ML20108D902
| ML20108D902 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/03/1996 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20108D895 | List: |
| References | |
| NUDOCS 9605090099 | |
| Download: ML20108D902 (38) | |
Text
{{#Wiki_filter:_ _ _ _ _ _ ._ _ _ _ Section DEC 0 71994 Pane No. Coolant Chemistry. .............. 3.6/4.6-5 B. Coolant Leakage. .... . .......... 3.6/4.6-9 C. Relief Valves. ........ ........ 3.6/4.6-10 D. Jet Pumps. .............. 3.6/4.6-11 , E. . . ..
\
Recirculation Pump Operation . . ....... 3.'6/4.6-12 F.
~ Structural Integrity . . .... ....... 3.6/4.6-13 G.
Snubbers .......... . . . . .. 3.6/4.6-15 H. . . Containment Systems . . .,............. 3.7/4.7-1 3.7/4.7 _ Primary Containment. ............. 3.7/4.7-1
~
A. Standby Gas Treatment System . ........ 3.7/4.7-13 B. C. Secondary Containment. ............ 3.7/4.7-16 , f Primary Containment Isolation Valves . . . .. 3.7/4.7-17 D. Control Room Emergency Ventilation . . . . .. 3.7/4.7-19 E. Primary Containment Purge System . . . . . . . 3.7/4.7-21 F. Containment Atmosphere Dilution System (CAD) . 3.7/4.7-22 G. H. Containment Atmosphere Monitoring (CAM) 3.7/4.7-24
. , System H2 Analyzer . . . . . . . . . . . .
3.8/4.8-1 3.8/4.8 Radioactive Materials . . . . . . . . . . . . . . . Liquid Effluents . .............. 3.8/4.8-1 A. 3.8/4.8-3 B. Airborne Effluents . . . . . . . . . . . . . .
................. 3.8/4.8-4 C. (Deleted). .
(, Deleted). . . . . . 3.8/4.8-4 D.q ": '- ' ::1 ":: _; r ;.......... .. 3.8/4.8-5 E. Miscellaneous Radioactive Materials Sources. . 3.8/4.8-6 F. (Deleted). . . . ............... Auxiliary Electrical System . ........... 3.9/4.9-1 3.9/4.9 Auxiliary Electrical Equipment ........ 3.9/4.9-1 A. Operation with Inoperable Equipment. . . ... 3.9/4.9-8 B. AMENDMENT NE 213 BFN tii l Unit 1 9605090099 960503 PDR ADOCK 05000259 P PDR
1 } 4 . I 1.0 DEFIRITIQHS (Coat'd) E02M 1 GG. Site _Raundarv - Shall be that lias beyond which the land.is set l owned, leased, or otherwise controlled by tvd. i A
- 55. Unrestricted Area - &ay area at or beyond the SITE BOUNDdRY te which access is ast controlled by tha licenses for perpesas of
( preteetion of individuals free exposure to radiaties and. radioaative materials or any area within the SITE 800ED&It used l i for industrial, commercial, institutional, or recreattomal ; j purposes. t II. Damn tantwatame f in - The DOSE EQUIYALEEE I-131 shallbe the concentration of I-131 (in pC1/an) which alone would predeoe- l i j the. same thyroid dose as the gusatity and isotopic misture of I-131, I-132, I-133, I-134, and I-135 actually presamte The l thyroid dose conversion factor used for this calculaties:ehall l be those listed in Table III of TID-14844 "Calculaties:of Distance Factore for Power and Test Reactor Sites". JJ. "- -- -- Wanta Tema&e Swatan - The charcoal adsorber-vessels. installed on the discharge of the steen jet air ejector-to provida delay to a unit's offsas. activity prior to reiem. E3:. r -"en et the pahite - As 1 bs%4
=-i r Maul
- i: er.ssyt wkm
- cr n;;;d ^
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' -' T ' ': ; ; ; . _-- ^=
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""" .-- ; " "- - ---i ' '- ?_.i;'; 1; individual. receives -
an escapational dose (as defined in 10 CH 20). LL. Survattiance - Surveillance Requirements shall be set-darias the OPERATIOEAL COEDITICES or other conditions specified for individual limiting conditions.for operation untess4otherwise stated in an individual Surveillanae-Requirements.. Enah Surveillance Requirement shall be performed withia:ths: specified surveillance laterval with a maximum allevable. extension not to azeeed 25 percent of the specified. surveillanne interval. It is not intended that this. (extension) provision be used repeatedly as a convenience ta-extend surveillance intervals beyond that specified for-surveil 1==*== that are not performed during refueltas.oucases. Performance of a Surveillance Requirement within the specified time interval shall constitute ceay11ance and Oremaarf.rvy-requirements for a limitias condition for operation,and:. asseeisted action statamanes unless.etherwise required:by"these specifications. Surveillance Requirements do not have-to;be - performed on insparable equipment. BFN- 1.0-11 Unit.1
TABLE 3.2.A (Continu-4) PRIMARY CONTAINMENT AND REAC10R BUILDING ISOLATION INSTRUMENTATION c: en Minimum No. K@ Instrument n Channels Operable per Trio Svs(1)(111 Function Trio Leve5 Settina Action (11 Remarks 1(15) Instrument Channel - 1100 mr/hr or downscale F 1. 1 upscale channel or Reactor Building 2 downscale channels will Ventilation High
- a. Initiate SGTS Radiation - Refueling Zone
- b. Isolate refueling floor
- c. Close atmosphere control system.
2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm H and Below 2000 cfm airflow R.H. SGTS Flow - Train A (A or F) heaters shall be shut off. R. H. Heaters InstrumenEChannel 12000 cfm and i 4000 cfm H and Below 2000 cfm airflow R.H. 2(7) (8) (A or F) heaters shall be shut off. 5GTS Flow - Train 8 R. H. Heaters I u Below 2000 cfm airflow R.H. Instrireent Channel 12000 cfm and i 4000 cfm H and 2 2(7) (8) (A or F) heaters shall be shut off.
. SG15 'ilow - Train C y R. H. Heaters e
Reactor Building Isolation 0 i t i 2 secs. H or F 1. Below trip setting prevents 1 Timer (refueling floor) spurious trips and system perturbations from initiating isolation. Reactor Building Isolation 0 i t i 2 secs. G or A 1. Below trip setting prevents 1 or H spurious trips and system Timer (reactor zone) perturbations from initiating isolation. Group 1 (Initiating) Logic N/A A 1. Group 1: A Group I
$ 2(10) isolationisactuatedbyanyoftheli g following conditions:
c, a. Reactor vessel Low Low water Level' 3: Q (gy,f,f g b .I . . . . . . _ _ . . . . . . .
-4 c. ~ Main Steamilne High Flow a - d. Main Steam 1Ine Space High P Temperature &M y e. Main Steamilne Low Pressure g
to }
e 4 i i TABLE 3.2.A (Continued) , PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRtiMENTATION L e to Minimum No. E@ Instrument n Channels Operable Remarks per Trio Svs(1)(11) Function Trio Level Settino Action Ill ~ Group 1 (Actuation) Logic - N/A B 1. Group 1: A Group 1 l t 1 isolation is actuated by any of I the following conditions:
- a. Reactor Vessel Low Low Water (Qg/gfg b. ; Et::r!?re "! ? Proitti:n
' "g c.
d. Main Steamilne High Flow Main Steamilne Space High ' Temperature
- e. Main Steamline low Pressure N/A A or 1. Group 2: A Group 2 1 solation 1 2 Group 2 (Initiating) Logic is actuated by any of the I (B and E) '
following conditions:
- a. Reactor Vessel Low Water level I b. High Drywell Pressure Y I N/A D U 1 Group 2 (RHR Isolation-Actuation) Logic w N/A J Group 8 (TIP-Actuation) 1 o
1 Logic L Group 2 (Drywell Sump N/A K 1 Drains-Actuation) Logic ' N/A F and G 1. Part of Group 6 Logic 1 Group 2 (Reactor Building
& Refueling Floor, and ,
( Drywell Vent and Purge-Actuation) Logic N/A C 1. Group 3: A Group 3 Isolation is l g 2 Group 3 (Initiating) Logic actuated by any of the f ollowing conditions: E a. Reactor Vessel Low Water Level g b. Reactor Water Cleanup System 121 High Temperature 2l c. Reactor Wat'e r Cleanup System g High Orain Temperature g p tn N p.a g
_.A... sna a.msmA-m_ .h_u,L_--s2w.a_6-ue,a, +1Aswks mme_14__&%B--,-V_m_ n--u-oa ,n4mwsea._,.Amm-un J _ m ,k.mAan.4a.mm,.s,au,mme,.g m s,, n-, a,a, a, , , w _, _a _,,, a,_ _ __ i UNIT 2 MARKED UP PAGES i 1 1 l l i l l l
F*** "*- Section DEC 0 71994 l Coolant Leakage. ...... ......... 3.6/4.6-9 C.
........ 3.6/4.6-10 D. Relief Valves. ........
Jet Pumps. ........ ......... 3.6/4.6-11 E. . Recirculation Pump Operation . ........ 3.6/4.6-12 F. l Structural Integrity . ............ 3.6/4.6-13 G. l Snubbers . . ................. 3.6/4.6-15 ,
- H.
l Containment Systems . ....... ........ 3.7/4.7-1 3.7/4.7 Primary Containment. ............. 3.7/4.7-1 A. Standby Gas Treatment System . ........ 3.7/4.7-13 B. Secondary Containment. ............ 3.7/4.7-16 C. Primary Containment Isolation Valves . .... 3.7/4.7-17 D. Control Room Emergency Ventilation . . . . . . 3.7/4.7-19 E. Primary Containment Purge System . ...... 3.7/4.7-21 F. G. Containment Atmosphere Dilution System (CAD) . 3.7/4.7-22 H. Containment Atmosphere Monitoring (CAM) System H2 Analyzer . . . . . . . . . . . . 3.7/4.7-24 Radioac'tive Materials . . . . . . . . . . . . . . . 3.8/4.8-1 3.8/4.8 , 3.8/4.8-1 ! A. Liquid Effluents . . . . . . . . . . . . . . . B. Airbo rne Ef fluents . . . . . . . . . . . . . . 3.8/4.8-3 , 1
................. 3.8/4.8-4 C. (Deleted). .
gOsbetwaQe ..... D. M
. '^ '::' 9: .- .
; . ........... 3.8/4.8-4 Miscellaneous Radioactive Materials Sources. . 3.8/4.8-5 i
- 3. i 3.8/4.8-6 F. (Deleted). . . ................
Auxiliary Electrical System . ........... 3.9/4.9-1 3.9/4.9 Auxiliary Electrical Equipment ........ 3.9/4.9-1 A. Operation with Inoperable Equipment. ..... 3.9/4.9-8 B. i l l f I ' AMENDMEKT NU. 2 29
,g, gig l Unit 2
1.0 DEFINITIONS (Cont'd) g 21g
- 9. Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question. .
- 10. LSAig - A logic is an arrangement of relays, contacts, and other components that produces a decision output.
(a) Initiatina - A logic that receives signals from chsanals and produces decision outputs to the actuation Absic.
-. ~
(b) Actuation - A logic that receives signals (either from initiation logic or channels) and produces decision outputs to accomplish a protective action.
- 11. Channel calibration _Shall be the adjustment, as necessary, of the channel output such that it responds with necessary rsage and accuracy to known values of the parameters which ths channel monitors. The channel calibration shall encompass the l entire channel including alarm and/or trip functions and shall include the channel functional test. The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. Non-calibratable components shall be excluded from this requirement, but will be included in channel functional test and source check.
j
- 12. Channel Functional Test - Shall be:
- a. Analog / Digital Channels - the injection of a simulated signal into the channel as close to the sensor as practicable to
( verify OPERABILITT including alarm and/or trip functions.
~ .
b. Bistable Channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions. U De/eded) ~ =1' 13 75ou~rce Check - Shall be the qualitative assessment of eA
~
l g,responsewhenthechannelsensorisexposedtoar multiple of sources. p-e i AMENDMENT NO. 217 BFN 1.0-9l
'Jnit 2 ,w-
l k j 4 1 l 4 1 1.0 DEFINITIONS (Cont'd) DEC 0 21993 GG. Site Boundary - Shall be that line beyond which the land is not l owned, leased, or otherwise controlled by TVA. ( 2 II. Unrestricted Area - Any area at or beyond the SITE BOURRAM to which access is not controlled by the licenses for purposes of i protection of individuals from exposure to radiation anC i radioactive materials or any area within the SITE BOURR&RI used 4 for industrial, commercial, institutional, or recreattomal purposes. II. Dona Eauivalent I-131 - The DOSE EQUIVALEET I-131 shall be ths . concentration of I-131 (in pC1/sm) which alone would produce the same. thyroid dose as the quantity and isotopic mixture of-I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid i dose conversion factor used for this calculation shall be those i listed in Table III of TID-14844 " Calculation of Distance Factors for Power and Test Reactor Sites". i
- JJ. Gannona Waste Treatment System - The charcoal adsorbervessels. I installed on the discharge of the staan Jct mir ejector to. .
] provide delay to a unit's offgas activity prior to release. l Any idividual excart wasn +Ase - KE. Members of the Public - I j 5 - = """ ' -M "
- _ : _ ;;;. , _ ' " Ti f-- - ' i: .a . . __ -M-d ?""'l" 1 la w ;:r!" i= *!^ "- individual receives- an i j occupational dose (as defined in 10 CFR 20).
1 LL. Surveillance - Surveillance Requirements shall be met during the OPERATIONAL CORDITIONS or,other conditions specified for-- < individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements. Each:.
- Surveillance Requirement shall be perforceed within ths
- specified
- surveillance interval with a marimum allowable extensian
- not to i exceed 25 percent of the specified surveillance interval. It is ;
not intended that this (extension) provision be used repeatedly as a convenience to estand surveillance intervals beyond-that specified for surveillances that are not performed during. refueling outages. i Performance of a Surveillance Requirement within the specified 4 time interval shall constitute comp 11 ante and OPERABILITT' requirements for a limiting condition for operation and. associated action statements unless otherwise required by these specifications. Surveillance Requirements do not have to be performed on inoperable equipment. d
- (
j J ' arr 1.0-11 AMENDMDfrNC 220 Unit.2..
i TABLE 3.2.A (Continsed) , PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRtiMENTATION Minimum No. i E* rE Instrument Channels Operable Remarks " per Trio Svsf11(11) Function Trio Level Settina Action (1) u F 1. I upscale channel or 1(14) Instrument Channel - 1100 er/hr or downscale 2 downscale channels will Reactor Building a. Initiate SGTS Ventilaticn High .*
- b. Isolate refueling floor Radiation - Refueling Zone ,
- c. Close atmosphere ccatrel system.
H and Below 2000 cfm airflow R.H. 2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm heaters shall be shut off. SGTS Flow - Train A (A or F) R. H. Heaters H and Below 2000 cfm airflow R.98 u 2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm (A or F) heaters shall be shut off. w SGTS Flow - Train 8 N R. H. Heaters I e N H and Bekow2000cfmairflowR.H. 2(7) (8) Instrumer.t Channel 12000 cfm and i 4000 cfm heaters shall be shut off. I E SGTS Flow - Train C (A or F) R. H. Heaters H cr F 1. Below trip setting prevents 1 Reactor Building Isolation 0 i t i 2 secs. spurious trips and system Timer (refueling floor) perturbations from initiating isolation. G or A 1. Below trip setting prevents 1 Reactor Building Isolation 0 i t i 2 secs. or H spurious trips and system Timer (reactor zone) perturbations from initiating isolation. A 1. Group 1: A Group 1 isolation 2(10) Group 1 (Initiating) togic N/A is actuated by any of the following
@ conditions:
tz a. Reactor Vessel Low Low Water E __' ' -__ (Dej,{ed b.} Level"r" nun g n,as. i m
- c. Hain Steamilne High Flow
'~
Main Steamilne Space High M d.
% . Temperature Main Steamilne Low Pressure rJt h3 ,
e. Cg
l e' i TABLE 3.2.A (Continued) , 4 PRIMARY CONTAlletENT Als REACTOR BUILDING ISOLATION INSTRUMENTATION c: os Minimum No. , O Instrument
$g Channels Operable Trio Level Settine Action (1) * = rks (
t ser Tris Svs(1)(11) Functlen y t Group 1 (Actuation) Logic N/A 8 1. Group 1: A Group 1 Isolation {- 1 is actuated by any of the u , following conditlens:
- a. Reactor Vessel Low Low Water ,.
- m- Lo
,Ana.ve)s. u--i a.. us p m-an -a n - ,
. c. Main Steamilne High Flow ,
- d. Main Steamline Space High Teeperature ['
- e. Main Steamilne Low Pressure I
N/A A or 1. Group 2: A Group 2 Isolation l 2 Group 2 (Initlating) Logic is actuated by any of the (8 and E) following conditions:
- a. Reactor Vessel Low Water Level I b. High Drywell Pressure j Group 2 (RHR Isolation- N/A D i
1 Actuation) Logic I i
- Group 8 (TIP-Actuation) N/A J i
g
% Logic N/A K 1 Group 2 (Drywell Sump 8 Drains-Actuation) Logic o N/A F and G 1. Part of Group 6 Logic 1 Group 2 (Reactor Building
& Refueling Floor, and ,
Drywell Vent and Purge- , - Actuation) Logic . N/A C 1. Group 3: A Group 3 isolation is l ; 2 Group 3 (Initiating) Logic actuated by any of the following conditions: '
- a. Reacter Vessel Low Water Level E b. Reacter Water Cleanup (RWCU) '
g System High Temperature in the main steam valve vault o H E c. RWCU System High Temperature E2 in the RWCU pump roen 2A us A d. RWCU System Hirt Temperature
- = in the RWCU pump room 28 P e. RWCU System High i rature y in the RWCU heat onc anger room '
- f. RWCU System High Temperature CC in the space near the pipe Cl ' trench containing RWCU pleing l
4 TABLE 3.2.8 INSIRuttifliA110fi THAT INIIIATES OR CONTROLS THE CORE At40 CONTAlt4HENT COOLING SYSTEMS c, Hinimum No.
- 2 p g Operable Per Trip Snill runction Trio level Settino Action Remarks
" 2 Instrument Channel - 1 470" above vessel zero. A 1. Below trip setting initiates Reactor Low Water level HPCI. (LIS-3-58A-0) , 2 Instrument Channel - 1 470" above vessel zero. A 1. Multiplier relays initiate Reactor Low Water Level RCIC. (LIS-3-58A-D) Instrument Channel - 1 398 above vessel zero. A 1. Below trip setting initiates DELETE Reactor Low Water tevei CSS. l (LS-3-58A-D) Multiplier relays initiate LPCI.
- 2. Multiplier relay from CSS Y initiates accident signal (15).
es 2(16) Instrument Channgl - 1 398" above vessel zero. A 1. Below trip settings, in 3 Reactor Low Water Level conjunction with drywell (LS-3-58A-D) high pressure, low water
'(-
g level permissive, ADS timer
' timed out and CSS or RHR pump running, initiates ADS.
- 2. Below trip settings, in conjunction with low reactor water level permissive, ADS timer timed out.
ADS high drywell pressure bypass timer timed out.
' CSS or RHR pump running,
. initiates ADS.
T 1(IL) Instrument Channel - 1 544" above vessel zero. A 1. Below trip setting permissive 3 Reactor low Water Level for initiating signals on ADS.
} Permissive (LIS-3-184, ;
g 85) g 4 cs
, I Instrument Channel - 1 312 5/16" above vessel zero. A 1. Below trip setting prevents
-5 Reactor Low Water Level (2/3 core height) Inadvertent operation of M (J (LIS-3-52 and LIS-3-62A) containment spray during to H DELATE accident condition.
"Only one trip system will be required to be OPERABLE during the period that the Reactor Vessel water level instrumentation modification requested by NRC Bulletin 93-03 is being perforced, provided that the reactor is in the COLD SHUTDOWH CONDITION.
Snual and automatic initiating capability of CSS and LPCI will be available, but with a reduced number of instrument channels.
l L 9/4. 9 AffYTY T ARY TT ECTRIf*17. SYSTEM DEC o 71994 LIMITING CONDITIONS FOR OPERATION SURVEffT.ANCE REQUI L -- a Auriliary Electrical Eauinment 4.9.A. Aurfliary Elmetrical S 3.9.A. 3.9.A.3. (Cont'd)
- d. The 480-V shutdown boards 2A and 2B are energized.
- e. The unita 1 and 2 diesel auxiliary boards are energized.
- f. Loss of voltage and degraded voltage relays _
OPERABLE on 4-kV shutdown boards A, B, C, and D. .
- g. Shutdown buses 1 and 2 energized. ,
- h. The Ago-V reactor notor-operated valve (RMOV) boards 2D & 2E are energized with motor-generator (ns) sets 2DR, 2DA, 2EN, and 2EA in service.
- 4. The three 250-V unit batteries, 4. Undervoltage Relays the four shutdown board batteries', a battery charger a. (Deleted) for eheir battery, and associated battery boards are b. Once every 18 mont OPERABLE @Dne7E the conditions und l which the loss of and degraded volta relays are require be sinnlated with undervoltage on es shutdown board to demonstrate that t associated diesel generator will sta
}*Exceptasspecifiedin3'.9.B.Nc DELETE on page 3.9/4.9-10a from January 1, 1995, to December 31, 1995.
BFN 3.9/4.9-6 EEI28 Unit 2
. - - - - . . .~.-. . -..---.-. - - . . . - . . . . - . - - - - ~ - . -- _ _ - _ -
1 3.9/4,9 AffrTY.Takr FT.RCTRIf*1f. SYSTEM MITING CO EITIONS FOR OPIsATION SURVEft.tANCE is6Uls - a l l 3.9 Qperation With Inonerable Eauinment
. From and after the date that one i of the 250-V shutdown board ! atteries and/or its associated j ttery board is found to be 1 i erable for any reason, I con nued REACTOR POWER OPERATION
,' is pe insible during the
, succe five days in accordance i with 3. B.7 except as noted in 3.9.B.8.a b, and c belows ~
i l a. For the urpose of shutdown board bat ry and component ! replacemen only, REACTOR. POWER OPE ON is permissible f the succeeding for -five (45) j days providing: El.ETE l l
- 1. Only one of the shutdo j board batteries j associated compon ts s j being replaced at a ime.
i ! 2. All components n 1 supplied from a shutdown boar battery
- which is be replaced l are. fed fr its alternat source.
l 3. Units and 3 are i def ed.
- b. NRC tification for 3.9.B.7 is t required for shutdown l b rd battery and component j placement.
i j c Resumption of REACTOR POWER f OPERATION is permissible 4 following a shutdown while shutdown board battery and l component replacements are in progress.
- From January 1, 1995, to December 31, 1995, the provisions of Speci ation 3.9.B.8 on this page will apply while modifications are being perto on l
the shutdown board batteries and/or their associated battery boards.
; j J / BFN 3.9/4.9-10s ggg g g g g Unit 2 --
3
DEC 0 7199 D IS PAGE INTENTIONALLY LEFT BLARK i 1 5 3,9/4,9-10b O BFN' Unit 2
h
- 3.9/O.9 AfffT2.TARY 1._ ERIf*AT. 5 f s 11.ri Q(C Q 7 ]$$4
~
. LIMITING CONDITIONS FOR OPERATION suudli1ANCE RE6uia - -1a 3.9.B Oneration With Inonerable Eauinment s l l 30. From and after the date that one of the 250-V ~ DELETE i shutdown board batteries ! and/or its associated i battery board is found to } be INOPERABLE for any reason, continued REACTOR ; POWER OPERATION is (
- j. permissible during the i succeeding five days in l i '
l i accordance with 3.9.5.7. I _ 9. When one division of the . l 4 logic system is i INOPERABLE, continued
! REACTOR POWER OPERATION j is permissible under this condition for seven days, i provided the CSCS 4
requirements listed in Specification 3.9.B.3 are l satisfied. The NRC shall , be notified within i 24 hours of the I situation, the , precautions to be taken
- during this period, and
, the plans to return the i failed component to an OPERABLE state.
- 10. (deleted) i 11. The following limiting
' conditions for operation exist for the undervoltage relays which start the diesel generators on the 4-kV
- shutdown boards.
1 l DELETE > 1 - i
! e From January 1, 1995, to December 31, 1995, the provisions of Specification I 3.9.B.8 on page 3.9/4.9-10a will apply while modifications are being 4
performed on the shutdown board batteries and/or their associated battery i boards. -_ wM I BPN 3.9/4.9-11 EIIS Unit 2 i }
. . - - -. - _. _..--s. _.. - - . . . . ~ _ . . - . .. . - ~ . . . . . . - - - . . . _ - - - - . . ~ . . - - . . . - . . - . . - - . _ - . - _ _ _
i UNIT 3 l l l l l MARKED UP PAGES
l 1 1 Pane No. seet' " DEC 0 71994 Coolant Chemistry. ........... 3.6/4.6-5
- 3. ...
Coolant Leakage. . . ... .......... 3.6/4.6-9 C.
............ 3.6/4.6-10 D. Relief Valves. . . ..
Jet Pumps, ............. 3.6/4.6-11 E. . . . . . Recirculation Pump Operation . . . . . . . . . 3.6/4'.6-12 T. Structural Integrity . ............ 3.6/4.6-13 G.
............ 3.6/4.6-15 H. Snubbers . . ... ..
Containment Systems . ..; ............ 3.7/4.7-1 1 3.7/4.7
~
Primary Containment. ............. 3.7/4.7-1 A. Standby Gas Treatment System . ........ 3.7/4.7-13 B. Secondary Containment. ............ 3.7/4.7-16 C. D. Primary Containment Isolation Valves . .... 3.7/4.7-17 E. Control Room Emergency Ventilation . . . . .. 3.7/4.7-19 i l F. Primary Containment Purge System . ...... 3.7/4.7-21 1 1 4 I G. Containment Atmosphere Dilution System (CAD) . 3.7/4.7-22 ! H. Containment Atmosphere Monitoring (CAM)
~
System H2 Analyzer . . .......... 3.7/4.7-23a 3.8/4.8-1 3.8/4.8 Radioactive Materials . . . . . . . . . . . . . . . i A. Liquid Effluents . . . . . . . . . . . . . .-. 3.8/4.8-1 B. Airborne Effluents . . . . . . . . . . . . . . 3.8/4.5-3 4
.............. 3.8/4.8-4 C. (Deleted). ....
3.8/4.8-4 ? i D. I (" Deleted). r-'--i e e l " err:- .P.- . . .. ............ i f Miscellaneous Radioactive Materials Sources . 3.8/4.8-5 ; E. d 3.8/4.8-6 l F. (Deleted). . . . ............... 1 1 Auxiliary Electrical System . ........... 3.9/4.9-1 3.9/4.9
'Auriliary Electrical Equipment ........ 3.9/4.9-1 A.
i igg l AMDIDMDITlllL188 Unit 3
1 i 1.0 DEFINITIONS (Cont'd) l E0 2 W ! GG. Site Batmdev - Shall be that line beyond which the land is not
- owned, leased, or otherwise controlled by TVA.
l ' HE. Ilnrestricted Area - Any area at or beyond the SITE BOUEDART to I which access is not controlled by the licenses for purposes of protection of individuals from exposure to radiation and i radioactive materials or any area within tha SITE B00EDARY used
- for industrial, commercial, institutional, or recreatiamal l purposes.
l II. Dome raufvalene I-131 - The DOSE EQUIVALENT I-131 shall be the i i concentration of I-131 (in WC1/gs) which alone would produce tha j same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid j dose conversion factor used for this calculation shall be those ) l listed in Table III of TID-14 44 " Calculation of Distamaa l Factore for Power and Test Reactor Sitas". i
- JJ. Caseous Waste Treatment Svates - The charcoal adsorber ve6Jels
- installed on the discharge of the staan jet air ejector to 1 provide delay to a unit's offgas activity prior to release.
A indivhal ece.pt uden tas+ KK. Members of. the Public
- f.;q-'*-'f- ' i; ; :- :::512 ;;; j
- .. ... ; 2r2 ;;nn., nfrifr_i1 n: ; GP
! = "'C frr'-- - _ :ried i 9't er individual. receives an l [ occupational dose (as defined in 10 CFR 20). ' i
- LL. Surveillanen - Surveillance Requirements'ahall be met during the j OPERATIONAL CORDITIONS or other conditions specifieC for i
individual limiting conditions for operation unless otherwise i stated'in an individual Surveillance Requirements. Each j Surveillance Requirement shall.be performed within the specified l surveillance interval with a ==i=== allowable extension not to exceed 25 percent of the specified surveillance interval. It is j l not intended that this (extension) provision be used repeatedly
- as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during
! refueling outages. i \ Performance of a Surveillance Requirement within the specified i time interval shall constitute compliance and CPERABILITT requirements for a limiting condition for operation and j associated action statements unless otherwise required by these spruifications. Surveillance Requirements do not have to be i rarformed on inoperable equipment. i l 1 ) BfW ' 1.0-11 AE U Unit 3 i i
,- , , . . < e .,. ,
i TABLE 3.2.A (Continued) PRIMARY CONTAINMDIT AND REAC10R BUILDING ISOLATION INSTRtNENTATION E"
*5 Minlaum No.
Instrument
" Channels Operable u ser Trio Svs(1)(111 Function Trio level Settine Action lit pesarks 2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm H and Below 2000 cfm alrflow R.H.
SGTS Flow - Train 8 , (A or I) heaters shall be shut off. R. H. Heaters e 2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm H and Below 2000 cfm airflow R.H. SG15 Flow - Train C (A or F) heaters shall be- shut of f. R. H. Heaters 1 Reactor Building Isolation 0 i t i 2 secs. H or F 1. Below trip setting prevents Timer (refueling floor) spurious trips and system u perturbations from
- I inttleting isolation.
u s
- Reactor Building Isolation 0 i t i 2 secs. G or A 1. Below trip setting prevents 1
N 11mer (reacter mone) or H spurlous trips and system i perturbations from initiating 1 c) Isolation. Group 1 (Initiating) Logic N/A A 1. A Group 1 Isolation is actuated 2(10) by any of the following conditions:
- a. Reactor Vessel Low Low Water b.gLevel mse steam 1 5 h! f --'8etir gg8g c. Main steamilne high flow
- d. Main steamline space high temperature
- e. Main steamilne low pressure
- Group 1 (Actuation) Logle N/A 8 1. Group 1: A Group I (solation j 1 is actuated by any of the i following conditions:
q a. Reactor Vessel Low Low Water (DEleh d b? NIN swi, ==f =-an -in- h
. c. Main Steamilat High Flow
- d. Main Steamilne Space High M p Temperature g M e. Main Steamilne Low Pressure so '
CQ e t
ENCLO8URE 3 TENNESSEE VALLEY AUTHORITY BROWN 8 FERRY NUCLEAR PLANT (BFN) UNITS 1, 2, and 3 PROPOSED TECNNICAL SPECIFICATION (TS) CHANGE T8-352 REVISED PAGES I. AFFECTED PAGE LIST Unit 1 Unit 2 Unit 3 111 111 111 1.0-11 1.0-9 1.0-11 + 3.2/4.2-9 1.0-11 3.2/4.2-10 3.2/4.2-10 3.2/4.2-9 3.2/4.2-10 3.2/4.2-14 3.9/4.9-6 3.9/4.9-11 II. REVISED PAGE8 See Attached.
e 2,wa ,L m- maa- 6-----wameAmse m .esn 4- mm-w s ,a 4 M om-em-==A-A-Aan---- AmA uMm J s1A.MA- m-_~, - - --& . 4 14b-m n ait., a a- _.a.m, a 4 _ UNIT 1 1 l l REVISED PAGES l i 1 l l 1 l
1 l I i l Section Paae No. B. Coolant Chemistry. ... .. . ... . .. . . 3.6/4.6-5 C. Coolant Leakage. ..... . . . ... ... . 3.6/4.6-9 D. Relief Valves. ..... . . . . . . . . . . . 3.6/4.6-10 E. Jet Pumps. . .. . .. ... . . . . . - . . . . 3.6/4.6-11 F.- Recirculation Pump Operation . ... .... . 3.6/4.6-12 G. Structural Integrity . . . . . . . . . .. . . 3.6/4.6-13 H. Snubbers ... ...... . . . . .. . .. 3.6/4.6 l 3.7/4.7 Containment Systems . ..... . . . ..... .. 3.7/4.7-1 A. Primary Containment. ...... ....... 3.7/4.7-1
-B. Standby Gas Treatment System . ..... . . . 3.7/4.7-13 C. Secondary Containment. . .. . . . . .. . .. 3.7/4.7-16 i
l D. Primary Containment Isolation Valves . .... 3.7/4.7-17 E. Control Room Emergency Ventilation . . . _ . .. 3.7/4.7-19
.F. Primary Containment Purge System . ...... 3.7/4.7-21 G. . Containment Atmosphere Dilution System (CAD) . 3.7/4.7-22 H. Containment Atmosphere Monitoring (CAM)
System H2 Analyzer . . . . . . ...... 3.7/4.7-24 3.8/4.8 Radioactive Materials . . .. . . . . .... .. . 3.8/4.8-1 A. Liquid Effluents . .... . . . .. .... . 3.8/4.8-1 l l 1 B. Airborne Effluents . ... . . . .... ... 3.8/4.8-3 C. (Deleted). .. . . . .. .. . . ....... 3.8/4.8-4 D. (Deleted). . ... ..... . . . . .. ... 3.8/4.8-4 d E. Miscellaneous Radioactive Materials Sources. . 3.8/4.8-5 I F. (Deleted). .. . . . .. . . . . .. . ... . 3.8/4.8-6 ; 1 3.9/4.9 Auxiliary Electrical System . . . . . .. . . . . . -3.9/4.9-1 I A. Auxiliary Electrical Equipment . ... . . .. 3.9/4.9-1 l , B. Operation with Inoperable Equipment. ..... 3.9/4.9-8 BFN iii Unit 1 1
1.0 DEFINITIONS (Cont'd) GG. Site Boundary - Shall be that line beyond which the land is not owned, leased, or otherwise controlled by TVA. HH. Unrestricted Area - Any area at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for industrial, commercial, institutional, or recreational purposes. II. Dose Eauivalent I-131 - The DOSE EQUIVALENT I-131 shall be the l concentration of I-131 (in pCi/gm) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The ; thyroid dose conversion factor used for this calculation shall ' be those listed in Table III of TID-14844 " Calculation of Distance Factors for Power and Test Reactor Sites". JJ. Gaseous Waste Treatment System - The charcoal adsorber vessels installed on the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release. KK. Members of the Public - Any individual except when that individual receives an occupational dose (as defined in 10 CFR 20). l l LL. Surveillance - Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements. Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval. It is not intended that this (extension) provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications. Surveillance Requirements do not have to be performed on inoperable equipment. BFN 1.0-11 Unit 1
't TABLE 3.2.A (Continued)
PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTAIION c: os Minimum No.
- s m Instrument l755 Channels Operable per Trio Sys(1)(11) Function Trio Level Settino Action (1)
- Remarks 1(15) Instrument Channel - 1 150 mr/hr or downscale F 1. 1 upscale channel or Reactor Building Ventilation High 2 downscale channels will
- a. Initiate SGTS Radiation - Refueling Zone b. Isolate refueling floor
- c. Close atmospnere control system.
2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm H and Below 2000 cfm air tiow R.it. SGTS Flow - Train A (A or F) R. H. Heaters heaters shall be saut off. 2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm H and Below 2000 cfm airflow R.H. SGTS Flow - Train B (A or F) R. H. Heaters heaters shall be shut off. La 2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm H and Below 2000 cfm airflow R.H.
;, SGTS Flow - Train C (A or F) heaters shall be shut off.
s R. H. Heaters
,e PO 8, I Reactor Building Isolation 0 i t i 2 secs. H or F 1. Below trip setting prevents Timer (refueling floor) spurious trips and system perturbations from initiating isolation.
1 Reactor Building Isolation 0 i t i 2 secs. G or A 1. Below trip setting prevents Timer (reactor zone) or H spurious trips and system perturbations from initiating isolation. 2(10) Group 1 (Initiating) Logic N/A A 1. Group 1: A Group 1 isolation is actuated by any of the following conditions:
- a. Reactor Vessel Low Low Water Level b.
c. Deleted -j Main Steamline High Flow
- d. Main Steamline Space High Temperature
- e. Main Steamline Low Pressure
TABLE 3.2.A (Continued) PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION c: as Minimum No. [,8 l} Instrument n Channels Operable per Trio Sysfl)(11) Function Trio Level Settino Action (1) Remarks 1 Group 1 (Actuation) Logic N/A B 1. Group 1: A Group 1 isolation is actuated by any of the following conditions:
- a. Reactor Vessel Low Low Water Level
- b. Deleted
- c. Main Steamline High Flow -l
- d. Hain Steamline Space High Temperature
- e. Main Steamline Low Pressure 2 Group 2 (Initiating) Logic N/A A or 1. Group 2: A Group 2 isolation (B and E) is actuated by any of the following conditions:
- a. Reactor Vessel Low Water Level
- b. High Drywell Pressure 1 Group 2 (RHR Isolation- N/A D
, Actuation) Logic
[g i Group 8 (TIP-Actuation) N/A J
.c- Logic
's" 1 Group 2 (Drywell Sump N/A K
{} Drains-Actuation) Logic 1 Group 2 (Reactor Building N/A F and G 1. Part of Group 6 Logic
& Refueling Floor, and Drywell Vent and Purge-Actuation) Logic 2 Group 3 (Initiating) Logic N/A C. 1. Group 3: A Group 3 isolation is actuated by any of the following conditions:
- a. Reactor Vessel Low Water Level
- b. Reactor Water Cleanup System High Temperature
- c. Reactor Water Cleanup System High Drain Temperature
J - bs-n .no u,n2A--- AW A mA -- A L3wwd.4" %u '---n-,Ala.meO 4da o-nFme &A4 e*--- -_bAwasA=-4mm-4*M*--*u'mm mm-m--aa. ---sm--- w -- -- = .a,-- - - ----_,a ---w- _-wn -- w ,,.a_, y UNIT 2 l l l l l i l l 6 REVISED PAGES f _ . . -_, w
1 l l l l Section Paae No. C. Coolant Leakage. . ...... ........ 3.6/4.6-9 D. Relief Valves. . . .... . . . . . ..... 3.6/4.6-10 E. Jet Pumps. . . . . ... . . . . .. . .... 3.6/4.6-11 F. Recirculation rump Operation . . .. . .... 3.6/4.6-12 G. Structural Integrity . . . . . . .. . ... . 3.6/4.6-13 H. Snubbers . . ....... . .. . .. . .. . 3.6/4.6-15 I I 3.7/4.7 Containment Systems . . .... . .. .. . . .. . 3.7/4.7-1 l A. Primary Containment. ... . . . .. . . ... 3.7/4.7-1 B. Standby Gas Treatment System . ... . ... . 3.7/4.7-13 , i C. Secondary Containment. .. ... .. . .... 3.7/4.7-16 D. Primary Containment Isolation Valves . ... . 3.7/4.7-17 l l E. Control Room Emergency Ventilation . . ... . 3.7/4.7-19 F. Primary Containment Purge System . . . . ... 3.7/4.7-21 G. Containment Atmosphere Dilution System (CAD) . 3.7/4.7-22 l H. Containment Atmosphere Monitoring (CAM) I System H2 Analyzer . . . . . . .... .. 3.7/4.7-24 3.8/4.8 Radioactive Materials . . . . . . . ........ 3.8/4.8-1 A. Liquid Effluents . ..... . . . . . .... 3.8/4.8-1 l B. Airborne Effluents . . . . . . .... ... . 3.8/4.8-3 C. (Deleted). . ... ..... . . . . . . ... 3.8/4.8-4 D. (Deleted). . ....... . . . .. .... . 3.8/4.8-4 E. Miscellaneous Radioactive Materials Sources. . 3.8/4.8-5 F. (Deleted). . ... ..... . . .. . . ... 3.8/4.8-6 3.9/4.9 Auxiliary Electrical System . . . .. . .. . ... 3.9/4.9-1 l A. Auxiliary Electrical Equipment . ... ... . 3.9/4.9-1 B. Operation with Inoperable Equipment. . . . .. 3.9/4.9-8 1 ) BFN iii Unit 2
1.0 DEFINfTIONS (Cont'd) i
- 9. Simulated Automatic Actuation - Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.
- 10. Logic - A logic is an arrangement of relays, contacts, and other components that produces a decision output.
(a) Initiatinz - A logic that receives signals from channels and produces decision outputs to the actuation logic. (b) Actuation - A logic that receives signals (either from initiation logic or channels) and produces decision outputs to accomplish a protective action.
- 11. Channel Calibration - Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors. The channel calibration shall encompass the entire channel including alarm and/or trip functions and shall include the channel functional test. The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is l calibrated. Non-calibratable components shall be excluded from I this requirement, but will be included in channel functional test and source check.
- 12. Channel Functional Test - Shall be:
- a. Analog / Digital Channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alarm and/or trip functions,
- b. Bistable Channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alans and/or trip functions.
- 13. (Deleted) -
i BFN 1.0-9 Unit 2
1.0 DEFINITIONS (Cont'd) GG. Site Boundary - Shall be that line beyond which the land is not owned, leased, or otherwise controlled by TVA. EH. Unrestricted Area - Any area at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for industrial,. commercial,. institutional, or recreational purposes. II. Dose Eauivalent I-131 - The DOSE EQUIVALENT I-131 shall be the concentration of I-131 (in pC1/gm) which alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factor used for this calculation shall be tho.e listed in Table III of TID-14844 " Calculation of Distance Factors for Power and Tcr. Reactor Sites". JJ. Gaseous Waste Treatment System - The charcoal adsorber vessels , installed on the discharge of the steam jet air ejector to I provide delay to a unit's offgas activity prior to release. KK. Members of the Public - Any individual except when that individual receives an occupational dose (as defined in 10 CFR 20). LL. Surveillance - Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements. Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval. It is not intended that this (extension) provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. Performance of a Surveillance Requirement within the specified ) time interval shall constitute compliance and OPERABILITY ) requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications. Surveillance Requirements do not have to be performed on inoperable equipment. I BFN 1.0-11 , Unit 2 i I 1
. . _. ~. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - - - - TABLE 3.2.A (Continued) PRIMARY CONTAINMENT AND REACTOR 30!LDING ISOLATION INSTRUMENTATION c: os Minimum No. hlE2 Ins t rument r' Channels Operable ea per Trio Sys(1)(11) Function Trio Level Settina Action (1) Rec. ark s 1(14) Instrument Channel - 1 100 mr/hr or downscale F l. I upscale channel or Reactor Building 2 downscale channels will Ventilation High a. Initiate SGTS Radiation - Refueling Zone b. Isolate refueling floor
- c. Close atmosphere control system.
2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm H and Below 2000 cfm airflow R.H. SGTS tsow - Train A (A or F) heaters shall be shut off. R. H. Heaters 2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm H and Below 2000 cfm airflow R.H. SGTS Flow - Train B ( A or F) heaters shall be shut off. R. H. Heaters u Ia N 2(7) (8) Instrument Channel 12000 cfm and i 4000 cfm H and Below 2000 cfm airflow R.H. SGTS Flow - Train C (A or F) heaters shall be shut off.
.#* R. H. Heaters e
1 Reactor Building Isolation 0 i t i 2 secs. H or F 1. Below trip setting prevents Timer (refueling floor) spurious trips and system perturbations from initiating isolation. I Reactor Building Isolation 0 1 t i 2 secs. G or A 1. Below trip setting prevents Timer (reactor zone) or H spurious trips and system perturbations from initiating isolation. 2(10) Group 1 (Initiating) Logic N/A A 1. Group 1: A Group 1 isolation is actuated by any of the following conditions:
- a. Reactor Vessel Low Low Water Level
- b. Deleted -l
- c. Main Steamline High Flow
- d. Main Steamline Space High Temperature
- e. Main Steamline Low Pressure
TABLE 3.2.A (Continued) PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRUMENTATION c: os f[{@ Minimum No. n Instrument n, Channels Operable per Trio Svs(1)(11) Function Trio Level Settina Action (1) Remarks 1 Group 1 (Actuation) Logic N/A B 1. Group 1: A Group 1 isolation is actuated by any of the following conditions:
- a. Reactor Vessel Low Low Water Level
- b. Deleted
- c. Main Steamline High Flow -{
- d. Main Steamline Space High Temperature
- e. Main Steamline Low Pressure 2 Group 2 (Initiating) Logic N/A A or I. Group 2: A Group 2 isolation (8 and E) is actuated by any of the following conditions:
- a. Reactor Vessel Low Water Level
- b. High Drywell Pressure 1 Group 2 (RHR Isolation- N/A D Actuation) Logic I" 1 Group 8 (TIP-Actuation) N/A J
(( w Logic
, 1 Group 2 (Drywell Sump N/A K Drains-Actuation) Logic 1 Group 2 (Reactor Building N/A F and G 1. Part of Group 6 Logic
& Refueling Floor, and Drywell Vent and Purge-Actuation) Logic 2 Group 3 (Initiating) Logic N/A C 1. Group 3: A Group 3 isolation is actuated by any of the following conditions:
- a. Reactor Vessel Low Water Level
- b. Reactor Water Cleanup (RWCU)
System High Temperature in the main steam valve vault
- c. RWCU System High Temperature in the RWCU pump room 2A
- d. RWCU System High Temperature in the RWCU pump room 28
- e. RWCU System High Temperature in the RWCU heat enchanger room
- f. RWCU System High Temperature in the space near the pipe trench containing RWCU piping
TA8tE 3.2.8 INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS c D2 D y Minimum No. Operable Per
$7 u Trio Svs(1) Function Trio Level Settina Action Remarks 2 Instrument Channel - 1 470" above vessel aero. A 1. Below trip setting initiates Reactor Low Water Level HPCI.
(LIS-3-58A-D) 2 Instrument Channel - 1 470" above vessel sero. A 1. Multiplier relays initiate Reactor low Water Level RCIC. (LIS-3-58A-D) 2 Instrument Channel - 1 398" above vessel zero. A 1. Reactor Low Water Level Below trip setting iriitiates -l CSS. (LS-3-58A-D) Multiplier relays initiate LPCI.
- 2. Multiplier relay from CSS initiates accident signal (15).
2(16) Instrument Channel - 1 398" above vessel sero. A 1. Below trip settings, in ya Reactor Low Water Level conjunction with drywell to
's (LS-3-58A-D) high pressure, low water
.#" level permissive. ADS timer w timed out and CSS or RHR pump running, initiates ADS.
as
- 2. Below trip settings, in conjunction with low reactor water level permissive, ADS timer timed out.
ADS high drywell pressure bypass timer timed out, CSS or RHR pump running, initiates ADS. 1(16) Instrument Channel - 1 544" above vessel zero. A 1. Below trip setting permissive Reactor Low Water Level for initiating signsis on ADS. Permissive (LIS-3-184, j 185) 1 Instrument Channel - 1 312 5/16" above vessel zero. A 1. Below' trip setting prevents ' Reactor Low Water Level (2/3 core height) inadvertent operation of * (LIS-3-52 and LIS-3-62A) containment spray during ' accident condition. I I b
l 3.9/4.9- AUXILIARY ELECTRICAL SYSTEM l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9.A. Auxiliary Electrical Eaulement 4.9.A. Auxiliary Electrical System 3.9.A.3. (Cont'd)
- d. The 480-V shutdown boards i 2A and 2B are energized.
- e. The units 1 and 2 diesel
- auxiliary boards are energized.
- f. Loss of voltage and degraded voltage relays OPERABLE on 4-kV shutdown boards A, B, C, and D.
- g. Shutdown buses 1 and 2 energized.
- h. The 480-V reactor motor-operated valve (RMOV) boards 2D & 2E are energized with motor-generator (mg) sets 2DN, 2DA, 2EN, and 2EA in service.
l 4. The three 250-V unit batteries, 4. Undervoltage Relays ! the four shutdown board batteries, a battery charger a. l (Deleted) for each battery, and associated battery boards are b. Once every 18 months, b OPERABLE. the conditions under which the loss of voltage and degraded voltage relays are required shall be simulated with an undervoltage on each shutdown board to demonstra.a that the associated diesel i generator will start. 1 1 a l _ i BFN 3.9/4.9-6 l Unit 2 ! l
i l l 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9.B Operation With Inocerable l Eauipment 1 h 8. From and after the date that one of the 250-V shutdown board batteries and/or its associated battery board is found to be INOPERABLE for any reason, continued REACTOR POWER OPERATION is peraissible during the succeeding five days in accordance with 3.9.B.7.
- 9. When one division of the logic systen is INOPERABLE, continued REACTOR POWER OPERATION is permissible under this condition for seven days, provided the CSCS requirements listed in Specification 3.9.B.3 are satisfied. The NRC shall be notified within 24 hours of the situation, ';he precautions to be taken during this period, and the plans to return the failed component to an OPERABLE state.
- 10. (deleted)
- 11. The following limiting conditions for operation exist for the undervoltage relays which start the diesel generators on the 4-kV shutdown boards.
BFN 3.9/4.9-11 Unit 2 1
e--...a_+_c__.p A S-me. 4 _ __ _a.._a,. _a. ..ww. e.,,. Am A.e ,a .. w, eae. . u.2 ,m- _. -- - -- ,--_, --- _,_- _ --- --___,__, ___,_,, J h UNIT 3 REVISED PAGES J
il i Section Egge No . B. Coolant Chemistry. .. . . . . . . ...... 3.6/4.6-5 C. Coolant Leakage. ... ... . . - . .. . .. . 3.6/4.6-9 D. Relief Valves. . . .. ... . .. . . .... 3.6/4.6-10 E. Jet Pumps. . . . . .. . . . . .. .. . ... 3.6/4.6-11 F. Recirculation Pump Operation . . . ... ... 3.6/4.6-12 G. Structural Integrity . . . . . .. ... ... 3.6/4.6-13 i H. Snubbers . . . . ... . . . . . . ... .. . 3.6/4.6-15 3.7/4.7 Containment Systems . ...... . ... .. ... 3.7/4.7-1 l A. Primary Containment. ..... . . . . .... 3.7/4.7-1 B. Standby Gas Treatment System . . . .. . . .. 3.7/4.7-13 C. Secondary Containment. ... . .... .. . . 3.7/4.7-16 D. Primary Containment Isolation Valves . . ... 3.7/4.7-17 E. Control Room Emergency Ventilation . . .... 3.7/4.7-19 F. Primary Containment Purge System . . . . .. . 3.7/4.7-21 G. Containment Atmosphere Dilution System (CAD) . 3.7/4.7-22 H. Containment Atmosphere Monitoring (CAM) System H 2 Analyzer . . . . . ....... 3.7/4.7-23a 3.8/4.8 Radioactive Materials . . . ... . .. . . . ... 3.8/4.8-1 A. Liquid Effluents . . . . .. . .. . . . . .. 3.8/4.8-1 B. Airborne Effluents . .... . . . . .... . 3.8/4.8-3 C. (Deleted). . . ..... .. . . . .. .. .. 3.8/4.8-4 D. (Deleted). . .. ... ... . ... ... . . 3.8/4.8-4 -f E. Miscellaneous Radioactive Materials Sources . 3.8/4.8-5 F. (Deleted). . .. ... ... . ..... . . . 3.8/4.8-6 3.9/4.9 Auxiliary Electrical System . . . . . .. . . . .. 3.9/4.9-1 A. Auxiliary Electrical Equipment . . . . . .. . 3.9/4.9-1 BFN iii Unit 3 i
I 1.0 DEFINITIONS (Cont'd) ! i GG. Site Boundarv - Shall be that line beyond which the land is not owned, leased, or otherwise controlled by TVA. HH. Unrestricted Area - Any area at or beyond the SITE BOUNDARY to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the SITE BOUNDARY used for industrial, commercial, institutional, or recreational purposes. II. Doce Eouivalent I-131 - The DOSE EQUIVALENT I-131 shall be the concentration of I-131 (in pCi/gm) which alone would produce the i same thyroid dose as the quantity and isotopic mixture of I-131, I-132. I-133, I-134, and T-135 actually present. The thyroid dose conversion factor used for this calculation shall be those listed in Table III of TID-14844 " Calculation of Distance Factors for Power and Test Reactor Sites". JJ. Gaseous Waste Treatment System - The charcoal adsorber vessels installed on the discharge of the steam jet air ejector to provide delay to a unit's offgas activicy prior to release. KK. Members of the Public_ - Any individual except when that individual receives an occupational dose (as defined in 10 CFR 20). LL. Surveillance - Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements. Each Surveillance Requirement shall be performed within the specified surveillance interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval. It is not intended that this (extension) provision be used repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages. Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications. Surveillance Requirements do not have to be performed on inoperable equipment. l A BFN 1.0-11 Unit 3 l
TABLE 3.2.A (Continued) PRIMARY CONTAINMENT ANO REACTOR BUILDING ISOLATION INSTRUMENTATION [fCy Minimum No. Fu se Instrument
" Channels Operable La per Trio Svsfl)(ll) Function Trio Level Settino Action (1) Remarks 2(7) (8) Instrument Channel 22000 cfm and i 4000 cfm. H and Below 2000 cfm airflow R.H.
SGTS Flow - Train 8 (A cr F) heaters shall be shut off. R. H. Heaters 2(7) (8) Instrument Channel 22000 cfm and i 4000 cfm H and Below 2000 cfm airflow R.H. SGTS Flow - Train C (A or F) heaters shall be shut off. R. H. Heaters 1 Reactor Building Isolation 0 i t i 2 secs. H or F 1. Below trip setting prevents Timer (refueling floor) spurious trips and system perturbations from initiating isolation. 1 Reactor Building Isolation 0 i t i 2 secs. G or A 1. Below trip setting prevents Timer (reactor zone) or H spurious trips and system perturbations from initiating I" isolation. 2(10) Group 1 (Initiating) Logic N/A A 1. A Group 1 isolation is actuated by any of the following
$# conditions:
gg a. Reactor Vessel Low Low Water Level b .. Deleted -{
- c. Main steamline high flow
- d. Main steamline space high temperature
- e. Main steamline low pressure 1 Group 1 (Actuation) Logic N/A B 1. Group 1: A Group 1 isolation is actuated by any of the following conditions:
- a. Reactor Vessel Low Low Water Level
- b. Deleted -l
- c. Main Steamline High Flow
- d. Main Steamline Space High Temperature
- e. Main Steamline Low Pressure
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