ML18029A169
| ML18029A169 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/19/1984 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML18029A170 | List: |
| References | |
| DPR-33-A-113, DPR-52-A-107, DPR-68-A-081 NUDOCS 8410150499 | |
| Download: ML18029A169 (25) | |
Text
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++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 113 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 July 16, 1982, 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-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. 113, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
84fpf60 0500025+
499 8409f9 POR gDOCH pDR P
2 3.
This license amendment is effective as of the date of issuance.
Attachment:
Changes to the Technical Specifications FOR THE NUCLEAR REGULATORY COMMISSION
,I
~~~K....c~
Domenic B. Vassallo, Chief Operating Reactors Branch k'2 Division of Licensing Date of Issuance:
September 19, 1984
ATTACHMENT TO LICENSE AMENDMENT NO.
113 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.
37, 39, 181, 236, 244 2.
The marginal lines on these pages denote the area being changed.
tits I.1.1 tKACTOR PROTRCTLOH STSTGf (SCRAH) lrrSTRUHRAATION HNCTlouu. TRSTS HfÃflkIHflArCTLOHkL TRST PRKQUKHCIES,VOQ SAPEA lHSTR.
AHD COHTROl. ClRCUlTS
%Ac Svitch fn Shutdovn Manual Scree TRH Mfbh flux unctional Teat Place Hodc Suftch fn Shutdovn Trip Clrannel aod hlarrrr Trip Channel and Alarrs (4)
Hfnfaua fre ucac (3)
Each Retuelfng Outage Every 3 Hontha Once Per Meek Durfng Rcfuclfn
, and bc(ore tach Startup lnoperatf wa Trip.Channel and Alarrs (4)
Once tcr Meek Durfng Rctuclfn and before Each Startup LPRH Qfgh flux (lSI scrara) lliglr 1'lux (Plow Biased)
Bfgh flux (Fi.xed Trip)
Trfp Output Relays (4)
Trip Output Relays (4)
Trip Output Relays (4) before Cach Startup aod Mcckl Mhca Rcgufrcd to bc Operable Once/geek lnoperatfva Dounaca1a flew bfae Trip Output Relays (4) s.,'r
,I l
Trip Output Relays (4)
(6)
Once/Neck Once/Meek (6)
Qfbh Reactor treasure Qfgh Dryvell Prcssure Reactor Lou Mater LcI'e)
A Trip Channel and Alarrs I
Trip Channel and Alarrs Trip Clrannel and JL1arrs Once/Honth (1)
Once/Honth (1)
Once/Honth (11.
v lliglr Water Level irr Scram Disclrarpe Tank Float Switches (1.S-&5-45C-F) lligh i)ster Level in Scram Disclrarge Tank Electronic Level Switclrcs (LS-&5-45A, Br Gr ll)
Turbine Condenser l)ow Vacuum Hain Steam l.ine Ili&lr Radiation Trip Channel and Alarm Once/Honth Trip Channel and Alarm (2)
Once/Honth Trip Clrarrnel and Alarm Once/Hontlr (1)
Trip Clrannel and Alarm (4)
~
Once/3 Honthg (Q)
NOTRS
"..OR TABL= 4.l.h the minimum frequency for the indicated tests shall he once paz month.
2.
A description df the three t;roupy is included in thc Foses of'is specification.
Functional tests'zc not rcquircd when tha systamr
~r.
arne nrc not zeouireo to ha opcrablc oz are operntinp (i.a., already tripprd).
Tf tests azc
- missed, they shall be performed prior'tn rcturninr, thc syetcrns to an operable status.
This instrumcnration is esamptcd from thc ins rumant channel tcs" dct'inition.
This instrument channel funct'onal cast vi 1] consist of injcctinr a sinulatcd electrical si."ncl into tha mca"uzcmant channels.
(deleted) 6.
Qe functional test of the Qov bias necvork is.per=armed in accordance wf.th Table 4.2.C.
7.
Func"~onal test consists of the in)ection of a simulated signal into ke electronic t=ip circuitry in pIace of the sensor signal to ver'fy operabiIity of the t"ip end alarm functions.
The functional test frequency decreased to ance/')
months to reduce challenSes to relief valves per NUREG 0737, Item II.K.3.16.
39
(
Amendment No.,
1
~ 113
.TG CO~HZ GNS
=OR QPZ'3A'ION
~u- ~bNt H=QQ:~"~S
- 3. o.C Coolant Leakage 4.o.C Coolant Leakage 3 ~
Bath the s~
and a'" samnL~
systems shall be anerahle iu~~g eac or power operations and after the date Mt one of these systems is made or found to be moperable faz any reason, reactor power oaerat" an per~sible anLy dv mg "Ne suc seeing a ~ ~ou~s I
- he a'" sama~
system nay be remaved i~ serv'ce foz a pe~nd or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> roz caL'-
brat'an, functian testmg, acd tenance w"thou arav'dmg a: temnorary man'ar.
andi~
~a 1 o.
2 above cannot oe met, an orderly shutdown shall be initiated and the renctar sha3'e shut-Cold 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Relief Valves
~N"aen more than ane reei val'ves are known ta be failed, an orderly shutdmrn shaIL be ~mmt ed and the zeactaz depzessut ed ta Less than 105 ps'g wf.Min 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
J et Pumns t nenever the reactor is in the star
.zp ar ~ nodes, ~ jet pumps shall "oe oaerable.
'" is demafzed mt a jet p~
is moperable, oz
~U cwo or mre jet pump flow inst ~t utes occur and.Cannot be corrected vf.~ 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an orderly shutdawn shaLL be '"'"~-
aced and the reac"az shaL', be shutdown
~z the Cold Con@'.~
24 hnnzs.
I
- 0. Rel'i Valves
- 1. ~par~tely on~~ cf aL reliei va3.ves s~~
be bench-checxed oz renlaced w
h a bench~ecxed va've each ooerat~Mg ycle valves v '~ have been checkei or rea aced
.aan '"Ne "~l=
==an oi every secanc cycle.
Z. Once duwg each oaerat="g
- cycLe, each relief val re shall be ~ua>'y oaened untQ. the~cauales and acaust'c guitars dawns.earn ai the va'e inc'ate st earn flowing f~ the va've.
The integrity of the re3.ief valve bellows shall be continously monitored when. valves incorporating the bellows design are installed.
- 4. Ar least one re~'ei valve sha
be disassmiled and ~ect i each opera~g cycle.
Jet Pumas waenever the e is re 'rculat'an flow with ""e reactaz in =he sta=w or =m mades w th both "ec'~cion pumas
=~caine.
'et ouma oaerabf'ity sha3'e
="'ecked daQ,y by ver' jg
=he fc3'~mg conc't" ons da
.".a oc=
s~~taneouslv:
a 0 have a flow ~alance oi Qr care caen
~
u are oaerated at
=ce same sneed Amendment "lo. gg, 9d, 113
LZHZTXM COWXTXCBS VCR OPZQATXC5f SURVZXXZuCfM ~UXiQ2&528 3 ~ 7 COÃZAX NIEVE 8'ZSTEHS 0 ~ 7 O
ccl S'
~,
Standby Gap Treatment System St
~S<m'em Gao T. ea~~t 1 ~
Except as spec'fied in Specification 3.7 B
3 helmr, all three trains of the standby gas treatment system 1
At least once per year, the follcming
~
condit'ons shall be demonstrated.
shall be operable at all times
~hen secondary contairwent integrity is required; ae Pressure drop across the combined MPA filters and charcoal adsorber banks is less
~san 6
inches of eater at a f3ev of 9000 c=m f+
10%) ~
The inlet hoaters cn each ci cuit are test@8 in ac~rQance MSh AMX 8510 1975 and are capable of an output of at leaot 40 RH Ce Air dXst=ihxtion is uniform within 2CA ac oss BEPA filters and charcoal adsorbers.
Amendment No.
113 236
L'I!4ZTINC CONDITIONS FOR OPEPATION SURVEILLANC-RZQUI. ~~NTS CON VAI NUGENT S YST EHS
- 4. 7 COXSWAIN.IENT SYSTEMS C'
Control Room Emeraenc Ventilati'on 1.
Except as specified in specif ica tion 3.7. E. 3 below, both ccn tra 1 room emergency pressu riza tion systems shall be operable at all times when any reactor vessel contains irradiated fuel.
E.
Control Boom Emeraenc Ventilation At least once pe operatinq cycle, not to exceed 18 months, the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be d monstrated to be less than 6 inches of
~ater at system design flew rate
(+
10%).
2 ~
The results of the in-place cold COP and ha loqena ted hydrocarbon tes ts a t design flo~s on HEPA filters and charcoal adsorker banks shall show
>99%
DOP removal and
>99% halogenated hydrocarbon removal when tested in accordance with ANSI N510-1975.
b.
The results of laboratory carbon sample analy is shall show
?90%
'adioactive methyl iodide removal at a velocity when tested in accordance with ANSI N510-1975 (130 ~C e 95%
R H.)
244 2.
a.
b.
The tests and sample analysis of Sp cification 3.7.E.2 shall be performed at least ance per operating cycle or once every 18 months'hichever occurs first for standby service or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of syst: em operation and following significant painting, fire or chemical release in any ventilation zone communicating with th system.
Cold DOP testing shall be performed af ter each complete or partial replacem nt of the H"-PA filter bank or arter any structural maintenance an the system housinq.
Amendment No.
113
~>" "<~o.
0
~y ClO r+
~0
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
107 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 July 16, 1982, 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. 107, 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 NUCLEAR REGULATORY COl1MISSION
~/F/~~--
Domenic B. Vassallo, Chief Operating Reactors Branch k'2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 19.,
1984
ATTACHNENT TO LICENSE AMENDMENT NO. 107 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.
37, 39, 181, 236, 244 2.
The marginal lines on these pages denote the area being changed.
TAQLE i.l.l Rricrm rtortcrfoff srsrnf (scRAH) lfisraUHuvATtoa rifcrloffALTcsrs HDfffi>H FUMcllolfAL TEST tREqUEHClKS FOR SAtKTT ljlsTR. AHD CONTROL CLRCUlrS Hodc Svitch ia Shutdova Hanuel Scraa lhff High Flux lnoperatlra Grmu~&ll.
unctional Teat tlacc Hodc Svitch in Shutdova Trip Clisoacl and Alara Trip Channel aad Alake (i)
Trip Chaaael and Alone (i)
Htafaua Frc ucocy (3)
Each Rcrueliog Outage I
Rrery 3 '.fontha Once ter Vcek During Rcruelfn and Rctore Lech Startup Dace ter Veek Durfnj Reluclla and hefore Rach Stattup AFRH Rich Flux (1ST scraa) llil;h Flux (Flow Biased)
Ifhh Flux (Fixed Trip)
Inopere tlre Dovaacal ~
C Tqlp Output Relays (i) l I
8 Trip Output Relays (4)
I Trip Output Relays (i)
Trip Output Relays (i)
R Trip Output Relays (i) hetore Each Startup and Vcekl Vhca Required to 'be Opcrabla Once/Week Dace/'Meek Dace/Meek Once/Meek Rcllctor Lou Vater Lcrel fflhh Vatcr Lerel lo Scraa Discharge Teak Float Switches Flov hiaa ja Qlhh Reactor Frc ~aurc Rlrh Dryvel 1 treasure O
Differential Pressure Switches Turbine Condenser Low Vacuum Main Steam Line lligh lfndiat lou CO R
(6)
A Trip Channel aad Alara A
Triy Channel aad Alara A
~
Trip Chaaael aad Ala+a Trip Channel and Alarm Trip Cliannel and tJ.arm Trip Channel and Alarm Trip Cliannel anil hlarm Dace/Hoath (1)
Dace/Hooth (1)
Dace/Hoath (1)
Once/month Oi>ce/inonth
( /)
Once/month (l)
Once/3 lfonths (8)
frequency for the indicated tests shall In':ally =he minimum re oe once pe month.
A description o
". e tt-ee groups '" included 'n tne Bases of znis speci=ication.
Functiona tests a
1 t,
are not, required
~hen the system aze not ead requited to be operable oz aze operating
{i..e., alrea y
tripped).
Zf tests are missed, they shall 'be pezformed prior to returning the syszems to an operable status
's exempted from the instrument channel This instrumentation is exem test def'nition.
This instrument channel func=ional test
'ecting a simulated elec -ical signal into Mill consist of injecting a tne measurement channels.
5.
Deleted S.
The functional test o
e f the flew bias ne~zk is performed in accordance arith Table a. 2 C 7.
C-1fgz-ion oz master/slave trip-units only.
8.
The functional test. frequency decreased to once/3 months 'to reduce challenges to re1ief valves pef 'NUREG 0737, Item II.K.3.16.
39 Amendment Ho.
00, 105 107 I
ZHZ~ZNG CoiKZTZQNS FQR QFZBA ZQN SURV"ZLLANC= H:"QUZ~~'~P'S
. 6.G Coolant Leakage 4.6.C Coolant Leakage 3.
Both the sump and a" r sampling systems shall be operable during reactor power oaeration.
Fram and after the date that ane af these systems is made oz'ounci to be inoperable for any reason, reactor power operation is permissible on3.y during the succeeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The ai sampling system may be removed fram service for a periad oi 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Ear cali-
- bration, Eunction testing, and maintenance without providing a temparary monitor.
Kf the canditian in 1 oz 2
above cannot be met, an orderly shutdown shall be initiated anci the reactor shall be shut-down in the Cold Condi,tian 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. Relief Valves
- 1. Approximately one-hah.E oi a'1 relief valves shall be bench-checked oz replaced with 4 bench-checked va3.ve each operating cycle.
A11 13 valves wi13. have been checkeci oz ".enlaced uaon the comole-
""on oi every second cycle.
2.
Once dur'ng each operating cyc3,e, each relief va've shall be manu<<clly opened until thermacouples and acoustic monitors downstream of the valve indicate steam is Elowing from the valve.
3.
The integrity of the relief
~
~ valve bel3.ows shall be continously monitored when'.valves incorporating the bellows design are installed.
D 1.
)
Jet Pumas whenever the reactoz is in the stazzup or run modes, all jet pumps sha3.1
'oe operable.
Tf it is determined that a j et pump is inoperable, or if twa or mare jet pump flow instrument failures occur and cannot be corrected within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an orderly shutdown shall be initi-ared and the reactor shall be shutdown in the Co3.'d Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
RelieE Valves Qhen moze than'ne relief valves
~ are known to be failed, an orderly shutdown shall be initiat-ed and the reactoz depressuzized
. to less, than 105 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4 ~
At leaa one relic! valv>> shall br disasscnblcd and incpact>>d each operating cyclei E,
Jet Paws l.
%hen>>ver there is recirculation
!lov vith che reactor in the atartup or run no as" arith bo h recirculation p~s runn'ng,
)et punp operability aha
b>>
checked'aily by veri!ytnt cha che tollovint conditions co no occur sinu)taneoua)yc a.
Th>> tvo r>>circul= '.on loops have a floM inbalanc>>
o.'ing or nore vhen the pucss are operated at the aan>>
ap>>>>do LS1 Amendment No.
, 107
LZHXTXBG COZPZTXCZS VCR CPQBATZCN SURVEXLLRETM RQUX~&3
- 3. 7 COPE'AXNNZNT S'ZSTHHS 0 ~ 7 0
Be Standby Gas eatnent B
St see Tee~esses 1.
Except as specified in Specification 3.7.B.3 helmr, all three trains of the standby gas treatment system
~ssees 1.
At least once per year, the folluring
~
conditions shall be deaonstrated.
shall be operable at all times
~hen secondary contairment integrity is required.
ae be Pressure drop across the combined HEPA filters and charcoal adsorher hanks is less Man 6
inches of eater at a flee of 9000 c"m f+
10%)
~
The in2,et heaters cn each ci=cuit are tested in acm dunce Wth NcSZ 5510 1575 and are capable of an outpu of at.
laaot 00 kR Cr Air dist=ibx ion is unifozn within 20%
across HEPA filters and charcoal adsorhers.
Amendment No.
107
0 L'XlCXTXNG CONDXTXONS FOR OPERATXON I
SURVEZLLANC= RKQUX. ~'KNTS
. 7 CONTAIN4lENT SYSTENS
- 4. 7 CO%VAIN lENT SYSTEHS E ~
Cant rol Room Emeraenc Ventilation Except as specified in specification
'.7.E.3 below. both ccntrol room emergency pressurization systems
, shall be operable at all times when any reactor vessel contains irradiated fuel.
E.
Control Racm
=meraenc Ventilaticn
" 1'.
At leas once per operating cycle, not to exceed 18 months, the pressure drop across the comained HEPA fi1 ers and charcoal adsorber banks hall be d manstrated to be less than 6 inches of water at system design flew rate
(+
10%).
2 ~
a.
b.
The results of the in-place cold COP and haloqenated hydrocarbon tests at design flows on HEPA filters and charcoal
.adsorber banks shall show
?99%
DOP removal and
?99% halogenated hydrocarbon removal when
'ested in accordance with ANSI N5 10;197 5.
The results of laboratory carbon sample analysis shall show
?90'%adioactive methyl iodide
'emoval at a
velocity when tested in accordance with ANSI N510-1975 130OCr 95'5 R. H.)
~
244 2.
a e b.
The tests and sample analysis of Sp cification 3.7.E.2 shall be performed at least once per operating cycle or once every 18
- months, whichever occurs first for standby service or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation and following significant painting, fire or chemical release in any ventilatian zone co mmunica ting with th system.
Cold DOP testing shall be performed after each complete or partial replacem nt of the H=-PA filter bank or after any structural maintenance on the system housing.
Amendment No.
107
gp,~ REGS
~o
~p %~
~o
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROI'JNS FERRY NUCLEAR PLANT UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
8" 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 July 16, 1982, 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 B, as revised through Amendment No.
81
, 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 NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Domenic B. Vassallo, Chief Operating Reactors Branch 0'2 Division of Licensing Date of Issuance:
September 19, 1984
ATTACHMENT TO LICENSE AMENDMENT NO.
81 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.
36, 38,'192,
- 247, 256 2.
The marginal lines on these pages denote the area being changed.
+a".
TLR).E 4 1 ~ L RECTOR PPC LCT JOII STSTEH (SCRAII)
IIISTRU'IEIITAT)OIIrUIICT)OI>LI. TES II)II)'Iuq rulc))CIILL TLsr cfL~UDIc)Ls
)QR sar L I ills)A. LIID co:ITRQE c: culgs lIode Svitch Ln 'khutdovn lIanua) secan LRII a(gh Flue lnoperat)ve APR H il(gh l Luc ()5k acran) lligh Flux (l)lou Biased) gh f)"t (Fixed Trip) lnopecatl ve Dovnaca)c clou OLas Crou Cunct(ona)
Test place Ilzde SM(tch Ln shutdoun Tc(p channel an4 A)aca Trip Channel and A)acn (4)
I Tr)p Cnanncl and A)ara (4)
Trip Output Relaya (4)
Trip Ollrput Relays (4)
Trip Output Relaya (4)
Ttlp Output Re)aya (4)
Tcip Output Rclaya
( ~ )
plininun rrcquency
())
Each Re(uel)ng Outage Every l IIontha Once pec ueck Our)ng Aefue)lng and Se(ore Each Stactup Once fec )leek During Re(ucl(ng and bc(occ Each Stactup ae(ore Exch stactup and IIeekly
)Ihcn )lequirc4 to bc operab)e Once/ueek Once/ueck Once/clack Once/aleck Sigh Reactor prcssure S(gh Dr)Nell tteaaure
)Icactor Lou )latch ~vel t)lgh Mater Level Ln Sctaa Olrcharga Tan'k Floac. Sui rches
().S-BS-nc-l')
Elucrronic Level Su(lches (LS-85-45A, 0, G, II)
A A
A Tclp Channel an4 A)am Trip Channel an4 A)am Trip Channel an4 A)aca Once/Ilonth ())
Once/llonth Once/IIonth ())
Trip Ch'Inoel and Alarra Once/.')onth
'l'rip (:h:Iooul 'loll Alarm (I)-
Once/"alolh CI Turbine Condenser Lot) Vacuum Trip Channel and Alarm OncelHonth (l)
NOTES FOR TABL O.
1 1.. Initially the minimum frequency for the indicated tests shall be once per month.
~
e Z.
A description of'he three groups i" included in the Bases of this specification 3.
Functional tests are not required when the systems are not required to be operable or are operating
- g. e.,
already tripped)
~ If tests are missed, they shall be performed prior to returning the systems to an operable status This instrumentation is exempted from the instrument channel test definition This instrument channel functional test will consist of infecting a simulated electrical signal into the measurement channels.
5.
(deleted) 6.
7.
The functional test of the flow bias network is performed in accordance with Table' 2 C
":u"..c"'oaa3. test caasists of De in)ec&oa or a s'-u'ates s'~
.. o a~ eie~~Zc =fp c'--uf.azy Q place of the sensor 5 jDa to oue-aM"
~~
of the fp end ala~ ~unc ~~as.
Functional test frequency decreased to once/
3 months to reduce the challenges to relief valves per NUREG 0737, Ztem ZZ.K.3.16.
I 38 Amendment No. /7, g+
81
METING CONDI IONS FOR OP.ATION SURV"I~NCZ RZQUIR~~NTS
- 3. 6 PRZiARY SY~
BOOM)ARY 4 ~ 6 PRL~Y SYS.~i BOU".G)ARY 2.
Both the sump and air sampLing sampling systems shall ae operable during reactor power operation.
From and after the date that ane of these sysrems is made or found to be inoperable for any reason, reactor power opera ion is permissible only during the suc eecing 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
The air sampling system may be removed Crom service Eor a
period of '4.hours Eor calibra-tion, EunctionaL testinp, and maintenance without providing a temporary monitor.
- 3. If the condition in 1 or 2 above cannot be met, an orderly shutdawn shaLL be initiated and the reacror shall be shutdown the Cold Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
V.
RelieE Valves
- l. Approximately one-half oi alL relief valves shaL'e bench-checked or replaced with a bench-checked valve each ooerat'ng 'cycle;-
ALL 13 valves wilL have oeen checked or replaced upon the completion ai every second cycle.
2.
Once during each operating
- cycle, each relief valve shall be manually opened until thermocouples and acoustic monitors down-stream of the valve indicate steam is flowing f.om the'alve.
D.
Relief VaLves 1.
When mare than ane relief valve is known to be Eailed, an orderly shurdawn shall be initiated and. the reactor depressurized to less chan 105 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.
The integrity of the relieE
~
~ valve bellows shall be continously monitored when. valves incorporating the hello~ design are installed.
4 ~
P t least one relief valve shall be disassembled and inspected each operating cycle.
192 Amendment No.pg 81
LXHXTING CONQXTXCSS FOR OPXRhTXON SURVEZLLANCZ RZQUXREME?&8 3 ~ 7 CORTAINHZHT SIST>NS 0 7 Bi Stand Gas T ea m t t
ra B.
St
~sstem Gas re tment 1.
Except as specified in Specification 3 7 B 3 beld+< all three trains of the standby gas treatment systcR 1 ~
At least once per year, the follcwing conditions shall be deaonstrated.
'hall be operable at all times
+hen secondary containment integrity is required.
a.
Pressure drop across the combined HEPh filters and charcoal adsorher hanks is less than 6
inches of eater at a flew of-9000 cfm f+.
10%) ~
b The inlet heaters cn each circuit are tested in accordance Wth aSSX N510-1975 and are capable of an output of at least 40 kQ c.
Air distribution is uniform within 20%
across HEPA filters and charcoal adsorbers.
Amendment No.
81
LIMITING CONDITIONS POR OPERATION SURVEILLANCE REQUIREMENTS 3 ~ 7 COYVAINMENT SYSTEMS 4'
CONTAINMENT SYSTEMS Cont, rol Room Emer en Ventilation Except.. as specified in specif ication 3.7.E.3 below, both ccntzol room emergency pressurization systems shall be operable. at all t.imes when any reactor vessel contains irradiated fuel.
E Control Room Emer enc Ventilation At-least once per operating cycle, not to exceed 18 months, the pressure drop across the combined HEPA filters and charcoal adsorber banks shall be demonstrated to be less than 6 inches of water at system design flow rate g+
10%)
~
2 ~
a ~
The results of the in-place cold DOP and haloqenated hydrocarbon tests at design flows on HEPA filters and charcoal adsozher banks shall show
?:99%
DOP removal and
>99% halogenated hydrocarbon removal when tested in accordance with ANSI 5510-1975'.
The results of laboratory carbon sample analysis shall show
>90%
radioactive methyl iodide removal at a velocity when tested in accordance with ANSI N510-1975 (130 OC g 95%
R..H
)
256 2.
a.
The tests and sample analysis of Specification 3.7.Z.2 shall be performed at, least once per operating cycle or once every 18
- months, whichever occurs first for standby service or after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation and following significant painting, fire or chemical release in any ventilation zone communicating with the system.
b.,
Cold DOP testing shall be performed after each complete or partial replacement of the HEPA filter bank or after any structural mai.ntenance on
'the system housing.
Amendment No.
81