ML18029A491
| ML18029A491 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/05/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML18029A492 | List: |
| References | |
| DPR-33-A-116, DPR-52-A-111, DPR-68-A-086 NUDOCS 8504250037 | |
| Download: ML18029A491 (39) | |
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+p*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
'I TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
116 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 October 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
- CFP, 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:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and B,
as revised through Amendment No. 116, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8504250037 850405 PDR ADOCK 05000259 P
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3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 5, 1985 Domeni c 8. Vassal 1 o, Chi ef Operating Reactors Branch h'2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO. 116 FACILITY OPEPATING LICENSE NO.
DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
).
Remove the following pages and replace with identically numbered pages.
57, 58, 59, 60, 61, 86, 88, 109 2.
The marginal lines on these pages denote the area being changed.
()
~linis.ua No.
Instrument Channels Operable
.~er Tr'o c;s(l)Il; Remarks Action HorF
,ri Level Setti 1.
Belov trip setting prevents spurious trips and system pertur-hations frow initiating isolation Reactor Building Isolation Timer (refueling floor)
~
0
< t 5 2 secs.
TABLE 3 ~ 2 A
PRIMARY CONTAINMZtP'NO RKACTOR BUILDING ISOLATION INSTRUYZNTATION Reactor Building Isolation 0
< t 5 2 secs.
Tiwer (reactor zone)
GorA or B 1.
BeloM trip setting prevents
'purious trips and system pertur-bations frow initiating isolation (10)
Croup 1 (Initiating) Logic N/A Croup 1 (Actuation) Logic NIA 1.
Refer to Table 3.7.A for list of valves.
1.
Refer to Table 3.7.A for list of valves.
Minimum No.
Instrument Channels Operable D)>>
Funct io Tri Level Settin Action 1
TABLE 3 ~ 2 A PRIMARY CONTAINNENT AND REACTOR BUILDING ISOLATION INSTRUHENTATION Remarks Group 2 (Initiatin ) Logic N/A Group 2
(RHR Isolation-Actuation) Logic Group 8 (Tip-Actuation)
Logic A or (B and E) 1.
Refer to Table 3.7.A for list of valves'.
Group 2 (Drywell Sump Drains-Actuation)
Logic Group 2 (Reactor Building 5 Refueling Floor, and Dry-vell Vent and Purge-Actuation)
Logic N/A N/A F and G
1.
Part of Group 6 Logic.
Group 3 (Initiating) Logic N/A Grou p 3 (Actuation) Logic N/A 1.
Refer to Table 3.7.A for list of valves.
Group 6 Logic N/A F and G
1.
Refer to Table 3.7.A for list of valves.
Group 8 (Initiating) Logic N/A Reactor Building Isolation N/A (refueling floor) Logic Reactor Building Isolation N/A (reactor zone)
Logic HorF H or G or A 1.
Refer to Table 3.7.A for list of valves.
2.
Same as Group 2 initiating logic.
..inly..us~
.'.p, TABLc. 3.2.A PRINARY CONTAINHENI'ND REACTOR BUILDING ISOLATION INSTRUNENTATIOH O
Instrurent Channels Operable U-i vel Sett n
c on 1
Reamrks
~
1(7) (8)
SOTS Train h Ingle CXl 1{7) (8)
SGTS Train 8 Logic 1(7) (8)
SGTS Train C Itic N/A L or (h and F)
L or (A and F)
L or (h and F)
Refer to Table 3.2.8 for RcIc and Hpcl functions including Groups 4, S, and 7 valves
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HATES FOR TAbLE F 2.A 1.
Mhencver che respective functions are required to be operable, chere shall b>> tvo operable or tripped trip systems fot each funrcfon.
tf chc fitat colurst cannot be ~c for one of thc trip systems, thee eris sydcea or logfc for that funccfon shall be tripped (ot'he appropriate action listed below shall be Caken).
If the coiean cannot br tI>>c for all ttfp syscaus
~ the apptoptfate action listed below shall be taken.
A.
Initiate sn ordatly shucdovn snd have the reactors fn Cold Shutdovn Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b.
Iniciscc an orderly load reduction and have Main Sceara Lines isolated vfthin
~ ikht hnurs.
C.
Isolate Reactor ltaccr Cleanup Syscets.
V.
Isolate Shutdovn Coolfag V..
Iniciscr primary cnncairuieac isolation within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
F, The hsndfing of spent fuel will be prohibited and all operatfotis over spent fuels snd opaa reactor wells ohall be prohibited.
G.
Idolsce the reactor building and start the scandby gas tteatstent r
sydt>>%
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X.
Iersediacely perfortd a logic systetd functional eeet on the logic in che other trfp a/dtesLdaad daily thereafter not to exceed 7 days.
DELETE
.i.
Mithdrdv TIP.
Ksnually isolate the af(ected lines.
Refer to section 4.2.K for t.hc cqufzrmtrtcd of sn inoperable.
system.
L. ff one st'.'I."> t,rain is fttupcrablc cake actions X nr dccfon A and F.
If t'uo s('I train i orc innpct able cnkc act Irma A ttnd F
2, when ic is dcccmfned that
~ channel
$ s faflecf in chc unsafe condition, thr ocher chhnnrfu chsc monfcot the ssae variable shall be functionally te ~ Ced fcvoediately before the trip systerI Or logic for that tunccion id tripped.
The trip dydterI Or the logic for that function stay redtaln uncrfppcd fot short periods of t&o to allow functional Cesting of thc r thrr trip dysccti or logic fot that funcCioa.
3.
There are four ':u>>::ut'H per steam line of which tvo tcust be opec'able.
4.
Only rcqulrcd in Run Kode (interlocked with Mnde Svitch).
S.
Hoc r>>quired fn Run Mode (bypassed by tsode switch)
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60 Amendment No.
116
\\
6.
Channel shared by RPS and Primary Containment 6 Reactor Vessel Xsolation Control System A channel failure may he a
channel failure.in each system.
7 A train is considered a trip system.
8.
Two out of three SGTS trains required.
A failure of more than one ~ill require action A and P.
g.
(Deleted) 10.
Refer to Table 3.7.A and its notes for a listing of Isolation Valve Groups aad their initiating signals.
required surveil a A channel may be'placed in aa inoperable status For up t f
l f
o our
>ours or lance Mithout placing the trip system in the tri.
ed condition provided it least one OPERABLH ha n
~e tr ppe is monit i h
or ng t at parameter.
. c aanel in the same trip system 12.
h channel contains four sensors, all of crhich must be operable for the channel to be operable.
Pover operarioas p~'tted =or up ta 3p t~era=we r~ t=ees operable.
days ~th L3 of me '6 En the event that normal ventilation is unavailable in the main steam line tunnel, the high temperature channels may be bypassed for a period of not to exceed four hours.
During periods Mhen normal ventilation is not available, such as during the performance of secondary containment leak rate tests, the control. room indicators of she affected space temperatures shall be monitored for indications of
>mall steam leaks.
Zn the event of rapid increases in temperature (indicative of steam line break),
the operator shall.promptly'close'he main steam line isolation valves.
1..he aom.nal serpoints Eor alarm and reactor trip (1.5 and 3.0 times ac ground, respecrively) are established based oa he ao..ul back" pover.,
The alloMable setpoints for'larm and reactor t='p are 1.2-1.B and 2.4-3.6 tines backgrouad, resaectively.
61 Amendment No. 116
o TABLE 4 ~ 2 A SORVEZILAHCE RIQOIREKEHTS POR PRIHART COHTAIHHENI'ND REACTOR BUILOIHQ ISOLATION IHSTRQHENPATIOH
~nc~torL Znstruaent Channel-Reactor Building Ventilation High Radiation Refueling Zcee Instruaent ChanneL-SGTS Train A Heaters Instrunent Channel-SGTS Train B Heaters Instrusent ChanneL-SCTS Train C Heaters Reactor Building Isolation Tlaer (refueling floor) o a
e (il (> ~) (22)
(4)
(4)
Cal b ation Pr uen once/I aonths once/operating cycle nstruaent Check H/A Reactor Building Isolation Tiaer (reactor xone)
(4) once/operating cycle Hlh
TABLE a+2~A SORVEILIAHCE RBQQIREHEHTS tOR PAINARy COÃTAIHNENT ANC ~~R BUILDING IQ)LATIOH IHSTAQKEHTATIOH yunction Orcup 6 Logic croup S (lntt)sting)
Logic unct(ona1 Test once/operating cycle (16)
Checked during channel functional teste No further test requtse4.
Cal ibratton Fr
~ucnc Hlh Inst rusent Check H/A N/A Reactor Buil4)ng Isolation
( afueling floor) Logic Reactor Bu(14ing Isolation (reactor xone) Logic SGT5 Train A Iogic SCT5 Train 5 Logic SOTS Train C Logic once/6 o nths (18) once/6 eonths (1$ )
once/6 sonths (19) once/6 eonths (19) once/6 eonths (19)
(6)
(&)
H/A H/A
'H/A Inetruacat Channel-Saactor Clesnup S~
tloor Orain High Tenperature Instruaent Channel-Saactor Cleanup Syotea Space Sigh Teaperature (13)
RTQ l b.
Twperature Su( tcb oooe/operating cycle once/operatinq cycle
(
)
(once/o per sting cycle)
(
)
H/A
I I
- !':TYt: FQ:?
TARL:-:" 4.2.h THROUGH 4.2.H F>>~cr i'i>>>>'. tes' shall be perfoz'med once pcl month.
2.
Functional tests shall be performed before each startup vf?;h a required fzequ ncy not o exceed once per veeh.
".'his inst. umenta.ion is excepted from the functional test definftfan.
he functionc'est vill consist of in)ec'in@ a simulated electrical sign"1 into the measurement channel.
L.
Tested during lo-"ic syrtem functional tests.
5.
Refer to Tcble 4.1.B.
6.
h?. logic syste".unc.ioncl ests shall include a calibration o.-.ce per op.sting cvcle of tine delay relays and timers necesscry fc. propez functioning of the trip systems.
The functional tes. vill consist of verifying continunity aczoss the inhibit vith c volt-ohmmeter.
8.
nstrumen.
ch ck shall be performed in cccozdance vith the definftio>>
of Instrument Check (see Section 1.0, Definitions).
An instrument check is not applicable to a particular setpoint, such as Upscale, but fs a qualitative check that the instrument is behaving and/or indicating fn cn acceptable s<<oner for the particular plant condition.
Instrument check fs included in this table for convenience and to indicate that an Inst. umen Check vill be performed on the instrument.
Instrument checks are nat required vhcn these instruments are not required to be operable or a. e tripped.
9.
Calibration frequency shall be once/year.
DELETE ll.
Por fan of.he logic is functionally tested during outage only.
T1,e Qe ector vill be inserted during each operating cycle and the proper amount of travel into the coze verified.
13.
Functianal test vill consist of applying simulated inputs (see note 3).
Loca'larr. lights representinC upscale and dovnscale trips vill be verified, but no rod block vill be produced at this time. 'he inopera-tive trip vi'1 be initiated to produce a rod black (SRh) cnd IR'i inoperative a)sc bypassed vith the mode svitch in RUG).
The functions that cannot be verified to produce a rod block directly vfll be verified du ing the opera.'g
- cycle, 109 Amendment No.
116
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROMNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
111 License No.
DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated October 19, 1984, complies with the standards and requirements of the Atomic Enerqy Act of 1954, as amended (the Act},
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
C.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; 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. 111, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCI EAR REAULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 5, 1985 Domeni c B.
Ya ss a 1 1 o, Chi ef Operating Reactors Branch ¹2 Division of Licensing
ATTACHMFNT TO LICENSE AMENDMENT NO. ill FACILITY OPERATING LICENSE HO.
DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
57, 58, 59, 60, 61, 86, 88, 109 2.
The marginal lines on these pages denote the area being changed.
Hinimum No.
Instrument channels Operable TABLE 3+2+A PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION Fu ction Reactor Building Isolation Timer (refueling floor)
Tri Level Setti 0
< t < 2 secs.
HorF Remarks 1.
Below trip setting prevents spurious trips and system pertur-bations from initiating isolation Reactor Building Isolation 0 < t S 2 secs.
Timer (reactor xone)
GorA or H 1.
Belou trip setting prevents spurious trips and system pertur-bations from initiating isolation 2 (1Q)
Group 1 (Initiating) Logic N/A Group 1 (Actuation) Logic N/A 1.
Refer to Table 3.7.A for list of valves.
1.
Refer to Table 3.7.A for list of valves.
'Hinimum Ko.
. Instrument Channels Operable ct io Tri Level Settin Action 1
TABLE 3' A
PRIMARY OBTAINMENT AND REACTOR. BUILDING ISOLATION INSTRUMENTATION Remarks 2
Group 2 (Initiatin.) Logic N/A A or (B and E) 1.
Refer to Table 3.7.A for list of valves.
Group 2
(RHR Isolation-Actuation) Logic Group 8 (Tip-Actuation)
Logic Group 2 (Drywell Sump Drains-Actuation)
- .oqic N/A N/A Group 2 (Reactor Building N/h 5 Refueling Floor, and Dry-well Vent and Purge-Actuation) Logic F and G
1.
Part of Group 6 Logic.
Group 3 (Initiating) Logic N/A Group 3 (Actuation) Logic N/A C
1.
Refer to Table 3.7.A for list of valves.
Group 6 Logic N/A FandG 1.
Refer to Table 3.7.A for list of valves.
Group 8 (Initiating) Logic N/h Reactor Building Isolation N/A (refueling floor) Loqic Reactor Building Isolation N/A (reactor xone)
Loqic HorF BorG or A 1.
Refer to Table 3.7.A for list of valves.
2.
Sane as Group 2 initiating logic.
Nini.-..ug lnstrunent Channels Operable TABLR 3.2 A
PRIHARY COSThlhMKRT h:~ ABACTOR BUILGING ISOLATION IHSTRUlCBÃTATIOH Level Settin g (7) (Q)
SGTS Train A logic SGTS train B Logic 1(7) (8)
SOTS Train C Logic
- </h
'.e/h L or (h and F]
L or (h and F)
L or (h and F)
Refe to Table 3.2.B for RCIC and HPCI functions includinq Groups 4, 5, and 7 valves.
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HOTES FOIL TAbIC 3'.A I,
Mhencver che respective functions ate requited to be operable, there shall be tvo operable or tripped trip systems for each function.
tf che first column cannot be sec tor one of the trip system s, that trip syscca or logic for that function shall be tripped (or the appropriate action listed belov shall be taken).
If the coLean cannot be aet for all Crip sysceas, the approptiate action listed belov shall be taken.
A.
Initiate sn orderly shucdovn and have the reactors in Cold ShutdoMn Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.
Initiate sn orderly load reduction and have Hain St<<<<a Lines iso la c ed uithin eight hours.
C.
Isolate Reactor Mater Cleanup Systea.
O.
Isolate Shutdovn Cooling K.
Initiate primary contsinacnc isolation vithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
P, The handling of spenC fuel vill be prohibited and ail operations over spent fuels sod open tssctot veils shall be prohibited.
O.
Isolate the reactor building and start the standby gas Cteataenc systeh>>
N, Inssediately psrfora a logic aystea functional test on the logic in the other crip
<<tea<<sad daily thereafter not to exceed 7 days.
DELETE
.i.
Mithdrsv TIP.
2
~
R>>
annually isolate the affected lines.
Refer to section 4.2.K for che tcquizemtfics of an inoperable. syetea.
L.
tt one soa5 train is inoperable take actions H or action A and F.
If cuo SGTs trains are inoperable take actions A and F
1&en it is deterrained that
~ channel is failed in the unsafe condition, che ocher channels that aonitot the saae vatiablc shall be. functionally cested iascdiately before the trip systea or logic for that function is
. tripped.
The trip system oc'he logic for Chat function may tea<<in uncripped for short periods of tiae to allov functional testing of thc c cher trip systea or logic for that function.
3.
There <<re four gc:nnnrq p<<r
~ teaa line of vhich tvo aust be operable.
4.
Only required in Run Node (interlocked vith Hode Svitch).
N 5.
Hot required in Run Node (bypassed by aode svitch).
60 Amendment No.
111
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6.
Channel shared by RPS and Primary Containment 6 Reactor Vessel Isolation Conrrol System.
A channel failure may be a
channel failure in each system.
7, A train is considered a trip system.
8.
Two out of three SGTS trains required.
A failure of more than one will require action A and F.
(Deleted) 10.
Refer to Table 3.7.A and its notes for a listing of Isolation Valve Groups and their initiating signals.
ll.
A channel may be placed in an inoperable status for up to four hours for required surveillance without placing the trip system in the t&pped condition provided at least one OPERAGLK channel in the some trip system is monitoring that parameter.
12.
A channel contains four sensors, all of which must be operable for the channel to be operable.
Power operations permi ted for up to 30 days with 15 of ihe 16 temperature 'witcnes operable.
Zn the event that normal ventilation is unavailable in the main steam line tunnel, the high temperature channels may be bypassed for a period of not to exceed four hours.
During periods when normal ventilation is not available, such as during the performance of secondary containment leak rate tests, the control room indicators of
- he affected space temperature es shall be monitored for indications of
>mall steam leaks.
Zn the event of rapid increases in temperature (indicative of steam line break),
the operator shall. promptly close the main steam line isolation valves.
13..The nominal setpoints for ala d
background, respectively) ar
'is arm an reactor tri (1.5 a
'p
(.
and 3.0 times round at full pow r Th o
are established base e.
e owable se o
on tne normal bock-tpoints for alarm and reactor
~
an
. -3.6 times background, respectively.
Amendment No. ill 61
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VE LLAHCE R)r)QIBEHEHTS POR PRINART COHTAIIOLEHT AHD REACTO TABLE a 2.A REACTOR BUILDING ISOLATIOH INSTROHEHTATION Ql~llC 0
Inetruaent Channel Reactor Su))ding Ventilatice Biqh Radiation - Refuelinq Eche Inetrunent Channel SOTS Train A Beatere Inetruaent Channel-SCTS Train $ Beatere Inetruacnt Channel-SCTS Train C Beatere Reactor Build)ng Isolation Tiner {refueling floor) un o
a est l')) ll~) (32) le) al brat)on Fr uen once/3 nonths once/operating cycle netruaent Cheek H/A Reactor dul)ding Isolation Tiner (reactor tone) once/operat inq cycle
O TABLE aeIeA SUPVEILLAl'CK REQOIRlHQITS POR PRIMARY COW'Ait0%8tlr ANO RSACTOR SOILOING ISOLATIGS IHSTRONEHPATION Punctron Group 6 Logic croup 8 (Inrtrating)
Logic Reactor Bui lding Isolation (retuelrng tloor] Logic Reactor Buildinq Isolation (reactor rone)
Logic SCTS Train A Logic SCTS Train 8 Logic SOTS Train C logic Iunct rona I Test once/operatinq cycle (18)
Checked during channel tunct iona 1 test.
Ho turther test required.
once/6 nonths (18) once/4 aonths (18) once/6 nonths (19) once/6 nonths (19) once/6 nonths (19)
Calibratron Pr uenc H/h (6)
(6)
'.l/A Instrument Check M/A 11/A
)1/A
)I/A Inatruaent Channel-Reactor Cleanup Systea tloor Drain High Tenperature Instrunent Channel Reactor Cleanup System Space Sigh Tesperature (23)'TO b.
Teeperature Svitch oooe/operating cycle once/operating cycle
(
)
(once/o pera ting cycle)
(
)
I e'/(Y S FOR TAB~ 4.2.A TiiROUGH 4.2.H 1.
Func.iona.
tests shall be perfarmed once per month.
2.
Functioral tes s sha'1 be performed before each startup vith a required frequency not to exceed once per veek.
3.
This fnstrumentatian is excepted from the functianal test definition.
The functianal test vi'1 consist af inJectfng i simulated electrical signal 'nto the measurement channel.
4.
Tested during logic system functional tests.
5.
Refe. to Table 4.1.B.
6.
The logic system functional tests shall 'nclude a calibration once per operating cycle of time delay relays and timers necessary for prope.
.unctioning of the trip systems.
The functional test vill cansist of verifying continunity across the inhibit vfth a volt>>ohmmeter.
8, Ins rument, checks shall be performed fn accordance vith the deffnftfon
- o. Instrument Check (see Sectian 1.0, Deffnitfons).
An instrument check is not applicable to a particular setpoint, such as Upscale, but is a qualitative check that the instrument is behaving and/or fndfcating in an acceptable manner for the particular plant condition.
Instrument check fs fncluded in this table for convenience and to indicate that an Instrument Check vill be performed on the instrument.
Instrument checks are no. required vhen these instruments are not required to be operable or are tripped, 9.
Calibration f. equency shal'e ence/year.
DELETE 1'.
Portion of.he logic is fume ion. ly tested 4uring outage only.
12.
The detector vill be inserted dur'ng each operating cycle and the proper anount of travel intc he core verified.
13.
Functional test v'll consist of applying simulated inputs (see note 3).
Local alaw lights representing upscale and dovnscale trips vill be verified, but no rod black vill be produced a. this time.
The inopera-tive trip vi'1 be initiated to produce a rod block (SRM and IRM inoperative also bvpassed vith the node svftch fn RUl<).
The functions that cannot be verif'ed to produce a rod block directly vill be verified during the op rating cycle.
109 Amendment No. ill
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEF.
VALLEY AUTHORITY DOCKET NO. 50-296 BROMNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
86 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 October 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-68 is hereby amended to read as follows:
(2)
Technical S ecifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.
86, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance.
FOR THE HUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 5, 1985 Domeni c B.. Vassal 1 o, Chi ef Operating Reactors Branch k'2 Division of Licensing
ATTACHMENT TO LICENSE AMENDNFNT NO. 86 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.
59, 60, 61, 62, 63, 89, 91, 106 2.
The marginal lines on these pages denote the area being changed.
Hinimum No.
Instrunent
'hannels Operable TABLE 3 2 h PRIMARY CONTAINHERI AND REACTOR BUIid)ING ISOLATION INSTRUHENTATION Tri Lev Sett i Reaarks Reactor Building Isolation Tiier (refueling floor) 0 N t 5 2 secs.
HorF I
Belch trip setting prevents spurious trips and systew pertur-bations fron initiating isolation Reactor Building Isolation 0
S t I 2 secs.
Tiaer {reactor xone)
G or h or 8 1.
Below trip setting prevents spurious trips and systes pertur-bations fros initiating isolation 2 (10)
Group 1 (Initiatinq) Logic N/h Group 1 (Actuation) Logic N/h 1.
Refer to Table 3.7.A for. list of valves.
1.
Refer to Table 3.7.A for list of valves.
~)finimum No.
Instrument Channels Operable TABLE 3'.A PRIMARY COHTAIHHEHT AND REACTOR BUILDING ISOLATION IHSTRUMEHTATION Funct io Tri 'Level Settin 2
Group 2 (Initiating) Logic N/A Action 1
A or (B and E)
Remarks 1.
Refer to Table 3.7.A for list of valves.
Group 2
(RHR Isolation-Actuation) Logic Group8 (Tip-Actuation)
Ingle Group 2 (Dr@veil Sump Drains-Actuation)
Logic Group 2 (Reactor Building 6 Refueling Ploor, and Dry-vell Vent and Purge-hctuation)
Logic N/A N/A N/A F and G
1.
Part of Group 6 Logic.
S.
1 Group 3 (Initiating) Logic H/A Group 3 (Actuation) Logic N/h Group 6 Logic N/A Group 8 (Initiating) Logic N/A Reactor Building Isolation N/A (refueling floor) Logic Reactor Building Isolation N/h (reactor xone)
Logic P and G
HorF HorG or A 1.
Refer to Table 3 7.A for list of valves.
1.
Refer to Table 3.7.A for list of valves.
1.
Refer to Table 3.7.A for list of valves.
2.
Sane as Group 2 initiating logic.
)linimum No.
Instrument
'hanne1s Operable 1(7) (8)
SGTS Train h Logic ction 1
i I.ev I Se t L or (h and F)
L or (h and F)
L or (A and F)
"1(7) (8)
SGTS Train B Eagle 1(7) (8)
SGTS Train C Iagic H/A TABLE 3.2 h PRZHARY COHTAINHENT AND REACTOR BUILDING ISOLATION IHSTRUMEHTATION Remarks Refer to Table 3 2.B for RcIc and BpcI functions includlnq Groups a, 5, and 7 valves.
NOTES FOR TABLE 3 ~ 2 A
l.
whenever the respective functions are required to be operable, there shall be two operable or tripped trip systems for each function.
I If the first column cannot be met cr one of the trip
- systems, that trip system or logic for that function shall be tripped tor the appropriate action listed below shall be taken)
If the column cannot be met for all trip systems, the appropriate action listed belo~ shall. be taken.
A.
Initiate an orderly shutdown and have the reactor in
.. Cold Shutdown Condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
B.
Initiate an orderly load reduction and have Main Steam Lines isolated within eight hours.
C.
Isolate Reactor Mater Cleanup 'System.
D.
Isolate Shutdown Cooling.
E.
Initiate primary containment isolation within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
F.
The handling of spent fuel will be prohibited and all
~
operations over spent fuels and open reactor wells shall be prohibited.
G.
Isolate the reactor building and start the standby gas treatment system.
H.
. Immediately perform a logic system functional test on the logic in the other trip systems and daily thereafter not to exceed 7 days.
I DELETE J.
Withdraw TIP.
K L.
Manually isolate the affected lines.
Refer to section Q.2. E for the requirements of an inoperable system.
If one SGTS train is inoperable take actions H or action A and F. If two SGTS trains are inoperable take actions A and F.
2.
Mhen it is determined that a channel is failed in the unsafe condition, the other channels that monitor the same variable shall be functionally tested immediately before the trip system or logic for that function is tripped.
The trip system or the logic for that function may remain untripped for short periods of time to allow functional testing of the other trip system or l'ogic for that function.
Amendment No.
86
l s
~
~
1
~
(
I 3.
There are four channels
.per steam line of which two must be operable.
4.
Only required in Run Mode (interlocked with Mode Switch).
0 5.
Not required in Run Mode (bypassed by Mode Switch).
6.
Channel shared by RPS and Primary Containment 6 Reactor Vessel Isolation Control System.
A channel failure may be a channel failure in each system.
7.
A train is considered a trip system.
B.
Two out of three SGTS trains required..
A failure of more than one will require actions A and F.
(Deleted) 10.
Refer to Table 3.7.A and its notes for a listing of Xsolation Valve Groups and their initiating signals.
11.
A channel may be placed in an inoperable status for.up to Cour hours for required surveillance/maintenance without placing the trip system in the tripped condition provided at least one OPERABLK channel in the same trip system is monitoring that parameter.
12.
A channel contains four sensors, all of which must be operable for the channe1 to be operable.
2ove" operations pa
=t d for up to 30 days v'th U o-the 15 t~e=a~c'sA t&es operablo.
Zn the event that normal ventilation is unavailable in the main steam line tunnel, the high temperature channels may be bypassed for a period of not to exceed four hours.
During. periods when normal ventilation is not available, such as during the performance of secondary containment leak rate tests, the control room indicators of the affected space temperatures shall be monitored for indications of small steam leaks.
Zn the event of rapid. increases in temperature (indicative of steam line break),
the operator shall promptly close the main steam line isolation valves.
13 ~
The nomina1 serpoints for alarm and reactor trip (L.5 and 3.0 times background, respectively) are established based on the no..al baci.-
grousd at Evil power.
The allowable setpoints for aia~ and reactor trip are 1.2-1.8 and 2.4-3.6 thos background, respec ively.
63 Amendment No.
86
TLSLS a+1 L SQRYKILLAMCS RSQQIRSMSMTS yOR PRIMARY CXIMTLIMMSMTLMD RSACTOR SQIIDIMG ISOLATION XMSTRQMENTLTION Instcu<<ent Channel-Reactor Building Ventiletiaa Sigh Radiation - Refueling Xcae Instraacat Channel-SGTS Train L Seatecs Instrunent Channel-SGTS Train B Rosters Instcu<<cnt Channel-SGTS Train C Seateca Reactor Build)nS Isolation Tl<<er (cetueling Ilooc)
(1) (1II) PI) la) lal la) once/3 <<onths once/operating cycle net u<<ant Check once/day (S)
N/A Raactoc Build)ng Isolation Ti<<er (reactor acne) once/oparatiny oycle
t
~
r ~
TABLE 4 I A SORVRIILANCE RRQOIRENENTS yOR PRINARY ColffhIHCfÃyARD REACTOR BOILDING ISOLATION INSTRUNENTATION function cxoup 6 Logic Croup 4 (Initiating) ~ic Reactor Building Isolation (refueling floor) logic Reactor Building Isolation (reactor xone) Logic SOTS Train A Logic SOTS Train 5 Logic
~ Train C Logic functional Test once/operating cycle (14)
Checked during channel functional test.
No further test requited.
once/6 sonths (14) once/6 sonths (14) once/6 nonths (19) once/6 nontbs (19) once/6 nonths (19)
Calibraticn tr N/A (6)
(6)
Instrusent Check N/A N/A
'I Instrunent Channel-Rsactor Cleanup System tloor Drain Sigh Tenperature Instruaent Channel-Reactor Cleanup System Space Sigh Tesperature (23) onceloperating cycle ao RTQ h
Tenperature Switch
(
)
(once/operating cycle)
(
)
1 ~
2 ~
31 4i 5
S FOR ABLS 4 2
A THROUGH 4
2 H
tunctional tests shall be performed once per month.
Functiuml tests shall be performed before each startup vith a required frequency not to exceed once pcr vesk This instrumentation is excepted from the functional test definition.
The functional test villconsist of infecting i simulated electrical signal into the measurement channel.
Tested during logic system functional tests.
Refer to Table 4.1 B.
6 ~
7 ~
The logic system functional tests shall include a calibration once pcr operating cycle of time delay relays and timers necessary for proper functioning of the trip systems The functional test vill consist of verifying continuity across the inhibit with a volt-ohmmeter.
Si 9o
(~0.
11 12 ~
13 ~
Instrument checks shall be performed in accordance vith the definition of Instrument Check (sec section 1.0, Definitions).
An instrument check is not applicablc to a particular sctpoint, such as Upscale, but is a qualitative check that the instrument is behaving and/or indicating in an acceptable manner for thc particular plant condition.
Instrument check is included in this table for convenience and to indicate that an Instrument Check will be performed on the instrument.
Instrument checks arc not required vhcn these instruments are not required to be operable or are tripped.
Calibraticn frequency shall be ance/year.
DELETE Portion of the logic is functionally tested during outage only.
The detector vill be inserted during each operating cycle ind, the proper amount of travel into the core verified.
?unctional test villconsist of applying simulated inputs (scc note 3).
Local alarm lights representing upscale and downscale trips vill be verified, but no rod block vill be produced at this time.
The inoperative trip vill be initiated to produce a rod block (SR@ and IRM inoperative also bypassed vith the mode svitch in RUN).
The functions that cannot be verified to produce a rod block directly vill be verified during the operating cycle.
106 Amendment No.
86