHR -Isolaton Vv. Control Once/operstng cycle z

Shutdown Cooling Vys, P Head Spray

3) Reactor Water Cleanup Isolaton Once/operstng cycle M

4) Drywell isoleton Vvs.

Once/operseng cycle TIP Wthdrawal Atmospheric Control Vvs.

3

- Sump Drain Valves

5) Standby Gas Treatment System Once/operstng cycle jo Reactor Building isolaton g

~ H o N: g m m _m.__.__._-__m,...mm____m.,...m...-, -.,_.m#,..ew....- .m.%-.,,m, c-..,...%%,.... ..m~.,*-,.,-,..., --m,,m.m m.e.,--me ,m.1-.,m m.%._m...,,-m

4 Unit 2 TABLE 4.2.B MINIMUM TEST AND CAllBRATION FREQUENCY FOR CSCS Instrument Channel Instrument Functional Test Calibration Frequency Instrument Check l 1) Reactor Water Level (7) Once/3 months (3) Once/ operating cycle Once/dsy _ l 2) Drywell Pressure (7) Once/3 months (3) Once/ operating cycle Once/dsy l 3) Reactor Pressure (7) Once/3 months (3) Once/ operating cycle Once/dsy l 4) Reactor Pressure - Once/3 months Once/3 months None PCISILPCI interlock 5) Auto Sequencing Timers NA Once/ operating cycle None ? l 6) ADS - LPCI or CS Pump Once/3 months Once/3 months None Disch. Pressure Interlocks 'fg g l 7) Trip System Bus Once/3 months NA None g Power Monitors [ l 8) Core Spray Sparger d/p Once/3 ' months Once/6 months Once/ day N l 9) Steam Line High Flow Once/3 months Once/3 months None F. (HPCI & RCIC) ~ 10) Steam Line High Flow Timers NA Once/ operating cycle None (HPCI and RCIC) t o l 11) Steam Line High Temp. Once/3 months (3) Once/ operating cycle - Once/ day d (HPCI & RCIC) 8 l 12) Safeguards Area High Temp. Once/3 months Once/3 months None a ,m g u w--t--ev-wwr -w-eeav tee --- - -, - - - +-7-e- + ---erc' w e-t-w -t-t+- wr 1m'+-+--w'te--t-a=-t-t--w+----t--wa--- -&4-sm-T 1-me ~ w -tet e --me -se at-e

gy m.' s Unit 2 : TABLE 4.2.B (continued) MINIMUM TEST AND CALIBRATION FREQUENCY FOR CSCS Instrument Channel Instrument Functional Test Cahbration Frequency Instrument Check. 13) HPCI and RCIC Steam Line Once/3 months Once/3 months None Low Pressure 14) HPCI Suction Once/3 months Once/3 months None Source Levels 15) 4KV Emergency Power System _ Ors'cpeT4ing cycle Once/5 years None Voltage Relays (HGA,SV) 16) ADS Relief Valves Bellows Once/ operating cycle Once/ operating cycle None Pressure Switches

]

17) LPCl/ Cross Connect Once/refuehng cycle N/A N/A-3 Valve Position k 18) Coridensate Storage Once/3 months Once/operahng cycle Once/doy E Tank Level (RCIC) (7) S ?. 19) 4KV Emergency Power Source Once/ month Once/ eighteen months ' None 3 2o Degraded Voltage Relays (IAV,CV-6,lTE)

s?

6e w.$ j t (y i -C-w E -4 4 N-I y y-y-m-ny-e t =m - te ov*wvu-+..ga twk-4wwe-ege==ev.-Tp--t.<Nwi n- ,W_pW'" vvdte-=e-Te f y1 -9 ew1ep ereef '* 4 e.. W9e =*w-w' m g-=%w & D e-1's-s-ei= 4 e we =P w--4 w-e e W 6siatet ase g ec +$ e w e y g=hr-egeww @se tw w aeW e = wv%.ew***NP mh W geFr -M S*m-Vk&8eWhW= TM% MeWee8'id'Ea'n-e u

Br' % e dm V" B'W'

--M@-w 1 i

^ ~ s TABLE 4.2.C Unit 2 - MINIMUM TEST AND CAllBRATION FREQUENCY FOR CONTROL ROD BLOCKS ACTUATION Instrument Channel Instrument Functional Test Calibration Instrument Check

1) APRM - Downscale Once/3 months (3)

Once/3 months Once/ day. l

2) APRM - Upscale Once/3 months (3)

Once/3 months Once/ day

3) IRM - Upscale (2)(3)

Startup or (2) Control Shutdown

4) lRM - Downscale (2) (3)

Startup or (2) Control Shutdown

5) RBM - Upscale Once/3 months (3)

Once/6 months Once/ day 4, l

6) RBM - Downscale Once/3 months (3)

Once/6 months Once/dey .f Y

7) SRM - Upscale (2) (3)

Startup or (2) i Control Shutdown k

8) SRM - Detector (2)(3)'

N/A E Not in Startup Position (2)_ s k

9) IRM - Detector (2)-(3)

N/A Not in Startup Position (2)

10) Scram Discharge Quarterly Once/ Operating Cycle N/A jE Instrument Volume - High Level G

o Loaic System Functional Test (4) (6) Frequency

1) System Logic Check Once/ Operating Cycle I

~b$ C E -4 b PJ ~

TABLE 4.2.D Unit 2 MINIMUM TEST & CAllBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS Instrument Channels instrument Functional Test Calibration Instrument Check (2) l

1) Refuel Area Exhaust Once/3 months Once/3 months Once/ day Monitors. Upscale l 2) Reactor Building Area Once/3 months Once/3 months Once/dey.

3) Main Stack Monitor Once/3 months Once/12 months Once/doy as described in 4.8.C.4.a

4) Main Control Room Once/3 months Once/18 months Once/dey as described in 4.11.A.5 Loaic System Functional Test (4) (6)

Fi m ncy f

1) Reactor Building isolation Once/ Operating Cycle N

2) Standby Gas Treatment System Actuation Once/ Operating Cycle d*r+

J C. .h u m8 ~ .m .-a o---,., = - = -, -.., e w-m.~m -r-- .-.. + - + e,,. + =w c >4-- m

.u TABLE 4.2.E Unit 2 MINIMUM TEST & CAllBRATION FREQUENCY FOR DRYWELL LEAK DETECTION ' Instrument Channel Instrument Functional Test Calibration Frequency instrument Check l

1) Equipment Drain Sump Once/ month Once/3 months Once/ day Flow Integrator

2) Floor Drain Sump Once/ month Once/3 months Once/ day _ -

Flow Integrator l

3) Crywell Atmosphere Once/ month Once/3 months Oncelday Radior ctivity Monitor.

b m a v m a 'N M + C E -4 N l I -. _. -,, -..,. _,... - _.........,..,,..... _.,..... - ~.. -........ -. -...., ...-,.,.....-4,..._,4.-..~,.~,._.~.. ..s... ...._.--.,__..-..._,__.._..-m.

PbAP3 UNFF2 NOTES FOR TABLES 4.2.A THROUGH 4.2.F. 1. Deleted. 2. Functional tests, calibrations and instrument checks are not required when these instruments are not required to be operable or are tripped. Functional tests shall be performed before each startup with a required frequency not to exceed once per week. Calibrations shall be performed within 24 hours before each startup or controlled shutdown with a required frequency not to exceed once per week. i Instrument checks shall be performed at least once per day during those periods when the instruments are required to be operable. 3. This instrumentation is excepted from the functional test definition. The functional test will consist of injecting a simulated electrical signal into the measurement channel. These instrument channels will be calibrated using simulated electrical signals. 4. Simulated automatic actuation shall be performed once each operating cycle. Where possible, all logic system functional tests will be performed using the test jacks. 5. Reactor low water level, high drywell pressure and high radiation main steam line tunnel are not included on Table 4.2.A since they are tested on Table 4.1.2. 6. The logic system functional tests shall include a calibration of time delay relays and timers necessary for proper functioning of the trip systems. 7. These channels consist of analog transmitters, indicators and electronic Trip units. Amendment No. 30, 203

- m u TABLE 4.2.G Unit 2 - MINIMUM TEST AND CAllBRATION FREQUENCY FOR ALTERNATE ROD INSERTION AND RECIRCULATION PUMP TRIP instrument Channel Instrument Check Instrument Functicnal Test Calibration Frequency (1) (1) (1) Reactor High Pressure Once/ day Once/3 months Once/ Operating Cycle Reactor Low-Low Water Level Once/ day Once/3 months Once/ Operating Cycle. Lonic System Functional Test (2) Freauency h Attemate Rod Insertion / Recirculation Pump Trip Once/3 months e-g m Attemate Rod insertion / Recirculation Pump Trip Once/ Operating Cycle including air venting and breaker trip (3) a R5 Notes: E

1. In accordance with Table 4.2.B. These instrument channels are the same ones used by the Core and Containment jj Cooling Systems.

}

2. The recirculation pumps need not be tripped g

3. This test, performed while shutdown, will include venting of the scram air header and tripping of the recirculation pump breakers. The test will also verify operability of the manual actuation logic.

w C E -4 N >c--. 9, ein>Mmag--3--eye <s-g-g- +-de,= 4-e a:99#g 4 4-a m--,ev g, g M e yrp q e---a iv----gay--y-g eg e H -g--eewh-Wy7y% ys---,:4t- ,4-4.es-- g4ee 9-4W '-We +'WW' "=Mim W

- e+-tw4r-<-+-we'qw"m-4 w e e-e-a**

weees-euw*- eee d 4 'eL a

Unit 2 PBAPS i 32 RAggg In addition to reactor protection instrumentation which initiates a reactor scram, protective instrumentation has been provided which initiates action to mitigate the consequences of accidents which are beyond the operator's ability to control, or terminates operator errors before they result in serious consequences. This set of specifications provides the limiting conditions of operation for the primary system isolation function, initiation of the core cooling systems, control rod block and standby gas treatment systems. The objectives of the Specifications are (i) to assure the effectiveness of the protective instrumentation when required even during periods when portions of such systems are out-of-service for maintenance, and (ii) to prescribe the trip settings required to assure adequate performance. P 1 Channel functional test frequencies and allowed out of service times for repair and surveillance testing for Isolation Instrumentation have been determined in accordance with General Electric reports NEDC-30851P-A, Supplement 2, " Technical Specification Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," and NEDC-31677P-A," Technical Specification Improvement Analyses for BWR Isolation Actuation Instrumentation." The AOT is 12 hours for Table 3.2.A Items 1, 4, and 5 because these items have instrumentation that is common to the RPS. Other Table 3.2.A Items have an AOT of 24 hours. Channel functional test frequencies and allowed out of service times for repair and surveillance testing for ECCS Actuation Instrumentation have been determined in accordance with General Electric reports NEDC-30936P-A,"BWR Owners' Group Technical Specification Improvement Methodology with Demonstration for BWR ECCS Actuation Instrumentation," Parts 1 and 2, and RE-022," Technical Specification Improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for Peach Bottom Atomic Power Station, Units 2 and 3." Channel functional test frequencies and allowed out of service times for repair and surveillance testing for miscellaneous instruments have been determined in accordance with General Electric report GENE-770-06-1," Bases for t Changes to Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical s Specifications," and the associated NRC Safety Evaluation Report dated July 21, 1992. Channel functional test frequencies and allowed out of service times for repair and surveillance testing for RCIC instrumentation have been determined in accordance with Amendment No. 111, 141, 203 n p Unit 2 PGAPS 3.2 BASES. (continued)' .{ 'I General Electric report GENE-770-06-2," Bases for Changes to l L, Surveillance-. Test Intervals.'and Allowed Out-of-Service Times. for Selected Instrumentation Technical Specifications," and i the associated:NRC-Safety Evaluation Report dated September 13,'1991. l Some of 'the settings on the instrument!ation that initiate or. control core'and containment cooling have tolerances ( explicitly stated where the high and' low values are both-j critical;and may have a' substantial effect on safety.. The' ' set points of:other: instrumentation, where.only the high.or low end of the setting has a. direct bearing on safety, are- { chosen at a level away from the normal operating range to. j prevent inadvertent actuation of-the safety system involved and exposure to abnormal situations. 1 Actuation of primary containment valves is initiated by f protective' instrumentation shown in Table 3.2.A which senses the conditions for which isolation is required. Such instrumentation must be available whenever primary i containment integrity is required. i e The instrumentation which initiates primary system isolation is connected in a dual bus arrangement. The low water level instrumentation set to trip at zero inches indicated level (538 inches above vessel zero) closes all isolation valves except those in Groups 1,'4 and.5. l Details of valve grouping and required closing times are given in Specification 3.7. For valves which isolate at i this level, this trip setting'is adequate to prevent the core from being uncovered in the case of a break in.the i largest line assuming ~a 60 second valve closing time. 1 Required closing times are less than this. The low-low reactor water level instrumentation is set to trip when reactor water level is minus_48-inches indicated { 1evel (490 inches above vessel zero). This trip initiates j HPCI, RCIC, Alternate Rod Insertion and trips the recirculation pumps. The low-low-low reactor water level instrumentation.is set to trip tehen the reactor water level j is minus 160 inches indicated level (378 inches above vessel i zero). This trip closes Main Steam Line Isolation Valves, i Main Steam Drain Valves and Recirc Sample Valves (Group 1), j activates the remainder of the CSCS subsystem, and starts i a ~ i l -89a-Amendment No. 203 ~.. I

Unit 2 PBAPS 3.2 BASES (Cont'd) Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drops below 850 psig. The Reactor Pressure Vessel thermal transient due to an inadvertent opening of the turbine bypass valves when not in the RUN Mode is less severe than the loss of feedwater analyzed in section 14.5 of the FSAR; therefore, closure of the Main Steam isolation valves for thermal transient protection when not in RUN Mode is not required. The HPCI high flow and temperature instrumentation are provided to detect a break in the HPCI steam piping. Tripping of this instrumentation results in actuation of HPCI isolation valves. Tripping logic for the high flow is 1 out of 2 logic. Temperature is monitored at four (4) locations with four (4) temperature sensors at each location. Two (2) sensors at each location are powered by "A" DC control bus and two (2) by "B" DC control bus. Each pair of sensors, e.g., "A" or "B" at each location are physically separated and the tripping of either "A" or "B" bus sensor will actuate HPCI isolation valves. The trip settings of s 300% of design flow for high flow and 200 degrees F for high temperature are such that core uncovery is prevented and fission product release is within limits. The RCIC high flow and temperature instrumentation are arranged the same as that for the HPCI. The trip setting of s 300% for high flow and 200 degrees F for temperature are based on the same criteria as the HPCI. The Reactor Water Cleanup System high flow instrumentation is arranged similar to that for the HPCI System. The trip settings are such that core uncovery is prevented and fission product release is maintained within limits. The high temperature instrumentation downstream of the non-regenerative heat exchanger is provided to protect the ion exchange resin in the demineralizer from damage due to high temperature. Such damage could impair the resins' ability to remove impurities from the primary coolant and possibly result in the release of previously captured impurities back into the coolant in large concentrations. The instrumentation which initiates CSCS action is arranged in a dual bus system. As for other vital instrumentation arranged in this fashion, the Specification preserves the effectiveness of the system even during periods when maintenance or testing is being performed. An exception to this is when logic functional testing is being performed. The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR does not decrease to the fuel cladding integrity safety limit. The trip logic for this function is 1 out of n: e.g., any trip on one of 6 APRM's, 8 IRM's, or 4 SRM's will result in a rod block. The minimum instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met. Amendment No. 45, 43, 70, 104, 203

q.; PBAPS 4.2 BASES The. instrumentation listed in Tables 4.2.A through 4.2.F will be functionally tested and calibrated at regularly scheduled intervals. L Amendment No. BB, 203

PBAPS-4.2 BASES (continued) i l k I Intentionally Left Blank P i r ' Amendment No. 203

f Unit 2 PBAPS 4.2 BASES ' (continued) l l l Intentionally Left Blank i 1 I l l l l l l I l Amendment No. 203 1 l l \\ __.J

I l a Unit'2-I PBAPS

4~.2' BASES (continued)

P R .i Intentionally Left Blank 1 i t i ? i t i 1 i ) I i -) i l 4 i Amendment No. 203. -. -.

en nerg he t. UNITED STATES j 'j NUCLEAR REGULATORY COMMISSION ~* WASHINGTON, D.C. 20666 4 001 %,...../ PECO ENERGY COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.206 License No. DPR-56 1. The Nuclear Regulatory Commission (the Commission) has found that: A. The application for amendment by PECO Energy Company, et al. (the licensee) dated September 26, 1994, as supplemented by letters dated January 5, and March 23, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set i forth in 10 CFR Chapter I. B. The facility will operate in conformity with the application, the provisions of. the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health or safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and par: graph 2.C(2) of Facility Operating License No. DPR-56 is hereby-amended to read as follows:

p-t-, i (2) Technical Soecifications The Technical Specifications contained'in Appendices A and B, as revised through Amendment No. 206, are hereby_ incorporated in the license. ' PEC0 shall operate the facility in accordance with the Technical Specifications. 3. This license amendment is effective as of its date of issuance and is to be implemented within 30 days. FOR THE NUCLEAR REGULATORY COMMISSION i b ss<tUAl. .N-l '[- John F. Stolz, Director s Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical ~ Specifications Date of Issuance: June 6, 1995 i I t I i

3 'l ATTACHMENT TO LICENSE' AMENDMENT NO. 206 FACILITY OPERATING LICENSE NO. DPR-56 .) DOCKET NO. 50-278 l Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines. l Remove Insert. 35 35 36 36 i 36a 36a 37 37 38 38 39 39 i 41 41 42 42 43 43 i 44 44 45 45 46 46 47 47 i 51 51 i 52 52 53 53 i 53a .53a 'i 55 55 i 57 57 57a i 58 58 59 59 59a f 60 60 I 61 61 62 62 63 63 64 64 i 65 65 66 66 67 67 68 68 69 69 + 70 70 71 71-71a 71a l 71b 71b 72 72 72a 73 73 l 74 74 I

~ , ATTACHMENT TO LICENSE AMENDMENT NO.206 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278 Remove Insert 74a-74a 75 75 79 79 80 80 81 81 81a 81a 83 83 84 84 85 85 87 87 88 88 89 89 89a 91~ 91 94 94 95 95 96 96 98 98 i-

- a, g. PBAPS UNIT 3 UMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS t .3.1 Reactor Pesca System (RPS) 4.1 Reactor PM.cton System I...: A.- The RPS instrumenta6on for each trip function A. Each RPS instrument channel shall be i in Table 3.1.1 shall be Operable; and, there. demonstrated Operable by performance of a ~ shall be two Operable or tripped trip systems channel functional test and channel calibration. for each Trip Function. at the Frequencies shown in Tables 4.1.1 and - 4.1.2, respectively.- i ' The designed system response times from the Response time measurements (from the l opening of the sensor contact up to and opening of the sensor contact up to and i including the opening of the trip actuator including the opening of the trip actuator. '} contacts shall not exceed 50 rnilliseconds. contacts) are not part of the normalinstrument - test. The RPS response time of each reactor l ADDbCatNhtY trip function shall be demonstrated to be Within its Nmits once per operating cycle. According to Table 3.1.1. Conditions and Ranuired A9m: (1)(2)

1.. With one or more channel (s) required by Table i

' 3.1.1 inoperable in one or more trip functions, j place the inoperable channel or associated trip system in trip wthin 12 hours 2. With one or more trip functions with one or more channels required by Table 3.1.1 inoperable in both trip systems, place channel in one trip system in trip or place one trip system in trip within 6 hours I 3. With one or more automatic trip functions or l two or more manual trip functions (Mode Switch i in Shutdown. Manual Scram and RPS Channel .j Test Switches) with RPS trip mp=hility not i maintained, restore RPS trip capabiNty within one hour. 4. If the required actions and associated i completion time of Action 1 or 2 or 3 are not met. take the action required by Table 3.1.1 for the Trip Function. t (1) When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation ' of these Actions may be delayed for up to 6 hours provided the associated trip function rnaintains RPS trip capability.' (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the trip function to occur. In triese cases, if the inoperable channelis not restored to Operable status within the t required time, the Action required by Table 3.1.1 for that trip function shall be taken immediately.

Amendment No. 54, 50, 75, 206

7.. .e PBAPS UNIT 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.1 Reactor Protechon System (continued) 4.1 Reactor Protechon System (continued) B. N/A : B. Deleted ' C. N/A C. Deleted D. Reactor Protection System D. Reactor Protechon Sv,glam g Power Sunoiv Power Sucolv D.1 Reactor Protection System Power Supply: D.1 The foNowing RPS power supply (MG set) protective devices shall be funcbonelly One trip train

per RPS MG set may be in tested at least once overy six months and -

the bypassed or inoperative condition for a caibrated once each refue6ng outage period of 72 hours if this condition cannot be satisied, or if both trip trains are Acceptable inoperative, the RPS bus shall be Qggiga Egggg transferred to the allemate source or de-i energized within 30 minutes. Undervoltage 113

2 Volts

j Overvoltage 131

2 Volts Underfrequency 57 Hz t.2 Hz Underfrequency Time Deley 6 sec i 1 sec l

D.2 ' One trip train

of the RPS altemate power D.2

~ The following RPS attemate' power supply l. 4 supply may be in the bypassed or protectwo devices shall be funchonally ~ inoperative condition for a period of 72 tested at least once every six months and hours. if this condetson cannot be satisfied, calibrated once each refueling outage. or if both trip trains are inoperative, the RPS bus shall be transferred to the RPS Acceptable MG set or de-energized within 30 rninutes. Device Eggag i Undervoltage 113 2 Volts Overvoltage 131

2 Volts Underfrequency 57 Hz t.2 Hz Undervoltage Time Delay-Max. 4 secs.

A trip train consists of one breaker, one undervoltage relay, one overvoltage relay, one underfrequency relay, one time delay relay (MG set only), and the associated logic. l 36 Amendment No. 14, 101, 206

PBAPS UNIT 3 F 5 L Intentionally Blank Amendment No. '01. 123, 206 -36a.

PBAPS Unit 3 Table 31.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No.of Modes in which Function Operable instrument M W h @ re w Number of :.

--a...

Channeh per Channels Provided AcWon f flem Trip System Trip Functen Trip Level Sethng Refuel (7) Startup Run by Design (1) 1 1 Mode Switch in x x x 1 Mode Swech A Shutdown (4 Sectone) 2 1 Manuel Screm x x x 2 Instrument Chennels -A 3 3 IRM High Flux 1120/125 of fur Scote x x (5) 8 Instrument Channele A 3 1RM inoperative x x (5) 8 Instrument Chennele A 5 2 APRM Htph Flum (D 88W+71%-0 98AW) x 6 Instrument Chennele A or B (Clamp 9120%) (12)(13) g ta7 6 2 APRM Inoperative (11). x x .m 6 Instrument Chennels - A or B fn 7 2 APRM Downocele 22.5 Indicated k (10) 6 Instrument Chennele A of B on Scale tu$ 8 2 APRM High Flux in '115% Power u x 6 Instrument Chennele A g Stortup 3 r+ 9 2 High Reactor Pressure 11055 peig n (9) x x 4 Instrument Chennelo A 2 ,o 10 2 High Drywes Pressure 12 pois n (8) x (8) x 4 Instrument Chennele A ru Feet Closure Solenoid and M Disc Dump Velve 17 4 Turbine Stop Velve i 10% VeNe Closure X (4) 8 Instrument Channels A or D g Che r+ 18 2 RPS Channel Test E X .X X 4 instrument Chennels A Switchee bO bd bO [#. C-Z -4 bd .r0 o, . ~ ~... - -. ~.,..,,.

. _ _.. ~. _ s .UnR3 1 PBAPS i NOTES FOR TABLE 3.1.1 = 1. If the' required actions _and associated. completion. time of. 1; Specification 3.1.A, ActionsL1 or 2 or:3 are not met,.take the actionflisted below for the.affected trip function as required.by Table.-3.1.1. t A.: Initiate insertion of operable rods and complete insertion of~all operable rods within 12 hours. i B. Reduce power level to IRM range and place mode switch I in the start up position within 6-hours.- i l C. Reduce turbine load and close main steam line-isolation valves within 6 hours. l l D. Reduce. power to less than 30% rated within 4 hours. 2. Permissible to bypass, in refuel and shutdown positions of the reactor mode switch. i 3. Deleted. 4. Bypassed when: reactor thermal power is less.than 30% of rated as indicated by turbine first stage pressure. 5. IRM's are bypassed when APRM's are onscale and the reactor mode switch is'in the run position. 1 6. The design permits closure of.any two lines without a scram being initiated. ~ P 7. When the reactor is subcritical and the reactor water temperature is less than 212 degrees F, only the following [ trip functions need to be operable: A. Mode switch in shutdown l B. Manual scram C. High flux IRM D. Scram discharge instrument volume high level t 8. Not required to be operable when primary containment integrity is not required. l 9. Not required to be operable when the reactor pressure vessel head is not bolted to the vessel. i t t > Amendment No. 33, 100, 121, 133, 206 l t e -= n v, ,--,.-_._e-

m .a 1m. Unit 3 TABLE 4.1.1 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUlTS Group (2) Functimal Test Mmimum Frequency (3)'- Mode Switch in Shutdown A Place Mode Switch Each refue5ng outage in Shutdown Manual Scram A Trip Channel and Alarm Every 3 months l RPS Channel Test Switch A Trip Channel and Alarm Cis';;d or after channel maintenance IRM f High Flux C Trip Channel and Alarm (4) One per week dunng refuelng or stcetup and before each startup Inoperative C Trip Channel and Alarm (4) One per week during refuelng or d startup and before each startup. APRM 2 g High Flux B1 Trip Output Releys (4) Once/3 months g inoperative B1 Trip Output Relays (4) Once/3 months S Downscale B1 Trip Output Rolsys' (4) Once/3 months [ Flow Bias B1 Coltrate Flow Bias Signal (4) Once/ month p High Flux in Startup or Refuel C Trip Output Relays (4) One per week during refuelng or startup and before each startup. h High Reactor Pressure (6). iB2 Trip Channel and Alarm (4) Once/3 months High DryweN Pressure (6) B2 Trip Channel and Alarm (4) Once/3 months Reactor Low Water Level (5)(6) B2 Trip Channel and Alarm (4)' Once/3 months j -t-p 4 ..<.m - m . ~, _ _ _. - - - _ -, - -,. ~. -, ~ +.......,,. -... .-.,.~-w..~...,...___.-. .L....~. 2 m.__,...

,.4 Unit 3 TABLE 4.1.1 (Continued) REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT FUNCTIONAL TESTS MINIMUM FUNCTIONAL TEST FREQUENCIES FOR SAFETY INSTRUMENT AND CONTROL CIRCUITS Group (2) Functional Test Mmimum Frequency (3) High Water Levelin Scram A Trip Channel and Alarm Once/3 months Discharge Instrument Volume Turbine Condenser Low Vacuum (6) B2 Trip Channel and Alarm (4) Once/3 months f~ 1 Main Steam Une High Radiation B1 Trip Channel and Alarm (4) Once/3 months Main Steam Une Isolation A Trip Channel and Alarm Once/3 months - 3 Valve Closure p Turbine Control Valve A Trip Channel and Alarm Once/3 months E EHC Oil Pressure I Turbine First Stage Pressure A' Trip Channel and Alarm Once/3 months Permissive Turbir e Stop Valve Closure A Trip Channel and Alarm Once/3 months O O J " - cg -4 u ro CD mwwp-ee**=ue-ue9--v-m wvr'surgaw-Wmm' u$ r-

es egNys

-+w.ceaw a.*-meye-- wu :u- -p-1ee-3 wn. w v.gpgt, ev,-. 33**wwt'r-e.<-supai4emum e, iae.-

==L.n.$w gum 4v .e m== .-,he weer..-gygmoe-ye. war-%=e.e.,+%<eu .,m m-a u-m-m.maa s ..na2:.aw-a x-.e-A me se m. se m ..a4-emt-- - ' --.-.- a-h

PBAPS UNM 3 NOTES FOR TABLE 4.1.1 1. Deleted. 2. A description of each of the groups is included in the Bases l I of this Specification. i 3. Functional tests are not required on the part of the system that is not required.to be operable or are tripped. If tests are missed on parts not required to be operable or are tripped, then they shall be performed prior to returning the system to an operable status. 4. This instrumentation is exempted from the instrument' channel test definition. This instrument channel functional test will consist of injecting a simulated electrical signal into the measurement channels. 5. The water level in the reactor vessel will be perturbed and the corresponding level indicator changes will be monitored. This perturbation test will be performed every month after. completion of the functional test program. 6. These channels consist of analog transmitters, indicators and electronic trip units. Instrument checks shall be performed once per day. i 1 1 l 1 ', Amendment No. 29, 206

If . Unit 3 TABLE 4.1.2 REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENT CAllBRATION MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CHANNELS l Instrument Channel Group (1) Calibration Minimus Frequency (2) IRM High Flux C Comparison to APRM on Maximum frequency once Controlled Shutdown per week. APRM High Flux Output Signal 81 Heat Balance Twice per week. Flow Blas Signal B1 With Standard Pressure Every eighteen months. Source LPRM Signal B1 TIP System Traverse Every 6 weeks. k High Reactor Pressure 82 Standard Pressure Source Once per operating cycle: High Drywell Pressure B2 standard Pressure Source Once per operating ,g cycle. h Reactor Low Water Level 82 Pressure Standard Once per operating cycle. g g: High Water Level in Scram A Water Column Every' refueling outage. Discharge Instrument Volume Turbine Condenser low Vacuum 82 Standard Vacuum Source Once per operating cycle. 8 Main Steam Line Isolation Valve A Note (5) Note (5) jj Closure Main Steam Line High Radiation 81. Standard Current Source (3) Every 3 months. E Turbine First State Pressure A Standard Pressure Source Every 6 months. Pennissive t 8*

Unit 3' TAB LE 4'. l. 2 (Cont 'd. ) REACTOR PROTECTION SYSTEN (SCRAN) MINIMUM CALIBRATION FREQUENCIES FOR REACTOR PROTEC INSTRUNENT CALIBRATION. i h, i l Instrument Channel Grcup (1) Calihratton ,1 ' Minim'um Fraquency (2)- Turbine Control Valve Fast Closure Oil Pressure Trip A, Standard Pressure Bource Once'per operating -cycle. Turbine stop Valve Closure' A Note (5) Note (5) g a. Ut e e 8 p; y g tg n g ? a. ~ E, o e e e 6 t Ie

E, Unit 3 NOTES FOR TABLE 4.1.2 1. A description of these groups is included in the bases of this Specification. 2. Calibration test is not required on the part of the system that are not required to be operable or are tripped but is required prior to return to service. ~ The current source provides an instrument channel 3. alignment. Calibration using a radiation source shall be made each refueling outage. 4. Deleted. 5. Physical inspection and actuation of these position switches will be performed during the refueling outages. e-m-Amendment No. 206

i s Unit 3 i 3 PBAPS i BASES The~ reactor protection system automatically initiates a reactor scram j to: i 1. Preserve the integrity of the fuel cladding. l 2. Preserve the integrity of the reactor coolant system. 3. Minimize the energy which must be absorbed following a^ loss of- ~ l coolant accident, and prevent inadvertent criticality. i When there is not fuel in the reactor, the scram serves no function; [ therefore, the reactor protection system is not-required to be operable. s Allowed out of service times for repair and surveillance testing _for Reactor Protection System Instrumentation have been determined in l accordance with General Electric report NEDC-30851P-A, " Technical i Specification Improvement Analyses for BWR Reactor Protection System," 8 General Electric Company, March 1988. The reactor protection system is.of the dual channel type (Reference } subsection 7.2 FSAR). The system is made up of two. independent trip systems, each having two subchannels of tripping devices. Each subchannel has an input from at least one instrument channel which monitors a critical parameter. i i The outputs of the subchannels are combined in a 1 out of 2 logic; i.e., an input signal on either one or both the subchannels will cause a trip system trip. The outputs of the trip systems are arranged so j that a trip on both systems is required to produce a reactor scram. .i This system meets the intent of IEEE. - 279 for Nuclear Power Plant Protection Systems. The system has a reliability greater than that of i a 2 out of 3 system and somewhat less than that of a 1 out of 2 i system. With the exception of the Average Power Range Monitor (APRM) channels, j the Intermediate Range Monitor (IRM) channels, the Main Steam j Isolation Valve closure and the Turbine stop valve closure, each -subchannel has one instrument channel. When the minimum condition for operation on the number of operable instrument channels per untripped protection trip system is met or if it cannot be met and the affected protection trip system is placed in a tripped condition, the effectiveness of the protection system is preserved. 1 Three APRM instrument channels are provided for each protection trip f system. APRM's A and E operate contacts in one subchannel and APRM's l C-and E operate contacts in the other subchannel. 'APRM's B, D and F are arranged similarly in -47 Amendment No. G4, 206 l i I

b PBAPS UNIT 3 4.1 Bases i A. Channel functional test frequencies for Reactor Protection System Instrumentation have been determined in accordance with General Electric report NEDC-30851P-A, " Technical Specification improvement Analyses for BWR Reactor Protection System," General Electric Company, March 1988. k 'i i i i i Amendment No. 39, 206

PBAPS i UNIT 3 4.1 Bases (Con'id.) Intentionally Left Blank f 5 I } \\ i i Amendment No. 49, 206 1

PBAPS UNIT 3 i 4.1 Bases (Con'td.) intentionally Left Blank d P Amendment No. 14, 29, 206 PBAPS UNIT 3 l 4.1 Bases (Con'td.) f i i i Calibration frequency of the instrument channel is divided into two groups. These are as follows: 1. Passive type indicating devices that can be compared with like units on a i continuous basis. 2. Vacuum tube or semi-conductor devices and detectors that drift or lose sensitivity. f i ? i i i i i i Amendment No. 49, 206 j -53a-r- . ~ ~..,, - - __.. +,

PBAPS UNIT 3 4.1 Bases (Con'td.) Intentionally Left Blank 2 P h d -55 Amendment No. 206

~ t PBAPS UNIT 3l j LIMITING CONDITIONS FOR OPERATION SURVElLLANCE REQUIREMENTS t ' 3.2 Protective instrumentabon 4.2 Protectwo Instrumentation - t e i A. Primary Containment isolabon Functions . A.' Pnmary Containment isolabon Functions j The primary containment isolation Instrumentation shall be funchonally tested and i instrumentabon for each function in Table 3.2.A. cabbrated as indicated in Table 4.2.A. f . shall be Operable; and, there shall be two l Operable or tripped trip systems for each trip System logic shall be funcbona#y tested as { function.' ' indicated in Table 4.2.A. Acolicatnlity: Whenever Primary' Containment integrity is l required. 3 Condibons and Reauired Ae+ ions: (1)(2)' ,1'. With one or more channels required by Table 3.2.A inoperable, place channel in trip within 12 hours for items 1,4, and 5, and, place channel. i in trip within 24 hours for items other than 1,4, and 5. 2.' With one or more automatic functions with primary containment isolation function not - maintained,' restore primary containment isolation capability within one hour.(3) 3. If the required action and associated complebon time of Action 1 or 2 are not met, take the i action required by Table 3.2.A for the function. (1) When a channel is placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated Function maintains primary containment isolation capability. . (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the trip function to occur. In these cases, if the inoperable channelis not restored to Operable status within the j required time, the Action required by Table 3.2.A for that trip function shall be taken. - (3) This Action not applicable to item 11, Reactor Cleanup System High Temperature. i Amendment No. 206 - 1 j ,m _,,y a c e w - --e---- ~ ^ " ' '

_j PBAPS: UNIT 3 i UMITING CONDITIONS FOR OPERATION LIMITING CONDITIONS FOR OPERATION - l 3.2 Protective instrumentabon (Continued). 4.2 Protechve Instrumentaban (Continued) j h ~ B. Core and Containment CMno Systems - B. Core and Contenment CMna' Systems - frMahon and Control frubabon and Control Core and containment cooling system ir#ation Instrumentation shall be functionally tested, and controlinstrumentation for each Trip calibrated and checked as indicated in Function in Table 3.2.5 shall be Operable; and, Table 4.2.B.- there shall be two Operable or tripped trip systems for each Trip Function except as noted System logic shall be functionally tested as in Table 3.2.8. indicated in Table 4.2.B. i Acolicatality i . Each Trip Function listed in Table 3.2.5 shall be i Operable whenever the system (s)it initiates or i controls are required to be Operable as

specified in Section 3.5.

.i Cerew. and Reauired Actions: a With one or more channel (s) required by Table - 3.2.5 inoperable in one or more Taip Functions, take the Action required by Table 3.2.5. 1 i 1 i I 57a - Amendment No. 206 j 4

,1 .J '.PBAPS-l UNIT 3 - UMITING CONDITIONS FOR OPERATION' SURVEILLANCE REQUIREMENTS l 3.2 Protechve instrumentaban (Continued) 4.2 Protective Instrumentaton (Continued) C. Control Rod BM (CRB) A*"=> C. Control Rod Bl~+ (CRB) A+d=1 ~ The Control Rod Block Actuation _ instrumentation shall be functionally tested, l instrumentaban for each function in Table 3.2.C caEbrated and checked as indicated in - shall be Operable; and, there shall be two Table 4.2.C. f Operable or tripped trip systems for each function except as noted in Table 3.2.C. System logic shall be functionally tested as - J indicated in Table 4.2.C. Apolcabittv: (1) ~ l i The Rod Block Monitor (RSM) shall be Operable with setpoints as required by Table 3.2.C and the Core Operati'ig Umits Report (COLR). The APRM, IRM and SRM Control Rod Block (CRS) functions shall be Operable whenever the Reactor Mode Switch is in the Startup or l . Run positions except as follows. The SRM and IRM functions are r,ot required when the Reactor Mode Switch is in Run. t The APRM and RBM functions are not required to be Operable when the Reactor Mode Switch is in Startup except for the ~ APRM Upscale (Startup Mode) which is not - i required to be Operable when the Reactor Mode Switch is in Run. i ~J The scram discharge instrument volume high. 1 level rod block is required to be Operable whenever the Reactor Mode Switch is in the .) Startup or Run positions or in the Re'.Jel position whenever more than one control rod is - withdrawn. i CcEW cr and Reouired Actions: i With one or more channel (s) required by Table 3.2.C inoperable in one or more tvip functions, take the Action required by Table 3.2.C. (1) Section 3.3.B.5 is Applicable during operation wth a limiting control rod pattem. Amendment No. M4, 206 ,g,

L I p 'PBAPS. UNIT 3 } \\ LIMITING CONDITIONS FOR OPERATION SURVElLLANCE REQUIREMENTS

l 3.2 Protechve instrumentaban 4.2 Protechve Instrumentabon i

(Conbnued)' (Continued) D. P"-"~1 l4.-C.w S._:-.Maalaban and - D. Radiabon Monitorina Systems-isolabon and { initiaton Funchons trubaton Funcbons J s D.1. Reactor BW m isolation and Standby G== D.1. Reactor Buildino lu-"'n and Standby Gas ' 'i Treatment System Treatment System i The Reactor Building isolation and Standby Instrumentation shall be functionally tested, Gas Treatment System instrumentabon for calibrated and checked as indicated in each trip function in Table 3.2.D shall be Table 4.2.D. Operable; and, there shall be two Operable or tripped trip systems for each trip System logic shall be functionally tested as function. Indicated in Table 4.2.D. AnglcatdtY. Refuel Area Exhaust Monitors and Reactor Building Area Exhaust Monitors shall be Operable whenever the associated systems are required to be Operable. Main Stack Morntor shall be Operable - whenever the containment is purging and _ primary containment integrity is required. Conditions and Reouired A@ns:(1)(2) 1. Wth one or more channels required by Table 3.2.D inoperable in one or more trip i functions, place channelin trip within 24 hours 2. Wth one or more automatic Functions with containment isolation capabilty not maintained, restore containment isolation capabikty within one hour. l 3. If the required actions and associated completion times of Action 1 or 2 are not ' met, take the Action required by Table ' 3.2.D - i ' (1) When a channelis placed in an inoperable status solely for performance of required Surveidances, initiation of these Actions may be delayed for up to 6 hours provided the associated Trip Function maintains isolation capability. l (2) An inoperable channel or trip system need not be placed in the tripped condition where this would cause the _ i Trip Function to occur. In these cases, if the inoperable channelis not restored to Operable status within the required time, the Action required by Table 3.2.D for that trip Function shall be taken. 1 Amendment No. 104, 162, 189, 206-

1 1 PBAPS UNIT 2 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2 Protective instrumentation (Continued) 4.2 - Protective instrumentshon (Contmuod) ' 1 D. Radation Monitorina Systems-isolation and D. Radiation Monitorina Systems-Isolabon and initiation Functkms inibabon Funcbons (Continued) (Continued) ' D.2 ~ Main Control Room D.2 Main Control Room The limiting conditions for operation are ' Instrumentation shaN be functionsby tested, I given in Table 3.2.D. cabbrated and checked as indicated in Table 4.2.0. i E. DryweN Lealt Detection . E. DrvweN Leak Detechon The limiting conditions of operation for the Instrumentabon shall be calibrated and J instrumentabon that monitors dryweN leak checked as indicated in Table 4.2.E.- detachon are given in Section 3.6.C, "Coolent Leakage". s i F. SurveiNance Ir,foiic^2-r, Re@t = F. Surveinance information Readouts d -1 The limiting conditions for the instrumentabon shall be cabbrated and instrumentation that provides surveillance checked as indicated in Table 4.2.F. information readouts are given in Table 3.2.F. l l l 8 l 1 l 1 l - 59a. Amendment.No. 206

n. 9 F UNIT 3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2.Protecbve instrumentaban (Con 6nued) 4.2 Protec6ve instrumentamon (Conbrud) ~! G. Altemate Rod inserton (ARI) and G. Altemate Rod Insertion and. Recirculabon Pump Tnn (RPT) Rodrculanon Pump Trio t - 1 Two trip systems coneesting of two channels per Each RPT and ARI instrumentation channel j trip system for each instrumentation funcbon shall be demonstrated Operable by the - l that 3rstates an Altemate Rod Inser1 ion (ARI) performance of the Instrument Check, scram and trips the reactor recircule6cn pumps Instrument Functional Test, Channel Calibration l (RPT)in Table 3.2.G shall be Operable; and, and Logic System Functional Test at the - i the, manuel and automatic actuation logic and Frequencies shown in Table 4.2.G. j actuation devices of both trip systems shall be - . Operable. Acolicaldtv Whenever the Reactor Mode Switch is in the Startup or Run positions. Conditons and Reauired Actions:(1)(2) . 1. With one or more channels required by i -t Table 3.2.G inoperable, restore channel to .i Operable status or place channelin trip 1 within 14 days.(3) y 2. With one instrument function with trip capabiky within 72 hours. { capabiky not maintained, restore trip I 3. With both instrument functions or an actuation device with trip capability not maintained, restore trip capability for one function within 1 hour. l +. q s 4.- If the required actions and associated i completion times of Action 1,2 or 3 are not met, place the reactor in shutdown or refuel i 4 mode within 8 hours. { - (1) When a cha'inelis placed in an inoperable status solely for performance of required'Surveillances,- initiation of these Actions may be delayed for up to 6 hours provided the associated Trip Function

maintains ARl/RPT trip capability.

4 1 (2) An inoperable channel or trip system need not be placed in the tripped condition where this would l cause the Trip Function to occur. In these cases, if the inoperable channelis not restored to. Operable L status within the required time, the Action required by Condition 4 for that trip Function shall be taken. i (3) The action of placing the channelin trip is not applicable if the inoperable channelis the result of an 1 inoperable breaker. Amendment No. M 3, 206 g ..-.,,,i'_J,m,. ~, _ .-m-r.

c w'_-- Table 3.2.A - INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION Minimum No. of Operable Instrument Channels per Number of instrument - Action l Item Trip System Instrument Trip Level Setting - Channels Provided by D@ '(2) 1 2 (6) - Reactor Low Water Level a 0" Indicated Level (3) 4 Inst. Channels A 2 1 Reactor High Pressure s 75 psig 2 Inst. Channels D (Shutdown Coolng isolation) 3 2 Reactor Low-Low-Low at or above -160" indicated - 4 Inst. Channels Ac Water Level - level (4) 4 4 2 (6) High Drywell Pressure s 2 psig 4 Inst. Channels ~A~ g,l 1 ? Q" 5 2-High Radiation s 15 X Normal Rated Full 4 Inst. Channels B. g Main Steam Line Tunnel Power Background (8) 5. 6 2 Low Pressure a 850 poig (7) 4 Inst. Channels B y Main Steam Une " 7 2 (5) High Flow. s 140% of Rated Steam Flow 4 Inst. Channels B' y Main Steam Line g 8 2 Main Steam Line Tunnel s 200 Dog. F (9) 4 Inst. Channels B Exhaust Duct g High Temperature ? P o. a I l-

. _.=_.-__ _____._ _.. b .m Table 3.2.A INSTRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION Minimum No. of Operable Instrument ~ d Channels per Number of instrament Action l Item Trip System Instrument Trip Level Setting Channels Provided by Da==Jn (2) I 9 2 Main Steam Une s 200 Dep. F 4 Inst. Channels. B I Leak Detection High Temperature 10 1 Reactor Cleanup System s 300% of Rated Flow 2 Inst. Channels C 'l i High Flow l 11 1 Reactor Cleanup System s 200 Deg. F 1 Inst. Channels E i High Temperature b 12 2 Reactor Pressure s 600 psig 4 Inst. Channels F I m (Feedwater Flush g System Interlock) ait an r E$ P l .O k c) --.s___m. _ ~ ,_.m..__ 2 ___s-.

Unit 3 PBAPS NOTES FOR TABLE 3.2.A 1. Deleted 2. If the required actions and associated completion time of Specification 3.2.A, Actions 1 or 2 are not met, take the action listed below for the affected Trip Function as required by Table 3.2.A. A. Initiate an orderly shutdown and have the reactor in Cold Shutdown Condition in 24 hours. ] Initiate an orderly load reduction and have Main Steam B. Lines isolated within 12 hours. l C. Isolate Reactor Water Cleanup System within 1 hour. l D. Isolate Shutdown Cooling within 1 hour. l E. Isolate Reactor Water Cleanup Filter Demineralizers unless the following provision is satisfied. The RWCU Filter Demineralizer may be used (the isolation overridden) to route the reactor water to the main condenser or waste surge tank, with the high temperature trip inoperable for up to 48 hours, ) i provided the water inlet temperature is monitored once per hour and confirmed to be below 180 degrees F. F. Isolate Feedwater Flush System within 1 hour. l 3. Instrument setpoint corresponds to 538 inches above vessel zero. 4. Instrument setpoint corresponds to 378 inches above vessel zero. 5. Two required for each steam line. 6. These signals also start SBGTS and initiate secondary containment isolation. 7 Only required in Run Mode (Interlocked with Mode Switch). i 8. An alarm will be tripped in the control room to alert the control room operators to an increase in the main steam line tunnel radiation level. Amendment No. 31, 103, 115, 121, 1 2, 206 i

UNIT 3 TABLE 3.2.B INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS-Minimum No. of Number of Operable Instrument Instrument Channels per Trip Channels Prowded System (ACTION) Trip Function Trip Level Setting by Design Remarks l 2 (14) (15) Reactor Low-Low 2-48 in. Indicated level 4 HPCI & RCIC Initiates HPCI & RCIC. Water Level Inst. Channels gl2 (8) (11) (15) Reactor Low-Low-Low 2-180 in. Indicated level 4 Core Spray & 1. In conjuncton with Low Reactor y Water Level (4) RHR instrument Pressure initiates Core Spray 'g Channels and LPCI. 4 ADS Instrument

2. In conjunegon with conllrmatory Channels low wel, High Drywell Pressure, s

f 120 second time delay, and LPCI. or Core Spray pump interlock o k initiates Auto Blowdown (ADS). o 3. Initiates startmg of Diesel 7 . Generators i-P i U-4 ...-...~...-.. ~. . - ~ ~ ~

UNIT 3 TABLE 3.2.B (continued) lhlSIRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS / Minimum No. of Number of Operable instrument instrument Channels per Trip Channels Prowded System (ACTION) Trip Function Trip Level Setting by Design Remarks l 2 (9) (16) Reactor Mgh Water s +45 in. Indicated level 2 Inst. Channels Trips HPCI & RCIC turbines Level l 1 (8) (15) Reactor Low Level 2 +312 in. above vessel 2 Inst. Channels Prevents inadvertent operm6on of (inside shroud) zero (2/3 core height) containment spray during accident g Y _y conditons : g l2 (8) (15) Containment 1 (P (2 peig 4 Inst. Channels Prevents inadvertent operallon of High Pressure containment spray during accident conditions.- 3 l 1 (11)(15) Confirmatory Low Level a +6 in. Indicated level 2 Inst. Channels ADS Permissive. 5:si 2 (8) (11)(14)(IS) High Drywell Pressure s2 psig 4 Inst. Channels 1. Initiates Core Spray; LPCl; HPCI. ~ 2. Initiates starting of Diesel Generators 3. Initiates Auto Blowdown (ADS)in O conjunction with Low-Low-Low 8 Reactor water level,120 second time delay, and LPCI or Core Spray pump running. E

UNIT 3: TABLE 3.2.B (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of Operable Instrument Number of Channels per Trip Instrument l System (ACTION) Trip Function Trip Level Setting Channels Provided Remarks by Desson l 2 (9) (15) Reactor Low Pressure 400 - 500 psig 4 Inst. Channels Permissive for opening Core Spray and LPCI Admission volves. Coencids; t with high drywell pressure, stests LPCI and Core Spray pumps ~ l 2 (9) (15) Reactor Low Pressure 200 - 250 psig 4 inst. Channels Permissive for closing Recirculation Pump Discharge Velve. yl 1 (13) (16) Reactor Low Pressure 50 s P s 75 psig 2 Inst. Channels in conjunction with PCI signal permits closure of RHR (LPCI) injection valves. 5 E m C

+ UNIT 3 TABLE 3.2.B (Continued) INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Mrdmum No. of Operetde Instrument Number of Channels per Trip Instrument Channels System (ACTION) Trip Funcion Tdp Level Settng Provided by Design Remarks l 2 (9) (15) Core Spray Pump 6

1 sec.

4 tmers All pumps -loss of oflWte power ordy. Start Timer 13 sec. 7% of set 9ng 2 9mers A & C pumps - ofFsite power evelleble. 23 sec.

7% of seteng 2 Emers B & D pumps - ofhite power eyeliable.

l 1 per 4kV bus (7) 480V Emergency Load 3 i O.5 sec. 4 tmers All 5mers -loss of oflWie power only. Center Timer l 2 (9) (15) LPCI Pump Start Timer 2 sec. 7% of settng 4 Emers LPCI pumps A & B. E gy (Four Pumps) 8 sec.

7% of seteng 4 Imers LPCI pumps C & D.

(n l 1 (12) (15) ADS Actuston Timer 90 st s120 seconds 2 Emers in conjunegon with Low Reactor Water g Level. High DryweR Pressure and LPCI ro S. or Core Spray Pump running Intedock, sa Initetes ADS. l2 (12) (15) ADS Bypass Timer 8 st s10 trinutes 4 Smers in conjuncfon wigi Low Reactor Water e g Level, bypasses high drywsE pressure - iniseson of ADS. l 2 (12) (15) RHR (LPCI) Pump 50 10 pelg 4 channels Defers ADS actualon periSng Discharge Pressure conRrmelon of Low Pressure Core Intedock g Cooling system operefon (LPCI Pump <n runring interlock). 3 l2 (12) (15) Core Spray Pump 185 e.10 psig 4 channels Defers ADS actuaton pentSng o Discharge Pressure constmeton of Low Pressure Core Intedock CooRng system operston (Core Spiny Pump running inledock). j -t w Y m .x---_---.--__-___---._.----_--.-...---.._.-----------_-----.__.--_.---n-,. - - - - - - - - = - - - - - - - e,,. m m w

m C UNIT 3 TABLE 3.2.B (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS x THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No of OperatAe Number ofinstrument Instrument Channels per Channels Provided by l Trip System (ACTION) Trip Function Trip Level Setting Design Romerks 1 (8) (16) RHR (LPCI) Trip System NA 2 inst. Channels Monitors evelletWaty of ' l bus power monitor power to logic Fr.' ems. 1 (8) (16) Core Spray Trip System NA-2 Inst. Charmels Monitors eyeliablety of l bus power monitor power to logic systems. Y f1 (8) (16) ADS Trip System NA 3 Inst. Channels Monitors evollebility of - bus power monitor power to logic systems. co - l 1 (8) (16) HPCI Trip System NA 2 Inst. Channels Monitors availablety of bus power monitor power to logic systems 1 (8) (16) RCIC Trip System NA 2 Inst. Channels Monitors ovellabitty of i l bus power monitor power to logic systems. s EF CN -4 3

_~---.---,~~,_..-,,---,L~-,-

-..-a.,~ -rr,-- e,.-,,,o-, - - - -,,, r-w-c,,, ,,-,,,,l

= .y UNIT 3 TABLE 3.2.B (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS ^ THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of Operable Number ofInstrument instrument Channels per Channels Provided by Trip System (ACTION) Trip Function Trip Level Setting Demon Remarks l1 (8) (16) Core Spray Sparger 1 (plus or minus 1.5) paid 2 Inst. Channels Alarm to detect core to Reactor Pressure spray sparger pipe break.- Vessel d/p 2 (10) (15) Condensate Storage Greater than or equal to 2 Inst. Channels Provides irterlock to 43 Tank Low Level 5' above tank bottom HPCI pump suction y u-P valves j E 2 (10) (15) Suppression Chamber Less than or equal to 5' 2 Inst. Channels Transfers HPCI pump High Level above torus midpoint suction to suppression y chamber. 3 z 2 (10) (15) Condensate Storage Greater than or equal to 2 Inst. Channels Transfers RCIC pump F Tank Low Level 5' above tank bottom suction to suppression

3 chamber.

la t -C E o a m u

q; s ' UNIT 3 TABLE 3.2.8 (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of Operable Number ofInstrument instrument Channels per Channels Provided by l Trip System (ACTION) Trip Function Trip Level Setting Design Remerks l 1 (13) (15) RCIC Turbine High Flow s 450" H O - Q) 2 Inst. Channels 2 l 1 (13) (15) RCIC Turbine High Flow 3 i i seconds 2 Inst. Channels Time Delay l 2 (13) (15) RCIC Turbine s 200 deg. F Q) 4 Inst. ) Compertment Well ) 16 Inst. .i i yl 6 (13) (15) RCIC Steam Line s 200 deg. F Q) ) g Area Temp. 12 Inst. ) g l 2 (13)' (15) RCIC Steam Line 100 ) p ) 50 psig Q) 4 Inst. Low Pressurs l 1 (13) (15) HPCI Turbine Steam Line s 225" H O (3) 2 Inst. Channels - 2 High Flow yl 1 (13)- (15) HPCI Turbine High Flow 3

1 seconds 2 Inst. Channels Time Delay B

Ia w ^ ., _. _.. -.. ~, _. - -. _.,. -.. -. -. ~..,., ~....

TABLE 3.2.B (continued). UNIT 3 INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Mirimum No. of Operable Number ofinstrument inst. Channels per Channels Prodded by Trip System (ACTION) Trip Function Trip Level Setting - Design Remarks 4. (5) -(13) (15) HPCI Steam Une 100 )p )50 psig (3) 4 Inst. Low Pressure 2 (13) (15) HPCI Turbine s200 deg. F (3) 4 Inst. ) Compartment ) Temperature ) 4 (13) (15) HPCI Steam Une s200 deg. F (3) 8 Inst. ) 16 Inst. Area Temperature } hl2 (13) (15) HPCl/RHR Valve Station s200 deg. F (3) 4 inst. )- E Area Temperature ) 2 1 (1) LPCI Cross-Connect NA 1 Inst. Irdates annunciation Position when valve is not closed. 1 per 4 kV bus (1) 4 kV Emergency Bus 25% (15%) 1. Trips all loaded E. Undervoltage Relay of Rated Voltage breakers. 5 (HGA) 5 2. Fast transfer permissive. z 3. Dead bus start of desel. [ 1 per 4 kV bus (1) 4 kV Emergency Bus 95% (+0%, -10%) Permis sequential ~ Sequential Loading Relay of Rated Voltage starting of vitalloads ya (SV) u 5 m . m m m m .._,__m

i UNIT 3 TABLE 3.2.B (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of Operable Number of instrument Instrument Channels per Channels Provided by l Trip System (ACTION) Trip Function Trip Level Setting Design Remarks l 2 per 4 kV bus (1) Emergency Transformer 60% (15%)

1. Trips emergency Urdervoltage (IAV) of rated voltage.

transfer feed to 4kV (Inverse time-voltage) Test at zero volts in emergency bus. 1.8 seconds (110%). 2. Fast transfer permissive. d l 2 per 4 kV bus (1) Degraded voltage (27N) 98% of rated voltage

1. Trips emergency 5

1 '? ("non-LOCA" relay)

0.3% of setting transformer feed to j

(4077 volts i 12 volts) 4kV emergency bus. ~ 0.9 - 1.1 second internal 2. Fast transfer time delay permissive. f 60 second i 5% (13 sec.) time delay & l 2 per 4 kV bus (1) Degraded voltage (27N) 89% of rated voltage 1. Trips emergency ("LOCA" relay)

0.3% of setting transformer feed to g

(3702 volts

11 volts) 4kV emergency bus.

0.9 - 1.1 second intemal 2. Fast transfer time delay permissive. 3. Safety injection signal Z 9 second i 7%(10.6 sec.) required. j" time delay U

4 UNIT 3 TABLE 3.2.B (continued) INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS Minimum No. of Operable Instrument Channels per Number ofInstrument l Trip System (ACTION) Channels Provided by Trip Function Trip Level Setting Design Remarks l 2 per 4 kV bus (i) Emergency Transformer 87% (iS%) of Rated

1. Trips emergency Degraded voRage VoRage.

transformer feed to (Inverse time - voRage). Tests at 2940 vots in 30 4kV emergency bus. (CV-6) seconds (110%) 2. Fast transfer permissive. S E v 4 m a an bO I w s

l ~ l Unit 3 PBAPS NOTES FOR TABLE 3.2.B 1.- With one or more required channel (s) inoperable in one or more Trip Functions, piece channel in trip within one hour or the reactor shall be placed in the Cold Shutdown Condibon within 24 hours. 2. Close isolation valves in RCIC subsystem

3. -

Close isolabon valves in HPCI subsystem 4. Instrument setpoint corresponds to 378 inches above vessel zero. ' 5. . HPCI has only one trip system for these sensors. 6. Deleted e 1 7. The failure of a 480V Emergency Load Center timer could result in the failure of a 480V Emergency Load Center to re-energize following the loss of one or both offsite sources. Therefore, Technical Specification 3.9.B.7 will apply when a 480V Emergency Load Center timer is not Operable. 8. With one or more required channel (s) inoperable in one or more Trip Functions: l -1. Within 24 hours, place inoperable channelin trip; and, 2. Wlthin one hour from discovery of loss of feature initation capabilty in both trip systems for feature (s) supported by this trip function, declare supported feature (s) inoperable (See Fcotnote (1)). 3. If required acbons and associated complebon times of Action 1 or 2 are not met, deciere assocsated supported features inoperable immodately. 9. With one or more required channel (s) inoperable in one or more Trip Funcbons-1. Within 24 hours, restore channel to Operable status; and, 2. Within one hour from descovery of loss of inibabon capability in both trip systems for feature (s) supported by this trip function, declare supported feature (s) inoperable (See Footnote (2)). 3. If required actions and assocated completion times of Action 1 or 2 are not met, declare associated supported features inoperable immodately. 10. With one or more required channel (s) inoperable in one oimore Trip Functions: 1. Within 24 hours, place inoperable channel in trip or align affected (HPCI or RCIC) pump suction to suppression pool; and, 2. Within one hour of discovery of loss of initiation capability, declare affected system (HPCI or RCIC) inoperable if associated pump suction is not aligned to suppression pool. 3. If required actions and associated completion times of Action 1 or 2 are not met, declare associated system inoperable immediately. (1) Only applicable to the High Drywell Pressure and Reactor Low-Low-Low Water Level functions. (2) Not applicable to Reactor High Water level Function. - 72 Amendment No. 14, 115, 117, 175, 206

+ i PBAPS i s 11 With one or more required channel (s) inoperable in one or more Trip Func#ons. I '1. Within one hour from decovery of ions of ADS initiation capability in both trip systems,. ' declare ADS valves inoperable; and, - ~ j 2.' . Within 96 hours from discovery of inoperable channel concurrent with HPCI or RCIC - ) inoperable, place inoperable channel in trip; and, l 3. Within 8 days from decovery of inoperable channelif both HPCI and RCIC are - Operable, place inoperable channel in trip. 4. If required actions and associated completion times of Action 1 or 2 or 3 are not (not, { declare ADS inoperable immediately. l ' 12. With one or more required channel (s) inoperable in one or more Trip Functions: j 1. Within one hour from discovery of loss of ADS inibation capability in both trip systems, declara ADS valves inoperable; and, j 2. Within 96 hours from discovery of inoperable channel concurrent with HPCI or RCIC inoperable, restore channel to Operable status; and, -l 3. Within 8 days from discovery of inoperable channelif both HPCI and RCIC are i Operable, restore channel to Operable status. 4. If required actions and associated completion times of Action 1 or 2 or 3 are not met, - a declare ADS inoperable immediately. 13. With one or more required channel (s) inoperable in one or more Trip Functions: -l 1. Within 24 hours, place channelin trip; and, j 2. Within one hour from decovery of one or more automatic functions with primary i containment isolation capabitty not maintained, restore primary isolation capability. -j 3. If required actions and associated completion times of Action 1 or 2 are not met, isolate affected penetration flow path (s) within one hour. ? I 14. With one or more required channel (s) inoperable in one or more Trip Functions: 1. Within 24 hours, place inoperable channel in trip; and, i 2. Within one hour from decovery of loss of system (HPCI or RCIC) initiation capability, declare affected system (HPCI or RCIC) inoperable. 3. If required actions and associated completion times of Action 1 or 2 are not met, declare affected system (HPCI or RCIC) inoperable immediately. 15. When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of required Actions may be delayed for up to 6 hours provided i associated Trip Function maintains trip capability. 16. When a channelis placed in an inoperable status solely for performance of required Surveillances, initiation of required Actions may be delayed for up to 6 hours. 1 i t i i - 72a - Amendment No. 206 l l \\

Unit 3-TABLE 3.2.C INSTRUMENTATION THAT INITIATES CONTROL ROD BLOCKS Minimum No. of Operable Number of instrument Channels Instrument Channels Per Trip System Instrument Trip Level Setting Provided by Design - Action l 4 (2) APRM Upscale (Flow Biased) (0.66W+59%-0.66aW) 6 Inst. Channels (10) (14) (Clamp at 108% max) 4 APRM Upscale (Startup Mode) s 12% 6 Inst. Channels (10) (14)- l 4 APRM Downscale 2 2.5 indicated on scale 6 Inst. Channels (10) (14) l 1 (7) (11) (13) Rod Block Monitor (RTP 285%), S. sHTSP 2 Inst. Channels (12) (14) - (Power Biased) (65% sRTP <85%), S slTSP j ,y (30% sRTP <65%), S sLTSP g. l 1 (7) (11) (13) Rod Block Monitor Downscale aDTSP 2 inst. Channels (12) (14) 6 IRM Downscale (3) a 2.5 Indicated on scale 8 Inst. Channels . (10) [ 6 IRM Detector not in Startup Posibon (8) 8 Inst. Channels (10) 5 6 IRM Upscale s 108 indicated on scale 8 Inst. Channels (10) E 2 (5) SRM Detector not in Startup '(4) 4 Inst. Channels (1) ,,s,,,

faf Posstion

.; O 2-(5) (6) SRM Upscale s 10 counts /sec. 4 Inst. Channels (1) 5 to(0= P' ,a d ol co ;%.' 1 (15) Scram Discharge Instrument s 25 gallons 1 Inst. Channel (9) Sl' c Volume High Level .co -4 .u 'u . - -.. -.. -... - -. ~. - -. ~

1 PZAP3 UNIT 3 1 NOTES FOR TABLE 3.2.C l 1. If the first column cannot be met for one of the two trip systems, this condition may exist for up to seven days provided that during that time the operable system is functionally tested immediately and daily thereafter; if this condition lasts longer than seven days, the system shall be tripped. If the first column cannot be met for both trip systems, the systems shall be tripped. 2. W = Loop Recirculation flow in percent of design. Trip level setting is in percent of rated power (3293 MWt). 1 AW is the difference between two loop and single loop effective recirculation drive flow rate at the same core flow. During single loop operation, the reduction in trip setting is accomplished by correcting the flow input of the flow biased rod block to preserve the' i original (two loop) relationship between the rod block setpoint and recirculation drive flow. AW = 0 for two loop operation. 3. IRM downscale is bypassed when it is on its lowest range. 4. This function is bypassed when the count rate is 2100 cps. 5. One of the four SRM inputs may be bypassed. 6. This SRM function is bypassed when the IRM range switches are on range 8 or above. 7. The trip is bypassed when the reactor power is s 30%. i 8. This function is bypassed when the mode switch is placed in Run. l i Amendment No. 33, al, 52, 77, j 79, 150, 155, M4, 206

I PBAPST UNIT 3 NOTES FOR TABLE 3 2.C (Cont.) 9. If the number of operable channels is less than required by the minimum operable f channels per trip function requirement,' place the inoperable channel in the tripped i condition within twelve hours. 10. For the Startup (for IRM rod block) and the Run (for APRM rod block) positions of the Reactor Mode Selector Switch and with the number of OPERABLE channels: a. One less than required by the Minimum OPERABLE Channels per Trip Function requirement, restore the inoperable channel to OPERABLE status within 7 days or place the inoperable channel in the tripped condition within the next hour. b. Two or more less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at least one inoperable channel in the tripped condition within one hour. 11. The values of HTSP, ITSP, LTSP and DTSP are specified in the CORE OPERATING { LIMITS REPORT. t 12. With one or more required Rod Block Monitor channel (s) inoperable: a. With one rod block monitor (RBM) channel inoperable, restore RBM channel to Operable status.within 24 hours. b. If the required action and associated completion time in Action a above are not l met, place one RBM channel in trip within 1 hour. With 2 RBM channels inoperable, place 6ne RBM channel in trip within 1 hour. c. 13. Section 3.3.B.5 is Applicable during operation with a limiting control rod pattom. 14. When a channel is placed in an inoperable status solely for performance of required Surveillances, initiation of these Actions may be delayed for up to 6 hours provided the associated function maintains control rod block capability. h 15. The scram discharge instrument volume has only one trip system. i -{ .I -74a. Amendment No. 88, 93, 153, 18//, 206 i

TABLE 3.2.D Unit 3 RADIATION MONITORING SYSTEMS THAT INITIATE AND/OR ISOLATE SYSTEMS Minimum No. of Number of l Channels Operable instrument instrument Action 3 Channels Provided (1) l Per Trip System Trip Function Trip Level Setting by Design 2 Refuel Area Exhaust Monitor Upscale, <16 mr/hr 4 Inst. Channels A or B 2 Reactor Building Exhaust Upscale, <16 mr/hr 4 Inst. Channels -B Monitors 8 1 Main Stack Monitor Upscale, s 10 cps 2 Inst. Channels C 2 (2) Main Control Room Upscale, <400 cpm 4 Inst. Channels D h Notes for Table 3.2.D m

1. Action k

A. Cease operation of the refueling equipment. E B. Isolate secondary containment and start the standby gas treatment system. 5 C. Cease purging of primary containmert, and close vent and purge valves greater than 2 inches in diameter. D. As described in LCO 3.11.A.S. ? )h 2. The trip function is required to be operable whenever secondary containment is required on either unit. A CZ o E a u n ~, -- _ n +.. .. ~..,,,, -..., - -.

~ TABLE 3.2.G INSTRUMENTATION THAT INITIATES ALTERNATE ROD INSERTION AND RECIRCULATION PUMP TRIP - . Unit 3 l } Minimum No. of Number of Operable instrument instrument Chann les. Channels Provided by Design Per Trip System Instrument Trip Level Setting per Trip system 2 Reactor High Pressure s 1120 psig 2 2 Reactor Low-Low Water Level 2 -48 in. indicated level 2 = ar b i = e m._ h ,_'_m_. m.hhm- -um- _. - _ ..._-mmomu.___- __..-m-m> mm.. ____m.m. m

44 r N Unit 3 TABLE 4 2.A MINIMUM TEST AND CALIBRATION FREQUENCY FOR PCIS Instrument Channel (5) Instrument Func#onal Test Calibra6on Freauency Instrurr.ent Check

1) Reactor Hgh Pressure Once/ 3 months Once/3 months None (Shutdown Cooling Permissive)

2) Reactor Low-Low-Low OnceG months (3)

Once/operstng cycle Once/ day. Water Level (7)

3) Main Steam High Temp.

OnceG months (3) Once/operatog cycle Once/dey

4) Main Steam High Flow (7)

Once/3 months (3) Once/ epm.i.g cycle Once/ day

5) Main Steam Low Pressure Once/3 months Once/3 months

. None-

6) Reactor Water Cleanup.

Once/3 months Once/3 months Once/ day High Flow i

7) Reactor Water Cleanup Once/3 months Once/3 months None High Temp.

8) Reactor Pressure Once/3 months _(3)

Once/operetng cyde Once/ day (Feedwater Flush Permissive) i b 9 Loaic System Functional Test (4) (6) Freauency .j_

1) Main Steam Line isolation Vvs.

Once/operabng cyde Main Steam line Drain Vvs. E Reactor Water Sample Vvs. 3 Q 2) RHR - Isolation Vv. Control Once/ operating efcle g Shutdown Cooling Vvs. r* z 3) Reactor Water Cleanup Isolation Once/operatino cycle

4) Drywell !solabon Vvs.

Once/ operating cyde .ar, W TIP Wthdrawal Atmospheric Control Vvs. Sump Drain Valves

5) Standby Gas Treatment System Once/operabng cyde E $

Reactor Building isolation m* CZ-5 u 3-L. m. , ~.. ~.,. _. m. m.-,. ,m.,...,

I Unit 3 - TABLE 4.2.B MINIMUM TEST AND CAllBRATION FREQUENCY FOR CSCS Instrument Channel Instrument Functional Test Calibration Frequency Instrument Check l 1) Reactor Water Level (7) Once/3 months (3) Once/ operating cycle Once/dey l 2) Drywell Pressure (7) Once/3 months (3) Once/ operating cycle Once/dey l 3) Reactor Pressure (7) Once/3 months (3) Once/ operating cycle Once/dey l 4) Reactor Pressure - Once/3 months Once/3 months None PCIS/LPCI interlock 5) Auto Sequencing Timers NA Once/ operating cycle None f l 6) ADS - LPCI or CS Pump Once/3 months - Once/3 months None a, Disch. Pressure Interlocks fg 7) Trip System Bus Once/3 months NA None 3g Power Monitors

sg l 8)

Core Spray Sparger d/p Once/3 months Once/6 ' months Once/ day S 9) Steam Line High Flow Once/3 months Once/3 months None g (HPCI & RCIC) o> 10) Steam Line High Flow Timers NA Once/ operating cycle. None N (HPCI and RCIC) j$ 11) Steam Une High Temp. Once/3 months (3) Once/ operating cycle Once/dey (HPCl & RCIC) o 12) Safeguards Area High Temp. Once/3 months Once/3 months None ra E! E "u s -.n -a.,,,. .-.-.,en,. m._,,,_

Unit 3 TABLE 4.2.B (continued) MINIMUM TEST AND CALIBRATION FREQUENCY FOR CSCS Instrument Channel Instrument Functional Test Calibration Frequency Instrument Check 13) HPCI and RCIC Steam Une Once/3 months Once/3 months None Low Pressure l'14) HPCI Suction Once/3 months Once/3 months None-Source Levels 15) 4KV Emergency Power System Once/ operating cycle Once/5 years None Voltage Relays (HGA,SV) 16) ADS Relief Valves Bellows Once/ operating cycle Once/ operating cycle None g Pressure Switches 9 g-17) LPCl/ Cross Connect Once/ refueling cycle N/A N/A li Valve Position 18) Condensate Storage Once/3 months Once/ operating cycle Once/ day Tank Level (RCIC) (7) Po => [ 19) 4KV Emergency Power Source Once/ month Once/ eighteen months None g Degraded Voltage Relays (IAV,CV-6,lTE) 2

s

~ 8: s ,a m v, -e-v-. .e.. w e ~ e -,.w, m. m-, -.. e

,.--wr--e w.-

w -s

TABLE 4.2.C Unit 2 MINIMUM TEST AND CALIBRATION FREQUENCY FOR CONTROL ROD BLOCKS ACTUATION instrument Channel Instrument Functional Test Calibration Instrument Check.

1) APRM - Downscale Once/3 months (3)

Once/3 months Once/ day l

2) APRM - Upscale Once/3 months (3)

Once/3 months Once/ day

3) IRM - Upscale (2)(3)

Startup or (2) Control Shutdown

4) IRM - Downscale (2) (3)

Startup or (2)- Control Shutdown l

5) RBM - Upscale Once/3 months (3)

Once/B months Once/dey 6, l

6) RBM - Downscale Once/3 months (3)

Once/6 months Once/dey f, v

7) SRM - Upscale (2)(3)

Startup or (2) on ,3 Control Shutdown s

8) SRM - Detector (2) (3)

N/A (2) '[ Not in Startup Position S

9) IRM - Detector (2) (3)

N/A (2) g Not in Startup Position

10) Scram Discharge Quarterly.

Once/ Operating Cycle N/A co 1 Instrument Volume - High Level M 1

Loaic System Functional Test (4) (6)

Frequency O {

1) System Logic Check Once/ Operating Cycle co

~ R o o, U ,,.w- -e e ce<m m.. ,+-ar -er,, r-m.-----r+- ,a +. v nw .e. ,-..w ,,swc- .m,.n--. s ,wme

'.S@@ TABLE 4.2.D Unit 3 ' MINIMUM TEST & CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS Instrument Channels Instrument Functional Test Calibration instrument Check (2) l

1) Refuel Area Exhaust Once/3 months Once/3 months Once/ day Monitors - Upscale l 2) Reactor Building Area Once/3 months Once/3 months Once/ day -

3) Main Stack Monitor Once/3 months Once/12 months Once/ day as described in 4.8.C.4.a

4) Main Control Room Once/3 months Once/18 months Once/ day as described in 4.11.A.5 E

Loaic System Functional Test (4) (6) Frequency i

1) Reactor Building isolation Once/ Operating Cycle E

2) Standby Gas Treatment System Actuation Once/ Operating Cycle

.Po P. E '[n y .a c-O E A o. .m m.m t rGm r._,m.p ,.me.-.-... w ,,,...,y ,_yw ,,,-w w. ,y.w,.v.,, 9 g.y,

1 1 TABLE 4.2.E - Unit 3 - MINIMUM TEST & CAllBRATION FREQUENCY FOR DRYWELL LEAK DETECTION ' Instrument Channel Instrument Functional Test Calibration Frequency Instrument Check l

1) Equipment Drain Sump Once/ month Once/3 months Once/ day Flow Integrator l

2) Floor Drain Sump Once/ month Once/3 months Once/ day Flow Integrator l

3) Drywell Atmosphere Once/ month Once/3 months Once/ day Radioactivity Monitor.

Y R it i E E m w e--- s m. .--e--- ~ -, .w. .-n -w-- -.g-,e -s ew.. -- -i -w-e -em d.- .r+,.4 4,.- ,s.m- --.eew v---..-.., -

PZAPS UNn'3 NOTES FOR TABLES 4.2.A THROUGH 4.2.F 1. Deleted. 2. Functional tests, calibrations and instrument checks are not required when these instruments are not required to be operable or are tripped. Functional tests shall be performed before each startup with a required frequency not to exceed once per week. Calibrations shall be performed within 24 hours before each startup or controlled shutdown with a required frequency not to exceed once per week. Instrument checks shall be performed at least once per day during those periods when the instruments are required to be operable. 3. This instrumentation is excepted from the functional test definition. The functional test will consist of injecting a simulated electrical signal into the measurement channel. These instrument channels will be calibrated using simulated electrical signals. 4. Simulated automatic actuation shall be performed once each operating cycle. Where possible, all logic system functional tests will be performed using the test jacks. 5. Reactor low water level, high drywell pressure and high radiation main steam line tunnel are not included on Table 4.2.A since they are tested on Table 4.1.2. 6. The logic system functional tests shall include a calibration of time delay relays and timers necessary for proper functioning of the trip systems. 7. These channels consist of analog transmitters, indicators and electronic Trip units. l Amendment No. &9,'206 'I TABLE 4.2.G Unit 3.'. MINIMUM TEST AND CALIBRATION FREQUENCY FOR ALTERNATE ROD INSERTION AND RECIRCULATI instrument Channel Instrument Check Instrument Functional Test Calibrahon Frequency (1) (1)- (1) Reactor High Pressure Once/ day Once/3 months Once/ Operating Cycle Reactor Low-Low Water Level Once/doy Once/3 months Once/ Operating Cycle Looic System Functional Test (2) Frequency h Alternate Rod insertion / Recirculation Pump Trip Once/3 months i .( Altemate Rod insertion / Recirculation Pump Trip Once/ Operating Cycle including air venting and breaker trip (3) E g Notes: 1. In sccuidence with Table 4.2.B. These instrument channels are the same ones used by the Core and Containment f Coeling Systems. j$

2. The recimulation pumps need not be tripped h

3.. This test, peifvinred while shutdown, will include venting of the scram air header and tripping of the recirculahon pump breakers. The test will also verify operability of the manual actuation logic.

3 k- - s,a - 1. "e*,+==geme .-gm vw++es.mw. ew--%, c. m >. www-e-3-w'e= m--u-msy+3 -e -pav r e

->g-ve m e it-

,,s e s ew m-e e. + ra-e

wf--

n-emy-ew-g be y s-ysuwe ew -.mre.se e%+=*mses M-T++m-m-'=v=e-u. - e'e e* .=-+w+s .we 'h-- Me -wve m>

'm evw*ea-W

Unit 3 PBAPS 32 BAggg In addition to reactor protection instrumentation which initiates a reactor scram, protective instrumentation has been provided which initiates action to mitigate the consequences cf accidents which are beyond the operator's ability to control, or terminates operator' errors before they result in serious consequences. This set of specificatione provides the limiting conditions of operation for the primary system isolation function, initiation of the core cooling systems, control rod block and standby gas treatment systems. The objectives of the Specifications are (1) to assure the effectiveness of the protective instrumentation when. required even during periods when portions of such systems are out-of-service for maintenance, and (ii) to prescribe the trip settings required to assure adequate performance. Channel functional test frequencies and allowed out of service times for repair and surveillance testing for Isolation Instrumentation have been determined in accordance with General Electric reports NEDC-30851P-A, Supplement 2, " Technical Specification Improvement Analysis for BWR Isolation Instrumentation Common to RPS and ECCS Instrumentation," and NEDC-31677P-A," Technical Specification Improvement Analyses for BWR Isolation Actuation Instrumentation." The AOT is 12 hours for Table 3.2.A Items 1, 4, and 5 because these items have instrumentation that is common to the RPS. Other Table 3.2.A Items have an AOT of 24 hours. Channel functional test frequencies and allowed out of service times for repair and surveillance testing for ECCS Actuation Instrumentation have been determined in accordance with General Electric reports NEDC-30936P-A,"BWR Owners' Group Technical Specification Improvement Methodology with Demonstration for BWR ECCS Actuation Instrumentation," Parts 1 and 2, and RE-022," Technical Specification Improvement Analysis for the Emergency Core Cooling System Actuation Instrumentation for Peach Bottom Atomic Power Station, Units 2 and 3." Channel functional test frequencies and allowed out of service times for repair and surveillance testing for miscellaneous instruments have been determined in accordance with General Electric report GENE-770-06-1," Bases for Changes to Surveillance Test Intervals and Allowed out-of-Service Times for Selected Instrumentation Technical Specifications," and the associated NRC Safety Evaluation Report dated July 21, 1992. Channel functional test frequencies and allowed out of service times for repair and surveillance testing for RCIC instrumentation have been determined in accordance with Amendment No.15, ML 206 1 I Unit 3 g K' PBAPS

3.2} R& GEE (continued)

' General Electric report GENE-770-06-2," Bases for Changes to l

Surveillance Test Intervals and Allowed Out-of-Service Times for Selected Instrumentation Technical Specifications," and e

the associated NRC Safety' Evaluation Report dated September 13, 1991. Some of the settings on the instrumentation that initiate or control core and containment cooling have tolerances explicitly stated where the high and low values are both j critical and may have a substantial effect on safety. The 1 set points of other instrumentation, where only the high or low and of the setting has a' direct bearing on safety, are chosen at a-level away from the normal ~ operating range to prevent inadvertent actuation of the safety system involved and exposure to abnormal situations. I Actuation of primary containment valves is initiated by. protective instrumentation'shown in Table 3.2.A which senses the conditions for which isolation is required. Such instrumentation must be available whenever primary containment integrity is required. The instrumentation which initiates primary system isolation is-connected in a dual bus arrangement. The low water level instrumentation set to trip at'zero inches indicated level (538 inches above vessel zero) closes all isolation valves except those in Groups 1, 4 and 5. Details of valve grouping and required closing times are given in Specification 3.7. For. valves which isolate at 'this level, this trip setting is adequate to prevent the core from being uncovered in the case of a break in the 1 ' largest line assuming a 60 second valve closing time. { Required closing times are less than this. ) 1 The low-low reactor water leve1' instrumentation is set to l trip when reactor water level'is minus 48 inches indicated level (490 inches above vessel zero). This trip initiates HPCI, RCIC, Alternate Rod Insertion and trips the recirculation pumps. The low-low-low reactor water level instrumentation is set to trip when'the reactor water level is minus 160 inches indicated level (378 inches above vessel zero). This trip closes. Main Steam Line Isolation valves, 1 Main Steam Drain Valves and Recirc Sample Valves (Group 1), activates the remainder of the CSCS subsystem, and starts i -89a-Amendment No. 206

b i Unit 3 PBAPS l 3.2 BASES (Cont'd) Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drops below 850 i psig. The Reactor Pressure Vessel thermal transient due to an inadvertent opening of the turbine bypass valves when not in the RUN Mode i is less severe than the loss of feedwater analyzed in section 14.5 of the FSAR; therefore, closure of the Main Steam isolation valves for thermal transient protection when not in RUN Mode is not required. The HPCI high flow and temperature instrumentation are provided to detect a break in the HPCI steam piping. Tripping of this instrumentation results in actuation of HPCI isolation valves. Tripping logic for the high flow is 1 out of 2 logic. Temperature is monitored at four (4) locations with four (4) temperature sensors at each location. Two (2) sensors at each location are powered by "A" DC control bus and two (2) by '"B" DC control bus. Each pair of sensors, e.g., "A" or "B" at each location are physically separated and the tripping of either "A" or "B" bus sensor will actuate HPCI isolation valves. The trip settings of s 300% of design flow for high flow and 200 degrees F for high -temperature are such that core uncovery is prevented and fission product release is within limits. The RCIC high flow and temperature instrumentation are arranged the same I as that for the HPCI. The trip setting of s 300% for high flow and 200 degrees F for temperature are based on the same criteria as the HPCI. The Reactor Water Cleanup System high flow instrumentation is arranged similar to that for the HPCI System. The trip settings are such that core uncovery is prevented and fission product release is maintained within limits. The high temperature instrumentation downstream of the i non-regenerative heat exchanger is provided to protect the ion exchange resin in the demineralizer from damage due to high temperature. Such damage could impair the resins' ability to remove impurities from the primary coolant and possibly result in the release of previously captured impurities back into the coolant in large concentrations. The instrumentation which initiates CSCS action is arranged in a dual bus i system. As for other vital instrumentation arranged in this f'shion, the a Specification preserves the effectiveness of the system even during periods when maintenance or testing is being performed. An exception to this is when logic functional testing is being performed. The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR does not decrease to the fuel cladding integrity safety limit. The trip logic for this function is 1 out of n: e.g., any trip on one of 6 APRM's, 8 IRM's, or 4 SRM's will result in a rod block. f The minimum instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met. ! Amendment No. li, il, 79, 108, 206 r i i

~ .;c l Unit 3 PBAPS 4.2 BASES The instrumentation listed in Tables 4.2.A through 4.2.F will be functionally tested and calibrated at regularly scheduled intervals. 1 4 Amendment No. 206

Unit 3 PBAPS 4,2 BASES l' Intentionally Left Blank I [ I Amendment No. 206

Unit 3 i PBAPS 4.2 BASES (continued) Intentionally.Left Blank l 7 ! Amendment No. 206

Unit 3 PBAPS 4.2 BASES (continued) Intentionally Left Blank 3 i l ' haendment No. 206 .}}

ML20086B514

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ML20086B514
Site:	Peach Bottom (DPR-044, DPR-056)
Issue date:	06/06/1995
From:	Stolz J Office of Nuclear Reactor Regulation
To:	Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co
Shared Package
ML20086B515	List: ML20086B514 ML20086B525
References
DPR-44-A-203, DPR-56-A-206 NUDOCS 9507050425
Download: ML20086B514 (126)
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