ML18038B194
| ML18038B194 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/15/1995 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18038B195 | List: |
| References | |
| DPR-33-A-219, DPR-52-A-235, DPR-68-A-193 NUDOCS 9503170318 | |
| Download: ML18038B194 (86) | |
Text
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UNITED STATES NUCLEAR REGULATORY COIVIMISSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROMNS FERRY NUCLEAR PLANT
'UNIT 1
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 219 License No.
DPR-33 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the
~
licensee) dated October 12,
- 1993, 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; 8'.
The facility will operate in conformity with the application, the provisions of the Act, and'he 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 and 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.
95031703l8 950315 PDR ADOCK 05000259 P
PDR~
0 0
4
~ ~
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-33. is hereby amended to read as follows:
3.
(2)
Technical S ecifications The Technicyl Specifications contained in Appendices A and B,
as revised through Amendment No. 219, are hereby incorporated in the license.
The l.icensee shall operate the facili'ty in accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
()
Frederick J.
Hebdon, Director Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
Ihrch 15, 1995
Ik 0
ATTACHMENT TO LICENSE AMENDMENT NO.
219 FACIL'ITY OPERATING LICENSE NO. 'DPR-33 DOCKET NO. 50-259 Revise the Appendix A Technical Specifications by removing the pages
,identified below and inserting the enclosed pages.
The revised pages are identifi'ed by the captioned.
amendment number and contain marginal lines indicating the area of change.
Overleaf pages
.are provided to maintain document completeness.
REMOVE 3.2/4.2-9 3.2/4.2-10'.2/4.2-11 3'.2/4.2-11a 3.2/4.2-18 3.2/4.2-19 3.2/4.2-20 3.2/4.2-21 INSERT 3'.2/4.2-9
'3.2/4.2-10 3.2/4.2-11 3.2/4.2-11a*
3.2/4.'2-18*
3.2/4.2-19 3.2/4.2-20 3.2/4.2-21*
TABLE 3.2.A (Continued)
PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION Hinimum No.
Instrument n
Channels Operable r Tri 1 ll Fn in Tri Level tin Ac ion 1
R mark 1(15)
Instrument Channel Reactor Building Ventilation High Radiation
. Refueling Zone
< 100 mr/hr or downscale F
1-.
1 upscale channel or 2 downscale channels will a.
Initiate SGTS b.
Isolate refueling floor c.
Close atmospher'e control system.
2(7) (B)
Instrument Channel SGTS Flow Train A R.
H. Heaters
>2000 cfm and
< 4000 cfm H and (A or F)
Below 2000 cfm airflow R.H.
heaters shall be shut off.
2(7) (B)
Instrument Channel SGTS Flow Train 8 R. H. Heaters
>2000 cfm and
< 4000 cfm H and (A or F)
Below 2000 cfm airflow R.H.
heaters shall be shut off.
2(7) (B)
Instrument Channel SGTS Flow Train C
R. H. Heaters
>2000 cfm and
< 4000 cfm H and (A or F)
Below 2000 cfm airflow R.H.
heaters shall be shut off.
O 2(10)
Reactor Building Isolation 0
< t
< 2 secs.
Timer (refueling floor)
Reactor Building Isolation 0
< t
< 2 secs.
Timer (reactor zone)
Group 1 (Initiating) Logic N/A H or F G or A or H 1.
Below trip setting prevents spurious trips and system perturbations from initiating isolation.
l.
Below trip setting prevents spurious trips and system perturbations from initiating isolation.
1.
Group 1:
A Group 1
isolation is actuated by any of the following conditions".
a.
Reactor Vessel Low Low Water Level b.
Hain Steamline High Radiation c.
Hain Steamline High Flow d.
Hain Steamline Space High Temperature e.
Hain Steamline Low Pressure
0
~I t4, ~
I h
t T
TABLE 3.2.A (Continued)
PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION O
Hinimum No.
Instrument Channels Operable r Tri 1 ll Fn in Group 1 (Actuation) Logic Group 2 (Initiating) Logic Group 2
(RHR Isolation-Actuation) Logic Group 8 (TIP-Actuation)
Logic Group 2 (Drywell Sump Drains-Actuation)
Logic Group 2 (Reactor Building 4 Refueling Floor, and Drywell Vent and Purge-Actuation) Logic Group 3 (Initiating) Logic Tri v
1 in N/A N/A N/A N/A N/A N/A N/A A
i n 1
A or (8 and E)
F and G
R mark 1.
Group 1:
A Group 1
isolation is actuated by any of the fol 1 owing condi tions:
a.
Reactor Vessel Low Low Water Level b.
Hain Steamline High Radiation c.
Hain Steamline High Flow d.
Hain Steamline Space High Temperature e.
Hain Steamline Low Pressure 1.
Group 2:
A Group 2 isolation is actuated by any of the following condi tions:
a.
Reactor Vessel Low Water Level b.
High Drywell Pressure 1.
Part of Group 6 Logic 1.
Group 3:
A Group 3 isolation is actuated by any of the following conditions:
a.
Reactor Vessel Low Water Level b.
Reactor Water Cleanup System High Temperature c.
Reactor Water Cleanup System High Drain Temperature
~ ~
TABLE 3.2.A (Continued)
PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION lA I
Hinimum No.
Instrument Channels Operable er Tri 1
11 Func i n Group 3 (Actuation) Logic Group 6 Logic Group 8 ( Initia ting) Logi c Reactor Bui 1 ding Isol ati on (refueling floor) Logic Tri L v 1
tin N/A N/A N/A N/A A
ion 1
F and G
HorF Rem rk 1.
Group 6:
A Group 6 i sol ation i s actuated by any of the following conditions:
a.
Reactor Vessel Low Water Level b.
High Drywell Pressure c.
Reactor Building Ventilation High Radiation 1.
Group 8:
A Group 8 isolation is automatically actuated by only the following conditions:
a.
High Drywell Pressure b.
Reactor Vessel Low Water Level 2.
Same as Group 2 initiating logic.
Reactor Building Isolation (reactor zone)
Logic l(7) (8)
SGTS Train A Logic l(7) (8)
SGTS Train 8 Logic N/A N/A N/A l(7) (8)
SGTS Train C Logic N/A t4 8
Refer to Table 3.2.8 for RCIC and HPCI functions including Groups 4, H
O HorG or A L or (A and F)
L or (A and F)
L or (A and F) 5, and 7 valves.
II I
~ ~
THIS PAGE IHTEHTIOHALLYLEFT BLAHK BFH Uni't 1 AMENOMENTNO. I89
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C; CS Hinimum No.
Operable Per
~Tri
'~i~l 1(2) 1(2) 2(2)
Fn in HPCI Trip System bus power monitor RCIC Trip System bus power monitor Instrument Channel Condensate Header Low Level (LS-73-56A 8 B)
Instrument Channel Suppression Chamber High Level Instrument Channel Reactor High Mater Level Instrument Channel-RCIC Turbine Steam Line High Flo'w TABLE 3.2.B (Continued)
.Tri Lvl in
~Ain NIA N/A
> Elev. 551' 7" above instrument zero A
< 583" above vessel zero A
< 450" H20 (7) 1.
Honi tors availability of power to logic systems'.
Honitors availability of power to logic systems.
1.
Below trip setting will open HPCI suction valves to the suppression chamber.
1.
Above trip setting will open HPCI suction valves to the suppression chamber.
l.
Above trip setting trips RCIC turbine.
l.
Above trip setting isolates RCIC system and trips RCIC turbine.
I 00 4(4) 3(2) 3(2)
Inst'rument Channel-RCIC Steam Line Space High Temperature Instrument Channel-RCIC Steam Supply Pressure Low (PS 71-1A-D)
Instrument Channel-RCIC Turbine Exhaust Diaphragm Pressure-High (PS 71-11A-D)
<2000 F.
>50 psig
<20 psig l.
Above trip setting isolates RCIC system and trips RCIC turbine.
l.
Below trip setting isolates RCIC system and trips RCIC turbine.
1.
Above trip setting isolates RCIC system and trips RCIC turbine.
II
Hinimum No.
Operable Per
~Tri~~1 2(2) 4(4) 3(2) 3(2) 1 (16)
Func i n Instrument Channel-Reactor High Mater Level Instrument Channel-HPCI Turbine Steam Line High Flow Instrument Channel-HPCI Steam Line Space High Temperature Instrument Channel-HPCI Steam Supply Pressure L'ow (PS 73-1A-D)
Instrument Channel-HPCI Turbine Exhaust DiaphragIn (PS 73-20A-D)
Core Spray System Logic RCIC Sys tern (Initiating)
Logic RCIC System (Isolation)
Logic ADS Logic TABLE 3.2.B (Continued)
Tri Lev 1
in
<583" above vessel zero.
<90 psi (7)
<200'F.
>100 psig
<20 psig N/A N/A N/A N/A A
i n
A R
m rk l.
Above trip setting trips HPCI turbine.
l.
Above trip setting isolates HPCI system and trips HPCI turbine.
1.
Above trip setting isolates HPCI system and trips HPCI turbine.
l.
Below trip setting isolates HPCI system and trips HPCI turbine.
l.
Above trip setting isolates HPCI system and trips HPCI turbine.
1.
Includes testing auto initiation inhibit to Core Spray Systems in other units.
1.
Includes Group 7 valves.
2.
Group 7:
A Group 7 isolation is automatically actuated by I
only the following condition:
1.
The respective turbine steam supply valve not fully closed.
l.
Includes Group 5 valves.
2.
Group 5:
A Group 5 isolation is actuated by any of the following conditions:
a.
RCIC Steamline Space High Temperature b.
RCIC Steamline High Flow c.
RCIC Steamline Low Pressure d.
RCIC Turbine Exhaust Diaphragm High Pressure
I g ll P,
TABLE 3.2.8 (Continued)
Hinimum No.
Operable Per
~Tri ~l I
1 Functi n
RHR (LPCI) Sy'tem (Initiati on)
RHR (LPCI) System (Coritainment Cooling Spray) Logic HPCI System (Initiating)
Logic Tri
.Level ettin N/A N/A N/A
~Ac ion Rem k
l.
Includes Group 7 valves.
2.
Group 7:
A Group 7 isolation is automatically actuated by only the following condition:
1.
The respective turbine steam supply valve not fully closed.
\\A I
O HPCI System (Isolation)
Logic Core Sp'ray System auto initiati on inhibit (Core Spray auto initiation).
LPCI System auto initiation inhibit (LPCI auto initiation)
N/A N/A N/A l.
Includes Group 4 valves.
2.
Group 4:
A Group 4 isolation is actuated by any of the following conditions:
a; HPCI Steamline Space High Temperature b.
HPCI Steamline High Flow c.
HPCI Steamline Low Pressure d.
HPCI Turbine Exhaust Diaphragm High Pressure l.
Inhibit due to the core spray system of another unit.
2.
The inhibit is considered the contact in the auto initiating logic only; i.e.,
the permissive function of the inhibit.
l.
Inhibit due to the LPCI System of another unit.
2.
The inhibit is considered the contact in the auto initiating logic only, i.e.,
the permissive function of the inhibit.
4l 0
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)
J 4
'6 r
'd
TABLE 3.2.8 (Continued)
Hinimum No.
Operable Per
~Tri Fn in r
Lvl
~Ai n 1(3) 1(3) 1(3) 1(3) 1(10) 1(10) 2(10) 2(10)
Core Spray Loop A Discharge Pressure (PI-75-20)
Core Spray Loop B Discharge Pressure (PI-75-48)
RHR Loop A Discharge Pressure (PI-74-51)
RHR Loop 8 Discharge Pressure (PI-74-65)
Instrument Channel-RHR Start Instrument Channel Thermostat (RHR Area Cooler Fan)
Instrument Channel Core Spray A or C Start Instrument Channel Core Spray 8 or 0 0 - 500 psig Indicator (9)
D 0 - 500 psig Indicator (9)
D 0 - 450 psig Indicator (9) 0 0 450 psig Indicator (9) 0 N/A
<1000 F N/A N/A 1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
1.
Starts RHR area cooler fan when respective RHR motor starts.
l.
Above trip setting starts RHR area cooler fa'ns.
1.
Starts Core Spray area cooler fan when Core Spray motor starts.
1.
Starts Core Spray area cooler fan when Core Spray motor starts.
4k
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1'ECC c<
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++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001.
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT UNIT 2 AMENDMENT TO FACILITY OPERATING LICENS Amendment No. 235 License No. DPR-52 The Nuclear Regulatory Commission (the Commissi'on) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated October 12,
- 1993, 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; B.
The facility wi,l.l: 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 and 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.
0 II A
k'~
MS\\l'
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-52, is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 235, are hereby 'incorporated in the license.
The l.icensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 1~
Frederick J.
He don, Director Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to, the Technical Specifications Date of Issuance:
?au..ch 15, 1995
0 Se Qa y
d
ATTACHMENT TO LICENSE AMENDMENT NO.
235 FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications
.by removing, the pages identified bel'ow. and inserti'ng, the enclosed, pages.
The, revised pages are identi,fied by the captioned amendment number and'ontain marginal l,ines ind.icating the area of change.
Overleaf pages are provided to maintain document completeness.
REMOVE 3.2/4.2-9 3.2/4.2-10'.2/4.2-11 3.2/4.2-.11a 3'.2/4.2-18 3.2/4.2-19 3.2/4.'2-20 3.2/4.2-21 INSERT 3' 2/4.2-9 3.2/4.2-10 3.2/4.2-11 3.2/4.2-11a*
3.2/4.2=18*
3.2/4.2-19.
3.2/4.2-20 3.2/4.2-21*
4l 0
Wl
TABLE 3.2.A (Continued)
PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION C tu Y
Hinimum No.
Instrument Channels Operable r Tri 1 ll 1(14)
Fn in Instrument Channel Reactor Building Ventilation High Radiation Refueling Zone Tri L v 1
in A
i n
1
< 100 mr/hr or downscale F
R mark 1.
1 upscale channel or 2 downscale channels will a.
Initiate SGTS b.
Isolate refuelirig floor c.
Close atmosphere control system.
2(7) (8)
Instrument Channel SGTS Flow Train A R. H. Heaters
>2000 cfm and
< 4000 cfm H and (A or F)
Below 2000 cfm airflow R.H.
heaters shall be shut off.
2(7) (8)
Instrument Channel SGTS Flow Train 8 R. H. Heaters
>2000 cfm and
< 4000 cfm H and (A or F)
Below 2000 cfm airflow R.H.
heaters shall be shut off.
2(7) (8)
Instrument Channel SGTS Flow Train C
R. H. Heaters
>2000 cfm and
< 4000 cfm H and (A or F)
Below 2000 cfm airflow R.H.
heaters shall be shut off.
2(10)
Reactor Building Isolation 0
< t
< 2 secs.
Timer (refueling floor)
Reactor Building Isolation 0
< t
< 2 secs.
Timer (reactor zone)
Group 1 (Initiating) Logic N/A H or F GorA or H 1.
Below trip setting prevents spurious trips and syste~
perturbations from initiating isolation.
1.
Below trip setting prevents spurious trips and system perturbations from initiating isolation.
1.
Group 1:
A Group 1 isolation is actuated by any of the following I conditions:
a.
Reactor Vessel Low Low Hater Level b.
Hain Steamline High Radiation c.
Hain Steamline High Flow d.
Hain Steamline Space High Temperature e.
Hain Steamline Low Pressure
0 0
I.
N
\\
TABLE 3.2.A (Continued)
PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION Hinimum No.
Instrument Channels Operable r Tri 1 ll Fun ion Group 1 (Actuation) Logic Group 2 (Initiating) Logi c Group 2 (RHR Isolation-Actuation) Logic Group 8 (TIP-Actuation)
Logic Group 2 (Drywell Sump Drains-Actuation)
Logic Group 2 (Reactor Building 6 Refueling Floor, and Drywell Vent and Purge-Actuation) Logic
'roup 3 (Initiating) Logic Tri L v 1
tin N/A N/A N/A N/A N/A N/A N/A A
i n 1
A or (B and E)
F and G
Rem rk 1.
Group 1:
A Group 1 isolation is actuated by any of the following conditions:
a.
Reactor Vessel Low Low Water Level b.
Hain Steamline High Radiation c.
Hain Steamline High Flow d.
Hain Steamline Space High Temperature e.
Hain Steamline Low Pressure 1.
Group 2:
A Group 2 i sol ation is actuated by any of the following conditions:
a.
Reactor Vessel Low Water Level b.
High Drywell Pressure 1.
Part of Group 6 Logic 1.
Group 3:
A Group 3 isolation is actuated by any of the following conditions:
a.
Reactor Vessel Low Water Level b.
Reactor Mater Cleanup (RWCU)
System High Temperature in the main steam valve vault c.
RWCU System High Temperature in the RWCU pump room 2A d.
RMCU System High Temperature in the RWCU pump room 28 e.
RMCU System High Temperature in the RWCU heat exchanger room f.
RMCU System High Temperature in the space near the pipe trench containing RMCU piping
41
TABLE 3.2.A (Continued)
PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION a
as Hinimum No.
Instrument rr Channels Operable r Tri 1 ll IA I
Fun i n Group 3 (Actuation) Logic Group 6 Logic Group 8 (Initiating) Logi c Reactor Building Isolation (refueling floor) l.ogic Reactor Building Isolation (reactor zone)
Logic Tri L v 1
in N/A N/A N/A N/A N/A A
i n
1 F and G
HorF Hor G
or A R mark 1.
Group 6:
A Group 6 isolation is actuated by any of the following conditions:
a.
Reactor Vessel Low Hater Level b.
High Drywell Pressure c.
Reactor Building Ventilation High Radiation 1.
Group 8:
A Group 8 isolation is automatically actuated by only the following conditions:
a.
High Drywell P'ressure b.
Reactor Vessel Low Hater Level 2.
Same as Group 2 initiating logic.
l(7) (8)
SGTS Train A Logic N/A L or (A and F) l(7) (8)
SGTS Train 8 Logic N/A L or (A and F)
L or (A and F)
N/A Logic l(7) (8)
SGTS Train C
Refer to Table 3.2.8 for RCIC and 8
HPCI functions including Groups 4, 5, and 7 valves.
0 l
rE'
Hinimum No.
Instrument Chan'nels Operable r T TABLE 3.2.A (Continued)
PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION Lvl Instrument Channel Reactor Mater Cleanup System Hain Stean Valve Vault (TIS-069<34A-D)
Instrument Channel Reactor Mater Cleanup System Pipe Trench (T IS-069-835A-D)
Instrument Channel Reactor Mater Cleanup System Pump Room 2A (T IS-069%36A-0)
Instrument Channel Reactor Water Cleanup System Pump Room 28 (T IS-069-837A-D)
Instrument Channel Reactor Water Cleanup System Heat Exchanger Room (TIS-069-838A-D)
Instrument Channel Reactor Water Cleanup System Heat Exchanger Room (TIS-069-839A-D)
< 201.0'F
< 135.00F
< 152.00F
< 152.0'F
< 143.00F
< 170.00F Above Trip Setting initiates Isolation of
.Reactor Water Cleanup Lines to and from the Reactor Above Trip Setting initiates Isolation of Reactor Mater Cleanup Lines to and from the Reactor Above Trip Setting initiates Isolation of Reactor Mater Cleanup Lines to and from the Reactor Above Trip Setting initiates Isolation of Reactor Water Cleanup Lines to and from the Reactor Above Trip Setting initiates Isolation of Reactor Mater Cleanup Lines to and from the Reactor Above Trip Setting initiates Isolation of Reactor Mater Cleanup Lines to and from the Reactor
C tJS P g Hinimum No.
Operable Per YRQL 1(2)
Fn in HPCI Trip System bus power moni tor RCIC Trip System bus power monitor Instrument Channel-Condensate Header Lo'w Level (LS-73-56A & 8)
TABLE 3.2.8 (Continued)
Tri L v 1
n
~An N/A N/A
> Elev.551'.
Honi tors availabili ty of power to logic systems.
1.
Honi.tors availability of power to logic systems.
1.
Below trip setting will open HPCI suction valves to the suppression chamber.
1(2)
Instrument Channel
< 7" above instrument zero A
Suppression Chamber High Level 1.
Above trip setting will open HPCI suction valves to the suppression chamber.
LA c
I CO 2(2) 3(2) 3(2)
Instrument Channel Reactor High Water Level (LIS-3-208A and LIS-3-208C)
Instrument Channel-RCIC Turbine Steam Line High Flow (PDIS-71-lA and 18)
Instrument Channel-RCIC Steam Supply Pressure Low (PS 71-1A-D)
Instrument Channel-RCIC Turbine Exhaust Diaphragm Pressure High (PS 71-11A-D)
< 583" above vessel zero
< 450" H20 (7)
>50 psig
<20 psig l.
Above trip setting trips RCIC turbine.
l.
Above trip setting isolates RCIC system and trips RCIC turbine.
1.
Below trip setting isolates RCIC system and trips RCIC turbine.
l.
Above trip setting isolates RCIC system and trips RCIC turbine.
Cl
TABLE 3.2.8 (Continued)
Hinimum No.
Operable Per
~Tri >~~1 2(2)
Fun i n Instrument Channel Reactor High Mater Level (LIS-3-2088 and LIS-3-208D)
Instrument Channel-HPCI Turbine Steam Line High Flow (PDIS-73-1A and 1B)
Tri L v 1
in
<583" above vessel zero.
<90 psi (7)
~Ai n Remark 1 ~
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 73-1A-D) 1.
Below trip setting isolates HPCI system and trips HPCI turbine.
3(2) 1 (16)
Instrument Channel-HPCI Turbine Exhaust Diaphragm (PS 73-20A-D)
Core Spray System Logic RCIC Sys tern (Initiating)
Logic RCIC System (Isolation)
Logic ADS Logic RHR (LPCI) System (Initiation)
<20 psig N/A N/A N/A N/A N/A l.
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 5 valves.
2.
Group 5:
A Group 5 isolation is actuated by any of the following conditions:
a.
RCIC Steamline Space High Temperature b.
RCIC Steamline High Flow c.
RCIC Steamline Low Pressure d.
RCIC Turbine Exhaust Diaphragm High Pressure
I
Hinimum No.
Operable Per
~Tri ~l F n n
RHR (LPCI) System (Contairiment Cooling Spray)
Lo'gic HPCI System (Initiating)
Logic TABLE 3.2.B (Continued)
Tri v
1 in N/A N/A AttAI h R
ark HPCI System (Isol ati on)
Logic Core Spray System auto initiation inhibit (Core Spray auto initiation).
LPCI System auto initiation inhibit (LPCI auto initiation)
N/A N/A N/A l.
Includes Group 4 valves.
2.
Group 4:
A Group 4 isolation is actuated by any of the following co'nditions:
a.
HPCI Steamlin'e Space High Temperature b.
HPCI Steamline High Flow c.
HPCI Steamline Low Pressure d.
HPCI Turbine Exhaust Diaphiagm High Pressure l.
Inhibit due to the core spray'ystem'of another unit.
2.
The inhibit is considered the contact in the auto initiating logic only',
i.e.,
the permissive function of 'the inhibit.
l.
Inhibit due to the LPCI System of another unit.
2.
The inhibit is considered the contact in the auto initiating logic only, i.e.,
the permissive function of the inhibit;
Ck 41 I
'4
TABLE 3.2.B (Continued)
Hinimum No.
Operable Per
~Tri ~l Fn in Tri v
1
'n
~An
.50 1(3) l(3) 1(3) 1(3) 1(10) 1(10) 2(10) 2(10)
Core Spray Loop A Discharge Pressure (PI-75-20)
Core Spray Loop B
Discharge Pressure (PI-75-48)
RHR Loop A Discharge Pressure (PI-74-51)
RHR Loop 8 Discharge Pressure (PI-74-65)
Instrument Channel-RHR Start Instrument Channel Thermostat (RHR Area Cooler Fan)
Instrument Channel-Core Spray A or C Start Instrument Channel Core Spray 8 or D 0 500 psig Indicator (9)
D 0 - 500 psig Indicator (9)
D 0 - 450 psig Indicator (9)
D 0 - 450 psig Indicator (9) 0 N/A
<1000 F N/A N/A 1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
1.
Starts RHR area cooler fan when respective RHR motor starts.
1 ~
Above trip setting starts RHR area cooler fans.
1.
Starts Core Spray area cooler fan when Core Spray m'otor starts 1.
Starts Core Spray area cooler fan when Core Spray motor starts
0
~
gA~ REGII (4
C~~o 0
D$
~O
++*++
UNITED STATES NUCLEAR REGULATORY COMM(SSION WASHINGTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROMNS FERRY NUCLEAR PLANT UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 License No.
DPR-68 The Nuclear Regulatory Commission (the Commission),
has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated October 12,
- 1993, 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; 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 and 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.
4P gl e
i'P,
)y
'c~
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-68 is hereby amended to read as follows:
3.'2)
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 193, are hereby incorporated in the license.
The licensee shall operate the facility,i'n accordance with the Technical Specifications.
This license amendment is effective as of its date of issuance and shall be implemented, within 30 days from the date, of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Freder ick J.
Hebd n, Director Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to. the Technical Specifications Date of Issuance:
March 15, 1995
0 g
ATTACHMENT TO LICENSE AMENDMENT NO.
193 FACILITY OPERATING LICENSE NO.
DPR-68 DOCKET NO. 50-296 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified. by the captioned amendment number and contain marginal lines indicating the area of change.
Overleaf* pages are provided to maintain document completeness.
REMOVE 3.2/4.2-7 3.2/4.2-8 3.2/4.2-9 3.2/4.2'-10 3.2/4.2-11 3.2/4.2-11a 3.2/4.2-13a 3.2/4.2-13b 3.2/4.2-18 3.2/4.2-19 3.2/4.2-20 3.2/4.2-21 3.2/4.2-41 3.2/4.2-42 3.2/4.2-66 3.2/4.2-67 3.7/4.7-34 3.7/4.7-35 INSERT-3.2/4.2-7*
3.2/4.2-8 3.2/4.2-9 3.2/4.2-10 3.2/4.2-11:
3.2/4.2-11'a 3.2/4.2-13a 3.2/4.2-13b*
3.2/4.2-18*
3.2/4.2-19 3.2/4.2-20 3.2/4.2-21*
3.2/4.2-41*
3.2/4.2-42 3.2/4.2-66 3.2/4.2-67*
3.7/4.7-34 3.7/4.7-35*
TABLE 3.2.A PRIHARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION P a Hinimum No.
Instrument Channels Operable r Tri 1
F n
ri v
1 n
Instrument Channel
> 538" above vessel zero Reactor Low Water Level(6)
A or (B and E) 1.
Below trip setting does the following:
a.
Initiates Reactor Building Isolation b.
In)tiates Primary Containment, Isolation (Groups 2, 3, and 6) c.
Instrument Channel-Reactor High Pressure (PS-68-93 and 94)
Instrument Channel Reactor Low Water Level (LIS-3-56A-D, SW Sl)
Instrument Channel High Drywell Pressure (6)
(PS~56A-D) 100 g 15 psig
> 378" above vessel zero g 2.5 psig A or (B and E) 1.
Above trip setting isolates the shutdown cooling suction valv'es of the RHR system.
l.
Below trip setting initiates Hain Steam Line Isolation l.
Above trip setting does the following:
a.
Initiates Reactor Building Isolation b.
Initiates Primary Containment Isolation c.
Initiates SGTS
II af r
TABLE 3.2.A (Continued)
PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION Hinimum No.
Instrument Channels Operable r Tr 2(3) 2(12) 1(15) n n
Instrument Channel-Low Pressure Hain Steam Line Instrument Channel High Flow Hain Steam Line Instrument Channel Hain Steam Line Tunnel High Temperature Instrument Channel Reactor Building Ventilation High Radiation - Reactor Zone Instrument Channel Reactor Mater Cleanup System Hain Steam Valve Vault (TIS-069-834A-D)
Instrument Channel Reactor Water Cleanup System Pipe Trench (TIS-069-835A-D) i v
1 in
> 825 psig (4)
< 140K of rated steam flow
< 200<F
< 100 mr/hr or downscale
< 201.00F
< 135.04F A
rk 1.
Below trip setting initiates Hain Steam Line Isolation l.
Above trip setting initiates Hain Steam Line Isolation l.
Above trip setting initiates Hain Steam Line Isolation.
1 ~
1 upscale channel or 2 downscale channels will a.
Initiate SGTS b.
Isolate reactor zone and refueling floor.
c.
Close atmosphere control system.
Above Trip Setting initiates Isolation of Reactor Mater Cleanup Lines to and from the Reactor Above Trip Setting initiates Isolation of Reactor Mater Cleanup Lines to and from the Reactor
J J
TABLE 3.2.A (Continued)
PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION c."w Hinimum No.
Instrument n
Channels Operable er Tri 1
11 1(15)
Functi n
Instrument Channel Reactor Water Cleanup System Pump Room 3A (TIS=069-836A-0)
Instrument Channel Reactor Water Cleanup System Pump Room 38 (TIS-.069-837A-D)
Instrument Channel Reactor Water Cleanup System Heat Exchanger Room (TIS-069-838A-0)
Instrument Channel Reactor Water Cleanup System Heat Exchanger Room (TIS-069-839A-0)
Instrument Channel Reactor Building Ventilation High Radiation Refueling Zone Tri Level e tin
< 152.00F 152 OoF
< 143.0'F
< 170.04F
< 100 mr/hr or downscale A
ion 1
Remark Above Trip Setting initiates Isolation of Reactor Mater Cleanup Lines to and from the Reactor Above Trip Setting iriitiates Isolation of Reactor Water Cleanup Lines to and from the Reactor Above Trip Setting initiates Isolatiori of Reactor Mater Cleanup Lines to and from the Reactor Above Trip Setting initiates Isolation of Reactor Water Cleanup Lines to and from the Reactor 1.
1 upscale channel or 2 downscale channels will a.
Initiate SGTS b.
Isolate refueling floor c.
Close atmosphere control system.
R i
2(7) (8)
Instrument Channel SGTS Flow Train A R. H. Heaters
>2000 cfm and
< 4000 cfm H and (A or F)
Below 2000 cfm airflow R.H.
heaters shall be shut off.
O
4I f
4~
TABLE 3.2.A (Continued)
PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION Hinimum No.
Instrument Channels Operable r Tri 1 ll Fun i n Tri L v 1
in A
i n 1
R m rk 2(7) (B)
Instrument Channel SGTS Flow - Train B
R. H. Heaters
>2000 cfm and
< 4000 cfm H and (A or F)
Below 2000 cfm airflow R.H.
heaters shall be shut off.
2(7) (8)
Instrument Channel SGTS Flow - Train C
R. H. Heaters
>2000 cfm and
< 4000 cfm H and (A or F)
Below 2000 cfm airflow R.H.
heaters shall be shut off.
2(10)
Reactor Building Isolation 0
< t
< 2 secs.
Timer (refueling floor)
Reactor Building Isolation 0
< t
< 2 secs.
Timer (reactor z'one)
Group 1 (Initiating) Logic N/A Group 1 (Actuation) Logic N/A HorF G or A or H l.
a.
b.
c ~
d.
e.
l.
a.
b.
Co d.
eo Below trip setting prevents spurious trips and system perturbations from initiating isolation.
Below trip setting prevents spurious trips and system pe'rturbations from initiating isolation.
A Group 1 isolation is actuated by any of the following conditions:
Reactor Vessel Low Low Water Level Hain steamline high radiation Hain steamline high flow Hain steamline space high temperature Hain steamline low pressure Group 1:
A Group 1 i sol ati on is actuated by any of the following conditions:
Reactor Vessel Low Low Water Level Main Steamline High Radiation Main Steamline High Flow Hain St'eamline Space High Temperature Hain Steamline Low Pressure
~ I J
,3~
TABLE 3.2.A (Continued)
PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION Hinimum No.
Instrument Channels Operable r Tri' ll Fn in Group 2 ( Initia ting) Logic Group 2 (RHR Isolation-Actuation) Logic Group 8 (TIP-Actuation)
Logic Group 2 (Drywell Sump Drains-Actuation) Logic Group 2 (Reactor Building t Refueling Floor, and Drywell Vent and Purge-Actuation) Logic Group 3 (Initiating) Logic Tri L v 1
et in N/A N/A N/A N/A N/A N/A A
i n
1 A or (B and E)
F and G
R m rk 1.
Group 2:
A Group 2 isolation is <<ctuated by any of the following conditions:
a.
Reactor Vessel Low Mater Level b.
High Drywell Pressure 1.
Part of Group 6 Logic 1.
Group 3:
A Group 3 isolation is actuated by any of the following conditions:
a.'eactor Vessel Low Mater Level b.
Reactor Mater Cleanup (RMCU)
System High Temperature in the main steam valve vault c.
RWCU System High Temperature in the RWCU pum'p room 3A d.
RWCU System High Temperature in the RWCU pump room 38 e.
RWCU System High Temperature in the RMCU heat exchanger room f.
RMCU System High Temperature in the space near the pipe trench containing RWCU piping O
0
'i t
TABLE 3.2.A (Continued)
PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION Hinimum No.
Instrument Channels Operable r Tri 1 ll Fn in Group 3 (Actuation) Logic Group 6 Logic Group 8 ( Initiating) Logic Tri L v 1
tin N/A N/A N/A A
i n
1 F and G
rk 1.
Group 6:
A Group 6 isolation is actuated by any of the following conditions:
a.
Reactor Vessel Low Water Level b.
High Drywell Pressure c.
Reactor Building Ventilation High Radiation 1.
Group 8:
A Group 8 isolation is automatically actuated by only the following conditions:
a.
High Dry'well Pressure b.
Reactor Vessel Low Water Level Reactor Building Isol ati on (refueling floor) Logic Reactor Building Isol ati on (reactor zone) Logic l(7) (8)
SGTS Train A Logic l(7) (8)
SGTS Train 8 Logic 1(7) (8)
SGTS Train C Logic N/A N/A N/A N/A N/A HorF HorG or A L or (A and F)
L or (A and F)
L or (A and F) 2.
Same as Group 2 initiating logic.
Refer to Table 3.2.8 for RCIC and HPCI functions including Groups 4, 5, and 7 valves.
0 I
,k t'
.NOTES FOR TABLE 2 A (Cont'd) 14.
Deleted 15.
There is a RBVRM trip function for the refueling zone and a
RBVRM trip function for the.reactor zone.
Each trip function is composed of tvo divisional trip systems.
Each trip system has one, channel for each zone.
Each channel contains tvo sensors, both of vhich must'e OPERABLE for the. channel to. be 'OPERABLE.
A channel downscale/inoperable trip occurs. vhen either of the sensors, are indicating less than the lov radiation setpoint or are inoperabl'e.
A channel upscale trip occurs when both of the sensors are indicating higher than the high radiation setpoint.,
Only one channel upscale, trip is required for trip function initiation..
Tvo channel downscale trips in a zone are required for trip function initiation.
BFH Unit '3 3.2/4.2-13a
.AHENDHEHT NO. 193
41 l
~,
THIS PAGE IHTEHTIOHALLYLEFT BLAHK BFH Unit 3.
3.2/4.2-13b, AMENDMHffN5 16 p
4I
Hinimum No.
n Operable Per
~Tr i 1(2) 2(2)
F n i
HPCI Trip System bus power monitor RCIC Trip System bus power monitor Instrument Channel Condensate Header Low Level (LS-73-56A 4 B)
Instrument Channel Suppression Chamber High Level TABLE 3.2.B (Continued) i v
1 N/A N/A
> Elev. 551' 7" above instrument zero A
1.
Honitors availability of power to logic systems.
l.
Hen%ters avail ability of power to logic systems.
1.
Below trip setting will open HPCI suction valves to the suppression chamber.
1; Above trip setting will open HPCI suction valves to the suppression chamber.
'A I
<O 2(2) 4(4) 3(2)
Instrument Channel-RCIC Steam Line Space High Temperature
<2000 F.
Instrument Channel-
>50 psig RCIC Steam Supply Pressure - Low (PS 71-lA-D)
Instrument Channel
< 583" above vessel zero Reactor High Mater Level Instrument Channel
< 450" H20 (7)
RCIC Turbine Steam Line High Flow l.
Above trip setting trips RCIC turbine.
l.
Above trip setting isolates RCIC system and trips RCIC turbine.
l.
Above trip setting isolates RCIC system and trips RCIC turbine.
l.
Below trip setting isolates RCIC system and trips RCIC turbine.
3(2)
Instrument Channel-RCIC Turbine Exhaust Diaphragm Pressure High (PS 71-11A-0)
< 20 psig l.
Above trip setting isolates RCIC system and trips RCIC turbine.
II t (I
'h P
'4 jl'
Hinimum No.
Operable Per
~Tri >~~1 2(2) 4(4) 3(2) 3(2) 1 (16)
Fun i n Instrument Channel Reactor High Water Level Instrument Channel-HPCI Turbine Steam Line High Flow Instrument Channel-HPCI Steam Line Space High Temperature Instrument Channel-HPCI Steam Supply Pressure Low (PS 73-1A-D)
Instrument Channel-HPCI Turbine Exhaust Diaphragm (PS 73-20A-D)
Core Spray System Logic RCIC System (Initiating)
Logic RCIC System (Isolation)
Logic ADS Logic TABLE 3.2.B (Continued)
-Tri Level Settin
<583" above vessel zero.
<90 psi (7)
<200'F.
)100 psig
<20 psig N/A N/A N/A N/A Action R
ark l.
Above trip setting trips HPCI turbine.
l.
Above trip setting isolates HPCI system and trips HPCI turbine.
l.
Above trip setting i sol ates HPCI system and trips HPCI turbine.
1.
Below trip setting isolates HPCI system and trips HPCI turbine.
l.
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.
2.
Group 7:
A Group 7 isolation is automatically actuated by only the following condition:
l.
The respective turbine steam supply valve not fully closed.
l.
Includes Group 5 valves.
2.
Group 5:
A Group 5 isolation i
is actuated by any of the following conditions:
a.
RCIC Steamline Space High Temperature b.
RCIC Steamline High Flow c.
RCIC Steamline Low Pressure d.
RCIC Turbine Exhaust Diaphragm High Pressure
0 41 w
TABLE 3.2.8 (Continued)
Hinimum No.
Operable Per
~Tr i ~l Func ion RHR (LPCI) System (Initiati on)
RHR (LPCI) System (Containment Cooling Spray)
Logic HPCI Sys tern (Initiating)
Logic HPCI System (Isolation)
Logic Tri Level ettin N/A N/A N/A N/A
~Ac ion Remarks l.
Includes Group 7 valves.
2.
Group 7:
A Group 7 isolation is automatically actuated by I
only the following condition:
1.
The respective turbine steam supply valve not fully closed.
l.
Includes Group 4 valves.
2.
Group 4:
A Group 4 isolation is actuated by any of the following conditions:
a.
HPCI Steamline Space High Temperature b.
HPCI Steamline High Flow c.
HPCI Steamline Low Pressure d.
HPCI Turbine Exhaust Diaphragm High Pressure 1(3) 1(3) 1(3) 1(3) 1(10)
Core Spray Loop A Discharge Pressure
( PI-75-20)
Core Spray Loop 8 Discharge Pressure (PI-75-48)
RHR Loop A Discharge Pressure (PI-74-51)
RHR Loop 8 Discharge Pressure (PI-74-65)
Instrument Channel-RHR Start 0 500 psig Indicator (9)
D 0 500 psig Indicator (9) 0 0 - 450 psig Indicator (9)
D 0 450 psig Indicator (9) 0 N/A 1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
1.
Part of filled discharge pipe requirements.
beefer to Section 4.5.
1.
Part of filled discharge pipe requirements.
Refer to Section 4.5.
l.
Starts RHR area cooler fan when respective RHR motor starts.
Cl
~,
L
TABLE 3.2.B (Continued) m CD CR M
CO Ninimum No.
Operable Per
~Tri ~l 1(10) 2(10) 2(10) 1(10) 1(10) 1(10) 1(12) 1(12) 1(13)
Fn in Instrument Channel Thermostat (RHR Area Cooler Fan)
Instrument Channel Core Spray A or. C Start Instrument Channel Core Spray B or 0 Instrument Channel-Thermostat (Core Spray Area Cooler Fan)
RHR Area Cooler Fan Logic Core Spray Area Cooler Fan Logic Instrument Channel Core Spray Hotors A or C Start Instrument Channel Core Spray Hotors B or 0 Start Instrument Channel Core Spr'ay Loop 1 Accident Signal (15)
Instrument Channel Core Spray Loop 2 Accident Signal (15)
RPT Logic RHR% Initiate Logic Tri Lv1 in
<1000 F N/A N/A
< 100'F N/A N/A N/A N/A N/A N/A N/A N/A
~Ai n (17)
(14) 1.
Above trip setting starts RHR area cooler fans.
1.
Starts Core Spray area cooler fan when Core Spray motor starts.
1.
Starts Core Spray area cooler fan when Core Spray motor starts.
1.
Above trip setting starts Core Spray area cooler fans.
1.
Sta~ts RHRSW pumps A3, Bl, C3, and 01 1.
Starts RHRSW pumps A3, Bl, C3, and 01 1.
Starts RHRSM pumps A3, Bl, C3, and 01 1.
Starts RHRSW pumps A3, Bl, C3, and 01 1.
Trips recirculation pumps on turbine contrel valve fast closure or stop valve closure
> 3'ower.
Ik gE
TABLE 4.2.A SURVEILLANCE RE()UIREHENTS FOR PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION
~Fn ~in n
i n
T libr Fr n
rmn h
Group 1 (Initiating) Logic Group 1 (Actuation) Logic Checked during channel N/A functional test.
No further test required.(ll) once/operating cycle (21)
N/A N/A N/A Group 2 (Initia ting) Logic Group 2 (RHR Isolation-Actuation)
Logic Group 8 (TIP-Actuation) Logic Group 2 (Drywell Sump Drains-Actuation) Logic Group 2 (Reactor'uilding and Refueling floor, and Drywell Vent and Purge-Actuation)
Logic I
Group 3 (Initiating) Logic Group 3 (Actuation) Logic Checked during channel N/A functional test.
No further test required.
once/operating cycle (21)
N/A once/operating cycle (21)
N/A once/operating cycle (21)
N/A once/operating cycle (21)
N/A Checked during channel N/A functional test.
No further test required.
once/operating cycle (21)
N/A N/A N/A
- N/A N/A N/A N/A N/A
0 ep
SURVEILLANCE RE(lUIREHENTS TABLE 4.2.A (Cont'd)
FOR PRIHARY CONTAINHENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION
~Fnnc i n Group 6 Logic Group 8 (Initiating) Logic Reactor Building Isolation (refueling floor) Logic Reactor Building Isolation (reactor zone) Logic SGTS Train A Logic SGTS Train 8 Logic SGTS Train C Logic Instrument Channel Reactor Water Cleanup System Hain Steam Valve Vault (TIS-069-834A-D)
Instrument Channel Reactor Water Cleanup System Pipe Trench (TIS-069-835A-0)
Instrument Channel Reactor Water Cleanup System Pump Room 3A (TIS-069-836A-0)
Instrument Channel Reactor Mater Cleanup System Pump Room 3B (TIS-069-837A-0)
Instrument Channel Reactor Water Cleanup System Heat Exchanger Room (TIS-069-838A-D)
Instrument Channel Reactor Water Cleanup System Heat Exchanger Room (TIS-069-839A-D)
Fn i nl T once/operating cycle (18)
Checked during channel functional test.
No further'est required.
once/6 months (18) once/6 months (18) once/6 months (19) once/6 months (19) once/6 months (19)
(1) (28)
(1) (28)
(1) (28)
(1) (28)
(1) (28)
(1) (28)
Calibr ti n Fr u'enc N/A N/A (6)
(6)
N/A N/A N/A 4 months 4 months 4 months 4 months 4 months 4 months In tr men he k
N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A
~
P ez t~
~
~
3.2 BASES (Cont'd)
The setting of.200 F for the main steam line tunnel detector is low enough to detect leaks of the order of 15 gpm; thus, it is capable of covering the entire spectrum of breaks.
For large breaks, the high steam flow instrumentation is a backup to the 'temperature instrumentation.
In the event of a loss of the reactor building ventilation system, radiant heating in the vicinity of the main steam lines raises the ambient temperature above 200 F.
The temperature increases can cause an unnecessary main steam line isolation and reactor scram.
Permission is provided to bypass the temperature trip for four hours to avoid an unnecessary plant transient and allow performance of the secondary containment leak rate test or make repairs necessary to regain normal ventilation.
Pressure instrumentation is provided to close the main steam isolation valves in RUN Mode when the main steam line pressure drops below 825 psig.
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 a. 1-out-of-2 logic, and all sensors are required to be OPERABLE.
High temperature in the vicinity of the HPCI equipment is sensed by four sets of four bimetallic temperature sw'itches.
The 16 temperature switches are arranged in two trip systems with eight temperature switches in each trip system.
The HPCI trip settings of 90 psi for high flow and 200'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 450" water for high flow and 200'F for temperature are based on the same criteria as the HPCI.
High temperature at the Reactor Water Cleanup (RWCU) System in the main
,steam valve vault, RWCU pump room 3A, RWCU pump room'B, RWCU heat exchanger room or in the space near the pipe trench containing RWCU piping could indicate a break in the cleanup system.
When high temperature
- occurs, the cleanup system is isolated.
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.
BFH Unit 3 3.2/4.2-66 AMEND?LENT NO. 193
4l 4l
~,
4
'+
4
3.2 BASES (Cont'd)
The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR,does not decrease to 1.07.
The trip logic for this, function 'is 1-out-of-n:
e.g.,
any trip on one of six APRMs, eight IRMs, or four SRMs will result in a rod block.
The minimum instrument channel requirements assure sufficient instrumentation to assure the single failure criteria is met.
The minimum instrument channel requirements for the RBM may be reduced by one for maintenance, testing, or calibration.
This d'oes not significantly increase the risk of an inadvertent control rod withdrawal, as the other channel is available, and the RBN is a backup system to the written sequence for withdrawal of control rods.
The APRM rod block function is flow biased and prevents a significant.
reduction in MCPR, especially during operation at reduced flow.
The APRM provides gross core protection; i.e., limits the gross core power increase, from withdrawal of control rods in the normal wi,thdrawal sequence.
The trips are set so,that MCPR is maintained greater than 1.07.
The RBM rod block function provides local protection of the core; i.e.,
the prevention of critical power in a local region of the core, for a single rod withdrawal error from a limiting control rod pattern.
If the IRM channels are in the worst condition of allowed bypass, the sealing arrangement is such that for unbypassed IRM channels, a rod block signal is generated before the detected neutrons flux has increased by more than a factor of 10.
.A downscale indication is an indication the instrument has failed or the instrument is not sensitive enough.
In either case the instrument will not respond to changes in control rod motion and thus, control rod motion is prevented.
The refueling interlocks also operate one logic channel, and are required for safety only when the mode switch is in the refueling position.
For effective emergency core cooling for small pipe breaks, the HPCI system must function since reactor pressure does not decrease rapid enough to allow either core spray or LPCI to operate in time.
The automatic pressure relief function is provided as a backup to the HPCI in the event the HPCI does not operate.
The arrangement of the tripping contacts i's such as to provide this function when necessary and minimize spurious operation.
The trip settings given in the specification are adequate to assure the above criteria are met.
The specification preserves the effectiveness of the system during periods of maintenance, testing, or calibration, and also minimizes the risk of inadvertent operation; i.e., only one instrument channel out of service.
3.2/4.2-67
[
BFH Unit 3 Two radiation monitors are provided for each unit which initiate Primary Containment Isolation (Group 6 isolation valves) 'Reactor Building Isolation and operation of the Standby Gas Treatment System.
These instrument channels monitor the radiation in the reactor zone ventilation exhaust ducts and. in the refueling zone.
AMBOMENTgo. y ~8
ll 0
< <I J
4'
3.7/4.7 BASES (Cont'd) in the system, isolation is provided by high temperature in the cleanup system area.
Also, since the vessel could potentially be drained through the cleanup
- system, a low-level isolation is provided.
Grou s 4 and 5 Process lines are designed to remain OPERABLE and mitigate the consequences of an accident which results in the isolation of other process lines.
The signals which initiate isolation of Groups 4 and 5 process lines are therefore indicative of a condition which would render them inoperable.
G~rou Line's are connected to the primary containment but not directly to the reactor vessel.
These valves are isolated on reactor low water level (538"), high drywell pressure, or reactor building ventilation high radiation which would indicate a possible accident and necessitate primary containment isolation.
~Grou 7 process lines are closed only on the respective turbine steam supply valve not fully closed.
This assures that the valves are not open when HPCI or RCIC action" is required.
~Grou Line itraveling in-core probe) is isolated on high drywall pressure or reactor low water level (538").
This is to assure that this line does not provide a leakage path when containment pressure or reactor water level indicates a possible accident condition.
The maximum cl'osure time for the automatic isolation valves of the primary containment and reactor vessel isolation control system have been selected in consideration of the design intent to prevent core uncovering following pipe
,breaks outside the primary containment and the need to contain released fission products following pipe breaks inside the primary containment.
In satisfying this design intent, an additional margin has been included in specifying maximum closure times.
This margin permits identification of degraded valve performance prior to exceeding the design closure times.
In order to assure that the doses that may result from a steam line break do not exceed 'the 10 CFR 100 guidelines, it is necessary that no fuel rod perforation resulting from the accident occur prior to closure of the main steam line isolation valves.
Analyses indicate that fuel rod cladding perforations would be avoided for main steam valve closure times, including instrument delay, as long as 10.5 seconds.
BFN Unit 3 3.7/4.7-34 AIIENDHENT HO. 193
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3.7/4.7
~B SES (Cont'd)
These valves are highly reliable, have low service requirements and most are normally closed.
The initiating sensors and associated trip logic are also checked to demonstrate the capability for automatic isolation.
The test interval of once per operating cycle for automatic initiation results in a failure probability of 1.1 x 10 that a line will not isolate.
More frequent testing for valve OPERABILITY in accordance with Specification 1.0.MM results in a greater assurance that the valve will be OPERABLE when needed.
The main steamline isolation valves are functionally tested per Specification 1.0.MM to establish a high degree of reliability.
The primary containment is penetrated by several small diameter instrument lines connected to the reactor coolant system.
Each instrument line contains a 0.25-inch restricting orifice inside the primary containment and an excess flow check valve outside the primary containment.
3.7.E/4.7.E Co tro Room Emer en Ve t t o The control room emergency ventilation system is designed to filter the control room atmosphere for intake air and/or for recirculation during control room isolation conditions.
The control room emergency ventilation system is designed to automatically start upon control room isolation and to assist other sources of pressurization in maintaining the control room at a positive pressure.
High efficiency particulate absolute (HEPA) filters are installed prior to the charcoal adsorbers to prevent clogging of the iodine adsorbers.
The charcoal adsorbers are installed to reduce the, potential intake of radioiodine to the control room.
The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99 percent.removal of DOP particulates.
The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions. If the efficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the allowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power
- Plants, Appendix A to 10 CFR Part 50.
Operation of the, fans significantly different from the design flow will change the removal efficiency of the HEPA filters and charcoal adsorbers.
If the system is found to be inoperable, there is no immediate threat to the control room and reactor operation or refueling operation may continue for a BFN Unit 3 3.7/4.7-35 AMENDhINTNO. E 65
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