ML18029A738
| ML18029A738 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/08/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML18029A739 | List: |
| References | |
| DPR-33-A-118, DPR-52-A-113, DPR-68-A-089 NUDOCS 8508020347 | |
| Download: ML18029A738 (30) | |
Text
gg~ REDO (4
dp0 Cy 0
C O
+a*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 118 License No.
DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 19, 1984, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rales 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.
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:
Pan
+~ 8~0~O8 85080 hooch Osooo~>9 pna
(2)
Technical S ecifications 9
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
118
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 8, 1985 Domenic B. Vassallo, Chief Operating Reactors Branch ¹2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
118 FACILITY OPERATING LICENSE NO.
DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
34 37 40 44 2.
The marginal lines on these pages denote the area being changed.
I
~ ~
~
~ \\
~
~
~
11 SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY
- 2. 1 FUEL CLADDING INTEGRITY Power Transient To ensure that the Safety Limits established in Specification
- 1. 1.A are not exceeded,
'ach required scram shall bc initiated by its expected scram signal.
The Safety Limit shall be assumed to be exceeded when scram is accomplished by means other than the expected scram signal.
Scramturbine stop valve closure Scram--turbine control valve fast clo"ura or turbine trip 2 538 in.
above vessel zero 5
10 per-cent valve closure
~ 550 psig 4.
(Deleted) 5.
Scram--main steam line isol ation 5
10 per-cent valve losuro 6,
Main steam isola-tion valve closure nuclear system low pressure
~ 825 ps i".
C. Reactor Vessel Water Level ll C. Water Level Tri Settin s
Whenever there is irradiated fuel in the reactor vessel,
~ the water level shall. not be less than'7.7 in. above the top of the normal active fuel zone.
2.
Core spr~y and LPCI actuation
'reactor low water level HPCI and RCIC actuation reac-tor low water level 2 378 in.
above vesaeT zero 2
470 in.
above vessel zero Main"steam isola-tion valve closure reactor'ow
~ater level 2 378 above vessel zero Amendment No. 118
2.l BASES C, bII Hain Steaa Line Is~ Bstion on Lov Prcssure and Hain Steam line Isolation Scrsca i
The loBE preasure isolation of the main
~ teaEB lines at 825 psig BAS ~
provided to protect against rapid reactor depr'eseurization and the
'esulting rapid cooldcwn of the vessel.
hdvantage is taken of the acram feature that occurs BEhen the main steam line isolation valves are closed, to provide for reactor ahutdovn aa that high povsr opera-tion at lov reactor preoeur does not occur, thus providing protection for the fuel cladding integrity safety limit.
Operation of 'the reac-tor at pressures lover than 82> psig requires that the reactor cede avitch be in the STARTUP position, vhere protectfon of'he tuel cladding
'ntegrity safety limit is provided by the IIlM and APRH high neutron flux acrama.
- Thus, the combination of main steam line lov.pressure isolation and isolation valve closure scram assures the availability of neutron flux scram protection over the entire range 'ot applic b'lit f th f 1
cladd n
c a
ing integrtty saf ~ty licalt.
In addition, the isolation valve closure scrsEo anticipates ths pressure and flux transients that occur during normal or inadvertent isolation valve closure.
Mich ths scrams aat at 10 percent of valve closure, neutron flux does not increase.
Amendment No. 118 z4
r
TABLE 3.1.A REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENTS Min. No.
of Operable Inst.
Channels Per Trip Modes in which Function Must Be
~Oerable Shut-Startup/
Run Action(l)
-10X Valve Closure Isolatiqn Valve Closure X(3) (6)
X(3) (6)
X(6) 1.A or 1.C Turbine Control
>550 psig Valve Fast Clos-ure or Turbine Trip X(4) 1.A or 1.D Turbine Stop Valve Closure
-10X Valve Closure X(4) 1.A or 1.D Turbine First Stage Pressure Permissive not -154 psig X(18)
X(18)
X(18)
(19)
Main Steam Line 3 X Normal Full High Radiation Power Background (14)
(20)
X(9)
X(9)
X(9) 1.A or 1.C
TARt,E 4.i.p.
REACTOR PROTECT108 STSTEH (SCRAH) 1NSTXUHRfTAT10N FUNCTIONAL TESTS HDfDIH fUNCTIONAL TEST FREqUENClES POR SAFETT 1NSTRo AND CONTRDL CIRCUlTS o
Hode Svitch in Shutdovn Hanual Scree OO DN High flux functional Teat Place Hode Svitch in Shutdrrun Trip Channel and Alan@
'rip Channel and Ala+a (4)
Hinbnaa fre uency (3)
Each Refueliog Outage Every 3 Hontha Once Per Meek During Refuelin and Sefore Each Startup inoperative APRH Iiigh flux (lSl acres)
IIigh Flux (Flow Biased)
High Flux (Fixed Trip)
C Trip Channel and Alanna (A)
Trip Output Relays (4)
Trip Output Relays f4)
Trip Output Relays (A)
Once Per Meek During 1efuelin and Eefore Each Startup Sefore Each Startup and Meetl Mhen Required to be Operable Once/)I cele Inoperative Davnccale flov Eisa Trip Output Relaya (4)
Trip Output Relays (4)
(6)
Once/Meek Once(Meet (6)
Righ Reactor Pressure High Dryvoli. Pressure Reactor 4w Mater Level IIigh Water Level in Scram Discharge
-Tank
- Float Switches (LS"85-45C-F)
High Water Level in Scram Discharge Tank Electronic Level Switches (LS-85-45A, B, G, II)
Trip Channel and Alarm Trip Channel and biota Trip Channel and Alarm Once/Honth (l)
Once/Month (l)
Once/Honth (1).
Trip Channel and Alarm Once/Month Trip Channel and Alarm (7)
Once/Month Hain Steam Line IIigh Radiation B
Trip Channel and Alarm (4)
Once/3 months (8)
TABLE 4 1 ~ B REACTOR PROTECTION SYSTEM
{SCRAH)
ZHSTRQHEHT CALIBRATION KIHIHQH CALIBRATION FRRQQElLIES FOR REACTOR PROTECTIOH IHSTRQHEHT CHAHHELS Instrument Channel IRH High Flux APRH High Flux Output Signal plov Bias Signal LPRN Signal High Reactor Pressure High Dryvell Pressure Reactor Lov Mater Level Croup (1)
B B
Calibration Comparison to APRH on Control-led stsrtups (6)
Heat Balance Calibrate Floe Bias Signal (7)
TIP System Traverse (8)
Standard Pressure Source J
Standard Pressure Source Pressure Standard Itinimum Frequency (2)
Hote (4)
Once every 7 days Once/operating cycle Every 1000 Effective Pull Power Hours Every 3 Months Every 3 Months Every 3 Months High Water Lovel in Scrla Discharge Volume Float Switches (LS-85 "45 C"F )
Calibrated Water Column (5)
Note (5)
High Water Level in Scram Dischargo Volume Electronic Level Siritches (LS-85-45-A, B,
G, H)
B Cal ibra ted Water Column Once/Operating Cycle (9)
Main Steam Line Isolation Valve Closure Main Steam Line High Radiation Turbine First Stage Pressure Permissive (PT-1-81h and B, Pl'-1-91h and B)
B Note (5)
Standard Current Source (3)
Standard Pressure Source Note (5)
Every 3 Months Once/Operating Cycle (9)
Turbine Cont. Valve Fast Closure "or.
Ti)rbine Trip Turbine Stop Valve Closure Standard Pressure Source Note (5)
Once/Operating Cycle Note (5)
3.f lasts r
modes.
In the pover ringe the APR!{ system provides requ'red protection.
Ref. Section 7.5.7 FSAR.
- Thus, che IRH System is noc required in the Run modo.
The APRH' aod the IR!{'s provide adequate coverage ia the startup and intermediate range.
The high reactor
.pressure, high dryvell pressure, reactor lov vater level and scram discharge volume high level scrams are required for'Scarcup and Run sides of plant operation.
They are, therefore, required to be opera-tional for these modes of'eaccor operation.
The requirement to have cho scram functions as indicated in Table 3.1.1 operable io the Refuel mode is to assure that shifting to the Refuel cede during reactor povcr operatioa does not dimiaish the need for the reactor proceccion syste'st Because of the APB.'{ downscale 1&it of i 3Z vhea in the Run mode and hi,gh-level limit of c 15Z vhen in the Startup
- Hode, che transition betveea che Scartup and Run Hndes must be made vith che APL{ instrunencotioa indicating becveen 3Z and 15Z of raced pover or a control rod scram vill occur.
In
~ddi cion, the IR { system must be indicating below the High Flux setting (120/125 of scale) or a scram vill occur vhen in the Startup Hade.
'For normal operating conditions, these limits provide assurance of overlap betveen che IRH syscem and APR.'L syscem so thac there are ao "gapa" in the paver level indications (i.e.,
the pover level is continuously aanitored
'.rom beginning of atartup to full paver and from full pover to ahutdovn).
4'hen pover is being reducsd, if a transfer to the Startup mode ia made sad che IRH's have noc been fully inserted (a aLaloperatioaal but not impossible cdndition) a control rod block Mediately occurs so chat rsaccivicy wser-tion by control rod vithdraval caanoc occur.
Amendment No. 118 44
8 BEGOT.
Vp0 Op A.
UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
113 License No.
DPR-52 I.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 19, 1984, 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.
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. 113, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 8, 1985 Domenic B. Vassallo, Chief Operating Reactors Branch k2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
113
. FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
4 ~
34 37 40 44 2.
The marginal lines on these pages denote the area being changed.
SAFETY LIMIT
- 1. 1 FUEL CLADDING INTEGRITY E
2.1 FUEL CLADDING INTEGRITY B.
Power Transient
'=B. Power Transient Tri Settin s
To ensure that the Safety Limits
" established in Specification
- l. 1.A are not exceeded,
'ach required scram shall bc initiated by its expected scram.
signal.
The Safety Limit shall be assumed to be exceeded when scram is accomplished by means other than the expected scram signal.
- 2. Scram--turbine stop valve closure Scram--turbine control valve
~
fast closura or turbine trip 2 538 in above
'essel zero 5 10 per-cent valve closure 550 psig 4 ~
(Deleted)
Scrammain steam line isolation 5
1.0 per-cent valve
.. "losuro 6,
Main steam.isola-
~825 psi",
~ tion valve closure-nuclear system low pressure C. Reactor Vessel Mater Level C. Mater Level Tri Settin s
Mhenever there is irradiated fuel in the reactor vessel,
~ the water level shall not be less than 17.7 'in. above the top of the normal active fuel zone.
Core spray and LPCI actuation reactor low water level 2,
HPCX and RCIC actuation reac-tor low water, level Main steam isola-2 tion valve closure reactor low water level
~
378 in.
above vessel zero 470 in.
above vessel zero 378 above vessel zero Amendment No. 113
'(DELETED)
'C.
C 1, Hain Stosx Lino Ia~ stion on Lov pressure and Hain Steam Line Isolation Scran The lov prceaure irolation of the main stean lines at 825 paig ~as
. provided to protect against rapid reactor depressurixation and the reoulting rapid cooldovn of th>> vessel.
Advantage is taken of. the ocraa feature that occurs vhcn the naia eteau line isolation valves oro cloeed, to provide for reactor ahutdovn ao that high pover opera-,
, tioa at lov reactor proaeur does not occur, thus providing protection for the fuel cladding integrity safety limit.
Operation of the reac-tor at preaaurea lover than 825 poig requires that the reactor cede avitch be in the.STLRM position, vhere protection of thc fuel cladding integrity aafety linit ia provided by'the IRH and APRH high neutron flux octane.
- Thus, the caebination o! aain eteaa line lov pressure.irolation isolation valve closure acraa assures the availability of neutron
~
flux acres protection over the entire range of applicab'lity of the fuel cladding integrity safety liIIit. In addition, the isolation valve closure ecraa anticipatea the pressure and flux transients that occur hsriag nodal or inadvertent isolation valve closure.
Pith the scree set at 10 percent of valve closure, neutron flux does not increase.
Amendment No.
11 3
TABLE 3.1.A REACTOR PROTECTION SYSTEM (SCRAM) INSTRUMENTATION REQUIREMENTS Min. No.
of Operable Inst.
Channels Per Trip S stem 1
-10X Valve Closure Isolation Valve Closure Turbine Control
>550 psig Valve Fast Clos-ure or Turbine Trip Shut-down
~oar able Startup/
X(3) (6)
X(3) (6)
Modes in which Function Must Be Run X(6)
X(4)
Action(1) 1.A or 1.C 1.A or 1.D Turbine Stop Valve Closure
-lOX Valve Closure X(4) 1.A or 1.D Turbine First Stage Pressure Permissive not -154 psig X(18)
X(18)
X(18)
(19)
Main Steam Line 3 X Normal Full High Radiation Power Background (14)
(2O)
X(9)
X(9)
X(9) 1.A or 1.C
TAlLE 4.1.A REACTOR FROTRCTfOM STSTEH (SCRAH)
TÃSTRUHECATTON FUHCTfORAL TESTS N?XUSN BSCTfORAL TEST FREQOEHCIKS FOR SAPETT 1ÃSTR.
AND COHTROL CIRCUfTS Node Svitch fn Shutdova Hanual Scree TRH HfRh Flux Inopera tfve AFRH RfRh Flux (fSI scree)
)ligh Flux (Flow Biased)
BfRh Flux (Fixed Trip) j~~g Functional Teat A
place Hode Suftch fn Shutdoun A
Trfp Channel and Alarm Trip Channel and Ala+a (4)
Trip Channel an) Ala+a (4)
C Trfp Output Relays (C)
B Trip Output Relays (4)
B Trip Output Relays (4)
Hfninun Fr uency (3)
Each Refueftni Outate Every 3.'tontha Once Far Ueak DurfoR Retuelfn aod Refore Each Startup Once Fer Vcek Durfng Rcfuelfn and Refore Eac4 Startup before Each Stertup and MaeU Mhcn Required to be Operable Once/Meek Oace/Meek
- Inoperative Downscale Flou hfae Trip Output Relays (4)
I Trip Output kelaye (4)
(6)
Once/Meek Once/Meek (6) fffRh Reactor treasure HRh Dryvell pressure Reactor Lov Ater Level ffiRh 'Mater Level fo Scren Discharge Tank Float Switches Differential Pressure Switches B
Trip Channel and Alarm Trip Channel and Alarm A
Trip Channel and Aleta A
Trip Channel and 'larva A
. Trip Channel and A1ana Once/Honth (l)
Once/Month (l)
Once/Honth (l),
Once/month Once/month (7)
Main Steam Line lligh Radiation B
Trip Channel and Alarm Once/3 months g8)
TABLE 4 o \\ o B REACTOR PROTECTION SYSTEN (SCRAN)
IHSTRUNEHT CALIBRATIOH NIHINON CALIBRATION FREQUENCIES FOR REACTOR PROTECTIOH INSTRONEHT CHANNELS Instrunent channel IRN High Flux APRN High Flux output Signal Flow Bias Signal LPRN Signal High Reactor Pressure.
High Dryiell Pressure Reactor Low Mater Level High Mater Level in Scraa Discharge Volume Float Switches Differential Pressure Switches Croup (1)
A B
calibration Comparison to APRN on Control-led Itartupi (6)
Heat Balance Calitrate Flow Bias signal (7)
TIP Systen Traverse (0) standard Pressure source Srandard Pressure Source Pressure Standard Note (5)
Calibrated Mater Column Nininun Frequency'I)
Note (4)
Once every 7 days once/operating cycle Every 1000 Effective Full Power Hours Every 3 Nonths Every 3 Nonths Every 3 Nonths Note (5)
Once/Operating Cycle Main Steam Line Isolation Valve Closure A
kfain Steam Line High Radiation B
Turbine First Stage Pressure Permissive A
Turbine Stop Valve Closure Turbine Cont; Valve Fast Closure. or A
Turbine Trip Note (5)
Standard Current Source (3)
Standard Pressure Source Note (5)
Standard Pressure Source Note (5)
Every 3 Months Every 6 Months Note (5)
I Once/operating cycle
3.f modes.
In the powder ragge the APRH system pzavidos requirod ptotection.
Ref. Section 7.5.7 TSAR.
- Thus, the IRH Systom is not required in the Run mode.
The APRH' and the ILN'e provide adequate coverage Ln the
~tartup and intermediate range.
4
. The high reactor pressure, high dryvell pressure, reactor lov water level
~nd scram discharge volume high level scroms arc required for Stoitup and Run aedes of plant operation.
They are, therefore, required to be opera-tional fot these modes of'eactor operation.
The requirement to have tho scram functions as indicated in Table 3.1.1 operable ia the Refuel made is to assure that shifting to the Refuel cede during reactor paver operation dace not diminish the need for the reactor protection system
~
Because of the APRH davnscolo limit of i 3X vhoo in the Run mode and high.
level limit af c 15X vhcn in the Startup
- Mode, the transition between the Startup and Run Hade>>
must b>> made with the APL% instrumentation indicnting between 3X and 15X of raced power ot a con'trol zod scram vill occuz.
In
- addition, the IRR system must be indicating below tho High Plux setting (120/125 of scale) or a scram vill occur vhcn in tha Startup Made.
Fot normal operating conditions, those limits provide assurance
- o. overlap between thc IRH system and APRR system ao that theta arc no "gapa" in the paver level indicatiano (i.c., the povez level ia continuously monitored
.rom beginning ot atartup to full paver and from full paver to shutdovn).
Aen power is being reduced, if o tzansfer to ths Startup
'mode ia macho sad
'he IRH' have not beco fully inserted (a malopcratiano'ut not impassible condition) a control rod block immediately occurs so that reactivity ~maez-cion by control rod vithdraval cannat occur.
Amendment No. 113
~pg Rfgy P
~4 0
Cy 0
Pw, @fg
+>>*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 License No.
DPR-68 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated November 19, 1984, complies with the standards and requirements of the Atgmic 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 Collml1ss10n'.
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.
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:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 89
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 90 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 8, 1985 Domenic B. Vassallo, Chief Operating Reactors Branch P2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
89 FACILITY OPERATING LICENSE NO.
DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
13 23 33 36
\\
39 43 2.
The marginal lines on these'ages denote the area being changed.
SAFETY LIMIT
.LIMITING SAFETY SYSTEM SETTING 1.1 FUEL CLADDING INTEGRITY 2 1 FUEL CLADDING INTEGRITY B
Power Transient
."B. Power Transient Tri Settin s
To ensure that the Safety Limits es tab lish ed in Spec ifica tion
- 1. 1.A are not exceeded,
'ach required scram shall bc initiated by its expected scram signal.
The Safety Limit shall be assumed to be exceeded when
'scram is accomplished by means other than the expected scram signal.
Scram and isola-tion (PCIS groups 2,3,6) reactor low
~ater level
- 2. Scram--turbine stop valve closure 3, Scram--turbine control valve
~
fast cloaura or turbine trip (Deleted) 2 538 in.
above vessel zero 5
10 per-cent valve closure 550 psig 5.
Scrammain steam line isolation 5
1Q per-cent valve losuro 6.
Main steam isola-tion valve closure nuclear system low pressure
~ 825 psi"
~
1 I
,Whenever there is irradiated fuel in the reactor vessel,
~ the water level shall not be less than 17.7 'in. above the top of the normal active fuel zone.
C. Water Level Tri Settings Core spray and LPCI actuation--
reactor 1oM'water level HPCX and RCIC actuation reac-tor low water level R 378 in.
above vesseT zero p
470 above vessel zero Hain steam isola-I 378 in.
tion valve above closure--reactor vessel low ~ater level zero Amendment No.
89
" 13
~ I I ~
oil pressure at the main turbine control valve actuator disc dump valves>s This 1'oss of pressure is sensed by pressure switches ~hose contacts form,.:
the one-out-of-two-twice logic input to the reactor protection system.
This trip setting,.a -nominally 50K greater closure time and a different valve'characteristic from that:.of the turbine stop valve, combine to
-~:r<<
produce transients very similar to that for.the stop valve.
Relevant transient analyses are'iscussed in References 1 and 2.
. IThis scram is bypassed when turbine steam flow is below 30K of, rated, as measured bv the turbine first staae nressure.
p (DELETED)
G 6
H.
Hain Steam Line Isolation on Low Pressure and Main*Steam Line Isolation Scram The low pressure isolation of the main steam lines at 850 psiq was provided to protect against rapid reactor depressurization and the resulting rapid cooldown of the vessel.
Advantaqe is taken of the scram feature that occurs when the main steam line isolation valves are closed, to provide for reactor shutdown so that high power operation at low reactor pressure does not occur, thus providing protection for the fuel cladding integrity safety limit.
Operation of the reactor at pressures lower than 850 psig requires that the reactor mode switch he in the STARTUP Amendment No.
89
t
~
~
n T<RLF 3. 1.g (cont F 4)
T +)OR STSTF~, ( CRg'() lMSTRUtKA>T(OH RFOOTRFHFRT tu rd
. ~
O Clninus Hunbcr sC Operable fnstru=cnt hanncls Per 23 Tri Function High Mater Level ln Fast Scran Discharge Tatdc (LS85-45F H) thin Stean Line Isolation Valve Closure Turbine Control Valve Past Closure or Turbine Trip Tri Level Scttln
< 50 gallons c
10 percent valve closure s 550 psig Nodes in Mhlch Function Hust be 0 crablc Startup/Hot dh Idol
~heduet I
~tt dh tun 'totten
'I X
X(8)
X
).g X(6) 1.l or 1.C X(4) 1 A or 1.D Turbine Stop Valve Closure c
)OX Valve Closusc X(g) l.a or 1.0.
Tusblnc First Stage Prcsstdrc Pcrdclss ivc not i ~ 154 pslg X(18)
X(18)
X(18)
(19)
Hain Stoats Linc High Radiac Ion (IC) 3X Homal Full Poucr SackgrounJ (20)
X(9)
X(9)
X(9) 1.A or 1.C
~u I ~
d f I
~
~
TADLL 4 ~ 1vh REACTOR PROTKCTIOtl SYSTEM (SCRAM} 1MSTRUHEMTAT1OH FUHCT10MAL TESTS HI<<LOOM FulCTIO!lhL TEST FREOUG!clKS lOll SAFETY IllSTR~ hltD Co!ITROL CIRCUITS
~Crov
. I Functional 'fest Hininun Frequency IJ)
Hode SMitch in Shutdovn Hanual Scrag IRHlligh Flux place Mode sMitch In shutdovn Each Reluellng outage Trip Channel and hlara Every 3 Hontlis Trip Channel and hlarn
)4)
'nce Per Meek During Retuellng and before Each Startup Inoperative APRM lligh Flux (1SX.scran)
})Igloo Flux (Flou )}i<<sod)
<<igh Flue (Fixed grip) u Inoflerative Douns ca le Flou blas Ifigh Reactor Pressure High Dryuell Pressure Reactor Lov Mater Level lllgh Mater Level in Scraa Discharge Tank F}not.SM) tclics (I.S-85-45C-I')
Eluctronic Leva} Sul tchcs (LS-85-45h, fl, C, lf)
C 8
B h
8 Trip Channel and hlara (4)
Trip Output Relays (4)
I v$ "~
Trip Output Rciays (4)
Trip Output Relays If)
Trip Output Relays (4)
Trip Output Relays (4)
I6)
Trip Channel and fliara Trip Channel and hlara Trip Channel and hlara Trip Chnnn<<l and A)err~
I'rip (:harm<<l nncf hl;lra (I)
Once Pcr Meek During Refueling and Before Each Startup before Each Startup and Meekly Mhen Required to be Operable Once/Meek once/utep Once/Meek "I
Once/Meek I6}
Once/Honth Onco/Honth Once/Month Once/.'font h Cocci: lontll
TABLE 4
- 1. B REACTOR PROTECrION SYSTEM (SCRAH)
INSTRUHENT CALIBRATION HINIHUH CALIBRATION FREQUENCIES FOR REACTOR PROTFA:TION IHSTRUHENT CHANNELS Instrument Channel IRH High Flux APRH High Flux Output signal Flow Bias Signal LPRH Signal Group (1)
C B
B B
calibration Comparison to APRH on Control-stsrtups (6) r Heat Balance Calibrate Flow Bias Signal (7)
TIP System Traverse (8)
Hinimum Frequency (2)
Note (4)
Once. every 7 days Once/opera):ing cycle Every 1000 Effective Full Power Hours High Reactor Pressure High Drywell Pressure Reactor Low Mater Level Standard Pressure Source Standard Pressure Source Pressure Standard
~
Every 3 Honths Every 3 Honths Every 3 Honths Hish Mater Level in Scram Dischar8e Voluse Float Switches (LS-85-45C F)
Electronic Level Switches (Ls a, 8, G, H)
B Cali'brated Ma'ter Colucn (5)
Calibrated Mater Coluoo Note (5)
Once/Opcrstln8 Cycl c (9)
Hain Steam Line Isolation Valve Closure Hain Steam Line High Radiation Turbine First Stage Pressure Permissive
')urhlne Cnnt. Vilve Fast Closure or Turhine Trip Turbine Stop Valve Closure B
A h
Note (5)
Standard Current Source (3)
Standard Pressure Source Standard I'ressure Source Note (5)
Note (5)
Every 3 Honths Every 6 Honths once/ope('at)ng cycle Note (5)
vhich a ecraa mall be required but not be able to perforN its function adequately.
A source range monitor. (IRM) system is also provided to supply additional neutxon level.inforaation during staxtup but hae no scram functions Ref Section 7 5 4 tSAR Thus, the IRM ie required in the Refuel and Staxtup modes, In.the parer range the APRM eyetaa provides repaired protection Ref Section 7 ~ 5 7 tSAR Thus, the IRM Systea ie not required in the Run aode The APRM's and the IRM's provide adequate coverage in the startup and 9,nteraadiate range~
The high reactor pressure, high drprell pressure, reactor low star level and scram discharge volume high level scrams are required for Startup and Run aodae of plant operation.
They are~
therefore, required to ba operational for these modes of reactor operation.
The requirement to have the scram functions aa indicated in Table 3.1 ~ 1 operable in the Refuel aodo ie to assure that shifting to the Refuel neda during reactor pc.mr operation does not diad.nish tha need for the reactor protection eystea Because of the APRM demscale lied.t of h 3g shan in the Run mode and high level limit of 5 15% +hen in the Startup Mode, the transition bet~can the Startup and Run Modes must. be made arith the APRM instrumentation indicating between 3% and 15% of rated pen<ax oz a control xod screw vi11 occur In addition, the IRM system must ba indicating baloee the High tlux setting (120/t25 of scale) or a scram vill occur vhen in the Startup Mode For normal operating conditions, thaea limits provide assurance of overlap between the IRM systeaa and APRM syetea so that there are no "gapa" in the pc+ax level indications (i e., the peeer level ie continuously monitored froa beginning of startup to full parer and frol full parer to shutdee).
Shen purer ie being reduced<
if a transfer to the Startup Node is made and the ZRMI s have not been fully inserted (a aaloperational but not impossible condition) a control rod block isunadiately occurs so that reactivity insertion by contxol rod withdrawal cannot occur~
Amendment No. 89 43