ML18033A656
| ML18033A656 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/24/1989 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18033A654 | List: |
| References | |
| NUDOCS 8903080159 | |
| Download: ML18033A656 (20) | |
Text
Enclosure 1
Propo ed Technical Specifications Revi "ions Brows Ferry Nuclear Plant Unit 2 (TVA BFN TS 263) 89030SOi59 890224 PDFi ADOCK 05000260 P
I 0'
TABLE 4.1.8 REACTOR PROTECTION SYSTEH (SCRAM)
INSTRUMENT CALIBRATION HINIHUH CALIBRATION FREQUENCIES FOR REACTOR PROTECTION INSTRUMENT CIIANNELS Instrwnent Channel IRM Iligh Flux APRH lligh Flux Output Signal Flow Bias Siijnai LPRH Signal lligh Reactor Pressure tPIS-3-22 AAp BBp Cp D) lligh Drywell Pressure (PIS-64-56 A-D)
Reactor Low bhter Level (LIS-3-203 A-D) lligh 4hter Level in Scram Discharge Volume Float Switches (LS-8545-C-F)
Electronic Level Switches (I.S-85-45 A, B, G, ll)
Hain Steam Line Isolation Valve Closure Hain Steam Line Iligh Radiation Turbine First Stage Pressure Permissive (PIS-1-81
- AEB, P 15-1-91 AEB)
Turbine Stop Valve Closure I
Turbine Control Valve Fast Closure on Turbine Trip Low Scram Pilot Air Ileader Pressure (PS 85-35 Al, A2, Bl, 6 B2)
Grou 1
Calibration Comparison to APRH on Controlled Startups (6)
Ileat Balance Calibrate Flow Bias Signal (7)
TIP Systen Traverse (8)
Standard Pressure Source Standard Pressure Source Pressure Standard Calibrated Mater Column Calibrated Mater Colunm Note (5)
Standard Current Source (3)
Standard Pressure Source Note (5)
Standard Pressure Source Standard Pressure Source Minimum Fre uenc 2
Note (4)
Once/1 Days Once/Operating Cycle Every 1000 Effective Full Power Hours Once/6 Honths (9)
Once/18 Honths (9)
Once/10 Honths (9)
Once/10 Months Once/18 Honths (9)
Note (5)
Every3 Honths
. Once/18 Months (9)
Note (5)
Once/Operating Cycle Once/18 Honths BFN-Unit 2
I
TABLE 3.2.B ltlSTRUHENTATION TINT INITIATES OR CONTROLS TllE CORE AND CONTAINMENT COOLING SYSTEHS Hininun No.
Operable Per T~ri Ss i
Function Tri Level Settin Action Remarks 2(16) 1(16)
Instrument Channel Reactor Low bhter Level (LIS-3-58A-D)
Instrunient Channel Reactor Low bhter Level (LIS-3-58A-0) lnstrunient Channel Reactor Low bhter Level (LS-3-58A-D)
Instrument Channel Reactor Low bhter Level (LS-3-58A-0)
Instrunient Channel Reactor Low bhter Level Permissive (LIS-3-184, 185)
Instrument, Channel Reactor Low bhter Level (LISH-52 and LIS-3-62A)
> 470" above vessel zero.
A
> 470" above vessel zero.
A
> 378" above vessel zero.
A
> 378" above vessel zero.
A
> 544" above vessel zero.
A
> 312 5/16" above vessel zero.
A T2/3 core height) l.
Below trip setting initiated Itpcl.
1.
Hultiplier relays initiate RCIC.
l.
Below trip setting initiates CSS.
Hultiplier relays initiate LPCI.
2.
Hultiplier relay From CSS initiates accident signal (15).
1.
Below trip settings, in conjunction with drywell high pressure, low water level permissive, 120 sec.
delay timer and CSS or RllR puny running, initiates ADS.
1.
Below trip setting permissive For initiating signals on ADS.
l.
Below trip setting prevents inadvertent operation oF containment spray during accident condition.
< The autoniatic initiation capability of this instrument channel is not required to be OPERABLE awhile the Reactor Vessel water level nenitoring nndification is being perFormed.
Hanual initiation capability of the associated system wi 11 be available during that time the automatic initiation logic is out-of-service.
BFN-Vnit 2
Hinimum Wo.
Operable Per
~Tri Ss i
2(16)
Function Instrument Channel-Drywell High Pressure (PIS-64-58 E-H)
Instrument Channel-Drywell High Pressure (PIS-64-58 A-D)
Instrunient Channel-Reactor Low Mater Level (LS-3-56A-0)
Instrument Channel Reactor High Pressure (PIS-3-204A-D)
Instrument Channel-Drywell High Pressure (PIS-64-58A-D)
Instrument Channel-Drywell High Pressure (PIS-64-5IAW)
TABLE 3.2.B (Continued)
Tri Level Settin 1< p<2.5 psig
< 2.5 psig
> 470" above vessel zero
< 1120 psig
< 2.5 psig
< 2.5 psig Action Remarks l.
Below trip setting. prevents inadvertent operation oF containment spray during accident conditions.
l.
Above trip setting in con-junction with low reactor pressure initiates CSS.
Hultiplier relays initiate HPCI.
2.
Hultiplier relay from CSS initiates accident signal.
( 15) l.
Below trip setting trips recirculation pumps.
l.
Above trip setting trips recirculation pumps.
l.
Above trip setting in conjunction with low reactor pressure initiates LPCI.
l.
Above trip setting, in conjunction with low reactor water level, drywcll high
BFII-Ilnit 2
H IllilMll Ho Operable Per T~ri S s 1)
Function HPCI Trip System bus power nionitor RCIC Trip System bus power nionitor TABLE 3.2.B (Continued)
Tri Level Settin H/A N/A Action Remarks 1.
Honitors availability of
~
power to logic systems.
1.
Honitors availability of power to logic systems.
1(2)
I(2) 2(2) 4(4) 3(2) 3(2)
Instrument Channel Condensate Header Low Level (LS-73-55A 4 B)
Instrument Channel-Suppression Chamber High Level Instrument Channel Reactor High Mater Level (LIS-3-208A and LIS-3-200C)
Instrument Channel-RCIC Turbine Steam Line High Flow (PDIS-71-1A and B)
Instrument Channel-RCIC Steam Line Space High Temperature Instrument Channel-RCIC Steam Supply Pressure Low (PS 71-'IA-D)
Instrument Channel-RCIC Turbine Exhaust Diaphragm Pressure - High (PS 71-11A-D)
> Elev. 551' 7" above instrument zero A
< 503" above vessel zero
< 450" H20 (7)
<2000F.
>50 psig
<20 psig l.
Belo~ trip setting will open HPCI suction valves to the suppression chaniber.
l.
Above trip setting will open HPCI suction valves to tlie suppression chamber.
l.
Above trip setting trips RCIC turbine.
l.
Above trip setting isolates RCIC system and trips RCIC turbine.
1 ~
Above trip setting isolates RCIC system and trips RCIC turbine.
l.
Below trip setting isolates RCIC system and trips RCIC turbine.
l.
Above trip setting isolates RCIC system and trips RCIC turbine.
BFH-Unit 2
Hininvan Mo.
Operable Per T~ri Ss i
2(2)
Function Instrument Channel Reactor High Mater Level (LIS-3-20BB and LIS-3-2000)
Instrument Channel-HPCI Turbine Steam Line High Flow (PDIS-73-1A and 1B)
TABLE 3.2.8 (Continued)
Tri Level Settin
<583" above vessel zero.
<90 psi (7)
Action Renarks l.
Above trip setting trips HPCI turbine.
l.
Above trip setting isolates HPCI system and trips HPCI turbine.
3(2)
Instrument Channel-
>100 psig HPCI Steam Supply Pressure - Low (PS 73-lA-D) 1.
Below trip setting isolates HPCI system and trips HPCI turbine.
3(2)
Instrument Channel-HPCI Turbine Exhaust Diaphrayn (PS 73-20A-D)
<20 psig l.
Above trip setting isolates HPCI system and trips HPCI turbine.
4(4) 1 (16) 1 lns truant Channel -
<200'F.
HPCI Steam Line Space High Tenyerature Core Spray System Logic RCIC System (Initiating)
Logic RCIC System (Isolation)
Logic ADS Logic RHR (LPCI) System (Initiation)
H/A H/A W/A W/A N/A 1 ~
Above trip setting isolates HPCI system and trips HPCI turbine.
l.
Includes testing auto initiation inhibit to Core Spray Systems in other units.
l.
Includes Group 7 valves.
Refer to Table 3.7.A for list of valves.
1.
Includes Group 5 valves.
Refer to Table 3.7.A for list of valves.
BFM-Unit 2
TABLE 4.2.8 SURVEILUQICE REQUIREMEtlTS FOR INSTRUMEtJTATION THAT ItllTIATE OR COHTROL TllE CSCS Function Functional Test Calibration Instrument Check Instrument Channel Reactor Low Mater Level (LIS-3-58A-D)
Instrunent Channel Reactor Lou Mater Level (I ISA-104 8 105)
Instrument Channel Reactor Lo~ Mater Level (LIS-3-52 4 62A)
Instrument Channel Reactor Lou Mater Level (LS-3-56A-D)
Instrunmnt Channel Reactor lligh Pressure (P IS-3-204A-D)
Instrument Channel Orwell Iligh Pressure (PI5-64-50E-ll)
Instrunv~nt Channel Orwell Iligh Pressure (P IS-64-50A-D)
Instrument Channel Orywell lligh Pressure (P IS-64-57A-D)
Instrument Channel Reactor Lou Pressure (P 15-3-74 SB, PS-3-74lQLB)
(PIS-60-95, PS-60-95)
(PI5-60-96, PS-68-96)
(1) (27)
(1) (27)
(1) (27)
(1) (2I)
(1) (27)
(1) (27)
(1) (27)
(1) (2I)
(1) (2I)
Once/18 Honths (20)
Once/18 Honths (20)
Once/18 Honths (20)
Once/18 Honths (20)
Once/18 Honths (20)
Once/10 Months (20)
Once/10 Months (20)
Once/18 Months (20)
Once/6 Honths (20)
Once/day Once/day Once/day none none none none none none BFtl-Unit 2
TABLE 4.2.8 (Continued)
SURYEILIJQICE REI)UIREHEHTS FOR IHSTRUHCHTATION THAT INITIATE OR CONTROL THE CSCS Function Functional Test Calibration Instrument Check Instrument Channel-RIIR Pump Discharge Pressure Instrument Channel Core Spray PIuIy Discharge Pressure Core Spray Sparger to RPV d/p Trip System Bus Power Honitor InstrunIent Channel-Condensate Header Lov Level (LS-13-56A, B)
Instrument Channel Suppression Chan1ber High Level Instrument Channel Reactor High Mater Level Instrument Channel-RCIC Turbine Steam Line High Floe Instrument CIIannel-RCIC Steam Line Space High TenT1erature Instrenent Channel-RCIC Steam Supply Low Pressure Instrunv.nt Channel-RCIC Turbine Exhaust Diaphragm High Pressure once/operating Cycle once/31 days once/31 days once/3 months once/3 months once/3 months H/A once/3 months once/3 months once/3 ninths once/3 months once/3 months once/18 months once/18 months none none once/day none none none once/day none none none
, none BFH-Unit 2
TABLE 4.2.B (Continued)
SURVEILLANCE REIlUIREHEIITS FOR ItJSTRUYiEHTATION TIIAT INITIATE OR CONTROL TIIE CSCS Function Instrument Channel-IIPCI Turbine Steam Line lligh Flow Instrument Channel-IIPCI Steam Line Space Itigh Ten@erat,ure Instrument Channel-IIPCI Steam Supply Low Pressure Instrument Channel-IIPCI Turbine Exhaust Diaphragm Itigh Pressure Core Spray System Logic RCIC System (Initiating) Logic RCIC System (Isolation) Logic IIPCI System (Initiating) Logic IIPCI System (Isolation) Logic AOS Logic LPCI (Initiating) Logic LPCI (Containnent Spray) Logic Core Spray System Auto Initiation Inhibit (Core Spray Auto Initiation)
LPCI Auto Initiation Inhibit (LPCI Auto Initiation)
Functional Test once/31 days once/31 days once/18 months once/18 months once/18 months once/18 months once/18 months once/18 months once/18 months once/18 months once/18 months (7) once/18 months (7)
Calibration Once/3 months Once/3 nenths once/18 months once/18 months (6)
H/A (6)
(6)
(6)
(6)
(6)
(6)
N/A Instrument Check none none none none tJ/A N/A H/A N/A H/A tt/A N/A H/A BFH-Unit 2
TABLE 4.2.F HIHIHUR TEST AHD CALIBRATIOH FREQUENCY FOR SURVEILLANCE INSTRUHEHTATIOH Instrument Channel
- 1) Reactor Mater Level
( LI-3-SSNR)
- 2) Reactor Pressure (PI-3-74@as)
- 3) D~eli Pressure (Pl-64-678)"and XR-64-50
- 4) Dryuell Temperature (TI-64-52AB) and XR-64-50
- 5) Suppression Chamber Air Tenyerature (XR-64-52)
- 8) Control Rod Position
- 9) Neutron Ronitoring
- 10) Orwell Pressure (PS-64-678)
- 11) Dryuell Pressure (PIS-64-58A)
- 12) Orwell Tenyerature (TS-64-52A)
- 13) Tier (IS-64-67A) 14)
CAD Tank Level
- 15) Containment Atnesphere Honitors Calibration Fre uenc Once/6 nenths Once/6 months Once/6 months Once/6 months Once/6 months N/A (2)
Once/6 months Once/6 months Once/6 months Once/6 months Once/6 nenths Once/6 months Instrument Check Each Shift Each Shift Each Shift Each Shift Each Shift Each Shift Each Shift H/A H/A N/A H/A Once/day Once/day BFH-Unit 2
l
Hnclosure 2
Description and Justification Browns Perry Nuclear Plant Unit 2 Reason Eox; Chan e
This technical pecification change corrects Browns Fexry unit 2 technical specification tables 4.1.B, 4.2.B, and 4.2.F for calibration frequencies and includes administrative changes to instrument numbers.
Instrument loops that contain transmitters manuEactured by Tobar Inc. will only permit a 6-month calibration frequency.
Instrument numbers in the tables are added or corx.ected to provide a concise set of technical specifications.
Instrument checks for (4) instrument channels in table 4.2.B that have no remote ox; local indication are deleted.
Descri tion and Justification Calibration Frequency Changes:
In general surveillance fx.equencies are based on industry accepted practice and engineering judgment considexing the conditions required to perform a given test, the ease of performing the test and the likelihood oE a change in the
.ystem/component tatus.
Instrumentation calibration fx.equencies consist oE an optimum selection of time vex.sus drift.
Setpoint scaling calculations are performed to provide assurance there is adequate margin to account Eor all inaccuracies in tho instrument loop between the requix;ed trip setpoint and the limiting safety "ystem settings.
These changes to the calibration frequencies are required to support the results of the setpoint and scaling calculations for various instrument loops.
The specific changes are illustrated and justified below:
Table 4.1.B Instrument Hxistin Pre uenc Pro osed Chan e
liigh Reactor Pressux;e (pg 3.1/4.1-11)
Once/18 months Once/6 months 0358y
Table 4.2.8
'I 1n's trument Hxistin Fre uenc Pro osed Chan e
Reactor low pressure (pg 3.2/4.2-44)
Once/18 months Once/6 months These instrument loops contain tran. mittevs manufactured by Tobar inc.
The tvansmittevs only permit a 6-month calibvation frequency.
Reactor Pressure (pg, 3.2/4.2-54)
Table 4.2.F Once/12 months Once/6 months Thi: loop contains tvansmitters manufactured by Tobar Inc.
These transmitters only permit a 6-month calibvation frequency.
'Note:
DFH technical specification definition "Surveillance" permits a maximum allowable extension not to exceed 25 percent of the surveillance interval.
This allowable extension of the surveillance interval was considered in defining the calibration frequencies.
Additions/change to in"trumentation numbers Table 3.2.8 Instrument Rxistin Number Pro osed Chan e
Reactor low water level (pg 3.2/4.2-14i)
(LIS-3-58A-D)
(LS-3-58A-D)
Note:
This change pr.oposed for 2 places on pg 3.2/4.2-14.
Reactor low water level (pg 3.2/4.2-14)
(I IS-3-62)
(LIS-3-62A)
Drywall high pressuz.e (pg 3.2/4.2-15)
(PS-64-58A-D)
(PIS-64-58A-D)
Reactor:
l.ow water level (pg 3.2/4.2-15)
(LIS-3-56A-D)
(LS-3-56A-D)
Reactor high water level (pg 3.2/4.2-18)
(LIS-3-208A and LIS-3-208C)
RCIC turbine steam line high flow
( pg 3. 2/4. 2-18)
(PDXS-71-lA and 18)
Reactor high water level (pg 3.2/4.2-19)
(LIS-3-2088 and LIS-3-208D) 14PCI turbine steam line high flow (pg 3.2/4.2-19)
(PDIS-73-1A and 18)
Table 4. 2.8 Reactor low water level (pg 3.2/4.2-44)
(LIS-3-62)
(LIS-3-62A)
Reactor low water level (pg 3.2/4,2-44)
(LIS-3-56A.-D)
(LS-3-56A-D)
These changes are administr.'ativo in natur:e and do not change the function,
- setting, or calibration interval of any of the listed instr:uments.
They are included in the technical specifications for completeness.
Deletion of instrument ch k for llPCI/RCIC instrument chan ls:
Table 4.2.9 Instrument Fxistin T/S Pro osed chan e
RCIC steam supply low pressure (pg 3.2/4.2-46)
Once/day none RCIC turbine exhaust diaphragm high pressure (pg 3.2/4.'2-46)
Once/day none RPCI turbine steam line high flow (pg 3.2/4.2-47)
Once/day none lkPCI turbine exhaust, diaphragm high pressure (pg 3.2/4.2-47)
Once/day none These instrument channels consist of pres ure switches (PS71-1A-D, PS71-11A-D, PS73-1A-D, PS73-20A-D) that have no indication.
An instrument check is a qualitative determination of acceptable behavior by observation of the instrument during operation.
These pressure switches have no indication function.
The functional test of the instrumentation which verifies operability including the alarm and trip functions is performed once/31 days.
Determination of Ho Brown" Enclosure 3
Significant )lazar.ds Consideration Ferry Nuclear Plant Vnit 2 Descei tion This technical specification change revises the calibration feequencies and coeeects instr~ment numbers of various insteuments in Bx;owns Fevx.y unit 2 technical specification tables 4.1.B, 4.2.B, and 4.2.F.
The instrument checks fov high peessux.e coolant injection (IlPCI) and x.eactoe cox.e isolation cooling (RCIC) system instrument channels are deleted fvom table 4.2.B.
Basis for Peo osed Ho Si nificant llazards Consideration Determination HRC has provided standaeds for determining whethev a significant hazaeds consideration exists as stated in 10 CFR 50.92(c).
A proposed amendment to an operating license involves no significant hazards considevations if operation of Uxe facility in accordance with the proposed amendment would not (1) involve a significant inceease in the peobability or consequences of an accident peeviously evaluated, (2) create the possibility of a new or diffeeent kind of accident from an accident previously evaluated, or (3) involve a..ignificant eeduction in a margin of safety.
1.
The proposed amendment does not involve a significant inceease in the peobability ox. consequences of an accident previously evaluated.
Tho primary factor in setting the calibration intevvals is the drift of the teansmittees and teip units.
TVA has performed setpoint scaling calculations that support the proposed change using manuEacturees reconxmended intevvals and indu..tey standard practices.
This change does not involve a design change ov physical change to the plant.
The x;evised surveillance fvequencies will not affect the consequences of an accident peeviously analyzed.
The reliability of the llPCI/RCIC diaphragm high pressuee, steam line flow and steam supply pressure insteuments ax.e adequately assueed by the perfonnance of Eunctional tests every 31 days.
Clarifications ov coevections of typogvaphical ereovs ave administrative changes which improve technical specification x;eliability and thevefoee can have no deteimontal impact.
2.
The peoposed change does not create the possibility of a new or diffevent kind of accident Eeom any accident previously evaluated because changing the technical.speciEications to x.'eflect diEfeeent calibration fvequencies does not affect oe change design operating limits or pvotective setpoints.
No new ox different mode" of operation are allowed by those changes.
3.
The proposed change.does not involve a significant reduction in a margin of afety because in no instance will these changes affect the technical specification safety limits.
These changes have no affect on the instrument setpoints.
All parameters will continue to be monitored as currently required.
Since the application for amendment involves a proposed change that is encompa.,
ed by the criteria for: which no significant hazards consideration
- exist, TVA has made a proposed determination that the application involves no significant hazards consideration.
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