ML20040G962
| ML20040G962 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/08/1982 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20040G949 | List: |
| References | |
| NUDOCS 8202160668 | |
| Download: ML20040G962 (15) | |
Text
JAFNPP TABLE 3.1-1 (Cont'd)
REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENT Minimum No. Modes in Which Total of Operable Function Must Be Number of Instrument Operable Instrument-Channels Trip Function Trip Level Channels. Action per Trip Setting Provided (1)
System (1) Refuel Startup Run by Design (6) for Both Trip Systems 2 APIN Downscale >2.5 indicated on X 6 Instrument - A or B scale (9)
Channels 2 liigh Reactor g 1045 psig X(8) X X Pmssum 4 Instrument A Channels 2 liigh Drywell .2.7
< psig X(7) X(7) X Pressure 4 Instrument A Channels 2 Reactor Iow Water 412.5 in.
indicated level X X X 4 Instrument A level
(> 177 in. above Channels tiie top of active fuel) 2 liigh Water Level < 36 gal X(2) X X 4 Instrument A in Scram Discharge ~ Channels Volume mmo 2 Main Steam Line <3 x normal full X X X 4 Instrument A So" liigh Radiation power background Channels 4 Main Steam Line <10% valve X(3) (5) X(3) (5) X(5) 8 Instrument A Isolation Valve Closure closure Channels /g W
AmendmentNo.g,g 41a 2=5 =
JAFNPP TABLE 3.1-1 (Cont'd)~ ,
1 RE/CIOR PROTECTION SYSTEM (SCRAM) INSTRLNENTATHN RF4UIREMENT Mininun No. Modes in Which 'Ibtal of Operable Function Must Be Number of Instrunent Operable Instrunent Channels Trip Function Trip IcVel Channels Action per Trip Setting Provided (1)
Systen (1) Refuel Startup Run by Design (6) for Both Trip Systems l
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2 Turbine Control 500<F<850 psig X(4) 4 Instrunent A or C l Valve Fast Closure Control oil pressure Channels between fast closure solenoid and disc dtmp valve l
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l Amerdnent No. 41b
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TABLE 3.2-1 INSTRUMENTATION TIIAT INITIATES PRIMARY CONTAINMENT ISOLATION Minunum Number of 'Ibtal Ntut;er of Instrument Oparable Instrunent Channels Channels Provided by Design Action per Trip System (1) Instrunent Trip IcVel Setting for Both Trip Systens (2) 2 (6) Reactor Iow Water 112.5 in Indicated 4 Inst. Channels A Ievel Invel (>l77 in, above the top of active fuel) 1 Reactor liigh Pressure s 75 psig 2 Inst. Channels D (Shutdown Cooling Isolation) 2 Reactor Irw-Iow > -38 in. indicated 4 Inst. Channels A Water Invel level (> 126.5 in. above the top of active fuel) 2 (6) High Drywell Pressure s2.7 psig 4 Inst. Channels A 2 High Radiation Main 53 x Normal Rated 4 Inst. Channels B Steam Iane Tunnel Full Power Background 2 Iow Pressure Miin y_825 psig (7) 4 Inst. Channels B Steam Iane 2 High Flow Main Steam < 140% of Rated Steam 4 Inst. Channels B Line Flow 2 - Main Steam Line Icak < 40*F above max 4 Inst. Channels B Detection High ~ ambient TENUperature o
3 Reactor Cleanup Sys- 5 40 F above max 6 Inst. Channels C tem Equipnent Area ambient High TEsoperature 2 Iow Condenser Vacuum y 8" H g. Vac (8) 4 Inst. Channels B closes MSIV's hmerdvent No. ) Wu y f,Atf 64
4 JAMPP TABE 3.2-1 (Cont'd)
INSTRNENTATION TiiAT INITIATE PRIMARY CONIAIM1ENT ISOIATICN NOIE FOR TAB 2 3.2-1
- 1. Whenever Primary Containment integrity is required by Section 3.7, there shall be two operable or tripped trip sys' cans for each function.
, 2. Frm and after the titre it is found that the first column cannot be met for one of the trip systesnc, that trip systs shall be tripped or the appropriate action listed below shall be taken.
A. Initiate an orderly shutdown and have the reactor in cold shutdown condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B. Initiate an orderly load reduction and have main steam lines isolated within eight hours.
C. Isolate Reactor Water Cleanup System.
D. Isolate shutdown cooling.
- 3. Deleted
- 4. Deleted
- 5. % c required for each steam line.
- 6. These signals also start SBGTS and initiate secondary containment isolation.
- 7. Only required in run node (interlocked with Mode Switch) .
- 8. Bypassed when reactor pressure is less than 1005 psig and turbine stop valves are closed.
L Amendment No. # , J4f 6S
JAFNPP TABLE 3.2-2 l
INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS l
Mininun No. Total of Operable Ntznber of Instru-Instrunent ment Channels Pro- i Item Channels Per vided by Design For '
No. Trip Systen (1) Trip Function Trip Invel Setting Both Trip Systens Itsnarks l
l 1 2 Reactor Iow-Iow >-38 in. indicated 4 HPCI 4 BCIC Initiates HPCI, ICIC & l l Water Invel Tevel(>l26.5 in.
~
Inst. Channels SGIS.
I above the top of ac-tive fuel) 2 2 Reactor Iow-Iow- > -146.5 in. indicated 4 Core Spray & RHR Initiates Core Spray, Iow Water level level (> 18 in, above Instrunent (2annels LPCI, and Bnergency the top of active fuel) Dianal Generators.
4 ADS Instrument Initiates ADS in conjunc-Channels tion with confinnatory low level, High Drywell Pressure, 120 second time delay and IKI or Core Spray ptmp discharge preamwe interlock.
3 2 Reactor High Water <+58 in. indicated 2 Inst. Channels Trips HPCI and RCIC Invel level (<222.5 in. 'Ibrbines ,
above tiin top of ac-tive fuel) 4 1 Reactor Iow Invel > +352 in. above 2 Inst. Channels Prevents inadvertant (inside shroud) vessel zero(> 0 in, operation of containment above the top of active spray during =v'idant fuel) condition.
Amendment Nofrf E6
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JAFNPP TABIE 3.2-2 (Cont'd)
INSTRUMENTATION TIAT INITIATES OR CONIBOIS TIE CORE AND CONTAIMENT COOLING SYSUNS 1
\ l Minimum No. Total of Operable Ntznber of Instru- 1 Instrument ment Channels Pro-Itan Channels Per vided by Design for No. Trip Systen (1) Trip Function Trip IcVel Setting Both Trip Systems Ihanarks )
5 2 Contairunent High 1< P< 2.7 psig 4 Inst. Channels Prevents inadvertent l Pressure operation of contain- l l ment spray during ;
I accident condition.
6 1 Confirmatory Low > 12.5 in, indicated 2 Inst. Channels ADS Pennissive.
IcVel Tevel (> 177 in, above l the top of active fuel) l l
7 2 High Drywell < 2.7 psig 4 IIPCI Inst. Chan- Initiates Core Spray,IPCI, HPCI &
Pressure nels SGES.
4 RHR & Cbre Spray Initiates starting Inst. Channels of Diesel Generators 8 -2 Reactor Low Pressure > 450 psig 4 Inst. Channels Permissive for opening Core Spray and IPCI Admission valves.
Amendment No. ) % g 67 9
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JAFNPP ,
TABLE 3.2-2 (Cont'd)
INSTRUMENTATION 'IIIAT INITIATES OR ONIPOIS 'IIIE CORE AND ONTAIPNENT COOLING SYSTENS 1
NOTES EUR TABLE 3.2-2 l 1. Whenever any EOCS subsysts is required by specification 3.5 to be operable, there shall be two l operable trip systms. Frm and after the time it is found that the first coltunn cannot be met for one of the trip systa s, that trip syst s shall be placed in the tripped condition or the reactor shall be placed in the cold condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l
! 2. Deleted s 3.' Pcfer to Technical Specification 3.5.A for limiting conditions for operation, failure of one (1) instrment channel disables one (1) puip.
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Amendment No. /
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TABIE 3.2-6 SURVEILIANCE INSTRLNENTATIO4 Mininun No.
of Operable No. of Channels Instrument Type Indication Provided Channels Instrument and Range by Design Action Reactor Invel Indicator (D) (2)
(Note 3) 0 - +60 (164.5 to 224.5 in.
2 above the top of .i active fuel) l 5
Reactor IcVel Recorder (Note 4) 0 - +60 (164.5 to 224.5 in. above ' l the top of active fuel) -
I l i
1 Reactor Icvel Indicator 2 (2) l
-150 - +60 (14.5 to 224.5 in.
above the top of active fuel) l Reactor Pressure Indicator ;
(Note 5) 0-1200 psig Decorder 2 Reactor Pressure (Note 6) 0-1200 psig Drywell Pressure (Narrow Range) ,
(Narrow Range) Indicator Recorder 10 - 19 psia Drywell Pressure (Wide Range)
(Wide Range) Indicator Recorder 0 - 100 psia hmeng1 ment No. W JM(, yf 76
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TABLE 3.2-6 SURVEILLANCE INSTRUMENTATION Minimum No.
of Operable No. of Channels Instrument . Type Indication Provided Chrnnels Instrument and Range by Design Action (Suppression Chamber Indicator )
(Water Level Recorder )
( (Wide Range) -72 to + 72 inches) 1 ( 2
) (2) .
(Suppression Chamber Indicator )
(Water Level Recorder )
( (Narrow Range) -6 to +6 inches )
N/A Control Rod Indicator 1 (7)
Position Indication Position 00 to 48 2 Source Range Indicator 4 (8)
Monitors Recorder 1 to 106 cps 3 Intermediate Indicator 8 (8) (9)
Range Monitor Recorder 10-4 to 404 Rated Power 2 Average Power Indicator 6 (8) (9)
Range Monitors Recorder 0-325% Rated Power 1 Drywell-Suppression Recorder 2 (2)
Chamber Differential O to 5 psi Pressure Computer 0 to 5 psi 1 Safety / Relief Valve Indicator 2 (12) (11)
Position Indicator Open/ Closed (Note 10)
NOTES FOR TABLE 3.2-6
- 1. From and after the date that the minimum number of operable instrument channels is one less than the minimum number specified for each parameter, continued operation is permissible during the succeeding 30 days unless the minimum number specified is made operable sooner.
' Amencfment Ho M 76 b
y NOTES FOR TABLE 3.2-6 (CONTINUED)
- 2. In the event that all indications of this parameter is disabled and such indication cannot bn restored in six (6) hours, an orderly shutdown shall be initiated and the reactor shall be in a Hot Shutdown condition in six (6) hours and a Cold Shutdown condition in the following eighteen (18) hours.
- 3. Three (3) indicators from level instrument channel A, B, & C. Channel A or B are utilized for feedwater control, reactor water high and low level alarms, recirculation pump runback. High level trip of main turbine and feedwater pump turbine utilizes channel A, B, & C.
- 4. One (1) recorder utilized the same level instrument channel as selected for feedwater control.
- 5. Three (3) indicatora from reactor pressure instrument channel A,.B, & C. Channel A or B are utilized for feedwater control and reactor pressure high alarm.
- 6. One (1) recorder. Utilizes the same reactor pressure instrument channel as selected for feedwater control.
- 7. The position of each of the 137 control rods is monitored by the Rod Position Information System. For control rods in which the position is unknown, refer to Paragraph 3.3.A.
- 8. Neutron monitoring operability requirements are specified by Table 3.1-1 and Paragraph 3.3.B.4.
9.
A minimum of 3 IRM or 2 APRM channels respectively must be operable (or tripped) in each safety system.
- 10. Each Safety Relief Valve is equipped with two acoustical detectors of which one is in service and a backup thermocouple detector.
11.
From and after the date that none of the acoustical detectors is operable but the thermocouple is operable, continued operation is permissible until the next outage in which a primary containment entry is made. Both acoustical detectors shall be made operable prior to restart.
12.
In the event that both primary and secondary indications of this parameter for any one valve are disabled and neither indication can be restored in forty-eight (48) hours, an orderly shutdown shall be initiated and the reactor shall be in a Hot Shutdown condition in twelve (12) hours and in a Cold Shutdown within the next twenty-four (24) hours.
13.
From and after the date that the minimum number of operable ins ~trument channels is one less than the minimum number specified for each parameter, continued operation is permissable during the succeeding 7 days unless the minimum number specified is made operable sooner, hmendment No. 40 , )1 76 c
JAFNPP TABIE 3.2-7 INSTPINENTATION ' MAT INITIATES RECIBCUIATION PUMP TRIP Minumum Nmber of Total Nmber of Instrument' Operable Instnznent Channels Provided by Channels per Trip Design for Both Systen (1) Instrument Trip level Setting Channels Action 1 Reactor High Pressure > 1120 psig 4 (2) 1 Reactor Iow-Iow > -38 in. indicated 4 (2)
Water Invel level (>126.5 in. above the top'of active fuel Notes for Table 3.2-7
- 1. Whenever the reactor is in the run mode, there shall be one operable trip sytsu for eaah parameter for each operating
- recirculation punp. From and after the time it is found that this cannot be met, the indicated action sinll be taken.
- 2. Reduce power and place the Mode Selector Switch in a Mode other than the Run mde witlun 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment No. 77
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ATTACHMENT I PROPOSED TECHNICAL SPECIFICATIONS CHANGES RELATED TO REACTOR VESSEL - COMMON REFERENCE LEVEL POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
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1 ATTACHMENT II.
SAFETY EVALUATION 7
4 RELATED TO REACTOR VESSEL.- COMMON ,
REFERENCE LEVEL 1
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 i
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e g Section I - Description of Modification The proposed changes to the James A. FitzPatrick Nuclear Power Plant -(JAJHPP)
Operating License, Appendix A (Technical Specifications) incorporate additional
'information concerning reactor vessel water level in Tables 3.1-1, 3.2-2, 3 2-6 and 3.2-7 of the Technical Specifications (pages 41a, 64, 65, 66, 67, 71, 76 and 77) . Where indicated reactor vessel water levels are given in these tables, a notation has been cdded to give the equivalent water level above the top of active fuel. These changes cre proposed in response to Reference (c).
Section II - Purpose of the Modification The proposed changes provides additional information concerning reactor vessel w;ter level in Tables 3.1-1, 3.2-2, 3.2-6 and 3 2-7 of the Technical Specifications (pages 41a, 64, 65, 66, 67, 71, 76 and 77). Where indicated reactor vessel water levels are given in these tables, a notation has been added to give the equivalent water level Ebove the top of active fuel. This amendment, if approved, will fulfill the commitment for Technical Specification changes made in Reference (d) .
Szction III - Impact of the Change These changes to the Technical Specifications provide reactor vessel water level miasurements from a common reference point (the top of active fuel). These changes also assure that the Technical Specifications contain the same reactor vessel water levels as provided by the control room instrumentation.
Section IV - Implementation of the Modification The modification as proposed will not impact the Fire Protection or ALARA Programs at JAFNPP.
Section V - Conclusion The incorporation of these modifications: a) will not change the probability nor the consequences of an accident or malfunction of equipment important to safety as
. previously evaluated in the Safety Analysis Report; b) will not increase the possibility for an accident or malfuncti 1 1 of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Techical Specification; and d) does not constitute an unreviewed safety quistion.
Section VI - References (a) JAF FSAR (b) JAF SER (c) Letter, T. A. Ippolito (NRC) to G. T. Berry (PASNY), dated October 19, 1981, concerning NUREG-0737 Item II.K.3.27 - Common Reference Level.
(d) Letter, J. P. Bayne (PASNY) to T. A. Ippolito (NRC), dated November 25, 1981, concerning NUREG-0737 Item II.K.3.27 - Common Reference Level.
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