ML20151U103
| ML20151U103 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/27/1998 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20151U095 | List: |
| References | |
| NUDOCS 9809100286 | |
| Download: ML20151U103 (160) | |
Text
{{#Wiki_filter:ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1.1-1 APPLICABILITY: CA, CP, DC, WC REQUEST: CTS 1.3, Analog Channel Operations Test CTS 1.3, Channel Operational Test [Diablo Canyon) CTS 1.7, Channel Functional Test [Diablo Canyon) CTS 1.35, Trip Actuating Device Operational Test [ Wolf Creek) CTS 1.36, Trip Actuating Device Operational Test [Callaway] CTS 1.37, Trip Actuating Device Operational Test [ Comanche Peak] CTS 1.38, Trip Actuating Device Operational Test [Diablo Canyon) DOC 1-30-A ITS 1.1, Channel Operational Test (COT) ITS 1.1, Channel Functional Test (CFT) [Diablo Canyon) ITS 1.1, Trip Actuating Device Operational Test (TADOT) JFD 1.19 These are changes to both the CTS and the STS and are considered generic. Therefore, they are beyond the scope of the conversion review. The DOC states that these changes are consistent with TSTF-39, Rev.1. Also, Diablo Canyon's ITS markup appears to be in error as shown by " Channel Operational" versus " Channel Operational Test (COT)." Comment: If NRC has not approved TSTF-39 by the time the draft safety evaluation is prepared, then these changes should be withdrawn from the conversion submittal at that time. These changes will not be reviewed on a plant-specific basis. In addition, correct the Diablo Canyon ITS markup for COT. FLOG RESPONSE: TSTF-39 Rev.1 has been withdrawn by the TSTF. However, changes addressed in TSTF-39 Rev.1 have been subsumed by TSTF-205. Revision 1 of TSTF-205 is currently undergoing final review by the TSTF members. After finai wording changes for the COT definition as well as Section 3.3 Bases changes to establish the requirements for relay contact surveillance testing (issue originally raised at Peach Bottom) are agreed upon, Revision 1 will be submitted for NRC review. The attached pages represent the definition changes to be included in Revision 1. The Section 3.3 Bases changes will be addressed under that Section's review. ATTACHED PAGES: , CTS 1.0 - ITS 1.0 , pages 1-1,1-1a,1-3,1-5,1-6, and 1-6a A, page 6 B, page 4 Enclosure SA, Traveler Status Sheet Enclosure SA, pages 1.1-2,1.1-4, and 1.1-6 A, page 2 B, page 2 9009100286 ADOCK980827 05000483, PDR p PDR f.
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-+-e- DEF]NITIONS RE VISIOf.s ]
l ~., The defined terms of this section appear in capi (alized type ano are applicable /- throughout these Technical Specificatio g an/ /f u ef, ACTION g, ;gg.j;,,, ./, ja f,)<an
-h ACTIONSshall be that rt of a -T;;F-i::! Specification tict? prescribes i
- rdi:1 x:;ru rau-;r;d nder designated [nditionsw/#i n syre/[/,/ t /--4/ -A
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ACTU TION LOGIC TEST regurre r 0/'EA'Mg ,44 /oj,c circaf-k 4-+ An ACTUATION LOGIC TEST shall be the application o variots simulate e de/sde/ input combinations in conjunction with each possible interlock logic state and j_g verification of the required logic output. The ACTUATION LOGIC TEST g shall f, include a continuity che -as-.a-m*4eenr of output devices. j af , mfng ,
-'"".LO7 CHANNEL OPERATIONAL TEST [ COT)
O /'I~A A cst 2.2 ' . "';" LOC 0;.n.aCL OPC",ATIO,"'L T ""shall be the injection of a simulated /~8 /~A or cc-/ssal signal intope channel as close to the sensor as practicable to verify /-84-A The l'",LO" C:=CL Cd7~ OPERABILITY;fci;rm, 0"""^T!0':'m T ';T shall include
'nt:r!=k =d/;r trip a ustments, asfun:ti=:.
necess y, of th ala in er- / n ek andh Trip 5etpoint at t the Setpoints within t r: uir:d --Q j,; neceneryrange and accuracy. regu, retutra -R,rcGnne .1ygggy 9,/. / --/S ,_ AXIALFLUXDIFFERENCE(AS OfER $ l.2r)/tueA j, j,,A 1.' /XIAL TLUX 0:TTERER^ shall be the difference in normalized flux signals 7,,,g f,,j between the top and botto halves of ? +: n:t; =gexcore neutron detector.
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CHANNEL CALIBRA W og4y d sac n ecena - 5- A CHANNE lonm Aun vnall be th adjustmen , as nece s y, of the i channel M that it responds within t -re';;ir d- ange a ccuracy to known /-d2-d luu v f , .sut. The CHANNEL CALIBRATION-~snaii encompass th: entir: ch:nn:1 g ':1; din; th; .4c r; and cie. .,, int ri n k =d/;r tri- f =:ti=: =d may be wf _72 , ,A ,
,p performed by4any series of sequential, overlapping, or total channe step ' ' " >-
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$ /,'/ g, CHANNEL CHECK .g,,el,nn,f[niferr. !* !~8
) by eJ,arvegnj 4 A CHANNEL CHECK shall be the qualitative assessment V of channel behavicr / g/-A during operation t; eb: m tier This determination shall include, where possible, comparison of the channel indication and h status other indications -aeeMor status derived f rom independent instrument ch nels measuring the same parameter. .f.,
l l CALLAWAY - UNIT 1 1-1 -
_ INSERT 1.1-A f i o.p all device r in -fk f<aj f;,- cLnnel o/>rRA8rtrrf.
-!"c!uding-all-components in the cha=c!, such as *nne, inter!cchs, displays, /-3'0-A
- 2"d trip fhnetions, required 10 pc-form the :;pecified cafety function (s) The /-32-A m , . . _ ,
l " "~ COT may be performed by means of any series of sequential, overlapping, or 'Q r total channel steps,3c i;; the entire ch;=d is tes cd. g f, f._, m _ - INSERT 1.1-B o // devicer rn 44e e Aoane / l regu rad -R>,- cL.nnel l QOFEAAtrLr ry. )
- these components, such as sensors, a!a:=, display and trip f=^tions, /-07-M
-required to perr em the specif!:d ::afety fulAction(3)kCalibration ofinstrument
/-32-A l channels with resistance temperature detector (RTD) or thermocouple sensors M-/ 3- 440 may consist of an inplace qualitative assessment of sensor behavior and S / /G l normal calibration of the remaining adjustable devices in the channel.
"/hencver a senciag e!ement-iweplaced, the next regt' ired C"ANNEL-- TR-/. o-404 l w D A Y . YT3 T4 A T*^17 1 11 _1_ _ J ._ __ _ . ._1 m m m om,, o n ] ,'kro s .* _ __ AL 4 mm-___--_ AL - '
VnL A1J AV"k i lVlN Dildll AllblLJLAb QA A AAlp4uww ha vaa vus a va utaVA4 LA AGE bVA4 4pG140 LA Ab
--other sensing elements-with the recently-insta!!cd sensing e!ement. The CHANNEL CALIBRATION l
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DEFINITIONS 4 7 - AVERAGE DISINTEGRATION ENERGY
' .17- I shall be the average (weighted in' proportion to the concentration of I each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95?, of tne total noniodine activity in the coolant.
(Erf) V ENGINEERED SAFETY FEATURES RESPONSE TIME i: Th. C:0:.';;;",' CAI'TY I:A C: SF RESPONSE TIME shall be that time [ interval from when the monitored parameter exceeds its ESF Actuation Setpoint at the channel sensor until the ESF equipment is capable of performing its /-4/-d safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.g
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LEAKAGE,
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"^J,.0Aov LEAKAGE; or (gcr) LEAMACE fru.mre w'} *
.7. cr,- V Reactor Coolant System l;;L.;s through a steam generatorg te the Secondary 0;;i...;. Systemj
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MASTER RELAY TEST Nu(& m & r con.ru+ *E reta d /-D/-A
+-Mr A MASTER RELAY TEST hallU: " energiz;;u c' eachVmaster relay and /.-yd A veri i;:ti;n e' OPERABILITY of eachblay. The MASTER RELAY TEST shall include a co inui.ty check of each associatedg slave relay.7Xe /MArrsA g rErr d/,/-
reyfred meant "E"eEQ-Me le fsdeemed
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Thi; ;e:c;;rj dee; in;; de per;;n; h; .:; pertion; ;' :n; :it; f r r:; ::- ti;r.;;, ;;;;p;ti nel, or thcr purp;;;; ;; :::::icted ith th: ?! !Nt. CALLAWAY - UNIT 1 1-3 Amendment No. 75, 75', 58 _ ~ . _ . . - , _ .
DEFli4ITXONS . 00ADRANT POWER TILT RATIO [&f14) pp-rg l-/?-A
" 25 ^U?;P.^.."T "CWER 7:LT RAT:vvshall be the ratio of the maximum upper excore l
. detector calibrated output to the average of the upper excore detector cali-brated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, which-ever is greater. Wi;th one excore detector inoperable, the remaining three detectors shall be used for computing the average.
RATEDTHERMALPOWER(417) R1-f 1.25 RATE T""TS.AL POWETJshall be a total core heat transfer rate to the /-e/-lA reactor coolant of 3565 KWt.
. (A"r0 REACTOR TRIP SYSTEMYRESPONSE TIME AYE (~ R 1~E /-67-A i.27 The-R"ACT n TR:I YSTC"' RESPONSE T) ME shall be the time interval from l when the monitored parameter exceeds its1 Trip Setpoint at the channel sensor until loss of stationary gripper coil voltage. ENIE#7-/./-G n_t D R_ D. T h __D , T_ T_ U. T U.
- 1.2S A 'I"0",TA"L" :" !'T h:11 b; Ony ^ f th::0 ::nditi^"! !?^"'#4ad 4a l S ti:n 50. 72 t^ 10 C"", $ rt 50.
4 DES **IC*ED ^r0 ODED.^!OW /-27_M
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w, whichever i: 1 c: , . APL"" nd APL ^"" crc d; fir.cd 'n Speci#icatic-: 2.2.'
- nd d. C. ". , r;;p;;tively. "A."00 may bc nttr;d :t the dit r *icr Of the 1icca:::.
SHUTDOWN MARGIN (fbM) sg e can+n ) (~ (R c car) j yg 1.20 """T00R" It"RC:!Nshall be the instantaneous amount of reactivity by which l the reactor is subcritical or would he suberitiq a1 from its present condition assuming all # 1' 1:ngth rod clustemassemblies+(:h down ;nd ;catr;ii are fully inserted except for the singl rd cle:t:r :::ctly- of highest reactivity worth which is assumed to be fully thdrawn. J2~NMgr- /./-g e r. . e. o n. ,.,u. . n_, e v 8CCA l-2+-A
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The SIT: 000NOARY 3 hell be thet line bejcad which the 1:nd i: tither l 1.
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SLAVE RELAY TEST concit+ o-f in W','g / l-A 4-s4- A SLAVE RELAY TEST shal1V4c the' energi :t$ n ;P eachVslave relay and -3D-A , veri ic:ti: ;f OPERABILITY of each relay. The SLAVE RELAY TEST shall includ A/~/ a co tinuit check 2: 2 4 " 4 -"r o - ss i dgtes le actuation device E hva W' mi , yiy Se 1-5 Amendment No. JE, 48, 25. 50 CALL A - UNIT 1
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1 STAGGERED TEST BASIS rNfr_g7 /. /--E -
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3.ou 1._. 3 .E. ...L.. .- . THERMAL POWER reache V
-hM DiERMAL POWER shall be the tota 1 core heat transfer rate to the reactor N/'A
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TRIP ACTUATING DEVICE OPERATIONAL TEST [7A' bd /~) ,
-4rG+ T AC*"ATING "C"IC: 0" O ' '
1 consist of operating the /-- 4 Tripm.._..m.._u._. Actuating _ The .... Device,.and. . _v.erify(.kMAL m.. ms. .
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6 J l CALLAWAY - UNIT 1 1-6 Amendment No. J5,2S, M,50
I l INSERT 1.1-I A STAGGERED TEST BASIS shall consist of the testing of one of the /-2 2-A systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function. V~ N INSERT 1.1-J ef a lI olevrce.r in +Ae naIr.-a) A h-r as ala:y y evree da eduadrC&AA' &tzrf. inc!uding !! ccmponents in the eA. channe , eey! such =, inter!ccas, displays, /-Jo-A
, -and t:ip func icns, required te perform the specified safety function (s). The /-32-A TADOT may be performed by means of any series of sequential, overlappingFf /.3 Jes--
or total channel steps;-se that the entire channcM:csted. 4 / /- / __ .s. . 1. _ n 1 ,. . Q l. I- 2
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- CHANGE NUMBER HSHC DESCRIPTION addressed by the definition of the term Mode. This I definition stipulates that fuel be in the vessel in order '
to be in a "H0DE." These changes are administrative /7n ndure, except for the = =ter b and c, :dded per trevela- _-r A/J ^;f TSTF SS and addressed in NSHC LS 2.-- g /, / 9 1 26 A New sections 1.2,1.3, and 1.4 are incorporated into the improved TS to be consistent with NUREG-1431 Rev. 1. Section 1.2 provides specific examples of the use of the logical connectors AND and 03 and the numbering sequence associated with their use in the improved TS. Section 1.3 deals with the proper use and interpretation of Completion Times, and specific examples are given that will aid the user in understanding Completion Times. Section 1.4 deals with the proper use and interpretation of surveillance frequencies. Specific examples are given that will aid the user in understanding surveillance frequencies as they appear in the improved TS. The proposed changes are administrative in nature and by themselves are not technical changes, incorporating travelers-WOC 74 Rev.1 Y / F .^ d ,
=d uE 90- ~73YP~- 310 and '7^.t'rF~ 2g1, & f, +-l 1 27 M The definition of Restricted AFD Operation (RAFDO) is deleted from the current TS, in accordance with NUREG 1431 Rev. 1. See CN 115 H in the 3/4.2 package.
1 28 LG The current TS definition of CONTROLLED LEAKAGE is deleted to be consistent with NUREG 1431 Rev. 1. The RCP seal water' return flow limit is moved to a licensee controlled document.
. z~h/. CERT ~ .Sh-6 Q 3 S~ S*-2 1 29 LS 3 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B).
T.r7F~- 2 OS, 1-30 A Consistent with 4STT-39. Rev. 1 Vthe definitions of -? /, H0 3-- Channel Operational Test (C0T)g ] and Trip Actuating O /. /-/
# pj,y4,,. ge h 7~e r+; pevice Operational Test (TAD 0T) are expanded to include 1 the details of acceptable performance methodology.
fj g, 4(h,,.+ Performance of these tests in a series of sequential, overlapping, or total denrci steps provides the necessary ssutance of appropriate oper ion of the m,t-;rc channel, relay, or-l o/evtce, reig<chvef.This change also makes the COT [ ] and TAD 0T definitions consistent with the efinition of Channel Calibration which already cont ns similar wording. c u , <o + T5 on d +L e AluREG-I f3'I
,4 DESCRIPTION OF CHANGES TO CURRENT TS 6 5/15/97 l
CONVERSION COMPARISON TABLE - CURRENT TS 1.0 Page 4 of 4 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 1-28 The definition of CONTROLLED LEAKAGE is deleted. The RCP No - See change No. See Change Yes - Moved to USAR Yes - Moved to FSAR LG seal water return flow limit is moved to a licensee number 1-05 A. Nunt>er 1-05 A. Section 16. Section 16.4. t controlled document. 1-29 Allows measuring QPTR when one or more excore detector No Yes - Portion of No No LS-3 channels are inoperable with movable incore detectors. definition being ff,4 Wg changed is only in I' J f/.ve r ge
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/,7"Ti,r+.j CPSES CTS. 1
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1-30 The definitions of Channel Operational Test (C0TPT ] and Yes Yes Yes Yes 7 /,0--cgg-A TADOT are expanded to include the details of acceptable $ /, /.-f , performance methodology. Performance of these tests in a series of sequential, overlapping or total f.Al steps , provides the necessary assurance of appropriate operation of the-entwe-channe1, re lay, or NevEce y Ye rf ecHval y. 1-31 Definitions of specific plant systems which are defined by Yes Yes No - not in current No not in current TS. TS. A the plant design are deleted. 7-rp.rF-25 e [ g 1+32 The definitions of Channel Cal bration. COT.dand TADOT areYes Yes Yes Yes A reworded to be consistent withMT" " - The revised wording O / /-2 clart fies what is meant by " entire channel."7 Ae o/e0,sr/r,n ,[ A 6 ,/fon dej Te Te s-/- 7,r C ls~ /adjfL/ aNS' . I [* O- U3 1 33 This change revises the current TS definition of Core Yes Yes N AS. A A M'Yes O/*l-3 A Alteration to delete "or manipulation" and " conservative." /07 /*'*8'7 8 # C I- U/ Prs ~ndr .
/- 3+ T h l Seer /-34-U-2 No No Nor- t-w A Afo -ree yez Alo -ra e No-se e Q 36.w2 CONVERSION COMPARISON TABLE - CURRENT TS CN I-T1-A. CN /-31-A . 5/15' CN /-37-A.97 -.m_ _ _ _ _ - _ . _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - r
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INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0
..~.1 TRAVELER # STATUS DIFFERENCE # COMMEhTS TSTF-19. Rev. 1 Net-Incorporated -#A- /. /-/2 h NRC approvedg:: 0f ^
R -/ H /4 irr;cler cut of' dte.
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TSTF Z. "cJ 1 Incorporated 1.1 9) Q /,/-/ g/;:3j TSTF Si :,cerp;r tcd 1.1 -- 1 g /, /-2 -- -%f--/.f tes F ,
-!STI ^^ Ir.cerp;r:ted 1 g /,fg g f,f .g h*i TSTF 111. Incorporated 1.1 5 -
Rev. 1 e' ! T C gTP,c'i-upi Q
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fk .. E' - MARK UP OF WOG STS REV 1 (NUREG 1431) 5/15/97 i i
l Definitions 1.1 i 1 l ) 1.1 Definitions CHANNEL CALIBRATION sequential, overlappingp:11b aticns or total channe~i *' (continued) steps,-ce that thc catire chenaci is calibrated. ' '
~ l Q/'.~/-2 CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
l CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual TEST (C0T) signal into the channel as close toge ser.sor as practicable to verify the OPERABILITY ef-rcquired e[a///evhu/nV-l'" clara, intericck, display, end trip f cticas. Un = ding-- 111 Sanne/regur~rd b -))).";a ;^nentCjghelchpne]3;fZ::"f:=% 1.1 9-Gnnel 0fEKAfrLrff. 9ttCbKT 7 2 ?; D K +2l7 3 'y.tip Q M y iX Ed 7tc -en 73 g
~ BY'6~'? wWWWM'#tYf'intt 45nM")'*1heiCOTunay Q l.j-l peipenfgtmegbjMI@Eayeser4esigfjsMehtiH]J Q /. /-2 bV,eflappfsggtot~aKchange]Esteng tC;Zt.'^ hr@t' _d F l > reta'j " 4"^* Mft;EiLe;t'ipThe wi shall include adjustments, and tri as j O/'E#Atr4.n7ruc4 necessary, of Ine requiredare alarm, within interlock,Se#88/qEg 1
setpoints ke that range and accuracy.< the setpoints t r- j 1 CORE ALTERATION CORE ALTERATTON shall be the movement of any fuel, I sources, or reactivity control components, within the < reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position. CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5, Plant operation within these limits is addressed in individual Specifications. DOSE EQUIVALENT I 131 DOSE EQUIVALENT I 131 shall be that concentration of 1131 (microcuries/ gram) that 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. Tha thyroid dose conversion factors used for this
) (continued)
MARK UP OF WOG STS REV 1 (NUREG 1431) 1.1 2 5/15/97 i
l I l Definitions 1.1 x 1.1 Definitions l l LEAKAGE 2. LEAKAGE into the containment atmosphere from (continued) sources that are both specifically located ; and known either not to interfere with the : operation of leakage detection systems or not j to be pressure boundary LEAKAGE: or l
- 3. Reactor Coolant System (RCS) LEAKAGE through a steam generator (SG) to the Secondary System:
1
- b. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injcctica or 1.1 10 leakoff) that is not identified LEAKAGE:
- c. Pressure Boundary LEAKAGE LEAKAGE (except SG LEAKAGE) through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.
sk MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing each
~ /./-9 regwTrel master relay and verifying the OPERABILITY of each relay. Mf.C O'?
The MASTER RELAY TEST shall include a continuity check of O//-/ each associated 4 reguireofslave r)elay. ,.Yy7,,g g,_ MODE A MODE shall correspond to any one inclusive combination l of core reactivity condition, power level, average reactor ! coolant temperature, and reactor vessel head closure bolt i tensioning specified in Table 1.11 with fuel in the ) reactor vessel. l OPERABLE OPERABILITY A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of g 7.gy performing its specified safety function (s) and when all necessary attendant instrumentation, controls, normal or
' */' /"'b'I['/' #'" emergency electrical power, cooling and seal water,
/lubrication, and other auxiliary equipment that are ue 4ever 8 h4gty/Jer/ef oferg/
,,-,t,., ff, equired for the system, subsystem, train, component, or v ; -//.,/ , fj / device to perform its specified safety function (s) are i effe, i Z f" {f also capable of performing their related support l
_' "'7' "~ '" ' ~ n " function (s) . ' J] (continued) i MARK UP OF WOG STS REV 1 (NUREG-1431) 1.1-4 5/15/97 ' i
. - . = - _ _ - - - . - . _ - -
l Definitions 1.1 1.1 Definitions l SHUTDOWN MARGIN (SDH) SDH shall be the instantaneous amount of reactivity oy which the reactor is subtritical or would be subcritical : i from its present condition assuming: 1
- a. All rod cluster control assemblies (RCCAs) are fully I inserted except for the single RCCA of highest l reactivity worth, which is assumed to be fully l withdrawn. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDH: and
- b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal Icro pcar B PS dcsign icvcl bot 3 ero;'powe Clempenatur_esI SLAVE RELAY TEST A SLAVE RELAY TEST shall consist of energizing each slave- J./-9 \
g 4; g i relay and verifying the OPERABILITY of eac slave lay. gf,f_j The SLAVE RELAY TEST shall include, er .i =2 .gd continuity check of associated 4 testable ac u inn devices. 1 reywred reguireQ l STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the
'T4e AMvr #E TEIT% 7 Surveillance Frequency, so that all systems, subsystems,
)
/cje-/arme/
a A caw < Fay channels, or other designated components are tested during
/ n Surveillance Frequency intervals, where n is the total '
fewey o ver/4 , - f.reguen#d /sdeg
, number of systems, subsystems, channels, or other
- /:
/,( ., 7, ,[j, ,e,}-/,
,_- ;/ - /_- u designated components in the associated function.
~rL, m L. :)
ERMAL P0iiLK THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. e fAe - TRIP ACTUMING DEVICE A TADOT shall consist of' operating the trip actuating 3 OPERATIONAL TEST device and verifying theV0PERABILIT Cf icquired alore. 1.1 1 l (TAD 0T) anter;cck, dispicy, and trip functi]Y ons, j :]gdigg;elj 1.1 9 { g.// evtc,f /n f4e 'C^""^"^"tE "4"
' "4 th""chfhf~T#2$O'.tGslht0-3 0Mf, ~
W 4. . ;3 c Aanne / reguf**/ b - EI' ?? 7 "^'IIIE2 #dO0tI0"'I'~ 5 4Ui?dd I NIOi" tb d)/ /-/ Ay,- gerree g f, /_2 ea^c4+4=d"sefety y means of any series .ofun @f; sequential,loyverlappigg. or .1 M
- total channel steps ~ - "" " " ' ' ~ 5560 ?,~ ,4.t2cf.
~
- The TADOT shall include adjustment, as necessary, of the l trip actuating device so that it actuates at the required l setpoint within the requirchaccuracy.%
! n e cc.r.ra ry ? l l l MARK UP OF WOG STS REV 1 (NUREG 1431) 1.1 6 5/15/97
CHANGE NUMBER JUSTIFICATION r figures, as well as the methodology for developing the [COMS] p) setpoints. This change is consistent with traveler "^" " "- ' O / /-5~ 7Trp .:233, 2!J:l 1.1 7 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 68). 1.1 8 The reactor vessel head closure bolt requirements for H0 DES 4, 5. and 6 are clarified. The proposed change revises note b for H0 DES 4 and 5 to ) refer to " Required reactor vessel head closure bolts fully tensioned" and note c for H0DE 6 is revised to read " Required reactor vessel head closure bolts less than fully tensioned." The transition point between j H0 DES 5 and 6 would also be clarified as occurring when the required ' reactor vessel head closure bolts are less than fully tensioned. The required number of closure bolts. which may be less than,the total number, is established by analysis that demonstrates adequate 0 ring compression to prevent leakage and ensures that ASME Section III limits g j, j_9 , , , , for affected components are not exceeded. This change is consistent ' ' ' ' ~ ~ wit b .M terseler Sc4ne TSTF
// o ? - } mag ab 19P p)& Mwfc- tu 3 (da+e)WR 1.1 9 Consistent with TSTF J. b.1.- the definitions of Channel Operational CC '"
Test (C0T)j[ ] and Trip Actuating Device Operational Test (TAD 0T) are " b 'N. 3 /%eb 8'I'/ 3xpanded to include the details of acceptable performance methodology.m ,
~T?s4; Ilave '
erformance of these tests in a series of sequential. overlapping. or ~ 'd M l 7' tal dr4 steps provides the necessary assurance of appropriate E/*/-/ el.7 e @ operation of the Mrc channel This change also makes the COThnd TAD 0T definitions consistent wi h the definition of Channel Calibration which already contains similar ording.
> re lay, o - clevice j verf a chivoIy.
1.1 10 This change is based on the current 15 definition of CONTROLLED l LEAKAGE. This change is a clarification only and does not affect the way RCS water inventory balances are performed. 1.1 11 Adds new example to ITS Section 1.4 to clarify surveillance frequencies that are contingent on both a specified frequency and plant conditions. The ITS contains many Surveillance Frequencies that are contingent on both a "specified Frequency" and plant conditions. For example.
"Within 7 days prior to the initiation of Physics Tests." and " Prior to entering MODE 4 from H0DE 5 if not performed within the previous 92 days." These Frequencies do not fall clearly under any of the existing Section 1.4 examples. The proposed example is needed to make clear that 1) the SR 3.0.2 extension of 1.25 times the specified frequency applies, and 2) that the interval allowed to perform a missed Surveillance by SR 3.0.3 applies.
l SR 3.0.2 is clear that the 1.25 extension may be applied to "the interval specified in the Frequency". so the proposed change does not < change the intent of the Specifications. SR 3.0.2 applies if a Surveillance is not performed within the "specified Frequency". Again.
) the example does not change the intent of the Specifications but only JUSTIFICATION FOR DIFFERENCES TS 2 5/15/97
\ .
CONVERSION COMPARISON TABLE FOR NUREG-1431 DIFFERENCES' Page 2 of 2 SECTION 1.0 DEFINITIONS I DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON C0HANCHE PEAK WOLF CREEK CALLAWAY n Marke Relay -n.s+, Elave fe f=y-Gr+, 1.1-9 The definitions of Channel Operational Test (C0Tf[ ] and Yes Yes Yes Yes Trip Actuating Device Operational Test (TA00T) are expanded to include the details of acceptable performance methodology. Perforniance of these tests in a series of -p /,3 y sequential, overlapping, or total :t - 2 steps provides g 7* the necessary assurance of appropriate operation of the
. ... channely re laf, e w &evice, verpc-lively.
1.1-10 This change is based on the current TS definition of No - Not part of No - Not part of No - Maintaining ' CONTROLLED LEAKAGE. This change is a clarification only Yes current TS. current TS. ISTS wording. and does not affect the way RCS water inventory balances are performed. . 6 1.1-11 Adds new example to ITS Section 1.4 to clarify surveillance Yes Yes- Yes frequencies that are contingent on both a specified Yes frequency and plant conditions. '
+
f, /-j y 1~4 e $ehn,*-lfon oh ClfANNEl. CA LrdfATroAl
?? r-evTre)f e,- T~fYf--/Q -/s neve Ne-lwll1 af eg fet ftf ler T h l 0~094 frb s n a/ +4 e->,, ce,.7 / a c. hk % A +4a rrs 2. .T &sar a.rroer.ded wr+4 c /,%ke n i of 4$ere cors, fog,fe, n
l*I~/3 2*NsGR7 g'8 2 yes yes y es M.6.14 i (e.r t CONVERSION COMPARISON TABLE - NUREG-1431 5/15/97
ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: Q 1.1-2 APPLICABILITY: CA, CP, DC, WC REQUEST: CTS 1.3, Analog Channel Operations Test CTS 1.5, Channel Calibration CTS 1.35, Trip Actuating Device Operational Test [ Wolf Creek) CTS 1.36, Trip Actuating Device Operational Test (Callaway] CTS 1.37, Trip Actuating Device Operational Test [ Comanche Peak) j CTS 1.38, Trip Actuating Device Operational Test [Diablo Canyon) DOC 1-32-A l ITS 1.1, Channel Calibration ITS 1.1, Channel Operational Test (COT) ITS 1.1, Trip Actuating Device Operational Test (TADOT) JFD 1.1-1 These are changes to both the CTS and the STS and are considered generic changes. Therefore, they are beyond the .~ 7e of the conversion review. The DOC states that these changes are consistent wit :STF-64. Comment: If NRC has not approved TSTF-64 by the time the draft safety evaluation is ; prepared, then these changes should be withdrawn from the conversion submittal at that time. These changes will not be reviewed on a plant-specific basis. I l FLOG RESPONSE: TSTF-64 has been withdrawn by the TSTF. However, changes addressed in TSTF-64 have been subsumed by TSTF-205. Revision 1 of TSTF-205 is currently undergoing final review by the TSTF members. After final wording changes for the COT definition as well as Section 3.3 Bases changes to establish the requirements for relay contact surveillance testing ; (issue originally raised at Peach Bottom) are agreed upon, Revision 1 will be submitted for NRC I review. The attached pages represent the definition changes to be included in Revision 1. The I Section 3.3 Bases changes will be addressed under that Section's review. ATTACHED PAGES: Attachment 4, CTS 1.0 - ITS 1.0 l Enclosure 2, pages 1-1,1-1a,1-6, and 1-6a Enclosure 3A, page 7 Enclosure 3B, page 4 Enclosure SA, Traveler Status Sheet Enclosure 5A, pages 1.1-1,1.1-2, and 1.1-6 . Enclosure 6A, page 1 I Enclosure 68, page 1 I
/.e /LTE ANb A/YLrcArrsy
/. /
1.0 DEFINITIONS RE VIS1011 1 1 The defined terms of this section appear in capi lized type and are applicable throughout these Technical Specificatio p an/ af. /-d/-A ACT10N g, ;g g.),y, -l, J,, .f,jc,, 4,4- ACTION $shall be that art of a T :.'-ic:1 Specification-. chi;;? prescribes /_,#!~ I r: rdi:1 == =r;; rcwi.;d neer designated %nditionsw//4/n yse/[/,/
/e+1on%. ---
ACTU T10N LOGIC TEST regusee r 0l'EA' Aft- oS a /o oc circaf-l-
~
6 An ACTUATION LOGIC TEST shall be the applicatinn of various simulate racM/ input combinations in conjunction with each possible interlock logic state and , verification of the required logic output. The ACTUATION LOGIC TEST g shall ,,, include a continuity che as- a-*+e+eem of output devices. j a f , m pn g ,f
"" I' I ~
. .LCO CHANNEL OPERATIONAL TEST [Co7) A Cs*T~
1.2 ', ";ALOC CLA.e:L CICI,ATIO ,AL T:0"'shall be the injection of a simulated !'8I-A pr cc-/Wa/ signal into ge channel as close to the sensor as practicable to verify /-74-A ; OPERABILITyf;kr, '-t:ri n k = d/;r trip f=:ti =;. The "". LOC CllAZ:L Cd7-CP D"!C'.".L TEST shall include a ustments, as necess y, of th ala nter- a l o anddec Trip Setpoint A ti t the Setpoints withiri t pi cd q j,; g j necen yrang and accuracy. q u/ reel S /./ / 1 l retur,-e) -Gr. clanne I ygy 9 ,, ,_- 2 1
- AXIAtFLUXDIFFERENCE(afb Of' M # # /'#"# /, /-A I.i A%IAL TLUX CITTC^ NC: shall be the difference in normalized flux signals f _,gj,,4 between the top and botto halves of : t: = tangexcore neutron detector.
CHANNEL CALIBRAT
, & sack n ece.f.fo
-4 3.e A CHANNE ON'shall be the adjustmen , as nece ry, of the channel -eee+Athat it responds within th -re-"#r:d- ange a accuracy to known /~d2-AI
. ;. i m of
...put. 4 The CHANNEL CALIBRATION shall encompass th: .tir; ch; n:1 /, 3 A i chding th; ;c.- ; ; =d sk. ..., interhek =d/;r t;-ip f unctin; =d may be _o ,,
gg
,p performed by4any series of sequential, overlapping, or total channe ste "
"w-d g hat thc ar, - :t nna : r:13 rat 4,_ G /.'/ -a.
# values & M e anmeber Ma+ A CHANNEL CHECK g , ek ,,,,j n;4,rf , /. /--8
) by e$tervaf.ony 4- A CHANNEL CHECK shall be the qualitative assessment Y of channel oehavier /-g/-A during operation,h Mem t :r i This determination shall include, where possible, comparison of the channel indication andsee status-w W, other indications -emMor status derived from independent instrument ch nels measuring the same parameter. ./.,
) CALLAWAY - UNIT 1 1-1 -
]
INSERT 1.1-A i o.S all devicer in 4ke c Lnnel returd C< channel of'ERAdrLrrf'.
-iac!uding 1! components in the cha=c!, such 2: o1="3, inter!ccks, disp!ays,
/-70-A
-and trip functions, required to perform the specified safety function (s) The l-32-4 COT may be perfonned by means of any series of sequential, overlapping, or < " " " .
j total channel steps,::c Sat the entire ch==! is testcd. & /, /--2 INSERT 1.1-B o // devreef /n 44e ekene /
, eegu rad -R,< cLnna /
{ QOFERAtrLr Ty. 1
-4he:;e components, such as censors,21==, displays, =d trip fu= tic =,
-required to pedonn the speciEed screty nmcGuu(3).1Calibration ofinstrument /-07-M
/-32-A channels with resistance temperature detector (RTD) or thermocouple sensorsW--/ 3-44:3 -
may consist of an inplace qualitative assessment of sensor behavior and S / /-G ( normal calibration of the remaining adjustable devices in the channel.
"Nh=cver 2 censing e!ement is replaced, the next rannired CHMOEL- TR-/ 0-404
-C = - N = - e= = =!ih= m = mpme1m nther sensing e!ements with the recently instelled sc=ing element.-The CHANNEL CALIBRATION l
l 3
;I
/-la.
% DEFINITIONS
.. 4 W u . rv. wn c. w r.
22 3..,,. a e n .nare . . ru..e
. . - r.v,
. . . . .u. 3. ,. .t ,.. ...u..,., ....,<._.+4.m...._.._...,n_r._-.wa
..._1 menn
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- c. -
wk ._ a. . t_ h.m_ c_ h a_ n n._1_e_ ._ ._ c_ a_ e_ ._ w nn_ e a_ d_ + n_ . 4.s.. _ e n_ n_ ee_ n_n_f inr_emated radinmetivit.v STAGGERED TEST BASIS .rNfag7 f, f _y , jg i.SA . A
.ev. n ear e.en.
_ _ _ , . . t. r..e?. nacte
. .. ...L.
99
..u..t..*..
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a A teet e e kad ul a_ s n_w n .c u_ , . u_ k e u, e. +_ _ ,- ,,.+.. 4.., ..k.- a_._,4..._.+
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. . u,m . a. <. m u. s. .. ,. . u. ... .. . ,. a. s t.. a...
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. .. . . . . , ....m.,...._.,..........o..
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. L.1. n_ A ..-- . . , . .
THERMAL POWER reache
-MH5 TliERMAL POWER shall be the totalVcore heat transfer rate to the reactor / U ~'A coolant.
TRIP ACTUATING yg DEVICE OPERATIONAL TEST'(TA' bd 7-)
-MHi-
.,,r- .-.
...n m e . . . . . , m ,. . . . . . . . m . ..
' /-dI-A
. wn.in, ww.4ww .. a. .N. m ..
. .m
.ww.-p' l consist of operating the /-fd-A
_.- .IL.,ITY. . r E.im.. St ri-d or.d/e. RAB Trip
. A.....u..n,.
,. ,ctuating Device,.and verif ., ....
.~un. . 32_A The .m,,, ,...n...
.y adjustment, as
. o. .m..n. ww w . - ..,m uo shall include -,-
cessary, of the that it actua s' '['j"*"j at the require Setpoint within theTriptgLtjng r: uired accurac g Devic 7g ZNSEA'7~ /. /- .,fd 0 l* I' t.fM. T. m f. M. .*' t. ? T. P. m.,I. P. A V. P.F - P n ecer.ra7 f ;j A 83 "? L
- 9. wa n tif f.wn...
-a. nt"u* T et.we n ia.Pw.r. V.p u nsh FF .. e . s1 1 .L i. i. 9. .s . L. ... .L..J.... L. 4. .,, . . ...
._* . .y. T orw
. hfM.T a. ? f.f f.M
. ar .f.=" .P-. R V.P.P E nnmt a.Ewn. t Pws,V rv .,P.P t
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y nrw n on .. ums_,.....__<--->-. o ____ --. . . . . . . ~
. w. w gunw uns win. uvunwnni
_ . , , . . _ . .__ __+ 4. ., ._+. ,_ m . . m s. ,. a_ u.,m .w. _m_ a 4 ,_.w 3 4.. .. . .. ._... .<.. . . . .. ,..... , e. r. .... ..
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......a...u.....,. . . . . . . . .
. ... z..... --. . . .. . .-t, .n. . . . . .
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--e . . ... . - . <. .. 6 4.. .w. .e r.v. e. e. n.n.u.nr ..... ....a. <m., ..,o._...
. . 4._.3 ,.._._...,m.. , , .
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i i CALLAWAY - UNIT 1 1-6 t Amendment No. E, U, /h,50
_ . .- - .__ . .. .-. - -. . ~ _ . . .. .-
~
INSERT 1.1-I : A STAGGERED TEST BASIS shall consist of the testing of one of the /-2 2-A systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
# N INSERT 1.1-J of a ll elevrees in +Ae c). ,nal caer,-a} -R,. -M kV devree C&fA$tL1*Tf,
--iac!uding all ec:npenents in the channel, such as ala.y a y c~ns, inter!cems, /-3'd-A displays, i
"d tdp hetiens, required to perfann the :;pecified safety bctis(s). The /-32-A TADOT may be performed by means of any series of sequential, overlapping,Tf /.3 Jos 1 r total channel steps;sc that the entire channcQ tested. 4 / l' /
&:, ::LR g den Q l. l- 2 j A
l l 4
/ - 4, o l
r
l l CHANGE l 1
.)
NUMBER HSBC DESCRIPTION l 1 31 - Not applicable to Callaway. See Conversion Comparison Table (Enclosure 38). -r.rre - D o.T C^] 1 32 A The definitions of Channel Cal'bration. COT. and TAD 0T are , reworded to be consistent with ;Tr@to clarify the -# /.3 M i phrase " entire channel." thus reducing the potential for Q / / inconsistent interpretation of the phrase as experienced by a number of p1 ants. A .rin:Iar e i.cr& ca-hon i.r jorovided F, - Ac +aa-hon Lopic n el. 1 33 A This change revises the current TS definition of Core Alteration to delete "or manipulation" and " conservative." consistent with NUREG 1431 Rev. 1. The words as used in the definition are redundant and deleting the words does not alter the meaning of the definition. e /. /-9 l-3+ L S .2 SNSEA-r /-3+-t_ S- :t M ^- l os1
.rN.rsRT l-- Ts -A Q-3. L. H G-2. 4, 7- l j.-g g- l}
/-yl, A *NSEl'~ /- 24 -A Q-34.!-l G-7 4 2- I
,. l- g 1 A rNJ'str / .77- A Q-x. b. l-l Q-y.t ,1- g A Gnvem n l- 19 Alo+
c,-f.- aff>fic
, 7:4/. (1/a s e/4v -e C 76. l/~1. See l- 39 A l- + o A g-s.&. H Q-s. 4.1 l-+t A zusenr l- +I- A DESCRIPTION OF CHANGES TO CURRENT TS 7 5/15/97
CONVERSION COMPARISON TABLE - CURRENT TS 1.0 Page 4 of 4 TECH SPEC CHANGE APPLICABILITY , NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY . 1 20 The definition of CONTROLLED LEAKAGE is deleted. The RCP No - See change No. See Change Yes - Hoved to USAR Yes - Moved to FSAR LG seal water return flow limit is moved to a licensee number 1-05-A. Nunter 1-05-A. Section 16. Section 16.4. controlled document. 1-29 Allows measuring QPTR when one or more excore detector No Yes - Portion of No No LS-3 channels are inoperable with movable incore detectors. definition being ,
/yA fe changed is only in O El, ve r /*e ge/,7"Th+% 1,1 .
CPSES CTS. t
/ J 1-30 The definitions of Channel Operational Test (C0T)V[ ] and Yes Yes Yes Yes 7 /,N@ '
A TADOT are expanded to include the details of acceptable p f, f.,_f performance methodology Performance of these tests in a series of sequential. overlapping. or total :t .-d steps ; provides the necessary assurance $tviceof appropriate operation of them channel, re lay, or 0 y reJf ecHvely. 1-31 Definitions of specific plant systems which are defined by Yes Yes No - not in current No - not in current TS. TS. A the plant design are deleted. 7-.r-M yg, c [ g 1-32 The definitions of Channel Cal bration.COThandTADOTare Yes Yes Yes Yes A reworded to be consistent with'TSF St - The revised wording O / /-2 clarifies what is meant by " entire I channel."7'A. dch,3;/rn o[ Ach,,/4,,,, /,, 3 /c71r-/- /s cim*~/de/prLfC /* riS'e . IO5 1 1-33 This change revises the current TS definition of Core Yes Yes b U. M8 *' dyes O/* /d
-UO[O #"/
A Alteration to delete "or manipulation" and " conservative." 107 /a cd'f8" ks wa.-of,y . l- T+ 45-2 Z NSErr- /-34-/1 *2 No No y, ti
/ es k-{*& >
f
-3 S .rNJG/?7~ /- 35-/) le, tjeg g, ,, g 3,g -g.j
/-JL 1'/\/ SEA'7 l- 36 -A yes y g, y, _, ya_, p 3,g, w ]
' /-3~1 rNSEgr- /-77A p yes yes I-3? xmyggy.j,gp A gj, . g,, fes fer Q 14. I-3 A y ,, ,g _ g, , go g,, 9 g(,,p.3 CN 1-T1-A. CN /-71-A
- 5l'5 97 CONVERSION COMPARISON TABLE - CURRENT TS CN /--? .
_..-_.__m. _ ___ _ ___-_-.__.__a____m__.-__._.2-_-_m.-- _ _ _ . . _ - _ - _ _ ___m- - . . _ _ - _ - _ _ . _ _ _ _ . _ _ _ - _ _ __ _..-_m_ e .e_ _ . _ _
- _ - - _ _ - - _ _ _ _ _ _
i- _ _ . _ - - __
. _ . _ = .
l i INDU5 thy TRAVELERS APPLICABLE TO SECTION 1.0 l
.. i l
l TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF 19 Rev. 1 M Incorporated -NA- /. /-/2 M NRC approvedge: cf- ce
.. . dr vekr cut of' d:tc. N-/ N#4 so s- 1 1-r TSTF 2. " V 1 Incorporated 1.1 9 , d /,/-/
O /. 33-j TT E', Ir,ccrpr;ted 1.1-1 4 /, / %f /.# JJC h . ; ETIG Ir.cerpr:ted 1.1 C i;::t
& /./-1 W -/.e 0;-;' Y TSTF-111 Incorporated 1.1 5 Rev. 1 J F.. f'v-275
- - . m . Incorporated 1.1 6 ggc off,,,/, p f, f_g _q f, g gj t 1
,J fYE.~.Q20 Incorporated O /.4._/ --m,,.
-- . 1.1 3
_ U.. . 7gV 25,7 Incorporated
.~, '_x .
1.1 11 g /,4-f -::;W /,f ff.,s :
- 2) S / h coejor & f,j_j3 f[;l; g .7 , j 1
i I rm {1YT F:tz " i l l liM ?' I t 4 E s i ' '.Y I e - I 't ; i t o l z-MARK UP OF WOG STS REV 1 (NUREG 1431) 5/15/97
l Definitions i
- 1.1 l 1.0 USE AND APPLICATION l l l 1.1 Definitions
........................................N0TE -
The defined terms of this section appear in capitalized type and are applicable 1 throughout these Technical Specifications and Bases. l l Itts Definition l 1 ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times. ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in /. / - / l
/, 0-da.F !
l conjunction the withofeach verification possiblelogic the required interlock output logic stat and,"b//~~2 ACTUATION LOGIC TEST, as a minimum, s nel e > continuity check of output devices. r'tsrred A- FEA'AffIM of a le oe cirear+ y
~
AXIAL FLUX DIFFERENCE AFD shall be the difference in normalized flux signals B PS (AFD) between the top 38fLd3qtt6m3dlWsTof a two acetion ),n
)XcoreNieutr6n! detector..
os&f ud ruck CHANNEL CALIBRATION A CHANNEL CALIBRATION sha 1 be the adjustment, as necessary, of the channel that it responds within the equired range and accuracy to known input Thc ClL*J t:CL l n ece.r.rer7,CALICMTIO!; shall caces. pass ythe cati c channci, ' 3 /u,f ,f #4, including the requircd scasor, clara, intericck, o j ernmcJer .,tA.4 f/e di;pley, cad trip functions. ThejcHANNEL' CAL ~IBRATION 1.1 1 c /u nn,/ n,ont-/,-v.
- BhalU encompa'ssy tg D = $ r C ;; $;ps!;cn;;r;; .
-74 /: cy; '
=1=y,7di;pijy:",2:Kt-1p2 fin,ctjcir4Lre_q0ireJ iv pgJuife Q/,/-a tY.. p^ci f..it.d.~~;..;..f.etffun.ct..i;;i'.:.I.. - Calibration of
! a // devree r /n f4e instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace j "" "* j "#f"'"#j A " qualitative assessment of sensor behavior and normal Nd""*/ ###7. calibration of the remaining adjustable devices in the
' ^
channel. 'Jencver : sensing cicecnt is rephc-J. the next-- /. /-/2
-required Cit *f't:CL CALICMTI0t; shall include na inplacc TA/.o cof, ,
-cross calibratica thet ceEp;res the othcr scasing el;; cats -
-with the reccatly inst +Hed sensing elemcid. The CHANNEL CALIBRATION may be performed by means of any series of (continued) l MARK-UP OF WOG STS REV 1 (NUREG 1431) 1.1 1 5/15/97 l
Definitions 1.1 1
) 1.1 Definitions CHANNEL CALIBRATION sequential, overlapping,cMibraticn3 or total channei * #- /
(continued) steps,',0 th& th; cntire chenaci is calibrated. , , , ,
' ',~~/-2
' 4/
CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter. CHANNEL OPERATIONAL A COT shall be the injection of a simulated or actual TEST (C0T) signal into the channel as close toge sensor as
,[ o // de v, hee /n -/4e practicable to verify the OPERABILITY cf requircd 3337;, 5 a;37333.g, g53p337, 333 ;7jpf ;$333, yac;ggjag 1.1 1 Cdanne/ regu,rel far -gllWnett*the ':hrne'pech'r"f Y%
m-we 119 cLnn, / 4/EN4drLx rf a4 cnuwm-d*+-4a r ~4*amAw=a-n e ,, .. , N h N ' N M $ b h= Y ' N N ,'. h h 0b may 3 U-7# beTJe3 farmed (byMsIpffyMDer"Les)of.gsjegehtla]f Q / /-a hienTapp]ggryt,otEphjng(1ssteps30,755t[thr@jN
- s.
- rep'"rj g" 4"^* -@@CgjogglpThe wI snail include adjustments, as and t 1 necessary, O/'E#Agr4rfreuc4 ) setpointshe or Ine that the required setpoints alarm, are within te interlock,9%#kg mrw j range and accuracy.<
CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS snall not preclude completion of movement of a component to a safe position. CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications. DOSE EQUIVALENT I 131 DOSE EQUIVALENT I 131 shall be that concentration of I 131 I (microcuries/ gram) thet alone would produce the sama i thyroid dose as the quantity and isotopic mixture ! of I 131 I 132, I 133,1 134, and I 135 actually present. i The thyroid dose conversion factors used for this 1
) (continued) 1 MARK UP OF WOG STS REV 1 (NUREG 1431) 1.1 2 5/15/97 J
Definitions 1.1 s I 1.1 Definitions SHUTDC"" MARGIN (SDM) SDH shall be the instantaneous amount of reactivity oy , which the reactor is subcritical or would be subcritical l from its present ccndition assuming: 1
- a. All rod cluster control assemblies (RCCAs) are fully J inserted except for the single RCCA of highest ;
reactivity worth, which is assumed to be fully l withdrawn. With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM: and
- b. In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal zcro pc.;cr B PS~
dC3 iso ICVCl h0!t].2_eJgpower ltemp,egaWr_eg SLAVE RELAY TEST J. /- 9 A SLAVE RELAY TEST shall consist of energizing each slaverfg j; g slave lay. gf,j_f relay The and RELAY SLAVE verifying TEST the OPERABILITY shall include ?! : " . of eacg1:::. continuity check of associated testable ac u ion devices.
& retbed reguireQ STAGGERED TEST EMSIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated I components during the interval specified by the l 7~4e S69vc tEtA[7E#T a Surveillance frequency, so that all systems, subsystems, le feMms//7 Ae/w e Fany 'nurveillance Schannels, or other Frequency designated intervals, where ncomponents is the total are teste rewef o ve,-/ ,8erguen#.M/M 4 , number of systems, subsystems, channels, or other / /' 9, 7,p,jj , & .;/ ,L..e o designated components in the associated function.
mL ; m -L, J;}, _ ERMAL POWEx THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant, e +ke TRIP ACTUATING DEVICE A TAD 0T shall consist of' operating the trip actuating OPERATIONAL TEST device and verifying theYOPERABILITY[cf rcquircd alora, 1.1 1 (TAD 0T) intcrieck, displey, and trip functicas. M c]uM agio],) 1.1 9 p il evicer in +$e N^""'""""?NO "LtW("$1:$TNO.N;;[UtN0 C5 TA l.: :::
- $"'"yC""CtniP M e*1^ % Jf^^Di & /./-/
cA.,,,,,/,).urr,/A 4,/ g /,- devee r 'aac N s Fety'func % h ed~tr 4 Ue" @ AD0TjinafTelperformed g j, f-g y.means of'any series of:sequentialloyerlappigg of_ , _ N ~ total channel stepsde thet~ thc cati. ; ?.:21W:M520f The TAD 0T shall include adjustment, as necessary, of the trip actuating device so that it actuates at the required setpoint within the te';uirc6 4accuracy.t n ecena ry r MARK UP OF WOG STS REV 1 (NUREG 1431) 1.1-6 5/15/97
JUSTIFICATIONS FOR DIFFERENCES FROM NUREG 1431 Section 1.0
, , This enclosure contains a brief discussion / justification for each marked up technical change to the NUREG 1431 Revision 1 to make them plant-specific or to incorporate generic changes resulting from the Industry /NRC generic change process.
The Change Numbers are referenced directly from the NUREG 1431 mark ups. For Enclosures 3A. 3B, 4, 6A, and 68, text in brackets "[ ]" indicates the information is plant specific and is not common to all the Joint Licensing Subcommittee (JLS) plants. Empty brackets indicate that other JLS olants may have plant- cif information in that location. q, w " utr./"If amt u,uf 3 CAanaeloferskew/
*4 tus)ech m is Hon % oad %f ch*ks; A CHANGE Ar 6 wAe#er & /r.tf r hevies @ er= % I Tir+ 4
"'*l^
JUSTIFICATION "phd*rc4At 1 NUHBER Inclusivt ar refrecordukve. Rt.tco brk
.timila 1.1-1 The NUREG 1431 Rev.1 definiti@f Chann Calibratio.-:t = r. S p,d: rare C".'f0CL C.'.L:""."T!0' h:l' en; x4 = $ he e ire channel, includina the include /ly r required sensor, alann, interlock, display, and trip functions."} This "cil devrees n r/d%i change clarifies what+c ca--'!!::: the :ntir :h:nnci by r;;;rdi g t N cAanael etpfre [or 6'4 - cgete *= _ g c44n.wl#d!i8A .$ ,_::iti:n
- nt:,u ruch tte, "W :: =C".^?'I'.
re :, m C'LIOR"T!0'
- . di play . e-A :h:l't-ip feactiene _
A #TA rlar gic;d t: prf: - t'; gccified refety '""etien(0." The Ch;nn:1 It /*'I/8ME*"O ,;0 : tion;l Te.,t :nd Trip ^. t= tin; 00110 O p eti:: 1 T a t defi-iti n: 1 Ae/arMen hre } :r; ;i;;;ilarl.7 . m W. This change is consistent with TSTF@205. Not used. 1.1 3 Adds new example to ITS Section 1.4 to clarify the meaning of SR notes of the type "Only required to be performed in M00E...." This change is consistent with traveler = N. ".n.1. - 7~tTF- D 70, 4 /.f-/ 1.1 4 Not used. 1.1 5 The definitions for ESF Response Time and RTS Response Time are revised to substitue the word " verified" in lieu of " measured", consistent with the requirements of NUREG 1431 SR 3.3.1.16 and SR 3.3.2.10. This change ensures consistency between the definitions for Response Time and the requirements to periodically verify, Response Time is within limits. This change is consistent with traveler TSTF 111 Rev.1. 1.1-6 The definition of the Pressure and Temperature Limits Report is revised to include the maximum allowable PORV lift settings and arming temperature associated with the [ Cold Overpressure Hitigation System (COMS)] and to be consistent with the COLR definition. Improved Technical Specification 3.4.12 states that the PORY lift settings are specified in the PTLR. The current definition for PTLR does not identify these lift settings as being contained in the PTLR. The [COMS] arming temperature was added to the PTLR, since changes in the heatup/cooldown figures could change the arming temperature. This change corrects the PTLR definition to be consistent with all of the requirements contained in the PTLR. Referenced methodologies for the PTLR contain the methodology used to develop the heatup and cooldown JUSTIFICATION FOR DIFFERENCES TS 1 5/15/97
, Cog cJ 'TAbd7J y rejis173}Le exirlf3 cdynr wedt wi# Gall devrearin Ka c%l ret =rred b
'I N ERSION COMP ABLE FOR NUREG-1431 DIFFERENCES Page 1 of 2 SECTION 1.0 DEFINITIONS DIFFERENCE FR NUREG-1431 APPLICABILITY NUMBER DESCRIPTION [ DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY .
/ -
ed 1.1-1 This change rifles ":t - 6 s....- J.. .. d - Yes Yes l Yes Yes b . .~ , J . .y he oefinitih:d;:;;;~. "NCHANNEL pf,f._2 CALIBRATICL.2:" :- : ; :: O~a ;- ;:---tc, :9 :: t . : h' b
-Neet definitiqsimilarly revised. Aef,,afg, , L,7, 7pff-1.1 2 Not used BIS N/A N/A N/A N/A 1.1-3 Adds new exagle to ITS Section 1.4 to clarify the meaning Yes Yes Yes Yes of SR Notes of the type "Only required to be performed in MODE...."
1.1-4 Not used N/A N/A N/A N/A 1.1-5 The definitions for ESF Response Time and RTS Response Time Yes Yes Yes Yes are revised to substitue the word " verified" in lieu of
- measured
- consistent with the requirements of NLREG-1431 SR 3.3.1.16 and SR 3.3.2.10.
1.1 6 The definition of the Pressure and Tegerature Limits Yes Yes Yes Yes Report is revised to include the maximum allowable PORY lift settings and the arming te merature associated with the system, and to be consistent with the COLR definition. 1.1-7 The definition of Channel Functional Test in the current TS Yes No - Not part of No - Not part of No - Not part of will be retained in the igroved TS. This definition is not current TS. current TS. current TS. in NtREG-1431 Rev 1. 1.1-8 /Jote l b is revised to refer to the " Required reactor vessel -4ee-/% -Vec- 4/, -ee-44 Yes p /,/y
' head closure bolts fully tensioned' and note c is revised to read ' Required reactor vessel head closure bolts less than fully tensioned."
l .rn a Callauny-ryeegre cj ,, CONVERSION COMPARISON TABLE - NUREG-1431 5/15/97
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1.1-3 APPLICABILITY: CA, CP, WC REQUEST: CTS 1.9, Core Alteration DOC 1-06-LS The DC^ does not provide adequate technical justification to support this change. Comment: The associated NSHC for this change appears to provide the necessary justification. Revise the DOC by incorporating the information contained in the associated NSHC. FLOG RESPONSE: Additiontiinformation supporting this DOC is in NSHC LS-1 in . DOC 1-06-LS-1 is revised to include the following information: "The proposed revision more explicitly defines those operations that have a potential for adding positive reactivity to the core and excluding from the definition the use of non-core" components (such as cameras, lights, etc.) that would not significantly alter core reactivity. This would allow movement of other components within the reactor vessel (with fuel in the vessel) that would have no effect on core reactivity. The proposed change would continue to maintain the required level of safety while eliminating unnecessary restrictions on the movement of items such as cameras, etc. The proposed change would continue to allow the application of appropriate limits to the movement of components that could affect core reactivity." For WCGS, Amendment No.109 dated September 18,1997 revised the CTS CORE ALTERATION definition (1.9) to the wording in NUREG-1431, Rev.1. Therefore, DOC 1-06-LS-1 and DOC 1-33-A are no longer applicable to WCGS. ATTACHED PAGES: , CTS 1.0 - ITS 1.0 A, page 2
CHANGE 7' ' ' NUMBER H2iG DESCRIPTION 1 06 LS 1 The current TS definit' ion for Core Alteration is modified consistent with NUREG 1431 Rev.1 to qualify a Core Alteration as movement of fuel, sources or other reactivity control components. This proposed change is less restrictive since the current TS definition defines the movement of any component within the reactor vessel wi fuel in the vessel as a Core Alteration. "r:rr , - p /, /-3
/ e the proposed definition would limit Co Alterations o those manipulations that could affect co reactivity, the proposed change is acceptable from the tandpoint of the health and safety of the public. DW8#T 3A-2A 1 07 -
Not applicable to Callaway. See Conversion Comparison Table (Enclosure 38). 1 08 A The current TS definitions for Engineered Safety Features Response Time and Reactor Trip System Response Time are modified to be consistent with NUREG 1431 Rev.1. In addition, the term'* measured" is replaced by " verified" to be consistent with the requirements of improved TS SR 3.3.1.16 and SR 3.3.2.10 to verify response time is within limits. The addition of the statement that response time may be verified by means of any series of sequential, overlapping, or total steps so that the entire response time is verified. is administrative in nature. This is consistent with the methodology presently described in the current TS Bases for demonstrating total channel response time. 1 09 A The current TS definition for Frequency Notation (and Table 1.1. Frequency Notation) is deleted to be consistent with NUREG 1431 Rev. 1. The acronyms defined in Table 1.1. Frequency Notation, are no longer used in NUREG-1431. Surveillance frequencies are spelled out in NUREG 1431, thereby obviating the definition. This is a non technical change made to conform to NUREG 1431. 1 10 A- rhe finition for maximum allowable primary cont,ammenti leakage ) is added to the i to be consistent with N . . This addition has bee determined to administra i on the basis that efinition has simply been [copie rrent TS 6.8.4.g] to the definitions. . Alo + a.re d. Q ?.4./-fo DESCRIPTION OF CHANGES TO CURRENT TS 2 5/15/97
INSERT 3A-2A o 1,1 3 The proposed revision more explicitly defines those operations that have a potential for adding positive reactiv;ty to the core and excluding from the definition the use of "non-core" components (such as cameras, lights, etc.) that would not significantly alter core reactivity. This would allow movement of other components within the reactor vessel (with fuel in the vessel) that would have no effect on core reactivity. The proposed ; change would continue to maintain the required level of safety while eliminating unnecessary restrictions on the movement of items such as cameras, etc. The proposed change would continue to allow the application of appropriate limits to the movement of components that could affect core reactivity. l t l l
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1.1-4 APPLICABILITY: CA, CP, DC, WC REQUEST: CTS 1.13, Engineered Safety Features Response Time [Diablo Canyon, Wolf Creek, and Callaway) CTS 1.14, Engineered Safety Features Response Time [ Comanche Peak] CTS 1.27, Reactor Trip System Response Time (Wolf Creek and Callaway) CTS 1.29, Reactor Trip System Response Time (Diablo Canyon and Comanche Peak) DOC 1-08-A ITS 1.1, Engineered Safety Feature (ESF) Response Time ITS 1.1, Reactor Trip System (RTS) Response Time . JFD 1.1-5 The definitions for ESF Response Time and RTS Response Time are proposed to be revised to substitute the word " verified" in lieu of " measured." The JFD states that this change is made to be consistent with STS SR 3.3.1.6, SR 3.3.2.10, and TSTF-111, Rev.1. However, the DOC does not refer to TSTF-111 applicability for this change. Comment: If NRC has not approved TSTF-111 by the time the draft safety evaluation is prepared, then this change should be withdrawn from the conversion submittal at that time. This change will not be reviewed on a plant-specific basis. Also, revise the DOC to include TSTF-111 applicability. FLOG RESPONSE: The response to Comment Number 1.1-4 will be provided separately after the August 17,1998 NRC letter to NEl on TSTF-111 has been fully evaluated. ATTACHED PAGES: None i
r ADDITIONAL INFORMATION COVER SHEET ; ADDITIONAL INFORMATION NO: Q 1.1-5 APPLICABILITY: CA, CP, DC, WC REQUEST: DOC 1-17-A ITS 1.1, Pressure and Temperature Limits Report (PTLR) JFD 1.1-6 The definition of Pressure and Temperature Limits Report (PTLR)is added to be consistent with STS. While this is acceptable, the changes to both CTS and ITS to include the maximum allowable PORV lift settings, arming temperature associated with the Cold Overpressure Mitigation System (COMS) [for Callaway only], and arming temperature associated with Low Temperature Overpressurization Protection (LTOP) (for Comanche Peak and Wolf Creek) are generic and are beyond the scope of the conversion review. JFD 1.1-6 states that these changes are consistent with traveler WOG-67, Rev.1. Comment: Provide the current status of WOG-67. If WOG-67 is not approved by the TSTF, then this change should be withdrawn from the conversion submittal at the time of the TSTF rejection. If WOG-67 has not been acted upon by TSTF, or has been approved by the TSTF, but not been approved by the NRC at the time the draft safety evaluation is prepared, then this change should be withdrawn from the conversion submittal. This change will not be reviewed on a plant-specific basis. FLOG RESPONSE: WOG-67, Rev.1 has been designated TSTF-233 and was issued to the NRC by NEl on March 10,1998. The latest status report from the TSTF industry database, dated July,27,1998, indicates that NRC has approved TSTF-233. The proposed wording in TSTF-233 was modified from WOG-67 and these modifications have been incorporated into the ITS. In addition, the PTLR definition includes the PORV lift settings consistent with the traveler's change to ITS Section 5.6.6. The FLOG continues to pursue the changes proposed by this traveler. l ATTACHED PAGES: Attachment 4, CTS 1.0 - ITS 1.0 Enclosure 2, page 1-4a Enclosure 3A, page 4 Enclosure SA, Traveler Status Sheet Enclosure SA, page 1.1-5 Enclosure 6A, page 2 I i
. _ - . - - _ . . . . -- -- .- . - . - = . _ - . - . i INSERT 1.1-F ,
) l (NEW) PRESSURE AND TEMPERATURE LIMITS REPORT (P1 LR) /-/ 7.-A l The PTLR is the unit specific document that provides the reactor !
vessel pressure and temperature limits, including heatup and : cooldown rates, the power operated relief valve (PORV) lift i settings, and the Cold Overpressure Mitigation System (COMS) anning temperature, for the current reactor vessel fluence period. These pressure and temperature limits shall be ; determined for each fluence period in accordance g f, f._s l Specification 5.6.6. Plant operation within seAimity,'is
" " /.c 0; / :
addressed in indi.id"4 eme!Ecstiens. r #/'? y% Lce f.+.3, "te cs from<e anel Mf emhre (flb limI4.cf and L C e 3.4. l.2 " Cold Overfrom"e Mikg*Non } Sy.rk ( coms),." i
- v^ ,
i l
/-4 A
l CHANGE - NUMBER NSt{C DESCRIPTION 1 17 A The definition of a Pressure Temperature Limits Report (PTLR) is added to be consistent with NUREG 1431 Rev.1 s'y and ".0C C7 .. 1. The definition will support the use of " /g ;;/
'a PTLR. Adding th definition is purely administrative in d/./-S j' n_ature 1 18 A O ed/sfoty $ r c The portion or um vuaui om. rum n it Ratio uennm
?Yf$d -A( ,.
e e f,ET' f.'jl 3 dealing with an inoperable excore detector is addressed 1 , ,4 ft,g, i3 , the Conditions and Surveillance Requirements of improved -- TS 3.2.4. Zh/JER1~ 3A~A~ bl l* l~ S ? 1 19 A The current TS definition of Reportable Event is not used in the improved TS and is deleted to be consistent with NUREG 1431 Rev. 1. This definition is deleted on the basis that a reportable event is defined by 10 CFR 50.72 R and 50.73. This change is administrative in nature because h it will have no effect on current reporting practices. g 1 20 M The current TS definition of Shutdown Margin is revised to # be consistent with NUREG 1431 Rev. 1. The requirement to account for any RCCAs not capable of being fully inserted was simply moved from current TS Action and Surveillance f Requirements. The only substantive technical change to ' this definition is the addition of the requirement that. in Modes 1 and 2. the fuel and moderator temperatures be im changed to the hot zero power temperatures. This ensures ER that the power defect due to shutting the reactor down from Mode 1 or 2 is accounted for in the shutdown margin. , ! While this requirement is consistent with current L ., practice, it has not been specified in the existing . definition. Consequently, it has b en cat'egorized as a more restrictive change. , t 1 21 - Not used.
'ebi' 1 22 .A The definition of Source Check is deleted from the current /
TS in accordance with NUREG 1431 Rev.1. No surveillances in the improved TS require Source Checks; therefore, this i is an administrative change. Where used in licensee ; controlled documents it will be defined; however, it has l not been used in the current TS since the implementation 6 of NRC GL 89 01. ._ e. bi DESCRIPTION OF CHANGES TO CURRENT TS 4 5/15/97
,e INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF 19, Rev. 1 W Incorporated -NA- /. /-/I -Net- NRC approved,-:: Of +
s , u- ~ .s -<< a,+- 7p_/, n sg
- o s- i.i-i :.
TSTF 35. n:V 1 Incorporated 1.1 9) Q /,/-/ g g; ;;3 ; TST" 55 Ime ,,; ted - 1.1 1 g f, /-2 2 4i 3J3 '. ve, --
,_______.-; ', 1 l g j,jg
,,o
~ . . oo
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g ,,, f ;g TSTF 111, Incorporated 1.1 5 - - Rev. 1 j. ' ;
"G.f. .rf.;;.Wd Incorporated
1 1.1 6 ggc app,,ye], g j, j_S _.g f,:-::l . unTfYV.
-- . 07- Q. ~J_0 Incorporated 1.1 3 g f,4_j 'S4; f;2 ,; ,
h"C b3. f Incorporated 1.1 11 g /,4-/ T /,? ff; I MM) Aw./ Zncoeper,h] /,/-13 g 3, g, ,__. k 1 1 ,
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'. i MARX-UP 0F WOG STS REV 1 (NUREG 1431) 5/15/97 ,
j
Definitions 1.1 1.1 Definit ons PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:
- a. Described in Chapter 14 Initici Tat Pr;;;raa of g.ps the FSAR
- b. Authorized under the provisions of 10 CFR 50.59: or
- c. Otherwise approved by the Nuclear Regulatory Commission.
PRESSURE AND The PTLR is the unit specific document that provides the TEMPERAlDRE LIMITS reactor vessel pressure and temperature linits, including REPORT (PTLR) beatup and cooldown ratesm -1.1-6 .
'EiRFeis~sif6 i
. for the PS I current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence Plant period operation in accordance within with Specification these operet4tigflimits is 5.6.6. Dg7 addressed ini hi
,@.4.7. NCS *e 64eh re=e K r=nur; ;rna-n,tii inn L1=t:.
4
^" "
J hrkenes " 2d Lc0 :.4.r.
"La T- - retur; Overpr;nur; Mr}ryakon Pret;; tier. (LTOP) 5)7tci" d /
CoIGverfrestare yf .els (C.omr ." QUADRANT POWER TILT QPTR shall be the ratio of the maximum upper excore * ' RATIO (QPTR) detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the , maximum lower excore detector calibrated output to the I average of the lower excore detector calibrated outputs, whichever is greater. RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to B PS (RTP) the reactor coolant of 2093 3555 MWt. ! REACTOR TRIP The RTS RESPONSE TIME shall be that time interval from i SYSTEM (RTS) RESPONSE when the monitored parameter exceeds its RTS trip setpoint TIME at the channel sensor until loss of stationary gripper ' coil voltage. The response time may be ;;rured 1.1 5 [FriifiFd by means of any series of sequential, ~ overlapping, or total steps so that the entire response I time is ;caured y.erp3ed. (continued) MARK UP 0F WOG STS REV 1 (NUREG 1431) 1.1 5 5/15/97 Y
-- &s 4: m a l
CHANGE , NUMBER JUSTIFICATION figures, as well as the methodology for developing the [COMS] ' setpoints. This change is consistent with travel r '.f'C 57. 5.1. - @/ /-f 1.1 7 N o I y ef p'~ o ,"g, hg-(Enclosure 68). - 1.1 8 The reactor vessel head closure bolt requirements for H0 DES 4, 5. and 6 L are clarified. The proposed change revises note b for H0 DES 4 and 5 to _ refer to " Required reactor vessel head closure bolts fully tensioned" L and note c for H0DE 6 is revised to read " Required reactor vessel head % closure bolts less than fully tensioned." The transition point between , MODES 5 and 6 would also be clarified as occurring when the required . reactor vessel head closure bolts are less than fully tensioned. The required number of closure bolts, which may be less than the total number, is established by analysis that demonstrates adequate 0 ring e compression to prevent leakage and ensures that ASME Section III limits [*I _, for affected components are not exceeded. This change is consistent ' -~r E wit tere!er TsTF - t b .Mckel/ $ +*lA w c r., A6 Er. /~-A (rw. A/esh h 1.1 9 Consistent with TSTFb. .1. a/Ying M, IAP9)of the definitions of Channel VLAttc- /443 (aCh]'" Operational $ Test (C0T)3[ ] and Trip Actuating Device Operational Test (TADOT) are M N.
/
3 Marhr 85/*/ expanded to include the details of acceptable performance methodology.m ,, d 72s+, II.ve, [erformance of these tests in a series of sequential, overlapping, or
-Z- ;
el 7, _*d, T t(tal d=1 steps provides the necessary assurance of appropriate El /-/ operation of tne -arc channel ThiscnangealsomakestheCOT9end ,4 , TAD 0T definitions consistent w h the definition of Channel Calibration which already contains similar ording. I y relay, oe ele vree, rerf a cd'ivel. 1.1 10 This change is based on the current TS definition of CONTROLLED ~ LEAKAGE. This change is a clarification only and does not affect the , way RCS water inventory balances are performed. 7 I* ' i 1.1-11 Adds new example to ITS Section 1.4 to clarify surveillance frequencies that are contingent on both a specified frequency and plant conditions. The ITS contains many Surveillance Frequencies that are contingent on i both a "specified Frequency" and plant conditions. For example, f "Within 7 days prior to the initiation of Physics Tests," and " Prior to entering MODE 4 from HODE 5 if not performed within the previous in. 92 days." These Frequencies do not fall clearly under any of the b existing Section 1.4 examples., The proposed example is needed to make clear that 1) the SR 3.0.2 extension of 1.25 times the specified [ frequency applies, and 2) that the interval allowed to perform a missed { Surveillance by SR 3.0.3 applies. P SR 3.0.2 is clear that the 1.25 extension may be applied to "the I interval specified in the Frequency". so the proposed change does not i change the intent of the Specifications. SR 3.0.2 applies if a I ' Surveillance is not performed within the "specified Frequency". Again. the example does not change the intent of the Specifications but only JUSTIFICATION FOR DIFFERENCES TS 2 5/15/97 j
1 l l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1.1-6 APPLICABILITY: CA, CP, DC, WC f REQUEST: CTS 1.24, Purge - Purging [Callaway and Wolf Creek) CTS 1.26, Purge - Purging [Diablo Canyon and Comanche Peak) CTS 1.38, Ventilation Exhaust Treatment System [ Wolf Creek) l CTS 1.39, Ventilation Exhaust Treatment System [Callaway) l CTS 1.39, Venting [ Wolf Creek) CTS 1.40, Venting CTS 1.40, Wasie Gas Holdup System [ Wolf Creek) CTS 1.41, Waste Gas Holdup System [Callaway) CTS 1.41, Ventilation Exhaust Treatment System [Diablo Canyon) CTS 1.42, Venting [Diablo Canyon) DOC 1-15-A The DOC states that the definitions of HVAC systems and functions are deleted to be j consistent with STS. While this is acceptable, the DOC does not provide sufficient ' justifications as to why this change is considered to be administrative. j l Comment: Revise DOC by providing additionaljustification for this administrative I change. l FLOG RESPONSE: DOC 1-15-A has been revised to provide additional justification that the deletion of the subject definitions is administrative in nature. The deletion of the subject definitions is consistent with ; NUREG-1431. These definitions are deleted since the CTS referring to the definitions no longer contain their use, or no longer are retained in the ITS. Discussion of the technical aspects of this change are addressed in each TS where they apply. Thus, the removal of the definition is considered administrative, with no impact of its own. ATTACHED PAGES: , CTS 1.0 - ITS 1.0 A, page 3
1 l 1 l 1 CHANGE l NUMBER liSBC DESCRIPTIQN 1 11 A The current TS definitions for Identified Leakage. , Unidentified Leakage, and Pressure Boundary Leakage have ) been merged into one definition for Leakage. This is a non technical change since it will not alter the manner in I which leakage is accounted for and treated from present I practice. The definition of Unidentified Leakage has been i expanded to include "except RCP seal water [ ] leakoff" l to be consistent with NUREG-1431 Rev. 1. I 1 12 A The current TS definition for Member of the Public is j deleted to be consistent with NUREG-1431 Rev. 1. This definition is deleted on the basis that it is defined in 10 CFR 20.1003 and 40 CFR 190. 1 13 A The current TS definition of the Offsite Dose Calculation l Manual (ODCM) [ ] would be [ ] incorporated into the ! Administrative Controls section of the improved TS. This change is non technical because the definition of the ODCM [ ] will be [ ] moved to another section of the improved TS. 1 14 A The current TS definition for Operational Mode is revised I to " Mode" and the wording revised to be consistent with i NUREG-1431 Rev. 1. The changes are non technical since they will not affect current practice, f rocsere.r V 1-15 A The current TS definitions of HVAC n'ste' nd fmctions ) are deleted to be consistent with NUREG 1431 Rev.1. ["Ventihtien Exhaust Trect ent Sy;te ", ugste g33 uglang g j_7
-Syst :",] " Purge Purging", and " Venting", where used, do not require special definitions. "INSE47 SA-3 8 /. /-d 1 16 LG The current TS definition of the Process Controls Program (PCP) is moved outside of the TS along with the Administrative Controls description of this program to be consistent with NUREG-1431 Rev. 1. The PCP definition and l program description from Administrative Controls are moved i into the FSAR. The PCP implements regulatory requirements and need not be restated in the TS. The requirement to comply with applicable Federal and State regulations for the processing of radioactive waste provides sufficient control of future changes to the PCP.
1 DESCRIPTION OF CHANGES TO CURRENT TS 3 5/15/97
i l l INSERT 3A-3 Q 1.1-6 l These definitions are deleted since the CTS referring to the definitions no longer ; contain their use, or no longer are retained in the ITS. Discussion of the technical aspects of this change are addressed in each TS where they apply. 3 l I I i l l l l
1 I ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 1.1-7 APPLICABILITY: CA, CP, DC, WC REQUEST: CTS 1.40, Waste Gas Holdup System [ Wolf Creek] ; CTS 1.41, Waste Gas Holdup System [Callaway and Comanche Peak] DOC 1-15-A DOC 1-31-A For Callaway and Wolf Creek, the DOC in reference to the subject CTS is DOC 1-15-A. ; However, the subject CTS refers to DOC 1-31-A for Comanche Peak. l Comment: Clarify this deviation and, if appropriate, revise the CTS markup with the ! correct DOC for the particular plant. I FLOG RESPONSE: DOC 1-15-A was intended to describe the deletion of definitions for HVAC processes which are in the CTS, Section 1.0. DOC 1-31-A describes the deletion of definitions for specific plant systems which are defined by the plant design and which are in the CTS, Section 1.0. DOC 1-15-A will be revised to insert the word " processes" after "HVAC" and delete the words
" systems and functions" which led to this confusion. The bracketed systems will also be deleted from DOC 1-15-A.
The " Waste Gas Holdup System" (for all FLOG plants except DCPP) and " Ventilation Exhaust Treatment System"(for all FLOG plants except CPSES) are not HVAC processes. The correct DOC for the deletion of the definitions of these systems is DOC 1-31-A. The Callaway, Diablo Canyon, and Wolf Creek references in their respective CTS markups will be changed to DOC 1-31-A. ATTACHED PAGES: Attachment 4, CTS 1.0 - ITS 1.0 Enclosure 2, page 1-7 Enclosure 3A, pages 3 and 7 Enclosure 3B, pages 2 and 4 l 1 l
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s.. CALLAWAY - UNIT 1 17 Amencment No. 73, 2Bl. 23
l CHANGE . NUMBER HMC DESCRIPTION ! 1 11 A The current TS definitions for Identified Leakage. l Unidentified Leakage, and Pressure Boundary Leakage have ' been merged into one definition for Leakage. This is a ! non technical change since it will not alter the manner in i which leakage is accounted for and treated from present l practice. The definition of Unidentified Leakage has been ! expanded to include "except RCP seal water [ ] leakoff" to be consistent with NUREG-1431 Rev. 1. l 1 12 A The current TS definition for Member of the Public is deleted to be consistent with NUREG 1431 Rev.1. This definition is deleted on the basis that it is defined in ; 10 CFR 20.1003 and 40 CFR 190. l I 1-13 A The current TS definition of the Offsite Dose Calculation l Manual (00CM) [ ] would be [ ] incorporated into the Administrative Controls section of the improved TS. This change is non technical because the definition of the ODCM [ ] will be [ ] moved to another section of the improved TS. 1 14 A The current TS definition for Operational Mode is revised to " Mode" and the wording revised to be consistent with NUREG 1431 Rev. 1. The changes are non technical since they will not affect current practice, p rocar.re.r 1 15 A The current TS definitions of HVAC V gst- d faction; l are deleted to be consistent with NUREG 1431 Rev.1. l ["'.';ntihti n Exhaust Trect .cnt Sy;te ", u33te g33 ung j j
-Systc;".] " Purge Purging", and " Venting", where used, do not require special definitions. TMIEA7~SA-3 8 /. /-d 1-16 LG The current TS definition of the Process Controls Program (PCP) is moved outside of the TS along with the Administrative Controls description of this program to be consistent with NUREG 1431 Rev.1. The PCP definition and program description from Administrative Controls are moved into the FSAR. The PCP implements regulatory requirements and need not be restated in the TS. The requirement to comply with applicable Federal and State regulations for the processing of radioactive waste provides sufficient control of future changes to the PCP.
DESCRIPTION OF CHANGES TO CURRENT TS 3 5/15/97
i i i , CHANGE NUMBER HSliC DESCRIPTION i
~
1 31 aA : a elin :y. See Cc ;;rsicr. Cc v: rim Table 'Er.cic=re 28) . 1.rrp-dos [ ^] 1 32 A The definitions of Channel Cal'bration. COT. and TAD 0T are reworded to be consistent with 0TI44 to clarify the ~7 !..' G'? i phrase " entire channel." thus reducing the potential for O / /~C-inconsistent interpretation of the phrase as experienced l by a number of plants. A rimilar el ~ifeca b is f " vided fa.- Ac+ua-h'on Lo ic ra.c+. 1 33 A This change revises b current TS definition of Core Alteration to delete "or manipulation" and " conservative." consistent with NUREG 1431 Rev.1. The words as used in the definition are redundant and deleting the words does , not alter the meaning of the definition. I m_i , .., , l-34 LS .*2 . r N.T C R-r" / .7+-L S ~1 """i '
,_g g- A rN.rsR-r /- Ts~-A O-3 L.H 0~I S T~I 7 gg A ENsstr~ (- 24 -A &-3.4.1-1 0-7.4.1-I j g7 A rN rser / .77- A g-z. b. l-l Q-7.t .1- 2 A Gve<x n f.-yy Alo+ s ? % 7 ; bleric.ita -h Call C&cI3~.e See . C-p Th . \
l- sq A i l-40 A A zusen-r- l-- +1- A Vs.&. l-l Q-s. 4
- l l-+t DESCRIPTION OF CHANGES TO CURRENT TS 7 5/15/97
4
- . INSERT 1-31-A Q 1.1-7 j i
i Definitions of specific plant systems which are defined by the plant design are deleted i consistent with NUREG-1431. The definitions contained in ITS 1.0 are intended for j definitions that are necessary for the understanding of the specifications and can be ; generically defined for most plants. Definitions of systems that are not used in the specifications, or are specific to a particular plant (or only a few plants) are no longer defined in this section. Where necessary, such terms are defined in the Bases for the ' applicable specifications. i 9 i l
)
J 3 e
t i CONVERSION COMPARISON TABLE - CURRENT TS 1.0 Page 2 of 4 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 1 10 t tr xt 5 airtr:t':: C::tr;h :::tir efiaiti-
-Ves-- A/p -Ves-A/p -Vee- A[/ 7 -Ves-A[/A
+ + - . i . . m ~ue y - y ~ t3< - + 3. g rete ry.
-10 Clid IC IIe 4.evid IS.- M-/- pf h 3 S. [i 1-11 The current TS definitions for Identified Leakage. Yes Yes Yes Yes ,
A Unidentified Leakage. and Pressure Boundary Leakage have been merged into one definition for Leakage and reworded. 1-12 The current TS definition for Member of the Public is Yes Yes Yes Yes A deleted. 1-13 The current TS definition of the Offsite Dose Calculation Yes Yes Yes Yes A Manual (ODCM) [ ] is moved to the A &inistrative Controls section of the ITS. 1 14 The current TS definition of ' Operation Mode
- is revised to Yes Yes Yes Yes A ' Mode
- and reworded. g recessus 1-15 The current TS definitions of HVAk;ti;; =d tration; are Yes Yes Yes Yes A deleted. - ['"xtiletien Lie-t Tra.~. 4 t=~. ""r*-
0;; ": M ; Oct ~.] ~ Purge - Purging", and " Venting", where O /- /- 7 used, do not require special definitions. 1-16 The current TS definition of the Process Controls Program Yes - Moved to Yes - Moved to Yes - Moved to Yes - Moved to FSAR LG (PCP) is moved outside the TS along with the A &inistrative FSAR. FSAR. USAR. Section 16.25. Controls description of this program. 1-17 The definition of a Pressure Tegerature Limits Report Yes Yes Yes Yes . A (PTLR) is added to support the use of a PTLR. 1-18 The portion of the Quadrant Power Tilt Ratio definition Yes Yes Yes Yes A dealing with an inoperable excore detector is addressed in the Conditions and Surveillance Requirements of igroved TS 3.2.4. 1-19 The current TS definition of Reportable Event is not used in Yes Yes Yes Yes A the i groved TS and is deleted. i CONVERSION COMPARISON TABLE - CURRENT TS 5/15/97
CONVERSION COMPARISON TABLE - CURRENT TS 1.0 Page 4 of 4 TECH SPEC CHANGE APPLICABILITY DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY NUMBER DESCRIPTION The definition of CONTROLLED LEAKAGE is deleted. The RCP No - See change No. See Change Yes - Moved to USAR Yes - Moved to FSAR 1-28 LG seal water return flow limit is moved to a licensee nteber 1-05 A. *luder 1-05 A. Section 16. Section 16.4. controlled document. 1 29 Allaws measuring QFTR when one or more excore detector No Yes - Portion of No No channels are inoperable with movable incore detectors. definition being LS-3 7 changed is only in 4 ff, O Ela ve r ge /,t'e la,e k "T14CPSES CTS.
~ / /
1-30 The definitions of Channel 0perational Test (C0TPT ] and Yes Yes Yes Yes 7 /,^ cc A TADOT are expanded to include the details of acceptable p f,f f performance methodology. Performance of these tests in a series of sequential, overlapping, or total i..d steps of appropriate ration of provides the necessary assurance levice them channel, vs lay,or o y retfe " vely . Definitions of specific plant systems which are defined by Yes Yes %; r,ct 4-euccent_ t =t " erret 1 31 A the plant ^-ign are deleted. r ~f~f77~- > f. r E~ ~3 'iI'~)/# f "IS~f## N / /-7 1-32 The definitions of Channel Cal- bration,COThandTADOTare Yes Yes Yes Yes O /. /-2 A reworded to be consistent withitT'~ 5t - The revised wording clarifies what is meant by " entire channel.""TL o/e8474 ,[ A4,/4,n 4,3 fe 7~g , ff c/m,- /a,./gg,e/.gAe/ M /,3-M 1-33 This change revises the current TS definition of Core Yes Yes Ndd. A**d d Yes 8 O/*l-3 M C-/ O a^/ A Alteration to delete "or manipulation" and " conservative." loi /a ee 7 8a Pr-J wn -/5#. l~ N INSEA*T~ /-34-L T ~2 No No y, ,, _8f*N ' /_S-2 l-3 S A INSEM /-35-f Y Y Y f & 3 4.2-/ l~3S Z/\/ SEW l-3J-j) A Y yer yez faz & 3.g,2-l l-3^7 r/vrER7' /-T7A p yes i;'e fes fes fer 6)34.1-3 x n se n i- s n A a -r.. y c, a -1.. m re- an.w CONVERSION COMPARISON TABLE - CURRENT TS CN /-T7-A- CN /-TN) . 5 CN /-2/15/97 FA.
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1.1-8 APPLICABILITY: CA, CP, WC REQUEST: CTS 1.25, Quadrant Power Tilt Ratio [ Wolf Creek and Callaway] CTS 1.27, Quadrant Power Tilt Ratio (Comanche Peak) DOC 1-18-A ITS 1.1, Quadrant Power Tilt Ratio (QPTR) The DOC states that the podion of the OPTR definition dealing with an inoperable excore , detectoris addressed in the Conditions and Surveillance Requirements of ITS 3.2.4. The 1 CTS markup does not reflect this statement since it still contains the definition podion dealing with an inoperable excore detector. l Comment: Revise CTS markup to reflect associated DOC and ITS. FLOG RESPONSE: As discussed in the transmittal letter and the " Methodology For Mark-Up of ) Current TS" in the back of Enclosure 2, the CTS has been marked up to reflect the substance of l NUREG-1431, Revision 1. In general, only technical changes have been identified. However, some non-technical changes have also been included when the changes cannot easily be determined to be non-technical by a reviewer, or if an explanation is required to demonstrate that , the change is non-technical. In general, if the requirement was relocated to a specification in the j improved TS which does not correspond with the specification in which that requirement is i located in the current TS, a DOC number was generated but the current TS text was not struck- ' through. DOC 1-18-A is revised to include the following: l "The CTS definition of Quadrant Power Tilt Ratio requires with one excore detector inoperable, j the remaining three detectors shall be used. ITS SR 3.2.4.1 Note 1 incorporates the CTS definition requirement such that with input from one Power Range Neutron Flux Channel inoperable, the remaining three Power Range Channel inputs can be used for calculating QPTR. In addition, for Callaway and Wolf Creek, see DOC 4-09-A in Section 3.2 (Attachment No. 8) which reflects that portion of the OPTR definition dealing with an inoperable excore detector and Note 1 to ITS SR 3.2.4.1." l The CTS markup is consistent with the methodology discussed in the back of Enclosure 2. ) l I ATTACHED PAGES: 1 , CTS 1.0 - ITS 1.0 A, page 4 l l
CHANGE
) NUMBER HSBC DESCRIPTION 1 17 A The definition of a Pressure Temperature Limits Report (PTLR) is added to be consistent with NUREG.1431 Rev. I andi E 07 6 . 1. The definition will support the use of T/.; ;;;
a PTLR. Adding t definition is purely administrative in S/./-5
" "~*
T.PrF--;233 1 18 A The portion of the Quadrant Power Tilt Ratio definition dealing with an inoperable excore detector is addressed in the Conditions and Surveillance Requirements of improved TS 3.2.4. 24/M47~ 'FA d /* /~ I 1 19 A The current TS definition of Reportable Event is not used in the improved TS and is deleted to be consistent with NUREG 1431 Rev. 1. This definition is deleted on the basis that a reportable event is defined by 10 CFR 50.72 and S0.73. This change is administrative in nature because it will have no effect on current reporting practices. 1 20 M The current TS definition of Shutdown Margin is revised to be consistent with NUREG 1431 Rev.1. The requirement to account for any RCCAs not capable of being fully inserted g was simply moved from current TS Action and Surveillance p Requirements. The only substantive technical change to ' this definition is the addition of the requirement that, in Modes 1 and 2, the fuel and moderator temperatures be changed to the hot zero power temperatures. This ensures ; that the power defect due to shutting the reactor down 1 from Mode 1 or 2 is accounted for in the shutdown margin. ; While this requirement is consistent with current ) practice, it has not been specified in the existing definition. Consequently, it has been categorized as a more restrictive change. 1 21 - Not used. 1 22 A The definition of Source Check is deleted from the current TS in accordance with NUREG 1431 Rev. 1. No surveillances in the improved TS require Source Checks; therefore this is an administrative change. Where used in licensee l controlled documents it will be defined; however, it has not been used in the current TS since the implementation , of NRC GL 89 01. l 1 DESCRIPTION OF CHANGES TO CURRENT TS 4 5/15/97 l i
INSERT 3A4 Q 1.1 8 The CTS definition of Quadrant Power Tilt Ratio requires with one excore detector inoperable, the remaining three detectors shall be used. ITS SR 3.2.4.1 Note 1 incorporates the CTS definition requirement such that with input from one Power Range Neutron Flux Channelinoperable, the remaining three Power Range Channelinputs can be used for calculating QPTR. In addition, for Callaway and Wolf Creek, see DOC 4-09-A in Section 3.2 (Attachment No. 8) which reflects that portion of the OPTR definition dealing with an inoperable excore detector and Note 1 to ITS SR 3.2.4.1.
l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 1.1-9 APPLICABillTY: CA, CP, DC, WC REQUEST: CTS Table 1.2, Operational Modes, added footnotes (b) and (c) DOC 1-25-LS ITS Table 1.1-1, Modes, footnotes (b) and (c) JFD 1.18 j New footnotes (b) and (c) are proposed to be added per traveler TSTF-88. This is a ! change to both the CTS and the STS and is considered a generic change. Therefore, it l l is beyond the scope of the conversion review. Comment: If NRC has not approved TSTF-88 by the time the draft safety evaluation is ! prepared, then this change should be withdrawn from the conversion submittal at that time. This change will not be reviewod on a plant-specific basis. FLOG RESPONSE: TSTF-88 has been withdrawn by the TSTF. Comanche Peak, Diablo i Canyon, and Wolf Creek have deleted the changes discussed in TSTF-88 and have adopted the ! STS footnotes. Callaway intends to pursue these changes as an out of scope item given the plant-specific NRC safety evaluation cited in new DOC 1-34-LS-2. DOC 1-25-LS-2 has been l reworded and revised to be DOC 1-25-A (see attached), applicable to all FLOG plants. New DOC 1-34-LS-2 is only applicable to Callaway. l J l ATTACHED PAGES: j Attachment 3, " Table of Changes not within the Scope of Full Conversion to the ISTS," page 10 Attachment 4, CTS 1.0 - ITS 1.0 Enclosure 2, page 1-9 Enclosure 3A, pages 5,6, and 7 Enclosure 3B, pages 3 and 4 Enclosure 4, page 16 Enclosure SA, Traveler Status Sheet Enclosure 6A, page 2 Enclosure 68,1 i L 1
i Attachment 3 TABLE OF CHANGES NOT WITHIN THE SCOPE OF FULL C0ffVERSION TO THE ISTS:
- ITS l ITS CHANGE
) SECTION NUMBER DESCRIPTION g/,/q 1.0 -Nene.1-3+-LS ~2{CTJ) feacdw- vene/ hea} ff lJ Jel l /. /-? rhol hovimi reguirema,dr. 2.0 None 3.0 None 3.1 None 3.2 None 3.3 1 30-M (CTS) One BDMS train required in H0DE 5: 3.3 121 suspension of positive reactivity additions and accelerated SDM verifications are clarified, i 1 42-H (CTS) 12 hours to MODE 3 in lieu of 3.0.3 entry for i 3.3 04 inoperable SG low low level EAM/TTD timers / channels. 1 46-A (CTS) SG low-level EAM/TTD 3.3 04 Actions Statement clarifications. I 1 54 LS 37 (CTS) Unborated water source isolation valve position verification interval revised from 14 days to i 31 days for consistency with other ITS sections. 2 18 LS-31 (CTS) Revisions to Action Statement for Loss of Power 3.3 99 Functional Unit. 2 il LS 30 (CTS)- 4efermattir.; liCFIS Actica-
-St;t-.;.t5 W. ISIS.
NM 2 42 LS 38 (CTS)- P,cvised SC icwic,, level 7D Functional Unit - CA-J'. 2-62 ' ("essel eT. Pcwer 1 ernj Pc o r 2) Applic dility tc=
-dcittc "100E 3.
j Changes to the ISTS. except those which involve the incorporation of , plant specific design information, which were developed as a part of ' s the industry traveler process, which were editorial corrections, which , j correct inconsistencies between specifications, or which incorporate l CTS information; and changes to the CTS which do not merit a separate ! change request. 10
TABLE '_.: f,/ / p
^'r~1:". MODES g5A c-rog V
REACTIVITY -%- RATED MODE CONDITION [K THERMAL POWER
) AVERAGE C00LAN - / .25'4g TEMPERATURE t ,-,,/-2, 5 -A,
- 1. POWER OPERATION > 0.99 > 5% ; ;;;^.~ NAg),"j,_"{
- 2. STARTUP > 0.99 < 5% _ :::*~ gA
- 3. HOI STAND 8Y < 0.99 0 NA > 350 F l
- 4. HOTSHUTDOWN(O < 0.99
. --+- NA 350*F > T
> 200'F avg
- 5. COLD SHUTDOWN < 0.99 : MA < 200 F
- 6. REFUELING"(c) ;,;; ._g yA ~. yor _ gA NA (a)&PExcluding cecay heat.
**FLei ... thm . esetw.- .caaol ,,;;L thm .mssel head cic;urc M it; ic;; th;r. fully tencie.ned er with the h::d r; :'/ d. I (f) ge(uies) reae.hr Venel head c}orure } elk hully -ftnsione .
-l-&lE
~
(c.') gecutre) reae-for vene } kes) clo.rure lo(+.r /en +han Sully ftnsione , I
& t.1-9 6
i CALLAWAY - UNIT 1 1-9 Amencment No. 15 l
. . - . _ . . _ .- - . . - . - . ~_-.- . --. -
I i CHANGE
} NUMBER HSBC DESCRIPTION 1 23 A The current TS definition for Staggered Test Basis is {
revised to be consistent with NUREG 1431 Rev. 1, but the l test intervals for surveillance requirements throughout i . the improved TS that are to be performed on a staggered l test basis are revised to be consistent with the new -l definition so that there will be no net change in current TS implementation of staggered test intervals. For j example, under the current TS, if a parameter is monitored j by three channels of instrumentation, and the test ' g interval is quarterly, one channel is tested each month during any given quarter by dividing the test interval into three equal subintervals. Under the new definition, the test interval for that same instrumentation in the improved TS is specified as monthly so that the net effect is the same. One channel is tested each month during any s-given quarter. 3 1 24 A The current TS definitions of Site Boundary and Unrestricted Area are deleted to be consistent with NUREG 1431 Rev. 1. These definitions are deleted on the basis that they are defined in 10 CFR 20.1003. Q t. l-9
) 1 25 A O2 - Table 1.2 of the current TS becomes Table 1.1 1 in the -W /.C 331 improved TS. The following changes are made to conform to I
NUREG 1431 Rev. 1. In ITS Table 1.1 1, the notation "NA" replaces "0" under
- Rated Thermal Power for Modes 3, 4, 5, and 6. This is a non technical change since with K,y less than 0.99, thermal power would be zero anyway. For Mode 6, the temperature has been replaced with NA since there is no safety analysis basis for the value of 140*F specified in the current TS. Also for Mcde 6, the reactivity condition has been designated NA since the value of 0.95 is specified in the Bases for improved TS 3.9.1. The temperatures for Modes 1 and 2 are designated as NA on the basis that temperature for these modes is dictated by the Minimum Temperature for Criticality and the operating program for reactor coolant system Tavg. A new note b has been added to Modes 4 and 5 stating that 4// the required reactor vessel head closure bolts are fully Q /./-9 tensioned and a new note c replaces the note applied tog-j,;g Mode 6. The new note c states that the rcquired reactor vessel head closure bolts are less han fully tensioned.{See a /.ro CN /-yf_Lg .?.] The new note c no longer specifie that fuel is in the vessel because the condition of f el in the vessel is DESCRIPTION OF CHANGES TO CURRENT TS 5 5/15/97
CHANGE
) NUMBER RSBC DESCRIPTION addressed by the definition of the term Mode. This definition stipulates that fuel be in the vessel in order to be in a " MODE." These changes are administrative /7n n. dure, except for the neri noter b rd c, 2dded per traveler- g-/J og -
TSTI 00 cnd addre3 sed in NS"C LS-2.- g /, / 9 1 26 A New sections 1.2, 1.3, and 1.4 are incorporated into the improved TS to be consistent with NUREG 1431 Rev. 1. Section 1.2 provides specific examples of the use of the logical connectors atiQ and DR and the numbering sequence associated with their use in the improved TS. Section 1.3 deals with the proper use and interpretation of Completion Times, and specific examples are given that will aid the user in understanding Completion Times. Section 1.4 deals with the proper use and interpretation of surveillance frequencies. Specific examples are given that will aid the user in understanding surveillance frequencies as they appear in the improved TS. The proposed clusges are administrative in nature and by themselves are not technical changes, incorporating travelers-WOC 70 Rc' 1 D ? -M
-d Hoc 00: ~7T17=~- 390 ad TM241. 0 / +-l 1-27 H The definition of Restricted AFD Operation (RAFDO) is deleted from the current TS, in accordance with NUREG 1431 Rev. 1. See CN 1 15 H in the 3/4.2 package.
1 28 LG The current TS definition of CONTROLLED LEAKAGE is deleted to be consistent with NUREG-1431 Rev. 1. The RCP seal water return flow limit is moved to a licensee controlled dccument.
- rh/ SERT
- SA-f, 1 29 LS 3 Q 3 m c .2 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B).
1 30 T.rTF'- a oS; A Consistent with TOTT-39. Rev. 1.Vthe definitions of 7 /.J-Ce} Channel Operational Test (C0T) j [ ] and Trip Actuating O /. /-/ > 44 ge /.h,,.hM; p uevice Operational Test (TADOT) are expanded to include fj* g, j,/
~
1 the details of acceptable performance methodology. Performance of these tests in a series of sequential, overlapping, or total-channch steps provides the necessary o/,vree, re.rgeche/7 .This change also makes the COT *[ance of appropriate operatio
] and TAD 0T definitions consistent with the efinition of Channel Calibration which already cont ns similar wording.
\ ! curro.h T5 and +Le AluREG-)f31 DESCRIPTION OF CHANGES TO CURRENT TS 6 5/15/97
CHANGE
,) NUMBER EllC DESCRIPTION 1 31 -
Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B). r rTF-205- C ',) 1 32 A The definitions of Channel Cal'bration. COT. and TAD 0T are . reworded to be consistent with .0TI-Ot-to clarify the -,.-v~ phrase " entire channel," thus reducing the potential for S / /-3 inconsistent interpretation of the phrase as experienced by a number of plants. A rr<ntlar- e l=<if,* cah*on it frw~d'd fe,- Ac-fuadron Log ic rn.r+. 1 33 A This change revises the current TS definition of Core Alteration to delete "or manipulation" and " conservative." consistent with NUREG 1431 Rev. 1. The words as used in the definition are redundant and deleting the words does not alter the meaning of the definition. 4 /.1,1
-rs_i ..,
/-2+ LS-2 .rNSGA' T~ l-3+-L S- 2 ""1 ZNSER-r* l- Ts -A Q-3,(.. l-l G-P. l, 7- /
l-yS- A
/-Tf, A rNSEAT- f-24-A g-3.g .1-l Q-2,4.:2- l j g-7 A rNretr / A Q-z. t.. l-l @-7. 4,1- 2 j_.7y l} j\/of a See 0 -
C ~ f* r.ranfic lie b 0(&cl
% Lla lI"$u<e 26. '****ri*n
/- 79 A l- + o A A xysen-r l- +1- A Q*o *S* H 0~
- b ' I'b' l-+t l
i I i I
-) DESCRIPTION OF CHANGES TO CURRENT TS 7 5/15/97 i
INSERT 1-34-LS-2 ENCL. 3A In ULNRC-1663 dated October 29,1987, Union Electric submitted a justification for operating Callaway Plant with one reactor vessel stud detensioned. NRC reviewed that S /. /-j justification and concurred with it per the safety evaluation attached to their letter from Thomas W. Alexion to Donald F. Schnell dated May 26,1988. As such, new notes b and c to current TS Table 1.2 are worded " Required reactor vessel head closure bolts fully tensioned
- and " Required reactor vessel head closure bolts less than fully tensioned",
respectively. The required number of closure bolts has been established by an analysis which demonstrates adequate O-ring compression to prevent leakage and ensures that ASME Section 111 stress limits for affected components are not exceeded. 3 I J
)
I
W j CONVERSION COMPARISON TABLE - CURRENT TS 1.0 Page 3 of 4: TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 1-20 The current TS definition of Shutdown Margin is revised. Yes Yes Yes Yes H The requirement to account for any RCCAs not capable of being fully inserted was simply moved from current TS Action and Surveillance Requirements. The only substantive technical change to this definition is the addition of the requirement that, in Modes 1 and 2. the fuel and moderator temperatures be changed to the hot zero power temeratures. 1-21 Not used. N/A N/A N/A N/A 1 22 The definition of Source Check is deleted. Yes Yes Yes Yes A 1-23 The current TS definition for Staggered Test Basis is Yes Yes Yes Yes A revised. The test intervals for surveill&nce requirements throughout the i g roved TS that are to be performed on a staggered test basis are revised to be consistent with the new definition. 1-24 The current TS definitions of Site Boundary and Unrestricted Yes Yes Yes Yes A Area are deleted. 1 25 Table 1.2 of the current TS becomes Table 1.1-1 in the Yes Yes Yes Yes e igroved TS. Several changes are made to conform to A NUREG 1431 Rev. 1 (e.g., in ITS Table 1.1-1, the notation NA" replaces "0" under
- Rated Thermal Power for Modes 3.
- 4. 5. and 6). Rc:cter vessel hc:d closure Mit tensioning. Q /, /-9
;j:-daar t r;;icr TSTI a,^ =d i: discussed-further-in-W f.; 0 4
~~w ..-
1-26 New sections 1.2. 1.3. and 1.4 are incorporated into the Yes Yes Yes Yes A igroved TS. 1-27 The definition of Restricted AFD Operation (RAFDO) is No No No Yes - definition H deletal. only in current Callaway TS. t CONVERSION COMPARISON TABLE - CURRENT TS 5/15/97
- V d CONVERSION COMPARISON TABLE - CURRENT TS 1.0 Page 4 of 4 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 1 28 The definition of CONTROLLED LEAKAGE is deleted. The RCP No - See change No. See Change Yes - Hoved to (JSAR Yes - Moved to FSAR LG seal water return flow limit is moved to a licensee nunter 1-05-A. Nunter 105-A. Section 16. Section 15.4.
controlled document. 1-29 Allows measuring QPTR when one or more excore detector No Yes - Portion of No No LS-3 channels are inoperable with movable incore detectors. definition being , pg changed is only in r ge/,7"T'~eg FJ J/.ve /*e fu TIAJ CPSES CTS. !
/
1-30 The definitions of Channel Operational Test (C0TP'[ ] and Yes Yes Yes Yes 7 /,Ne-3 A TAD 0T are expanded to include the details of acceptable f)/, / f performance methodology. Performance of these tests in a series of sequential, overlapping, or total &=d steps provides the necessary assurance $eviceof appropriate op*eration of them channe1, ve lay, or c y resf echvely . ' 1-31 Definitions of specific plant systems which are defined by Yes Yes No - not in current No - not in current A the plant design are deleted. r-rPrf-pos.f-- C ] TS. TS. 1-32 The definitions of Channel Cal' bration. COT.dandTADOTare Yes Yes Yes Yes A reworded to be consistent with M T" Si - The revised wording b /M clarifies what is meant by " entire channel."773, c/e ff,iffron o [ A 4 /fon /_ ,3 ,"e 7~,ag r - ff .r-/mt/.,./)fle* !* A !* I~ 1-33 This change revises the current TS definition of Core Yes Yes AS./i** M'Yes ],/;/N , A Alteration to delete "or manipulation" and " conservative." 107 ' a ed"/8"" """ ~'
.Frs m .-4 ~' .
l- 3+ %NSekr /-34-/ S-2 No No y, y,, - h _,$* ? & LS-2 / :
/-3 S rNsEM /-3s-y)
,} f'I V'C fas fer & 3.4.2-/
i
/46 Z/\/EE W /- 3l -f)
A Y Yer Ye' /*' & 34.2-1 i-s, nvreer i-gu lR,
~' ye' Ye' fe' fer Q 3.4. l-3 A 1NSEd'r /-SP- A Yo ~~ S' ' Ves AIo-See No-See Q sf,.:>-a OMI' D A-CONVERSION COMPARISON TABLE - CURRENT TS C N /-7 7-A . q J g 97
INSERT 1-34-LS-2 ENCL. 3B in a Callaway-specific change, new notes b and c to current TS Table 1.2 are worded $ /, /-9
" Required reactor vessel head closure bolts fully tensioned" and " Required reactor vessel head closure bolts less than fully tensioned", respectively.
1 I 1 )
IV. SPECIFIC N0 SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 2 ) 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS Current TS Table 1.2 (improved TS Table 1.1-1) is revised such that the required reactor vessel head closure bolt requirements for MODES 4, 5 and 6 are clarified. Currently a footnote applicable only to MODE 6 defines that Mode, in part, by I reference to " vessel head closure bolts less than fully tensioned." That footnote ' does not specify the transition point between MODES 5 and 6 with regard to the number of vessel head closure bolts that must be fully tensioned, leaving the issue open to interpretation. The proposed change provides the necessary clarification by adding a footnote to MODES 4 and 5, consistent with the approach used in NUREG 1431 Rev.1, to define those Modes as having the required number of reactor vessel head i closure bolts fully tensioned. The transition point between MODES 5 and 6 would j also be clarified as occurring when the required reactor vessel head closure bolts are less than fully tensioned. The required number of closure bolts, which may be less than the total number, is established by analysis that demonstrates adequate 0 ring compression to prevent leakage and ensures that ASME Section III stress limits for affected components are not exceeded. This change is consistent with _ . , , , vu . -fle NXc L Ee+y EwlwNon (T W. Alexion -fo b.R fchell
..o ldeol Ay 24; 14PP) of NLNRc'- /H,3 (daledo cme, .:t4, /971,). g St This proposed TS change has been evaluated and it has been determined that it 4 /./4 involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:
"The Comission may make a final determination, pursuant to the procedures in 50.91, that a proposed amendment to an operating license fcr a facility licensed under 50.21 (b) or 50.22 or for a testing facility involves no significant hazards consideration, if operation of the faci 1ity in accordance with the proposed amendment would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or
- 2. Create the possibility of a new or different kind of accident from any accident previously evaluated; or
- 3. Involve a significant reduction in a margin of safety. "
The following evaluation is provided for the three categories of the signi'icant hazards consideration standards:
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
NO SIGNIFICANT HAZARDS CONSIDERATION 16 5/15/97
INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF 19, Rev. 1 4k+-Incorporated -#A- /, /-/2 ikt NRC approved,-= cf - %!
.. . der! ler =t Of' 6tc. - N-/ H4 I
.w s s.1-ry TSTF 00, P. v. 1 Incorporated 1.1 9 ,
d /,/-/ C /.; ::3__i i TSTF 51 Incorpor t;d 1.1 i f) /, /-2 3-/.##J3I,, ETre Ir.cerpor:ted 6-G /,/q W ,'.e ;;_l [.? TSTF 111, Incorporated 1.1 5 Rev. 1 [."'.
'~,
t,~JcW;-27 d Incorporated 1.1 6 ggc app,,y,}, gy j, j_g g j, n :l >
,nTfTgVQ20
-- Incorporated 1.1-3 Q /.4 -l e, , ,/
.. . . ~-, . , .
"bbN Incorporated 1.1-11 g /,4-/
T // ef7_ MM) Aev./ Zncoepe,+e] /.l-/3 0 *T.6. /-f h. , I k I
- i
,.:: s., ;
b! LW i i e
) r..
pg-
'ej ;r ,
,.&? .
+.
t N ! ) i ... -
;@$.i,,
rin s
*h
,E~ MARK UP OF WOG STS REV 1 (NUREG 1431) 5/15/97 f l t I
.- _ . -= . _ - - - _ - . .- -- - . - .-. ._ --.------ -
CHANGE NUMBER JUSTIFICATION
~
figures, as well as the methodology for developing the [COMS] setpoints. This change is consistent with traveler M0047, ",r; - O /, /4
) 77sv7=~ 233. 12/4::l 1.1-7 Not applicable to Callaway. See Conversion Comparison Table ;
(Enclosure 6B). 1.1 8 The reactor vessel head closure bolt requirements for H0 DES 4. 5, and 6 are clarified. The proposed change revises note b for MODES 4 and 5 to refer to " Required reactor vessel head closure bolts fully tensioned" i l and note c for H0DE 6 is revised to read " Required reactor vessel head - ! closure bolts less than fully tensioned." The transition point between l l H0 DES 5 and 6 would also be clarified as occurring when the required l reactor vessel head closure bolts are less than fully tensioned. The required number of closure bolts, which may be less than,the total number, is established by analysis that demonstrates adequate 0 ring compression to prevent leakage and ensures that ASME Section III limitsgn_ g j,jg for affected components are not exceeded. This change is consistent ' ' ' ' ~ " ' with-t m e?e" TSH ** -M h b.Mckell $4"p N/ C .G fe+y)Eva lua-% (7~w. Ale >fon 1.1 9 Consistent with TSTFN.3.-c.M*g . Db 1999 the definitions of Channel & VLAttc- /tt 1 (a'de) Operational M "" ' Test (C0T)j[ ] and Trip Actuating Device Operational Test (TAD 0T) are "b #i#7) l i 3 MaErflave Ted; 85 /*/ expanded i to include the details of acceptable performance method) erfor: nance of these tests in a series of sequential, overlapping, or ' ' ' ' ' E/*/~/ e l. Ted3 tal &=1 steps provides the necessary assurance of appropriate ~ _ operation of the - channel IniscnangealsomakestheC0Thnd j TAD 0T definitions consistent w h the definition of Channel Calibration i which already contains similar ording. y ee lay, o r- ele vie j e te sf a c'I'IV* f I-l 1.1 10 This change is based on the current TS definition of CONTROLLED LEAKAGE. This change is a clarification only and does not affect the l way RCS water inventory balances are performed. l 1.1-11 Adds new example to ITS Section 1.4 to clarify surveillance frequencies i that are contingent on both a specified frequency and plant conditions. The ITS contains many Surveillance Frequencies that are contingent on both a "specified Frequency" and plant conditions. For example, "Within 7 days prior to the initiation of Physics Tests." and " Prior to entering MODE 4 from H0DE 5 if not performed within the previous 92 days." These Frequencies do not fall clearly under any of the existing Section 1.4 examples. The proposed example is needed to make clear that 1) the SR 3.0.2 extension of 1.25 times the specified i frequency applies, and 2) that the interval allowed to perform a missed l Surveillance by SR 3.0.3 applies. i SR 3.0.2 is clear that the 1.25 extension may be applied to "the interval specified in the Frequency", so the proposed change does not i change the intent of the Specifications. SR 3.0.2 applies if a g Surveillance is not performed within the "specified Frequency". Again, J the example does rot change the intent of the Specifications but only JUSTIFICATION FOR DIFFERENCES TS 2 5/15/97 I t
y Cog c.wiIAbdTJ y ref l eeig& enicity cdyar wenir wi# Call devrearin He cheneI <*t."id (*"'# I ' N VERSION COMP ABLE FOR NUREG-1431 DIFFERENCES Page 1 of 2 SECTION 1.0 DEFINITIONS DIFFERENCE FR NUREG-1431 APPLICABILITY NUMBER DESCRIPTION [ DIABLO CANYON C0HANCHE PEAK WOLF CREEK CALLAWAY -
/ _
eeF 1.1-1 This change c rifies _ , , . . ~ . . . . . . . . . . . . . Yes Yes Yes Yes th p g /__ g by 7; _ d. 7 :e definitih b.0;. "".jtHANNEL CALIBRATIC'. 2 !' n:-- x : I'.aa u;:: :." = _
'- ^ : &- di 7 1:y:. er.d L .y fe .;;%7.; . 7: Fir:d ,
p::f:-- tr.; 4 ;i:d : & ty f r t'.:d ;' "-- The COT e..d ;
#80F definitiqsimilarly revised. Achab laa TXerl-1.1-2 Not used bIE N/A ' N/A N/A N/A 1.1-3 Adds new example to ITS Section 1.4 to clarify the meaning Yes Yes Yes Yes !
of SR Notes of the type "Only required to be performat in , MODE. .." ' 1.1-4 Not used N/A N/A N/A N/A 1.1-5 The definitions for ESF Response Time and RTS Response Time Yes Yes Yes Yes are revised to substitue the word " verified' in lieu of
" measured" consistent with the requirements of NlREG-1431 SR 3.3.1.16 and SR 3.3.2.10.
1.1-6 The definition of the Pressure and Temperature Limits Yes Yes Yes Yes Report is revised to include the maximum allowable PORY lift settings and the arming tenperature associated with the system, and to be consistent with the COLR definition. 1.1-7 The definition of Channel functional Test in the current TS Yes No - Not part of No - Not part of No - Not part of will be retained in the improved TS. This definition is not current TS. current TS. current TS. in NUREG-1431 Rev 1. 1.1 8 p,) lote b is revised to refer to the ' Required reactor vessel -Vee-N, . Vee- //, . Wee-M Yes p f,/q
' head closure bolts fully tensioned' and note c is revised to read " Required reactor vessel head closure bolts less than fully tensioned."
l Z~n a O//asus7-rfecThe cda ej CONVERSION COMPARISON TABLE - NUREG-1431 5/15/97
. . - - _ , .. -- - - ~ _ . . _ . . . ~.
l l l ADDITIONAL INFORMATION COVER SHEET l l ADDITIONAL INFORMATION NO: Q 1.4-1 APPLICABILITY: CA, CP, DC, WC REQUEST: DOC 1-26-A ITS Example 1.4-4 ITS Example 1.4-5 JFD 1.1-3 JFD 1.1-11 1 1 Additional examples, Example 1.4-4 and 1.4-5, are proposed to be included in ITS. The DOC and the JFDs state that these ITS changes are to incorporate travelers WOG-74 and WOG-90. i l Comment: Provide the current status of WOG-74 and WOG-90. If WOG-74 and WOG-90 are not approved by the TSTF, then these changes should be withdrawn from the conversion submittal at the time of the TSTF rejection. If WOG-74 and WOG-90 have not been acted upon by TSTF, or have been approved by the TSTF, but not approved by the NRC at the time the draft safety evaluation is prepared, then these changes should be withdrawn from the conversion submittal. These changes will not be reviewed on a plant-specific basis. FLOG LSPONSE: WOG-74 and WOG-90 have been approved by the TSTF and are designated es TSTF-270 and TSTF-267, respectively. Both of these travelers have been submitted to the NRC and are under review. The proposed wording in TSTF-270 was modified l from WOG-74, Rev. 2, and these modifications have been incorporated into the ITS. The FLOG continues to pursue the changes proposed by these travelers. ATTACHED PAGES: Attachment 4, CTS 1.0 - ITS 1.0 Enclosure 3A, page 6 Enclosure SA, Traveler Status Sheet Enclosure SA, pages 1.4-5 and 1.4-6 Enclosure 6A, pages 1 and 3 1 l I 1 I 1 i
l l. CHANGE NLDBER HSBC DESCRIPTION . addressed by the definition of the term Mode. This definition stipulates that fuel be in the vessel in order , to be in a " MODE." These changes are administrative /;h mVurs, erret fer th = mtet b eM r, rffd pr travelm -rw- /3 g ., TSTP "" ;;;d addressed ir. NS."C LS 2. i p /, /_9 v. 1 26 A New sections 1.2, 1.3, and 1.4 are incorporated into the improved TS to be consistent with NUREG 1431 Rev. 1. ( 4 Section 1.2 provides specific examples of the use of the logical connectors 8NQ and QR and the nrtering sequence 1 associated with their use in the improu TS. Section 1.3 a deals with the proper use and interpretation of Completion . Times, and specific examples are given that will aid the user in understanding Completion Times. Section 1.4 deals with the proper use and interpretation of surveillance 2-frequencies. Specific examples are given that will aid + the user in understanding surveillance frequencies as they g
- l. appear in the improved TS. The proposed changes are ;
, administrative in nature and by themselves are not I technical changes, incorporating travelers L"C '" ": .1 TU = i '
- " m =. -rJYF~- 390 ano( TTrF~-341, & /. +-l 9
! Y 1 27 H The definition of Restricted AFD Operation (RAFD0) is i deleted from the current TS, in accordance with NUREG 1431 . Rev. 1. See CN 1 15 H in the 3/4.2 package. M N 1 28 LG The current TS definition of CONTROLLED LEAKAGE is deleted ? ' to be consistent with NUREG 1431 Rev. 1. The RCP seal i ; watar return flow limit is moved to a licensee controlled g document.
- 1~NSEKT' 3'A-la Q 3 C C .2 1 29 LS 3 Not applicable to Callaway. See Conversion Comparison ..
Table (Enclosure 38).
~1T71~- 3 OS, {F
? 30 A Consistent with +.,i,-39. Rev. 1,Vthe definitions of W /,0 003 - O Channel Operational Test (C0T)4[ ] and Trip Actuating & /, /-/
' ~/
f q uevice Operational Test (TAD 07) are expanded to include
> 4 A ,. ge/. k ,Trd; .h the details of acceptable performance methodology.
f!'" g, j7 Performance of these tests in a series of sequential, , overlapping, or total 57;.;' steps provides the necessary l {%e of appropriate operation of the ,.r.; ire channel, rely 3 or ( L o/,vree,reffeebe/ .This 7 change also makes the COT *[ ] and TAD 0T definitions u consistent with t efinition of Channel Calibration b which already cont ns similar wording. [ cu,.n.k TS ond +Le NUREG-If3'/ DESCRIPTION OF CHAhGES TO CURRENT TS 6 5/15/97 l
l 1 l 3 , INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 i l TRAVELER # ! STATUS DIFFERENCE # COMMENTS ' TSTF 19,'Rev. 1 h Incorporated -i#r /, /-/2 -Net- NRC approvedge: c f-- ca"
,. . 4rr/cler =t c" d:tc. - N -/ H 44 s o s- s.1-ry TSTF-30. " = 1 Incorporated 1.1 9 Q /,/-/ g /.; ::3j TSF Si Ireerpor;tcd- 1.1 1 4 /, /-2 %f- /. # JJC i .
%TI-So I,. serp;r:ted 1 g /,/q T f,f gg h !
TSTF 111. Incorporated 1.1 5 ;, Rev. 1 '* i 7 h0C .d,.T P,=- 2 55 K Incorporated
. . 1.1 6 Ngc .ff,,,/, p /, /_5 _g /,Ne /- l Ed6Y3# Incorporated 1.1 3 0 /,4. / 'S/,3 f;2 b h"X:bNNb Incorporated 1.1 11 S /,4-/ T / " 332-m = c / w.i nu.pc.+d i.ms og.s.i-g 4) u
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- . ~ _ . _ . _ . _ . _ . _ . . _ _ _ _ ._. _ . _ .___. _ _ ._.___.. _ ._ _ _
l Frequency l 1.4 1.4 Frequency l-l EXAMPLES EXAMPLE *T~4:4 1.1 3 l ;(continued) l- SURVEILlMCE.,IREQUIREH_ENTS SUR.yEILLANCE fREQUE_NCY , :==_:=:
- =._=, _N.OTE=._*=_ m _,., < ..=m=o:
l- pnlyf requi r reditoj beiperformedDnLHODERIX r - m -~= , :. . .::.==: , = -- = _m- - - r Nif9ta"congetcycMpfithea].g Udays Jh'e Id nterval2 conti nues# Whetherfor@ot*thej uni ttoperation'i. s?i n I tt0DE313,*;orZLthe"a ss0med ' App,licabilitylof1 theta ssoci ated 1LCO) betleenmerformancig l AsitheINoteMitiesjtheErguih,edfoerformancelof2the , Sutveill.anceHthelNot,eZiflconstree~d ytq?.be!p_artibfjtheTspe.gi fied l Frequency;MSholildjtheEdaylinterya]5be[exce. eded!while , l DPeration!]sinotJjn; MODE;1ilthi s;;'Not42.illowGentry~1ntoland ) l operation 31nlHODESJ2;andf3]tojperform1t.he.'Surveill anceIfThe Surveill anceli sistill3considereditoj be ? performed :withi n dhe Ispecified.irrequency;jiffcompleted:prioritoientering H0DE';1. ~ l Therefore,5.if2theJurveillancekwere,not~ performed within;the ! 7 T.dayJ(plus".theZextensioniallowedlby1SR.WO;2)~. interval *,3but l operationiwa s inot3 n1HODE[r.Mtlwoul d ' not ;consti tute7 a ll fail ure . of the;SR;ortfailure$olmeet the*.LC03AlsoRnoiviolation 'of SR; 3. 0,i4Jpecur,s jwhe.n).changi ng LHODES ,7, even;.wi th ,the,73 day Frequencysnotfmeti;;provi_dedjoperationsdoesinot? result :inientry into.HODE"1; Oncelthe-~ unit" reaches;HODE3,"thelFEquifement[for.;'the f- Surveillance!.to?be performed;.withinAts)spegifjed; Frequency l applies ~.and would require that the;Survei]l.ance,~ have 2b,_en e L PerformedOIf[the~,;Survejllarice9erel'notIperformedf prior;to l H0DE= 1',7here'Would'then'be a'Tailure7tolperform a' SurveilTance ! within:the specified Frequency,' and the provisions 'of SR 3.0:3 G /,+-/ would apply,OprNerijs171'ng.,,Asa per61&nTn SPSB2tL4LJ 7%' /.0- 00.2 - L ! I (continued) HARK UP OF WOG STS REV 1-(NUREG 1431) 1.4 5 5/15/97
, .-- - . , - . . _ . - . -. , , , - _ . _ _ _ . , .. _ . _ _ _ _ _ _ , , . _. -~ . . . , -.
l Frequency 1.4 1.4 Frequency I EXAMPE44~5 [D__(A._M_PLES_..
.:1.1 11 1
I W puedh SURFEIGNEEIREQU_IR,EMDEE SU.RVEIEDMIE
-- FREQUDICY.
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LMisamniteREMMMem!stiasettte3LangJtswrienot etigttj.ugusmarRedr(wemannsfie2itm-htnTSR*3YUT3 L*!3miescapgLqtB~g MARK UP OF WOG STS REV 1 (NUREG-1431) 1.4 6 5/15/97
JUSTIFICATIONS FOR DIFFERENCES FROM NUREG 1431 Section 1.0 This enclosure contains a brief discussion / justification for each marked up technical change to the NUREG 1431 Revision 1 to make them plant-specific or to ,
. incorporate generic changes resulting from the Industry /NRC generic change process. I The Change Numbers are referenced directly from the NUREG 1431 mark ups. For Enclosures 3A, 38, 4, 6A, and 6B, text in brackets "[ ]" indicates the information
-is plant specific and is not connon to all the Joint Licensing Subcomittee (JLS) plants. Empty brackets indicate that other JLS olants may have plant- if' information in that location. -rg, w {
CAnnne l e=Mns / ' Q .r,.
- 4 ru{Ieel-to d "tf a mr.rrn+n m 4kan w ur] l%3 *J CHANGE At /s w4eh & /td. )i hecrea@e. Ac%+
/71s ,
NUMBER JUSTIFICATION fne/urfys sr refreren/mhjve. 8 AMg
*fD g/g l 1.1 1 Channej Calibratio :tz:r, 7. !
ponen+rmew The
"""?5'.NUREG
.. . 1431 C^i!""^.TI^'.' :MiRev.1
' r : , n:definitigf,ihe ertire channel. includino the l inelade/37 tfe 4 7T required sensor, alarm, interlock, display, and trip functions.") This !
"clIdegeesr ange clarifies what"~""r:: tb -tir:
cAnnael re re d-{f"itten t: :t:te. "*- C"_^""EL C'i!","/.TI^" :bl' cm= = *=ch a d b ra rdi ; g the 044%el#- l A Irmr/a, e k." y3- . h 7;g r x t:. ' d n :: r t r , x;. S pl:y . ?"d t-ip '"di^~
- g7f;; e: .; gift:d ::<-ty <ne1:0':).- Th: Chrri It /
- N b N k;;r,:;t t al Te;t ud T-ip ^.:t rtin; ".i:: ^--"Eticn: 1 T st d:firiti:n:
Ae6-A Lye I 1 r: ;=iu., , e.i;W. This change is consistent with TSTFg.205. l
- 1. 2 ' Not used.
I 1.1 3 Adds new example to ITS Section 1.4 to clarify the meaning of SR notes I of the type "Only required to be performed in M00E...." This change is ; consistent with traveler WCC M. " v.1. ~77FF .7v, d2 / A / 1.1 4 Not used, i 1.1 5 The definitions for ESF Response Time and RTS Response Time are revised to substitue the word " verified" in lieu of " measured", consistent with l the requirements of NUREG-1431 SR 3.3.1.16 and SR 3.3.2.10. This i change ensures consistency between the definitions for Response Time and the requirements to periodically verify, Response Time is within limits. This change is consistent with traveler TSTF 111, Rev.1. l 1.1 6 The definition of the Pressure and Temperature Limits Report is revised to include the maximum allowable PORV lift settings and arming temperature associated with the [ Cold Overpressure Mitigation System (COMS)] and to be consistent with the COLR definition. Improved Technical Specification 3.4.12 states that the PORY lift settings are specified in the PTLR. The current definition for PTLR does not identify these lift settings as being contained in the PTLR. The [COMS] arming temperature was added to the PTLR, since changes in the heatup/cooldown figures could change the arming temperature. This change corrects the PTLR definition to be consistent with all of the requirements contained in the PTLR. Referenced methodologies for the
-PTLR contain the methodology used to develop the heatup and cooldown JUSTIFICATION FOR DIFFERENCES TS 1 5/15/97 I
CHANGE NUMBER JUSTIFICATION makes clear the application of SR 3.0.2 and SR 3.0.3 to surveillances 3
) with frequencies tied to plant conditions.
l This change will eliminate confusion and misapplication of the ITS and _will ensure consistent application of SR 3.0.2 and SR 3.0.3 to these types of Surveillance Frequencies. This change is consistent with Q /.f-/ l traveler 'mc ^0. "n. 1. rtrF P47 'T /- eos. , l- l~12. The de $i~nih% of CHArtritL CALSBRA7.;ahlis revise lj'c" " M -l.o-os4 7.tYF-19 -h nove Neheilt of RTb and the-mo couple calik Won h +1,, rr .r g, .g g,,,, ,,,, .gj wyj g
** Ill~ h% o S +1ere com7onen-kr, / l-/3 IN.rEW LA--3 Q 3. 4. /-f, l i
I i l JUSTIFICATION FOR DIFFERENCES TS 3 5/15/97
l l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION No: TR 1.0-006 APPLICABILITY: CA, CP, DC, WC l l REQUEST: Incorporate NRC-approved traveler TSTF-19 Revision 1 to move the details of the l RTD and thermocouple calibration process from the CHANNEL CALIBRATION definition to the l appropriate Section 3,3 Bases. Section 3.3 Bases mark-ups are tracked under No. TR 3.3-004. ATTACHED PAGES: Attachment 4, CTS 1.0 - ITS 1.0 Enclosure 2, pages 1-1 and 1-ia Enclosure 3A, page 1 Enclosure 5A, Traveler Status Sheet t Enclosure 5A. page 1.1-1 l Enclosure 6A, page 3 ' Enclosure 68, page 2 l Attachment 9, CTS 3/4.3 - ITS 3.3 (see changes labeled TR 3.3-004) Enclosure SA, Traveler Status Sheet Enclosure 58, pages B 3.3-66, B 3.3-143, B 3.3-173, and B 3.3-179 l l l l l l
/ ' IM ANb AM.rcma j N DErinITIOns REVISlou 3 l
l l I Ihe defined terms of this section appear in capi lized type ano are applicable I throughout these Technical Specificatio g an/ .e , /-d/-A
,g ,;g y g,.;(,n, .j, j, .),jc,,
I ACTION 2.1 ACTIONSshall be that art of a-T :F-ic:! Specification .crich" prescribes
- /_O!~ i
'ici ::::;r;; r; W. , ; d nder designated /bnditionsw/Mi tn fjsse/,C / ,/ j
/ehon1? w . - - -
1 ACTU TION LOGIC TEST reguire r Of'ERAgz29 op a /oh re circar-}-
+.+ An ACTUATION LOGIC TEST shall be the application of various simulate racM/
input combinations verification in conjunction of the required with each logic output. possible interlock logic shall The ACTUATION LOGIC TEST state and j_,g A i g j ,j include a continuity che .as a-e4e+mem of output devices. j u a minimq q g g l O/-
""".LCiCHANNELOPERATIONALTEST[Co7)
A C07" 1.2 f , ."""LCC C;;;mi;;L CIER'.T C."',L T ';'"shall be the injection of a simulated /~d /-A , e channel as close to the sensor as practicable to verify or achda/ signal into p:f ;1;r,:,'nt:ri::k nd/;r trip functi:n:. The ?"">LCC C;=:L Cd7 /-74-A I OPERABILITg C" P/ T C"". T . ';T shall include adjustments, as necess y, of th alarm, inter f ya A l lock and,I+e Trip Setpoints +wetrAthat the Setpoints within t required - o j,; i necemeyrange and accuracy. reguire) f> j, j _, j regira -R,rcGnne gyggg,- 9 ,, ,_ g_
"# A AXIALFLUXDIFFERENCE(AFh Of## # #'*~/ /, /-A
_ ) 1.0 'X f L TLUX CITTEROi^; shall be the difference in normalized flux signals f gf ,4 between the top and botto halves of : tm :::t ;ngexcore neutron detector. CHANNEL CALIBRATION po .ca ch n ecem . l
!r- A CHANNE L CALIB ATION shall be the adjustmen , as nece sary, of the ;
channel M that it responds within the r:quir:d- ange and accuracy to known /~#2- d
. i ou o f- ,i p t. 4The CHANNEL CALIBRATION shall encompass th: entir; ch;nn 'r- / pa A H:ludin;; th; .,u ;r; ;nd eier , int;ri;;h :nd/;r trip functi:n; :n-' may be _,_o ,,
'[ performed by4any eries of sequential, overlapping, or total channe steps ' ' " *S'- '
.a
.u.
. ..u.. ..
- . . + - - , : .
.a .w m ,o .
Q /.'/ -;2,, CHANNEL CHECK g, d,no, f [n;y_ar:r. !~ ~~!"#
) bye $terva4en) l
-i -{- A CHANNEL CHECK shall be the qbalitative assessment Y of channel behavior /-d/-A during operation,5; eb:: ~ t i er This determination shall include, where possible, comparison of the channel indication and,le+- status e other indications.eed or status derived from independent instrument ch nels measuring the same parameter. -yt, I
l
) CALLAWAY - UNIT 1 1-1 -
INSERT 1.1-A o.C alI devices in 4ke cLanne/ retur<aj L ch nne/ ofERA B.1-Lrrf.
-iac!uding all cmpenents in the channel, such as 212" , interleeksrdisp!ays, /-70-A
-aad trip functions, required to perfc= Se specified cafeoj function (s) The /-32-4
""r"""
l COT may be performed by means of any series of sequential, overlapping, o L total channel steps,30 Set Se entire channel is ic;ted.
& /. l-2 INSERT 1.1-D a // devic,.c rn -A e4.ane /
r urnd E,,- cLnnel Q O EA'A f.z~/ O f-Sese components, such as cen cre,21 =:, displays, and trip funct!5ns, /-03'-M l --req" ired to pMem the specihd afety nowuvu(3)3 Calibration ofinstrument / A l channels with resistance temperature detector (RTD) or thermocouple sensor # -/3 J00--
- l. may consist of an inplace qualitative assessment of sensor behavior and E / /-d normal calibration of the remaining adjustable devices in the chapnn
"/hencver a 3:ncing e!ement is replaced, Se next ragnired CEO!NEL- TR-/. o'do s i
. s. n m n . - ~ . ,n-um____i_______,n_A:__
.t_. _ ______ t_
UN AAJAM l lVIN D11411 AllblLAub u14 AA Apauww wa v 7.i vus s um maVA A LAsuL hva AlpCLa b0 Laib Mther Sensing elen',cnt: eii Se recently installed sensing element. The i CHANNEL CALIBRATION f l l [ I l l I ) i /-/ ~ l 1 l
1 l l Description of Changes i TS Section 1.0 DISCUSSION OF CHANGES This enclosure contains a brief discussion / justification for each marked up change to the current Technical Specifications (TS). The changes are identified by change numbers contained in enclosure 2 (Mark up of the current Technical Specifications). In addition, the referenced No Significant Hazard Considerations (NSHC) are contained in enclosure 4. Only technical changes are discussed; administrative changes (i.e.. format, presentation, and editorial changes) made to conform to NUREG 1431 Revision 1 are not discussed. For Enclosures 3A. 3B, 4. 6A. and 6B, text in brackets "[ ]" indicates the information is plant specific and is not common to l all the Joint Licensing Subcommittee (JLS) plants. Empty brackets indicate that ' other JLS plants may have plant specific information in that location. CHANGE NUMBER NSBC DESCRIPTION l 1 01 A These definitions are reworded to be consistent with i NUREG 1431 Rev. 1. The proposed rewording included in this category does not involve any changes of a technical nature. 1 02 - Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B). yQ f, T.r7F-M. 1 03 H The definition of Channel Calibration is reworded to be consistent with NUREG 1431 Rev. Iv The revised wording TX'-/.0-Ool, i provides additional detail concerning calibration of instrument channels with RTDs or thermocouples. l 1 04 -A- /_ G h definition is no longer used and the specific ioffs Q y,(,. /-/ in imp TS Section 3.6 and the Administra Controls Section are re d accordingly. The c t TS definition for Conta gnt Integri s deleted to be consistent with NUREG 143I . . This definition is effectively incorporat nto Bases for the new Containment Limit ondition for ation (ITS 3.6.1) , and the Admi rative Controls Sections . the ! Contai .. Leakage Rate Testing Program [an ntainment T on Surveillance Program]. rAVERT* l-o +-L G 1 05 - Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B). 4 DESCRIPTION OF CHANGES TO CURRENT TS 1 5/15/97
, - i l l INDUSTRY TRAVELERS APPLICABLE TO SECTION 1.0 t
TRAVELER # STATUS DIFFERENCE # COMMENTS l TSTF-19. Rev. 1 W Incorporated -NA- /, /-/2
-Net NRC approved,= cf-- Dyf irriekr =t of' tte. N -/ N #5 40 5- /,/~[
h 1 TSTF 30. n=. 1 Incorporated 1.1 9) d /,/-/ O /,3 ::3 _' l 1 i
, m. o. .
.. ,___,~..a 4 /, / 2 <,n<,>- -~ - ;y,
-ETT ^o Ir,arpr:ted +4 %
G /. /--? T /. e ; ;-l 1 i , TSTF 111. Incorporated 1.1 5 Rev. 1 [m.'~~.
-p i
, id5bi Incorporated 1.1 6 A/A c appe,ve /. p /. /-6 -W /,M3/
\
-WAG b~#? Incorporated 1.1 3 0 /.4 -/ S,'. 3 .": 2 . . ., .
L'0C k#$Y#N Incorporated 1.1 11 8 /.4-/ T /J
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T3YF-C/ev./ &coyorde/ /./-/3 0 3.t>. /-f, i J. ,i s a.., l l l
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MARK UP OF WOG STS REV 1 (NUREG 1431) 5/15/97 f
- -- _ ~ _ . _ . _ _ _ - .-_ . .
1 i Definitions 1.1 1.0 USE AND APPLICATION i ! 1.1 Definitions
........................................N0TE- - - - - - - -- -
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases. l lerm Definition ACTIONS ACTIONS shall be that part of a Specification that , prescribes Required Actions to be taken under designated l Conditions within specified Completion Times. l ACTUATION LOGIC TEST An ACTUATION LOGIC TEST shall be the application of i various simulated or actual input combinations in /. / - / conjunction with each possible interlock logic stat and ,rm .u w o the verification of the required logic output O / /~'2 ACTUATION LOGIC TEST, as a minimum, s ncine > continuity check of output devices. regur-ed & h # W ep , age circur+ i AXIAL FLUX DIFFERENCE AFD shall be the difference in normalized flux signals B PS l (AFD) between the pop 3TWb~o_tt5hi9iilVef~o~f a two scction en l
)Xd6rerneut'edn7 detector..
l oudyu-l ruck l CHANNEL CALIBRATION A CHANNEL CALIBRATION sh 1 be the adjustment, as necessary, of the channel that it responds within the l cquircd range and accuracy to known input. -The C"M:NCL n ecceserf"AL!0 C NATION ; hall cacca. pas;qthe cntia c channcl. W /urf a,C f /,, includins thC TCsuirCd 3Cn307 Olor;. intCTICCk- . j oen m ,Jer /4.4 f/c di3Play. and trip functions. TheTCHANNELTCAL'IBRATION 1.1-1 c L nn e/ n,o.,:-}ons* thalM' enc 6mpaiP+="=~"=-*=~m"' c"'se="n"~'~ " 3 = =r '~ -- M=s g , _ Edi,
,. n pl,ay;""'sYd;tfMWnct5Cricq0h4 iv M6o'yu.. ' G/
^ '. / '2.
. a mr. - ' -'a
- 2. T *.N d ""** *" m . Calibration of
, j/ 4,, f, gj,, instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace
# y '"'#j "#8"'"#j 4 " qualitative assessment of sensor behavior and normal c4,"nn,/ 4/'ESAg.r4rr/.calibration of the remaining adjustable devices in the chan @,cncver : seising element is replaced, the-next- /. /-/:'2
, -required C".MWEL CALIDMTION sh:11 include an inplacc Tg-/.o-og l -cross calibratisn th6t wi.parcs- the othcr scasing elc; cats-gjth -the reccatly installed sensing element-/he CHANNEL CALIBRATION may be performed by means of any series of
}
(continued) MARK UP OF WOG STS REV 1 (NUREG-1431) 1.1 1 5/15/97 l l l
l 1 l CHANGE NUMBER JUSTIFfCATION makes clear the application of SR 3.0.2 and SR 3.0.3 to surveillances
) with frequencies tied to plant conditions.
This change will eliminate confusion and misapplication of the ITS and will ensure consistent application of SR 3.0.2 and SR 3.0.3 to these i types of Surveillance Frequencies. This change is consistent with S /.f-/ traveler '40 00. ",a 1. T M P47 " X' / J "J 2 -
. /. I-/2 v4, de fr,;y,, ,p cgggrict cAcrBRAirsh/is revi.relfe~ *TX'-/. o-ost T.tvf-l9 -j, n,ye de +,i), oS A>rb a,,( +4 ann,, coup /e calik % h +),, .2~7~,r 7, 3 g,,,_, , ,,, , ,,.f,j 7.pg 4;e a a film kom o p +J,,,
c,,,,,,, g ,,
/. /-/3 Z~NSEg7 gg_3 & 3>. g. l-f, h
l
- )
JUSTIFICATION FOR DIFFERENCES TS 3 5/15/97
v CONVERSION COMPARISON TABLE FOR NUREG 1431 DIFFERENCES Page 2 of 2 SECTION 1.0 DEFINITIONS DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY c > /%.r+rr- Relay "Tirl, Slava Ks lay-T~ri, e 1.1 9 The definitions of Channel Operational Test (C0Tk[ ] and Yes Yes Yes Yes Trip Actuating Device Operational Test (TADOT) are expanded to include the details of acceptable performance methodology. Performance of these tests in a series of Q /,3 g sequential, overlapping, or total d ..... '. steps provides g 7, the necessary assurance of appropriate operation of the
& channel yrelay,ee devfce, nsfec-fively.
1.1-10 This change is based on the current TS definition of No - Not part of No - Not part of No - Maintaining Yes CONTROLLED LEAKAGE. This change is a clarification only current TS. current TS. ISTS wording. and does not affect the way RCS water inventory balances are performed. 1.1-11 Adds new exanple to ITS Section 1.4 to clarify surveillance Yes Yes Yes Yes frequencies that are contingent on both a specified frequency and plant conditions.
- f. j-j p T4e e-[,%.'-lfon oh CHANNEL CA t.rd't'AT.roAl
?? revise)j'ee ~1WW-/Q -Es r% eve $e-lnTls ah e,
les f1 ler TN-l.0~ML M onof ~/~$e+s cos(/a ce ll$oa& f +4e rYI 2. 3' deser o.r:oera-le} sv (+4 cal%Non
*S 'I'$ese com,*one,fr, '~'3 M sEtr 48-a yes ye.r O y.c.1-g y e, p .,
CONVERSION COMPARISON TABLE - NUREG-1431 5/15/97
INDUSTRY TRAVELERS APPL! CABLE TO SECTION 3.3 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF 19. Rev. 1 -Net-Incorporated NA -Net- NRC approved.-as-ef- 74- 7,3-tr;lEl ",r,3"gg{' dets-gar ggy. TSTF 36, Rev.-e-3 Incorporated 3.3 34 fy p, y ms-TSTF 37. Rev. 1 Not Incorporated NA ITS 5.6.8 still addresses PAM i reports. Sections after ITS 5.6.7 were not renumbered. TSTF 51 Not Incorporated NA Requires plant specific reanalysis to establish decay time dependence for fuel handling accident. TOTi ^1 L Imcerpor:ted 4 [ Trip Setyvints-end] Alivwable Velces for loss-cf valt69c and - degraded voltcgc will rc a4e--
-i-r, the TS.
T-2 F-@5- 1 TSTF 111 Rev. 1 Incorporated NA TSTF 135 -Im tiell., J. 3 - 41.S.5-++, Travelcr in tcc b cad scep^ in-Incorporated 3.3 93, naturc; cheuld have bcca 7N-7.7-45
. 3.3 95, 4cycrel separate tra"elem--
l '
# M#> 3.3 122 -Pertiens-of thc traveler thet-
, />
7.7-/I:2 -significently clarify
-opecebility requirements-have-
--bcen incorporatede ;
i j TSTF 161j /ey / Incorporated 3.3-79 -r2-7.7-40 2 T TI 100 Inc;rp;r;tcd -0.0 40 TSTF 169 Incorporated 3.3 42 Af[ove/l y Og C . -rg-y,S-. cog k'00 10C T , Incorporated 3.3 49 3.7-oos-J ry p g p 4 ,t pav e N Incorporated 3.3-107
..lon h72-1 3 -60 I 4
, ( D-l i 1~>rf-2+4 h
MARK-UP 0F WOG STS REV 1 (NUREG 1431) 5/15/97
1 RTS Instrumentat1on 1 ,s B 3.3.1
, BASES SURVEILLANCE SR 3.3.1.9 i REQUIREMENT I (continued) SR 3.3.1.9 is the performance of a TADOT and is performed every 9_2 days,asjustifiedinReference7p.
This SR is modified by a Note that excludes verification of j setpoints from the TAD 0T. Sinec this S", applies to ",C" l undcrvoltagc and undcrfrcqucacy rclays. Setpoint verification l rcquires ciaborat; bcach calibration and is accomplished during the CHANNEL CALIBRATION. SR 3.3.1.1Q A CHANNEL CALIBRATION is performed every 1.8 months, or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to a measured parameter I within the necessary range and accuracy. CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the unit speethe Callaway setpoint methodology. ! Thc diffcrcacc bctucca the currcat "as found" values and the ! previous tcst "as icft" valucs must bc consistent with the drift allowanct used ir. the setpoint ;cthodology. The Frequency of 18 months is based on the assumption of ca 18 ;; nth assumed calibration interval in the determination of the magnitude of equipment drift in the setpoint methodology. SR 3.3.1.10 is modified by a Note stating that this test shall. include verification that the time constants are adjusted to the prescribed values where applicable. This does,not . include verification of time delay relays.J.These are.. verified via response. time testing.per SR'3 3.1;16;~~.'See the,discussi.on'of: AT, I in the. Applicabl.e_ Safety. Analyse.s;for;thef.0v_ertemperaturefAT..and Overpower;~aTitrip.Tunctions. fN.rsg7' Sg 7.7./. /0 W-7.7-00+ Although not required for any. safety function,~ the CHANNEL CALIBRATION of Function ~10, Reactor Coolant Flow Low, will ensure proper performance and normalization of the RCS flow indicators. k (continued) MARK UP 0F NUREG 1431 BASES B 3.3 66 5/15/97
INSERT SR 3.3.1.10 Whenever an RTD is replaced in Functions 6,7, or 14.c, the next required CHANNEL ~7%-7, 7-044-CALIBRATION of the RTDs is accomplished by an inplace cross calibration that compares the other sensing elements with the recently installed sensing element. 1 1 1
1 1 / ESFAS Instrumentation s B 3.3.2 BASES SURVEILLANCE SR 3.3.2,9 REQUIREMENTS (continued) SR 3.3.2.9 is the performance of a CHANNEL CALIBRATION. A CHANNEL CALIBRATION is performed every 18 months, or approximately at every refueling. CHANNEL CALIBRATION is a complete check of the instrument loop, including the sensor. The test verifies that the channel responds to measured parameter within the necessary range and accuracy. CHANNEL CALIBRATIONS must be performed consistent with the assumptions of the unit specific setpoint methodology. The diffcccacc bctuc;n th; currcat "as found" values erd th; previous , tcst ";s icft" values ;ust bc censistent with the drift clicwence u;cd in th; sctpcint acthodology. The Frequency of 18 months is based on the :ssu;ption of an 10 ;; nth assumed calibration interval in the determination of the magnitude of equipment drift in the setpoint methodology. This SR is modi'ied by a Note stating that this test should include verification that the time constants are adjusted to the prescribed values where applicable. This does not -include ver,1fication .of time; delay l relays. -These are: verified 1via respon se ; time:tes ting , periSRl~3 ;3 ~2 /10.
.r/vrar Le .7.7. 3,9 47M+
SR 3.3.2.10 This SR verifies the required individual channel ESF RESPONSE TIMES are less than or equal to the maximum values assumed in the accident analysis. Response time verification required channels and acceptance criteria are included in th; Tcchnical Ccquirc; cats ";nual-(Ref. & 9. Individual component response times are not modeled in the analyses. The analyses model the overall or total elapsed time, from the point at which the parameter exceeds the trip setpoint value at the sensor, to the point at which the equipment in both trains reaches the required functional state (e.g., pu.nps at rated discharge pressure, valves in full open or closed position). For channels that include dynamic transfer functions (e.g., lag. lead / lag, rate / lag, etc.). the response time verification is may (continued) l MARK-UP OF NUREG 1431 BASES B 3.3 143 5/15/97
~ INSERT SR 3.3.2.9
)
Whenever an RTD is replaced in Function 6.d.(3), the next required CHA.NNEL CALIBRATION 7 2 - 7,~1 2$ 4 of the RTDs is accomplished by an inplace cross calibration that compares the other sensing elements with the recently installed sensing element. l
l l PAM Instrumentation s B 3.3.3
) ) BASES SURVEILLANCE SR 3.3.3.2 (continued)
REQUIREHENTS test verifies that the channel responds to measure parameter with the necessary range and accuracy. This SR is modified by a Note that excludes neutron detectors. Thc :.elibration acthod for neutrca dctcctors is ;pccified in the Cases of LOO 3.3.1,
""cacter Trip Systc;. ("sTS) Instr;;catation." This'SR71stalso modi,f_1e.d ibyJa isecond ? Note' that? di scu s.seslan [al,] owedjme,thpdol ogy forical ibrati ng :the;Contai nmen,tf Radiation',LeveT1(Hi gy; Range) function:.: The Frequency is based on operating experience and consistency with the typical industry refueling cycle. Duning i
Per.formance;of;the1 CHANNEL?CALI.BRATIONlforthpIContainment RadiatiorCleve);(Hj ghl. Range); monitors;;yerji g catipn mGt_he gw23 unitidi sp1 ay :ar)d ;al armifunctj ons'is2equired 4 cA.g g/9
.rN[ERT SA 3'. 3'. 3. 3 l 'Df-2,T- g 1
REFERENCES 1. Unit spccific -m....~... w... . ,m s . .mv... m 7 Cuidc 1.07 SE" ictief9- [SARJAppendih.. Kg 2; NRCT.LetterECal].away,iPlantHUnitWf.Emetgency?Respo.nse Capability 35ConformanceitoIRegu]ato iGuide3.97, Revision ^2,7.%3poungb];oodstolD)ff chn_ ell,7 dated April;10U1985'
- 3. ULNRCf3023.~ dated;May;20 D 994;
- 4. Ca11.away;0L: Amendment;N.o;"103;;date October 20,:3995; 5.0- Regulatory Guide 1.97, dete- Rev. . December 3980.
6.'G- NUREG-0737, Supplement 1, "THI Ac ion Items."
- 7. FSAR Sectio.n~7A.3 3 Zn ael/INon, reco,-der-l C7T/?do4o is in clude)
\ in N e C HA A'N E L CAltdA'A7'zoAl of loop W A-oblo.
) _ )
MARK UP OF NUREG 1431 BASES B 3.3 173 5/15/97 \
\ INSERT SR 3.3.3.2 i Whenever an RTD is replaced in Functions 2 or 3, the next required CHANNEL CAllBRATION 7#-Z7-44 of the RTDs is accomplished by an inplace cross calibration that compares the other sensing . j elements with the recently installed sensing element. Whenever a core exit thermocouple is ! l replaced in Function 14, the next required CHANNEL CALIBRATION of the core exit j thermocouples is accomplished by an inplace cross calibration that compares the other sensing ' elements with the recently installed sensing element. ! I t i i. l ! l i l l r r' I' 3 l i I J
Remote Shutdown System , c B 3.3.4 . ) J BASES SURVEILLANCE SR 3.3.4.1 (continued) REQUIREMENTS l The (Note ;excl udes 2 RCPJ br.eakeri posi tion.tindi cat.1 onifr.om;the CHANNELICHECK; si nceithere a re inoj other_cha.nnel s,qoricompati,so,nj SR 3.3.4.2 1 SR3.3.4.2verifieseachrequiredRemoteShutdownSystemESf control circuit and transfer switch performs the intended
; function. This verification is performed from the remete C4 7.7olo puxiliary shutdown panel. end locally, es ;pprepriate. Cp;retien
,. -ef the equipent from thu . m..ete sskj,1jeg shutd;wn panel .5 ,,ci-necessary. The Surveilicu.e cen bc :stisfied by grieraence cf ;
, - centinuity dsk.- This will ensure that if the control room becomes inaccessible, the unit can be placed and maintained in MODE 3 from the remote auxi,liary shutdown panel. ;nd th; local 3
centr;l st; tion;. The 18 month Frequency is based on the need to perform this Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. (However, this Surveillance is not required to be performed only { during a unit outage.) Operating experience demonstrates that remete auxiliary shutdown controls chonnels usually pass the Surveillance test when . performed at the 18 month Frequency. The1 Note; allows;theturbineidriven'AFWipumptandtSGfatmospheric steam dump: valves to be tested Lin7 MODE:3,untr t_h;jegajgd plant
<cpdition 3Ref. '_2). .rA/regr X 7. 7. 4, o. cA-7.7-gaf l I
SR 3.3.4.3 CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. The test verifies that the channel responds to a measured parameter within the necessary range and accuracy. l The Frequency of 18 months is based upon operating experience and consistency with the typical industry refueling cycle. The Notes exclude the source range neutron flux detectors and reactor trip breaker and RCP breaker position indications-from ' the CHANNEL CALIBRATION.
\ xnr sa 2.,.m -rx-2 > ~
j (continued) MARK UP 0F NUREG 1431 BASES B 3.3 179 5/15/97
1 1 s INSERT SR 3.3.4.3 i Whenever an RTD is replaced in Function 3.a or 3.b, the next required CHANNEL 72-7.7-44+ l CALIBRATION of the RTDs is accomplished by an inplace cross calibration that compares the ' other sensing elements with the recently installed sensing element. I 1 l l 1 1 l l l l I l l l l
. . . _ _ . . . . . _ _ _ _ _ ~ . _ . _ . _ _ _ . _ _ _ . _ _ _ _ . _ _ . . _ _ . . _ . -- . - _ .
l l 4 l l J l 1 JLS CONVERSION TO IMPROVED TECHNICAL SPECIFICATIONS CTS 2.0 - SAFETY LIMITS ITS 2.0 - SAFETY LIMITS l RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION AND LICENSEE INITIATED ADDITIONAL CHANGES I 1 l l i c .- -
. _ _ _ _ . _ _ _ . _ . _ . . . _ . , _ _ _ _ _ _ . . . . _ _ ._-..-...______--.____.....-.m__. .._
i INDEX OF ADDITIONAL INFORMATION ' l l ADDITIONAL INFORMATION APPLICABILITY ENCLOSED { NUMBER 2.0.G-1 CA, CP, DC, WC YES 2.0-1 CA YES ! 2.0-2 CA, CP, DC, WC YES 2.0-3 CA, CP, DC, WC YES ; 2.0-4 DC NA . 2.0-5 DC NA 2.0-6 WC NA CP 2.0-001 CP NA DC ALL-002 (2.0 changes only) DC NA DC ALL-003 (2.0 changes only) DC NA DC 2.0-001 DC NA i I
l 1 l JOINT LICENSING SUBCOMMITTEE METHODOLOGY FOR PROVIDING ADDITIONALINFORMATION : l , I l The following methodo!ogy is followed for submitting additional information: !
- 1. Each licensee is submitting a separate response for each section.
1
- 2. If an RAI does not apply to a licensee (i.e., does not actually impact the information that !
defines the technical specification change for that licensee), "NA" has been entered in the index column labeled " ENCLOSED" and no information is provided in the response for that licensee. 1
- 3. If a licensee initiated change does not apply, "NA" has been entered in the index column !
labeled " ENCLOSED" and no information is provided in the response for that licensee.
- 4. The common portions of the " Additional Information Cover Sheets" are identical, except i for brackets, where applicable (using the same methodology used in enclosures 3A,38, 4,6A and 6B of the conversion submittals). The list of attached pages will vary to match '
the licensee specific conversion submittals. A licensee's FLOG response may not address all applicable plants if there is insufficient similarity in the plant specific , ': responses to justify their inclusion in each submittal. In those cases, the response will be l prefaced with a heading such as " PLANT SPECIFIC DISCUSSION." I
- 5. Changes are indicated using the redline / strikeout tool of Wordperfect or by using a hand '
markup that indicates inseri;ons and deletions. If the area being revised is not clear, the affected portion of the pageiis circled. The markup techniques vary as necessary, based on the specifics of the area being changed and the complexity of the changes, to provide J the clearest possible indication of the changes. j
- 6. A marginal note (the Additional Information Number from the index) is added in the right margin of each page being changed, adjacent to the area being changed, to identify the source of each change.
- 7. Some changes are not applicable to one licensee but still require changes to the Tables provided in Enclosures 3A,3B,4,6A, and 6B of the originallicense amendment request to reflect the changes being made by one or more of the other licensees. These changes j are not included in the additional information for the licensee to which the change does <
not apply, as the changes are only for consistency, do not technically affect the request , for that licensee, and are being provided in the additional information being provided by l the licensees for which the change is applicable. The complete set of changes for the license amendment request will be provided in a licensing amendment request supplement to be provided later. l l l I 1
1 JOINT LICENSING SUBCOMMITTEE METHODOLOGY FOR PROVIDING ADDITIONALINFORMATION (continued) -
- 8. The item numbers are formatted as follows: [ Source) [lTS Section)-[nnn)
Source = Q - NRC Question CA- AmerenUE DC-PG&E WC - WCNOC CP - TU Electric TR - Traveler ITS Section = The ITS section associated with the item (e.g.,3.3), If all sections are potentially impacted by a broad change or set of changes, "ALL"is used for the l section number. nnn = a three digit sequential number or ED (ED indicates editorial correction with no impact on meaning) t 1 i I l i ? 9 1
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 2.0.G-1 APPLICABILITY: CA, CP, DC, WC i REQUEST: ITS 2.0.x Bases There have been a number of instances that the specific changes to the STS Bases are not properly identified with redline or strikeout marks. Comment: Perform an audit of all STS Bases markups and identify instances where additions and/or deletions of Bases were not properly identified in the original submittal. FLOG RESPONSE: The submitted ITS Bases markups for Section 2.0 have been compared to the STS Bases. Some differences that were identified were in accordance with the markup methodologies (e.g., deletion of brackets and reviewer's notes). Most of the differences were editorial in nature and would not have affected the review. Examples of editorial changes are:
- 1) Capitalizing a letter with on!y a " redline" but not striking out the lower case letter that it replaced.
- 2) Changing a verb from singular to plural by adding an "s" without redlining the "s".
- 3) Deleting instead of striking-out the A, B, C, etc., following a specification I title (e.g., SR 3.6.6A.7). '
l
- 4) Changing a bracketed reference (in the reference section) with only a
" redline" for the new reference but failing to include the strike-out of the old reference.
- 5) in some instances the brackets were retained (and struck-out) but the unchanged text within the brackets was not redlined.
l 6) Not redlining a title of a bracketed section. The methodology calls for the section title to be redlined when an entire section was bracketed.
- 7) Additional text not contained in the STS Bases was added to the ITS Bases by the lead FLOG member during the development of the submittal.
Once it was determined to not be applicable, the text was then struck-out and remains in the ITS Bases markup. l l Differences of the above editorial nature will not be provided as attachments to this response. l The pages requiring changes that are more than editorial and are not consistent with the l markup methodology are attached. i l l l ATTACHED PAGES: Attachment 5, CTS 2.0 - ITS 2.0 Enclosure SB, pages B 2.0-3, B 2.0-5, B 2.0-6, Figure B 2.1.1-1, B 2.0-8, and B 2.0-10 i (
Reactor Core SLs B 2.1.1 BASES APPLICABLE The Reactor Trip System 6]Iowableiyalues sctpcints (Rcf. 2) jr} SAFETY ANALYSES TableM;111:,i in combination with all the LCOs, are designed to (continued) prevent any anticipated combination of transient conditions for Reactor Coolant System (RCS) temperature, pressure RC5; flow,L AI',- and THERMAL POWER level that would result in a departure from nucleate boiling ratio (DNBR) of less than the DNBR limit and preclude the existence of flow instabilities. J Automatic caforc ;;nt of Protectibnl:fot these reactor core SLs is provided .by the fcilcWing functions. steamigeneratorZsafety valvesEand ithelfo]10wj ngEautomaticReactor;tripifunctions:' i
- a. High pressurirer pressure tr1p:-
1
- b. Low pressurizer pressure trip; l
- c. Overtemperature aT trip: l
- d. Overpower AT trip; and. -
- e. Power Range Neutron Flux trip.Wd & a*o* G-1 e....
_ - -..m. _. ... _. . a . a .,. . . . , . . . . &* N"* } The limitation that the average enthalpy in the hot leg be less ' than or equal to the enthalpy of saturated liquid also ensures that the aT measured by instrumentation, used in the RPS design as a measure of core power, is proportional to core power. l l The SLs represent a design requirement 'or establishing the RPS i trip sctpoint; AllowableHalues identified previously. LC0 3.4.1, "RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits," or and the assumed initial conditions of the safety analyses (as indicated in the FSAR, Ref. 2) provide more restrictive limits to ensure that the SLs are not exceeded. l 1 1 SAFETY LIMITS The curves provided in Figure B 2.1.1-1 show the loci of points l of THERMAL POWER, RCS pressure, and average temperature fee below l which the atmm calimlated DNBR is not less than the design DNBR3al_Ue? safcty analyscs limit, that fuel centerline
~
temperature remains below melting, that' the average enthalpy in (continued) l MARK UP OF NUREG-1431 BASES B 2.0 3 5/15/97 l
Reactor Core SLs B 2.1.1 BASES SAFETY LIMIT E-04 ';;-tirraed) I VIOLATIONS to MODE 3 places the unit in a MODE in which this SL is not g p,g,g_f (ceJueJ} applicable. 4 The allowed Completion Time of 1 hour recognizes the importance of bringing the unit to a H00E of operation where this SL is not applicable, and reduces the probability of fuel damage. B- M
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. ,mP that all r.ccessary reviews, analy , and action; are co.Tpleted l befer; the unit bc-ins its restart to nor ,el opcration. l REFERENCES 1. 10 CFR 50. Appendix A. GDC 10.
(continued) MARK-UP OF NUREG 1431 BASES B 2.0 5 5/15/97
l- Reactor Core SLs l t B 2.1.1 l-BASES i l i REFERENCES 2. FSAR, Sectic, '.2. Chapterl E.-. , ! (continued) ,
- 3. WCAP 8746 A, March 1977. i 1
- 4. WCAP 9273 NP A, July 1985. I
.; 10 = 50.72. f.SAR15ectionlEgrra t
1 i S. 10 C 50.73. ESARlSectionIE4"1122 i t 1 i I Q 2.o.c-I u r,,,,, ,4rrke- + J t' l l j i i l L l~ i l I i i e i MARK UP 0F NUREG 1431 BASES B 2.0 6 5/15/97
Reactor Core SLs B2
/r.1 p 4 a.o.s-/ bl; i
680 ' '- DO NOTf dPERATE OT DELTA T OP DELTA T IN fils AREA
/ AB AND TO THE 60 g ' \ -
3 f HT OF LINES l
', 'f ;
2235 PSIG NUCLEAR 4
,, OVERPOWER 640 .
3 -a, ,
\ '. ,
\ l
\
C ', 620 l Nh/ I
$ '\.
a8 O S/G SAFETY VA I 7 N N j 580 \' i
/ l l
~;w \
560 / ACCEPTABLE PERATION ' 540, 3 8 FOR ILLUSTRATION ONLY. DO NOT USE FOR OPERATION. 20 I I I o 20 40 60 80 00 120 PERCENT OF RATED THERMAL POWER %) rigure B 2.1.1;1 (page 1 of 1) Reactor Cora Safety Limits vs. Boundary of Protection WOG ST3 B 2.0-6 Rev 1, 04/07/9
l RCS Pressure SL B 2.1.2 BASES l APPLICABLE The RCS pressurizer safety valves are sized to prevent system ! SAFETY ANALYSES pressure from exceeding the design pressure by more than 10%, as (continued) specified in Section III of the ASME Code for Nuclear Power Plant Components (Ref. 2). The transient that establishes the required relief capacity, and hence valve size requirements and lift settings, is a ceapict; loss of cxtcinal load turbineltrjp without a direct reactor trip. Cases;withEarCwithout i pressurizergpraylandMVslare analyzed; Ouring the transient. 4 2 A6-/ nc control ;;tions ;rc assuT.cd, exccpt that the gfety valves on the secondary phmt side are assumed to open when u.e steam
- pressure. reaches the secondary plant safety valve setting ,end neainoi jain feedwater supply is maintained. lost:atithe1,nelpf; i turbine 3r_1p? p The Reactor Trip System AILowableivalues; r}sint:ndke.)
(acf. :) in Tablel32 Ill17 together with the setting of the MSSVs, provide ; pressure protection for normal ope ati and A00s. The reactor
]
high pressure trip setpoint is specif ally set to provide l protection against overpressurizatio$ (Rcf. 5). The safety ' analyses for both the high pressure trip and the RCS pressurizer safety valves are performed using conservative assumptions relative to pressure control devices. l 1 l Hore specifically, no credit is taken for operation of the following: i l
- a. Pressurizer power operated relief valves (PORVs) (cases ;
l analyzedIwithiand;R1thout)s
- b. Steam linc rclicf valyc, GeneratoQtmo.spherjc1 Steam; Dump Valvest l c. Condenser; Steam Dump Systcm, valves;i
- d. Reactor Control System:
l e. Pressurizer Level Control System; or
- f. Pressurizer spray valves [(cases? analyzed"withfand without)]
SAFETY LIMITS The maximum transient pressure allowed in the RCS pressure vessel under the ASME Code, Section III, is 110% of design pressure. (continued) HARK UP OF NUREG 1431 BASES B 2.0 8 S/15/97 l
RCS Pressure SL B 2.1.2 BASES SAFETY LIMIT VIOLATIONS 2.2.2.2 '- M h 6 g agg QA which would compound the problem by adding thermal gradient stresses to the existing pressure stress. A e o n
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REFERENCES 1. 10 CFR 50, Appendix A GDC 14, CDC 15, and GDC 28.
- 2. ASME, Boiler and Pressure Vessel Code, Section III, Article NB 7000.
1 (continued) MARK UP 0F NUREG 1431 BASES B 2.0 10 5/15/97
. . . . ~ . - ._-. . . .- - . - - - _ - . . . - - - - . - - - _ - - . _ . _ - . . l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2.0-1 APPLICABILITY: CA REQUEST: NUREG-1431 Bases (markup) , B 2.1.1 Reactor Core SLs (Cal!away [page B 2.0-1]) Comment: The BACKGROUND uses the acronym DNBR. The licensee should include
" departure from nucleate boiling ratio" first and then use the acronym DNBR.
FLOG RESPONSE: Comment incorporated on attached Bases page B 2.0-1. ATTACHED PAGES: Attachment 5, CTS 2.0 - ITS 2.0 Enclosure 58, page B 2.0-1 1 1 I
Reactor Core SLs B 2.1.1 B 2.0 SAFETY LIMITS (SLs) B 2.1.1 Reactor Core SLs BASES [ kepr-$vra. hrom nuclede boIl inh refic l BACKGROUND GDC 10 (Ref. I requires that specified acceptable fuel design limits are not exceeded during steady state operation, normal i operational tr nsients, and anticipated operational occurrences { (A00s). This accomplished by having a departure from nucleate i boiling (DNB) esign basis, which corresponds to a 95A probcbility ct c 00% confidcncc icycl (thc 05/05 DNS critericr+ that DNS will nc t cccur cad by rcquiring that fuci ccatcrline tcapcrcturc sta 3 bcicw thc aciting tcapcrcture- 95t probability that the minimu [DNBR)ofjt.heiljmitingfr_od during, Condition.11 l
$ O.d-/
a lleyents;isJgreat.er'thanloriequal"to'thelDNBR limitTof. the D rrelation;beingLusedjthe(WRB 2: correlation _fo.riVANTAGE. 5 ) fuel ~1n;this application).[The: correlation DNBR]imit ~is .. l establishedjbased,on the entire 7 applicable ; experimental 7datalset such_that,therelis~ a . 95tiprobabi.lityfwith 95ticonfidence .that ~ DNB willl;not;; occur when __the': minimum:DNBR is; at thejDNBR ~1imit (1~.17 ; forithelWRB 2 correlation). 'lIn_ meeting' this design' basis, uncertainties in. plant operating. parameters,; nuclear and thermal i parameters, and; fuel fabrication parameters areLconsidered statistically such that there isLat least a 95tJprobability with g 95t< confidence level that the minimum DNBR for. the limiting rod is greater than;or equal _to the DNBR.~ limit. The. uncertainties in the above< plant l parameters are_ usedito determine the plant DNBR uncertainty. This DNBR uncertainty. combined with the I correlation DNBR limit,Jestablishesia design DNBR value which ; must be met in plant; safe _tyEanalyses using values of input parameters without uncertainties. :~For Callaway, the design DNBR l values are 1.33 and 1.34 for thimble and typical cells, respectively, for VANTAGE:5f fuel.lIn addition, margin has been maintained by meeting ; safety.. analysis DNBR limits of 1.61 and 1.69 for thimble and typical .cel_ls, respectively, for VANTAGE 5 fuel. The design DNBRs of 1.33 and 1.35 (STD/0FA) and 1.33 and 1.34 (VS) are used as the bases for_ Technical Specifications, and for consideration of the applicability of unreviewed safety questions as defined in 10_ CFR,50.59. Reference 5 discusses three transients analyzed with. the .W 3 DNBR correlation. The restrictions of this SL prevent overheating of the fuel and cladding, as well as possible cladding perforation, that would result in the release of fission products to the reactor coolant. Overheating of the fuel is prevented by maintaining the steady (continued) MARK UP 0F NUREG 1431 BASES B 2.0 1 5/15/97
l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2.0-2 APPLICABILITY: CA, CP, DC, WC REQUEST: NUREG-1431 Bases (markup) B 2.1.1 Reactor Core SLs (Callaway and Comanche Peak [pages 2.0-3]) Comment: The SAFETY LIMITS refer to Figure B 1.1.1-1. This figure was not included in the B 2.1.1 markup of NUREG-1431. Provide Figure B 1.1.1-1. FLOG RESPONSE: The FLOG has carefully examined the use of examples and typical information in the Bases of the ITS. The intent of these examples and typical information is to clarify the meaning of the Bases and thus the meaning of the ITS. In some cases, the examples and typical information may create a human factors problem. If an example or typical information is not identical to the ITS, the operator may become confused and inadvedently use the , information in the Bases. Although this scenario should be unlikely, the value of the clarification ! provided must be weighed against the possibility and consequences if an operator error is induced. For the subject figure, it was the best judgement of the licensees that the typical information provided in the STS Bases figure should not be included in the ITS Bases and the figure is being intentionally deleted. Callaway and Comanche Peak removed the figure in their initial submittals. Diablo Canyon and Wolf Creek have revised the ITS Bases to reflect deletion of this figure from the ITS Bases. 1 ATTACHED PAGES: None 1
i l 1 l l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 2.0-3 APPLICABILITY: CA. CP, DC, WC l' l REQUEST: NUREG-1431 Bases (markup) B 2.1.2 RCS Pressure SL (All FLOG Plants (Callaway and Diablo Canyon [page B 2.0-8), Comanche Peak [page B 2.0-7), and Wolf Creek (page B 2.0-9)) l Comment: The APPLICABLE SAFETY ANALYSES has been revised to include, " ..The transient that establishes the required relief capacity, and hence valve size requirements and lift settings, is a completeriossef+xternal4oad turbine trip without a direct reactor trip. Cases i with and without pressurizer spray and PORVs are analyzed. During4he4ransentrnacontrol l i actions areessumed;-except4 hat 4he Safety valves on the secondary plant side are assumed l to open when the steam pressure reaches the secondary-plant safety valve settings, and l nominal Main feedwater supply is maintained--lost at the time of turbine trip. i Justify the revised STS Bases 2.1.2 changes. FLOG RESPONSE: These mark-ups directly reflect plant-specific accident analyses discussed in FSAR Chapter 15. Plant Specific Discussion FSAR Section 15.2.2 states the following: "A loss of extemal load event results in a NSSS ) transient that is less severe than a turbine trip event (see Section 15.2.3). Therefore, a detailed transient analysis is not presented for the loss of extemalload event." As such, the ITS Bases were revised to reflect the turbine trip analyses. FSAR Section 15.2.3.2 specifically states that main feedwater flow is terminated at the time of turbine trip and th.at cases with and without pressurizer spray and PORVs are analyzed. Copies of pertinent FSAR pages are attached for information. ATTACHED PAGES: ! Callaway FSAR pages 15.2-3 through 15.2-8, Table 15.2-1 l l l 1 i I l
CALLAWAY - SP signal. The steam generator shell side pressure and reacror (<~75 coolant temperature will increase rapidly. The pressurizer safety valves and steam generator safety valves are, however, sized to protect the RCS and steam generator against over-pressure for all load losses without assuming the operation of the steam dump system, steam / generator PORVs, pressurizer spray, pressurizer power-operated relief valves, automatic RCCA control, or direct reactor trip on turbine trip. The steam generator safety valve capacity is sized to remove the steam flow at 100 percent of rated thermal power from the steam generator without exceeding 110 percent of the steam l system design pressure. The pressurizer safety valve capacity f73%~) is sized based on a complete loss of heat sink with the plant i rL initially operating at the maximum calculated turbine load I along with operation of the steam generator safety valves. i The pressurizer safety valves are then able to relieve I sufficient steam to maintain the RCS pressure within 110 percent of the RCS design pressure. I A more complete discussion of overpressure protection can be found in Reference 1. I A loss of external load is classified as an ANS Condition II event, fault of moderate frequency. See Section 15.0.1 for a discussion of Condition II events. A loss of external load event results in a NSSS transient that < _ is less severe than a turbine trip event (see Section 15.2.3). I Therefore, a detailed transient analysis is not presented for l the loss of external load event. i su The primary side transient is caused by a decrease in heat transfer capability from primary to secondary, due to a rapid termination of steam flow to the turbine, accompanied by an automatic reduction of feedwater flow. Should feedwater flow not be reduced, a larger heat sink would be available and the transient would be less severe. Termination of steam flow to the turbine following a loss of external load occurs due to 3, automatic fast closure of the turbine control valves in approxi-ffsEf mately 0.2 seconds. Following a turbine trip event, l M6I termination of steam flow occurs via turbine stop valve closure, which occurs in approximately 0.19 seconds. Therefore, the transient in primary pressure, temperature, and water volume will be less severe for the loss of external load than for the turbine trip due to a slightly slower loss of heat transfer capability. The protection available to mitigate the consequences of a loss of external load is the same as that for a turbine trip, as listed in Table 15.0-6. m Rev. OL-4 15.2-3 6/90
CALLAWAY - SP l l 15.2.2.2 Analysis of Effects and Consequences l Refer to Section 15.2.3.2 for the method used to analyze the limiting transient (turbine trip) in this grouping of events. ~ / ) The results of the turbine trip event analysis are more severe ; than those expected for the loss of external load, as discussed l in Section 15.2.2.le j l Plant systems and equipment which may be required to function to mitigate the effects of a complete loss of load are dis- ; cussed in Section 15.0.8 and listed in Table 15.0-6. The reactor protection system may be required to function following a complete loss of external load to terminate core heat input and to prevent departure from nucleate boiling I (DNB). Depending on the magnitude of the load loss,
-pressurizer safety valves and/or steam generator safety valves l may be required to open to maintain system pressures below !
cllowable limits. No single active failure will prevent operation of any system required to function. Normal reactor control systems and engineered safety features are not I required to function. The auxiliary feedwater system may, 4 however, be automatically actuated following a lose of main i feedwater; this will further mitigate the effects of the transient. 15.2.2.3 Conclusions Based on results obtained for the turbine trip event (see ') Section 15.2.3) and considerations described in Secti'on 15.2.2.1, ..- the applicable acceptance criteria for a loss of external load ; j event are met.
- i 15.2.3 TURBINE TRIP 15.2.3.1 Identification of Causes and Accident Description For a turbine trip event, the reactor would be tripped directly (unless below approximately 50-percent power) from a signal derived from the turbine emergency trip fluid pressure trans-mitters and tv.rbine stop valve limit switches. The turbine i b;gg stop valves close rapidly (typipally 0.19 second) on loss of :iF) n- ,
trip fluid pressure actuated by one of a number of possible - turbine trip signals. Turbine trip initiation signals include:
- a. Generator trip
- b. Low condenser vacuum
- c. Loss of lubricating oil
- d. Turbine thrust bearing failure v'
Rev. OL-4 15.2-4 6/90
l CALLAWAY - SP p ., _ , e. Turbine overspeed
- f. Manual trip -
Upon initiation of stop valve closure, steam flow to the turbine stops. abruptly. Limit switches on the stop valves detect the turbine trip and initiate steam dump, and, if above , 50-percent power, a reactor trip. The loss of steam flow results in an almost immediate rise in secondary system tem-perature and pressure, with a resultant primary system tran-sient as described in Section 15.2.2.1 for the loss of external load event. A more severe transient occurs for the turbine trip event, due to the more rapid loss of steam flow caused by fr'd.
,e .
the more rapid valve closure.
~
The automatic steam dump system would normally accommodate the excess steam generation. Reactor coolant temperatures and pressure do not significantly increase if.the steam dump system and pressurizer pressure control system are functioning properly. If the turbine condenser was not available, the excess steam generation would be dumped to the atmosphere and main feedwater flow would be lost. For this situation, feedwater flow would
- be maintained by the auxiliary feedwater system to ensure adequate residual and decay heat removal capability. Should the steam dump system fail to operate, the steam generator safety valves may lift to provide pressure control. See 1 Section 15.2.2.1 for a further discussion of the transient. '
A turbine trip is classified as an ANS Condition II event, l fault of moderate frequency. See Section 15.0.1 for a dis-cussion of Condition II events, turbine trip event is more limiting than loss of external load, loss of condenser vacuum, and other turbine trip events. As such, this event has been analyzed in detail. Results and , discussion of the analysis are presented in Section 15.2.3.2. i
- -)
15.2.3.2 Analysis of Effects and Conspauences , .. Method of Analysis SWk. k.:# In this analysis, the behavior of the plant is evaluated for a
- complete loss of steam load from full power without direct reactor trip.
This is done to show the adequacy of the pres-sure relieving devices, and also to demonstrate core protection
, margins. The reactor is not tripped until conditions in the RCS result in a trip. The turbine is assumed to trip without actuating all the turbine stop valve limit switches. This j assumption delays reactor trip until conditions in the RCS result in a trip due to other signals. Thus, the analysis assumes a worst-case transient. In addition, no credit is taken for steam dump. Main feedwater Zlow is terminated at the
; time of turbine trip, with no credit P.aken,for auxiliary l
l ! Rev. OL-4 15.2-5 6/90
CALLAWAY - SP i feedwater (except for long-term recovery) to mitigate the ; consequences of the transient. , The turbine trip transients are analyzed by employing the ( ,,) detailed digital computer code LOFTRAN (Ref. 2). LOFTRAN l cimulates the neutron kinetics, RCS, pressurizer, pressurizer relief and safety valves, pressurizer spray, steam generators, end steam generator safety valves. It also computes pertinent plant variables, including temperatures, pressures, and power l level. l This accident is analyzed with the ITDP as described in Refer-cnce 4. Plant characteristics and initial conditions are discussed in Section 15.0.3. Uncertainties in initial condi- 1 tions are included in the limit DNBR as described in Reference 4. [~"\ i l Major assumptions are summarized below:
- a. Moderator and Doppler Coefficients of Reactivity The turbine trip is analyzed with both maximum and minimum reactivity feedback. The maximum feedback l cases assume a large negative moderator temperature 1 l coefficient and the most negative Doppler power coefficient. The minimum feedback cases assume a minimum moderator temperature coefficient and the least negative Doppler coefficient. t)
- b. Reactor control From the standpoint of the maximum pressures attained, it is conservative to assume that the reactor is in manual control. If the reactor were in automatic l control, the control rod banks would move prior to l trip and reduce the severity of the transient. j
- c. Steam release l No credit is taken for the operation of the steam dump i system or steam generator power-operated relief gl,.}idg valves. The steam generator pressure rises to the (f;if !
point where steam release through safety valves occurs thus limiting the secondary steam pressure increase.
- d. Pressurizer spray and power-operated relief valves w g
Two cases for both the minimum and maximum reactivity l l feedback cases are analyzed:
- 1. Full credit is taken for the effect of pressurizer I spray and power-operated relief valves in reducing or limiting the coolant pressure. Safety valves are also available. l w-l Rev. OL-4 15.2-6 6/90
CALLAWAY - SP 2. j"'?> No credit is taken for the effect of pressurizer spray and power-operated relief valves in )
- 1. '//
reducing or limiting the coolant pressure. y Safety valves are operable. I
- e. Feedwater flow '-
Mainfeedwaterflowtothesteamgeneratorsisassumed]' to be lost at the time of turbine trip. No credit is taken for auxiliary feedwater flow since a stabilized plant condition ~will be reached before auxiliary feedwater initiation is normally assumed to occur; however, the auxiliary feedwater pumps would be jfrpg expected to start on a trip of the main feedwater ' e > LW pumps. The auxiliary feedwater flow would remove core decay heat following plant stabilization.
- f. Reactor trip is actuated by the first reactor protec-tion system trip setpoint reached, with no credit taken for the direct reactor trip on the turbine trip.
Trip signals are expected due to high pressurizer pressure, overtemperature AT, high pressurizer water level, and low-low steam generator water level. Plant systems and equipment which may be required to function to mitigate the effects of a turbine trip event are discussed - in Section 15.0.8 and listed in Table 15.0-6.
- Except as discussed, normal reactor control systems and engi- !
neered safety features are not required to function. Cases are presented in which pressurizer spray and power-operated relief valves are assumed, but the more limiting cases where those l functions are not assumed are also presented. The reactor prctection system may be required to function following a turbine trip. Pressurizer safety valves and/or steam generator safety valves may be required to open to maintain system pressures below allowable limits. No single 1 active failure will prevent operation of any system required to l
.t function.
dhh wes' Results i I The transient responses for a turbine trip from full power operation are shown for four cases: two cases for minimum reactivity feedback and two cases for maximum reactivity feedback (Figures 15.2-1 through 15.2-8). The calculated sequence of events for the accident is shown in Table 15.2-1. Figures 15.2-1 and 15.2-2 show the transient responses for the total loss of steam load with minimum reactivity feedback, assuming full credit for the pressurizer spray and pressurizer power-operated relief valves. No credit is taken for the steam dump. The reactor is tripped by high pressurizer l Rev. OL-4 15.2-7 6/90
CALLAWAY - SP pressure trip channels. The minimum DNBR remains well above the safety analysis limit values. The pressurizer safety valves are not actuated for this case and, therefore, maintain 7 cystem pressure below 110 percent of the design value. The s_ I cteam generator safety valves open and limit the secondary cteam pressure increase. Figures 15.2-3 and 15.2-4 show the response for the total loss of steam load with maximum reactivity feedback. All other plant parameters are the same as the above. The reactor is tripped on the overtemperature AT signal. The DNBR increases throughout the transient and never drops below its initial value. Pressurizer relief valves and steam generator safety valves prevent overplessurization in primary and secondary i cystems, repectively. The pressurizer safety valves are not cetuated for this case. f~'\$ i l l The turbine trip accident was also studied assuming the plant , to be initially operating at full power with no-credit taken ' for the pressurizer spray, pressurizer power-operated relief i valves, or steam dump. The reactor is tripped on the high ! pressurizer pressure signal. Figures 15.2-5 and 15.2-6 show l the transients with minimum reactivity feedback. The neutron I flux remains essentially constant at full power, until the l reactor is tripped. The DNBR never goes below the initial ' value throughout the transient. In this case, the pressurizer cafety valves are actuated, and maintain system pressure below ,_, 110 percent of the design value. 3 ; 1 Figures 15.2-7 and 15.2-8 show the transients with maximum "" i reactivity feedback, with the other assumptions being the same ! cs in the preceding case. Again, the DNBR increases throughout ' the transient and the pressurizer safety valves are actuated to limit primary pressure. < Reference 1 presents additional results of analysis for a complete loss of heat sink, including loss of main feedwater. This analysis shows the overpressure protection that is efforded by the pressurizer and steam generator safety valves. 15.2.3.3 Conclusions gfh{g F Results cf the analyses, including those in Reference 1, show that the plant design is such that a turbine trip without a direct or immediate reactor trip presents no hazard to the integrity of the RCS or the main steam system. Pressure-relieving devices incorporated in the two systems are adequate to limit the maximum pressures to within the design limits. The integrity of the core is maintained by operation of the reactor protection system, i.e., the DNBR will be maintained tbove the safety analysis limit values. The applicable accep-tance criteria as listed in Section 15.0.1 have been met. The cbove analysis demonstrates the ability of the NSSS to safely withstand a full load rejection. - Rev. OL-4 15.2-8 6/90
.,. _ , . __ _ -~ _ . . _ . . . . . . _ . _ _ . . _ _ _ . _ . . . . _ . ._
l l CALLAWAY - SP i TABLE 15.2-1 ; I TIME SEQUENCE OF EVENTS FOR INCIDENTS WHICH , RESULT IN A DECREASE IN HEAT REMOVAL BY ' THE SECONDARY SYSTEM Time l Accident Event (sec) j j Turbine Trip ~
- 1. With pressurizer control (minimum reactivity feedback) Turbine trip; loss of 0.0
~~i main feedwater flow j High pressurizer pressure 7.4 reactor trip setpoint l reached
.i Initiation of steam 8.0 release from steam generator safety valves Rods begin to drop 9.4 Peak pressurizer 10.5 pressure occurs Minimum DNBR occurs 11.0
- 2. With pressurizer
! control (maximum l reactivity feedback) Turbine trip; loss of 0.0 l main feedwater flow Initiation of steam 8.0 release from steam l generator safety valves Peak pressurizer 9.0 pressure occurs Overtemperature AT 12.6 l reactor trip setpoint i reached j Rods begin to drop 14.6 Minimum DNBR occurs
- 1 4
Rev. OL-4 , 6/90
_. ~ CALLAWAY - SP TABLE 15.2-1 (Sheet 2) Time Accident Event (sec)
- 3. Without pressurizer control (minimum g reactivity feedback) Turbine trip; loss of 0.0 main feedwater flow j High pressurizer 4.8 pressure reactor trip setpoint reached l
s Rods begin to drop 6.8 ' Initiation of steam 8.0 release from steam generator safety valves Peak pressurizer 8.5 pressure occurs Minimum DNBR occurs *
- 4. Without pressurizer control (maximum '
j reactivity feedback) Turbine trip; loss of 0.0 main feedwater flow HigF pressurizer 4.7 pressure reactor trip setpoint reached l Rods begin to drop 6.7 Initiation of steam 8.0 release from steam generator safety valves , Peak pressurizer 8.0 pressure occurs Minimum DNBR occurs
- Rev. OL-4 6/90 l
q J
., A _. A__ L -w~ -J m A4, 4 M-tum. m T 2,._, .._a .a -ua, m.a _, u ,4%__;. -.mA 4 44_.#,,e.p. a_ A4a g_.4.A 3A .J.Ae + e 4.4.s .4=a--. ss M, a I
i I l l l JLS CONVERSION TO IMPROVED TECHNICAL SPECIFICATIONS CTS 3/4.0 - LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS ITS 3.0 - LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY AND SL'RVEILLANCE REQtilREMENT (SR) APPLICABILITY RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION AND LICENSEE INITIATED ADDITIONAL CHANGES
- INDEX OF ADDITIONAL INFORMATION ADDITIONAL INFORMATION APPLICABILITY ENCLOSED l NUMBER I 3.0.G-1 DC, CP, WC, CA YES l l
3.0-1 DC, CP, WC, CA YES 3.0-2 CP NA 3.0-3 DC, CP, WC, CA YES 3.0-4 DC, CP, WC, CA YES 3.0-5 DC, CP, WC, CA YES 3.0-6 DC,CP,WG,CA YES 3.0-7 DC NA DC 3.0-001 DC NA TR 3.0-001 DC, CP, WC, CA YES l TR 3.0-002 DC, CP, WC, CA YES I i a
I JOINT LICENSING SUBCOMMITTEE METHODOLOGY FOR PROVIDING ADDITIONALINFORMATION The following methodology is followed for submitting additional information: l
- 1. Each licensee is submitting a separate response for each section.
- 2. If an RAI does not apply to a licensee (i.e., does not actually impact the information that defines the technical specification change for that licensee), "NA" has been entered in the index column labeled " ENCLOSED" and no information is provided in the response for that licensee.
- 3. If a licensee initiated change does not apply, "NA" has been entered in the index column labeled " ENCLOSED" and no information is provided in the response for that licensee.
- 4. The common portions of the " Additional Information Cover Sheets" are identical, except for brackets, where applicable (using the same methodology used in enclosures 3A,3B, 4,6A and 6B of the conversion submittals). The list of attached pages will vary to match the licensee specific conversion submittals. A licensee's FLOG response may not address all applicable plants if there is insufficient similarity in the plant specific responses to justify their inclusion in each submittal. In those cases, the response will be prefaced with a heading such as " PLANT SPECIFIC DISCUSSION."
- 5. Changes are indicated using the redline! strikeout tool of Wordperfect or by using a hand markup that indicates insertions and deletions. If the area being revised is not clear, the affected portion of the page is circled. The markup techniques vary as necessary, based on the specifics of the area being changed and the complexity of the changes, to provide the clearest possible indication of the changes.
- 6. A marginal note (the Additional Information Number from the index)is added in the right margin of each page being changed, adjacent to the area being changed, to identify the source of each change.
- 7. Some changes are not applicable to one licensee but still require changes to the Tables provided in Enclosures 3A,3B,4,6A, and 6B of the originallicense amendment request to reflect the changes being made by one or more of the other licensees. These changes are not included in the additional information for the licensee to which the change does not apply, as the changes are only for consistency, do not technically affect the request for that licensee, and are being provided in the additional information being provided by the licensees for which the change is applicable. The complete set of changes for the license amendment request will be provided in a licensing amendment request supplement to be provided later.
l l l l
! JOINT LICENSING SUBCOMMITTEE METHODOLOGY FOR l PROVIDING ADDITIONALINFORMATION (continued) l l l
- 8. The item numbers are formatted as follows: [ Source] [lTS Section)-[nnn) l Source = Q - NRC Question CA- AmerenUE DC-PG&E WC - WCNOC CP - TU Electric TR - Traveler ITS Section = The ITS section associated with the item (e.g.,3.3). If all sections are potentially impacted by a broad change or set of changes, "ALL" is used for the section number.
nnn = a three digit sequential number or ED (ED indicates editorial correction with no - impact on meaning) l 1 l i
I ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.0.G-1 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 3.0.x Bases There have been a number of instances that the specific changes to the STS Bases are not properly identified with redline or strikeout marks. . 1 Comment: Perform an audit of all STS Bases markups and identify instances where additions and/or deletions of Bases were not properly identified in the original submittal. l FLOG RESPONSE: The submitted ITS Bases markups for Section 3.0 have been compared to l the STS Bases. Some differences that were identified were in accordance with the markup methodologies (e.g., deletion of brackets and reviewer's notes). Most of the differences were editorialin nature and would not have affected the review. Examples of editoria! changes are:
- 1) Capitalizing a letter with only a " redline" but not striking out the lower case letter that it replaced.
- 2) Changing a verb from singular to plural by adding an "s" without redlining the "s".
l
- 3) Deleting instead of striking-out the A, B, C, etc., following a specification title (e.g., SR 3.6.6A.7).
- 4) Changing a bracketed reference (in the reference section) with only a
" redline" for the new reference but failing to include the strike-out of the old reference.
- 5) In some instances the brackets were retained (and struck-out) but the unchanged text within the brackets was not redlined.
- 6) Not redlining a title of a bracketed section. The methodology calls for the section title to be redlined when an entire section was bracketed.
I
- 7) Additional text not contained in the STS Bases was added to the ITS Bases by the lead FLOG member during the development of the submittal.
Once it was determined to not be applicable, the text was then struck-out and remains in the ITS Bases markup. Differences of the above editorial nature will not be provided as attachments to this response. The pages requiring changes that are more than editorial and are not consistent with the markup methodology are atteched. ATTACHED PAGES: , CTS 3/4.0 - ITS 3.0 8, page B 3.0-6
_ m_ . - _ . . . _ _ . . . . . _ _ _ _ _ _ _ _ - _ . . _ _ _ _ . _ . _ _ _ _ 1 LCO Applicability j B 3.0 j BASES LCO 3.0.4 Exceptions to LC0 3.0.4 are stated in the individual
- (continued) Specifications.
5 m Exceptions may apply to all the ACTIONS or to a specific Required Action of a Specification. LCO 3.0.4 is only applicable when entering MODE 4 from H0DE 5, i MODE 3 from H0DE 4 H0DE 2 from H0DE 3, or H0DE 1 from H0DE 2. Furthermore, LCO 3.0.4 is applicable when entering any other " specified condition in the Applicability only while operating in H0 DES 1, 2, 3, or 4. The requirements of LCO 3.0.4 do not apply l in H0 DES 5 and 6, or in other specified conditions of the Applicability (unless in H0 DES 1, 2, 3 or 4) because the ACTIONS 1- of individual Specifications sufficiently define the remedial ] , meas _ures to be taken. /Tn some cases (e.g., 6 M 0' f 6 these ACTIONS provide a Note that
- states "While this LCO is not met, entry into a H0DE or other specified condition in the Applicability is not permitted, unless required to comply with ACTIONS." This Note is a requirement explicitly precluding entry into a H0DE or other specified
; condition of the ApplicabQity.
( )line p> Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as pemitted by SR 3.0.1. Therefore, changing MODES or other specified conditions while in an ACTIONS Condition, in compliance with LCO 3.0.4 or where an exception to LC0 3.0.4 is stated, is not a violation of SR 3.0.1 or SR 3.0.4 for those Surveillances that do not have to be performed due to the , associated inoperable equipment. However, SRs must be met to l ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance
, with the affected LCO.
LC0 3.0.5 LC0 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with ACTIONS. The sole purpose of this Specification is to provide an exception to LC0 3.0.2 (e.g., to not comply with the applicable Required (continued) HARK UP 0F NUREG 1431 BASES B 3.0 6 5/15/97
l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 3.0-1 APPLICABILITY: CA, CP, DC, WC l REQUEST: ITS SR 3.0.3 , CTS SR 4.0.3 (All FLOG Plants) l DOC 1-20-A Comment: The CTS Markups of CTS SR 4.0.3 for all FLOG plants do not accurately reflect the ITS end product, SR 3.0.3 (ITS 3.0.3 is compatible with the STS and acceptable). Correct CTS Markup, or revise ITS Markup and provide justification. FLOG RESPONSE: The markups for CTS SR 4.0.3 and CTS SR 4.0.1 have been revised to be consistent with ITS SR 3.0.3 and ITS SR 3.0.1. l The CTS markups have been revised to reflect moving CTS SR 4.0.3 phrases into CTS SR 4.0.1 and DOC 1-20-A has been revised to state:
" Editorial changes to CTS SR 4.0.1 are made for consistency with NUREG-1431 SR 3.0.1. The CTS SR 4.0.3 phrase " Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation" was moved to CTS SR 4.0.1 (ITS SR 3.0.1) to establish the relationship between Surveillance Requirements and meeting the nequirements of the LCO. In addition, the words "except as provided in Specification 4.0.3" are added at the end of the moved sentence to retain the exception provided by the CTS markup of SR 4.0.3. The CTS SR 4.0.3 phrase " Surveillance Requirements do not have to be performed on inoperable equipment" was moved to CTS SR 4.0.1 (ITS SR 3.0.1) to establish the relationship between Surveillance Requirriments and meeting the requirements of the LCO. This phrase has also been modified to include variables not within limits since Specifications covar more than equipment (e.g., containment pressure)."
CTS SR 4.0.3 is revised to specify required actions whenever the Surveillance Requirement fails or whenever the delay period is exceeded. DOC 1-08-LS-4 and NSHC LS-4 have been modified to specifically address this change by adding the following words:
"The CTS has been revised to add the phrases "If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition (s) must be entered" and "When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition (s) must be entered" to clarify the delay period."
ATTACHED PAGES: Attachment 6, CTS 3/4.0 - ITS 3.0 l Enclosure 2, page 3/4 0-2 l Enclosure 3A, pages 4 and 5 Enclosure 3B, page 2 Enclosure 4, page 47
- _ . _ . _ _ _ . _ _ _ - .- __._. _ ___._.q l
l . i 1
- 1 APPLICABILITY e SURVEILLANCE REOUTREMENTS l 1
v - 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL MODES or other conditions en*Hfied for individual Limiting Conditions for Operation un otherwise stated in an individual surveliiance Requiremer,t - CNIEg"T'f, o, / f_g_A N % _ 8yff 4.0.2 Each Surveillance Requirement shall be performed within the - specified' surveillance interval with a maximum allowable extension not to 25% of the specified surveillance interval. WSE.cr 4:D..;a -~
<- /-67-LS 4.0.3 re; ... . d 7., ,;n : : rc:m :.::: " ;ur: :-t "ith 4 a th: 9 i:. '/f-A e -" !'
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,,,q;j n; :t: 5:r : Li itin; ;;;gjti;,3 3,,g7~",g Or: :;;11::.ble ;; th; ti;; it i: identified th:t :. 0;r's;ill:,n;; P.;;uir;;;nt l 5:: n:t b;:n ;;rf;r;;d. Th: ACTION r:;uir.;;nt: ::2 b: d:hy:d f:r ; t:
21 h:gr: t: ;; mit th: :;;;hti:n :f th: : re:ilha : h n th: ;11: 21;
- eut;;; ti;; liaits ;f th; ACTION r;;;ir::::t: cr: h:: th: 21 5: r:. !
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4
- 4. 0: .4 Entry into an OPERATIONAL MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the
) Limiting Condition for Operation have been performed within the stated c surveillance interval or as otherwise specified. This provision shall not s
prevent passage throJu h- or to OPERATIONAL M0QES gs regtired s to com 2 ACTION requirements {er fAa+ are fac+ ef a Jhufamn er f48 Wilf, ply with j gg
~
3 t'NfEK7"' 4.b.+ l~0 f-AS 4 i 4.0.5 Surveillance Requirements for inservice '-~;::ti:r :nd testing of /-//-Lg. t ASME Code Class 1, 2, and 3 components shall be applicable as follows: !
/-/O-A
- a. -!,::r"i:: in:;::ti:n :f *.EME C:d: Ch:: 2, 2, 2nd ? : ;:n:nt: / //-/_G
- M inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda-es /-/4-A r
- ;;ir:d by 20 CF" P:rt 50, 5 : tier 50.55 C),.except where specific written relief has been granted by the Commission
- ;ur: ::t t: 10 CF" P:rt 50, 5::ti:n ~0.5 :.(;}(5)(i).
1, j CALLAWAY - UNIT I 3/4 0-2 Amendment No. 52,78
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-~
l INSERT 4.0.1 Q3.0-1 i
}
Failure to perform a Surveillance Requirement within the allowed surveillance interval, l defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY ! requirements for a Limiting Condition for Operation, except as provided in Specification 4.0.3. Surveillance Requirements do not have to be performed on inoperable ; equipment or variables outside specified limits. i 1 l
INSERT 4.0.2 I / J g For Frequencies specified as "once," the above interval extension does not /-d /-Lf ' apply. If a Completion Time requires periodic performance on a "once per . . ." , basis, the above Frequency extension applies to each performance after the initial performance. ] ., Exceptions to this Specification are stated in the individual Specifications. /-/f-A , e i l 1
- INSERT 4.0.3 !
4 Ifit is discovered that a Surveillance was not performed within its specified /-dt-L.S Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours or up to the limit of the specified Frequency, whichever is less. This delay period is permitted to allow performance of the Surveillance. _ gg_p
.rF +La fuevaiIIanc e ir no+ f arfo<m al wr#rn +L* delay f a n~o), +bn l-t t-LS L.co mu.r+ i'mmeolia +e ly 6e deelaeel no+ me+, and +As s,y/reaLIc Con)THon(r) mur+ L e e++e ad
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a + -a - I SR 4.0.4 is only applicable for entry into a MODE or other specified /-ti9-LS condition in the Applicability in MODES 1,2,3, and 4. 4 4 4 1 4
)
CHANGE NUMBER N_S11C DESCRIPTION
, from the perspective of safety, as equipment is normally demonstrated OPERABLE, not inoperable via surveillance performance. f M M F SA - 4 d#N 1-09 LS 1 Surveillance Requirement 4.0.4 was previously applicable for entry into all H0 DES. The specification has been revised to not prevent unit shutdowns and will apply only to entry into MODES 1, 2, 3, and 4 from lower H0 DES. This change is less restrictive in that it will allow H0DE changes from either direction into MODES 5 and 6 prior to the performance of Surveillance Requirements. As required in the " Reviewer's Note" of NUREG 1431 Rev.1, SR 3.0.4, a matrix is provided (see LS 1) which documents the plant- l specific review of all specifications for determination of )
where specific restrictions on. H0DE changes or Required Actions should be included in individual LCOs. The change is acceptable for those specifications for which specific restrictions were not deemed warranted. 1 10 A Specification 4.0c5, the surveillance requirements for inservice testing, are moved to .the Administrative l Controls Section 5.5.8 consistent with NUREG 1431 Rev.1. The reference to 10CFR50.55a is unnecessary and has been ! deleted. >
~
l 1-11 LG The portions of Specification 4.0.5 concerning Inservice Inspection are moved to the Inservice Inspection Program l Plan. The requirements of 10CFR50.55a are adequate and
, technical specifications are not necessary.
1-12 A Consistent with the NUREG 1431 Rev. 1, Programs and , l Hanuals section ITS 5.5.8, the CTS is clarified to I address the frequency (in days) for biennial requirements which was previously inferred but not explicitly stated in the CTS. 1 13 A Adds applicability of 4.0.3 (SR 3.0.3 in improved TS) for Inservice Testing for consistency with the wording in NUREG 1431 Rev. 1. In NUREG 1431 Inservice Testing is moved to the Programs and Manuals section (ITS 5.5.8) and is no longer a surveillance requirement. Thus, an explicit statement that ITS SR 3.0.3 (CTS 4.0.3) is applicable is necessary to provide for the performance of missed IST requirements. CTS 4.0.5 (Inservice Testing) is currently a Surveillance Requirement and thus, by definition, CTS 4.0.3 applies. 4 DESCRIPTION OF CHANGES TO CURRENT TS 4 5/15/97
l 1 : l l lNSERT 3A-4 Q3.0-1
\
The CTS has been revised to add the phrases "If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the l applicable Condition (s) must be entered" and "When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition (s) must be entered" to clarify the delay j period. ' l l c ( * # 3
. . - . . . _ _ . . . - . _ - . ~ . . - . . - _ . = _ - . . . - - . - . - - . .-
1 l CHANGE NUMBER GC DESCRIPTION 1 14 - Not applicable to Callaway. See Conversion Comparison Table (Enclosure 3B). I 1 15 - Not applicable to Callaway. See Conversion Comparison Table (Enclosure 30). 1 l 1 16 - Not applicable to Callaway. See Conversion Comparison l Table (Enclosure 3B). l 1 17 A Consistent with the wording used in NUREG-1431 Rev.1, l Section 5.5.8. the statement concerning performance of l l inservice testing being in addition to other specified i surveillance requirements is deleted. The statement is redundant to the usage rules and is not necessary. 1 18 LS 5 Revises LC0 3.0.4 to allow MODE entry if associated ACTION l has no time limit. consistent with NRC GL 87 09 and l NUREG 1431 Rev. 1. 1 19 A Consistent with NUREG 1431. Rev. 1 the phrase " Exceptions to this Specification are stated in the individual l Specifications" was added to CTS SR 4.0.2 to provide l exceptions in individual Frequencies where the allowances provided in SR 4.0.2 are not allowed. This additional wording will have no impact on current practice regarding compliance with SRs. 1 20 --A-- istent with NUREG-1431 Rev.1. the phrase "
, variab e ide specified limits" is to the i statement that su lances ave to be performed on inoperable equipme -
's is not a technical change in that "variab utside spec limits" is now explicit ated in the ITS whereas, he CTS. it was im it in the definition of inoperable eq nt.
ZAlfENT' 3%- S' S #'0~l Q 2.0-S l DESCRIPTION OF CHANGES TO CURRENT TS 5 5/15/97
INSERT 3A-5 Q3.0-1 1-20 A Editorial changes to CTS SR 4.0.1 are made for consistency with NUREG-1431 SR 3.0.1. The CTS SR 4.0.3 phrase " Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation" was moved to CTS SR 4.0.1 (ITS SR 3.0.1) to establish the relationship between Surveillance Requirements and meeting the requirements of the LCO. In addition, the words "except as provided in Specification 4.0.3" are added at the end of the moved sentence to retain the exception provided by the CTS markup of SR 4.0.3. The CTS SR 4.0.3 phrase " Surveillance Requirements do not have to be performed on inoperable equipment" was moved to CTS SR 4.0.1 (ITS SR 3.0.1) to establish the relationship between Surveillance Requirements and meeting the requirements of the LCO. This phrase has also been modified to include variables not within limits since Specifications cover more than equipment (e.g., containment pressure). Q3.0-5 1 Not applicable to Callaway. See Conversion Comparison Table (Enclosure 38). I l
CONVERS10N COMPARISON TABLE - CURRENT TS 3/4.0 Page 2 of 2 TECH SPEC CHANGE APPLICABILITY NWBER DESCRIPTION DIABLO CANYON COMANCE PEAK WOLF CREEK CALLAWAY 1-10 Specification 4.0.5. the surveillance requirements for Yes Yes Yes Yes A inservice testing, are moved to tne Administrative Controls Section 5.5.8. 1-11 The portions of Specification 4.0.5 concerning Inservice Yes Yes Yes Yes LG Inspection are moved to the Inservice Inspection Program Plan. 1-12 This change adds clarification to address biennial Yes Yes Yes Yes A requirements. 1-13 This change adds applicability of 4.0.3 (SR 3.0.3 in Yes Yes Yes Yes A inproved TS) for Inservice Testing. 1-14 The surveillance requirements for the Steam Generators are No - SG Yes No - SG No - SG A reformatted and moved to improved TS SR 3.4.13.2 and the surveillance is in surveillance is in surveillance is in Adninistrative Controls Section 5.5.9. current TS 3/4.4.5. current TS 3/4.4.5. current TS 3/4.4.5. 1-15 Clarification to remove potential interpretation problems No - SG Yes No - SG No - SG A related to probe orientation versus entry point. surveillance is in surveillance is in surveillance is in current TS 3/4.4.5. current TS 3/4.4.5. current TS 3/4.4.5. 1-16 The reporting requirement for steam generator tube No - SG Yes No - SG No - SG A inspections is moved to improved TS 5.6.10. surveillance is in surveillance is in surveillance is in current TS 3/4.4.5. current TS 3/4.4.5. current TS 3/4.4.5. 1-17 Current TS Surveillance Requirement [4.0.5.d] is deleted. Yes Yes Yes Yes A Performance of other specified Surveillance Requirements is mandated in the individual TS and does not require a separate section to ensure compliance. 1-18 Revises LCO 3.0.4 to allow MODE entry if associated ACTION No - already in No - alread; in Yes Yes LS-5 has no time limit. consistent with NRC GL 87-09. current TS. current TS. 1-19 The phrase " Exceptions to this Specification are stated in Yes No - already in Yes Yes A the individual Specifications" was added to CTS SR 4.0.2 to current TS. provide exceptions in individual Frequencies where the allo,wances provi.ded in SR
- - - 4.0.2 _. are not allowed. I n ..
... --_._ mYesconvirtwy wif,Aesstruggg-pyyy g.s y a.j, g) g o./
1-20 C,icut,;.o
, y m m -tal_.ou.o .m ouwuur-t* m ue My ye w MtA./ icu rs:e nmte,
.~ Yes A iu u.x aaie- sai a.. Ki'T r: : :1r.ct P.r: te h-
-g. :m e u,. .w.:,LT pi f I
Th a r*t**I'* **4 ~l8 LCD fr jfe-.r Y'er Afo fe, Cgj flg Je, cAf AC77DffyE"*mICo VERSION COMPARISON TABLE - CURRENT '.i pff Q V8 j gf d , /-d/-A hIh/hIg y < o -- - __2 s
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IV. SPECIFIC NO SIGNIFICANT HAZARDS EVALUATIONS NSHC LS 4 4 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS This change is administrative in nature as the time allowed to perform a missed surveillance upon discovery is changed from up to 24 hours when the allowed outage time limits of the ACTION requirements are less than 24 hours, to the lesser of 24 hours or the surveillance frequency interval. Additionally the equipment is not - required to be declared inoperable at the time of discovery of a missed surveillance. This prevents unnecessary entry into Conditions based solely on equipment inoperabilities when the equipment is anticipated to be demonstrated OPERABLE by surveillar.ce performance. The change is acceptable because it still restricts performance of the surveillance to within 24 hours of discovery and the equipment is normally demonstrated to be OPERABLE, not inoperable, by performance of the surveillance.EA/JEAT LS Q 7,d-/ This proposed TS change has been evaluated and it has been determined that it involves no significant hazards consideration. This determination has been performed in accordance with the criteria set forth in 10 CFR 50.92(c) as quoted below:
"The Comission may make a final determination. pursuant to the procedures in 50.91. that a proposed amendment to an operating license for a facility licensed under 50.21(b) or 50.22 or for a testing facility involves no significant hazards consideration. if operation of the facility in accordance with the proposed amendnent would not:
- 1. Involve a significant increase in the probability or consequences of an accident previously evaluated; or l
- 2. Create the possibility of a new or different kind of accident from any accident previously evalt.ated; or
- 3. Involve a significant redcction in a margin of safety."
The following evaluation is provided for the three categories of the significant hazards consideration standards: l
- 1. Does the change involve a significant increase in the probability or i consequences of an accident previously evaluated? l Surveillance performance is nominally considered to demonstrate equipment operability. Therefore identifying that a surveillance has been missed usually does not result in any true inoperabilities existing as the equipment i is demonstrated OPERABLE upon performance of the missed surveillance. This change potentially allows a longer time in some instances for performance of I NO SIGNIFICANT HAZARDS CONSIDERATION 47 5/15/97
INSERT LS-4 Q3.01 The CTS has been revised to add the phrases "If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition (s) must be entered" and "When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition (s) must be entered" to clarify the delay period. [ l
i ADDITIONAL INFORMATION COVER SHEET i ADDITIONAL INFORMATION NO: O 3.0-3 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS LCO 3.0.5 Bases (All FLOG Plants) l I Comment: The STS Bases has been revised to address "the performance of required testing" versus the " performance of SRs," to be consistent with the TS. Submit a TSTF to revise the STS. Suggest that the first instance this wording is to be revised to state, "the performance of required testing including applicable SRs," since testing to restore equipment to an operable state will frequently include the performance of SRs. FLOG RESPONSE: The ITS LCO 3.0.5 Bases were revised consistent with traveler TSTF-165. The latest status report from the TSTF industry database, dated July 27,1998, indicates that the i NRC has approved TSTF-165. The FLOG continues to pursue the changes approved in TSTF- i 165. l 1 l ATTACHED PAGES: 1 None l i l 1 l
l l l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 3.0-4 APPLICABILITY: CA, CP, DC, WC i 1 REQUEST: ITS SR 3.0.2 Bases (All FLOG Plants) Comment: Justify the revised STS SR 3.0.2 Bases. The STS provides an explanation i for the inapplicability; the ITS does not. l i FLOG RESPONSE: The ITS SR 3.0.2 Bases were revised based on traveler TSTF-52. I
- Comment Number 3.6.1-6 for Section 3.6, " Containment Systems," concerned the revision l l of the submittal to conform to the 11/2/95 letter from C. Grimes (NRC) to D. Modeen (NEI) and TSTF-52 as modified by the NRC staff. In the FLOG response to Comment Number 3.6.1-6, it i was identifierl that the ITS Bases were revised to incorporate proposed Revision 1 of TSTF-52.
The FLOG response provided changes to the ITS SR 3.0.2 Bases based on incorporating proposed Revision 1 of TSTF-52. ATTACHED PAGES: l i None I 1 l
- . . - _ _ . . . . - - . _ _ _ - - - . _ . - . _ - ~ _ _
l l l ADDITIONAL INFORMATION COVER SHEET , ADDITIONAL INFORMATION NO: Q 3.0-5 APPLICABILITY: CA, CP, DC, WC l l REQUEST: ITS LCO 3.0.1 & 3.0.2 l CTS 3.0.1 & 3.0.2 (All FLOG Plants) DOC 1-01-A I Comment: The markup of CTS 3.0.1 and 3.0.2 do not agree with the markup of STS
- LCO 3.0.1 and LCO 3.0.2. The markup of STS LCO 3.0.1 and 3.0.2 are correct. Revise i the CTS markup.
l l FLOG RESPONSE: The FLOG has re-examined the CTS markups for LCO 3.0.1 and 3.0.2. The ITS requirements are contained in the CTS markups but may not have been aligned with the same LCOs as in the ITS. Comanche Peak and Diablo Canyon have modified their CTS markups for LCOs 3.0.1 and 3.0.2 to line up the requirements with their corresponding ITS LCOs. DOC 1-21-A has been drawn to describe the modification. The CTS markups for Callaway and Wolf Creek are already lined up l
- with the ITS and no additional modifications are required.
l l ATTACHED PAGES: None l l \ s
ADDITIONAL INFORMATION COVER SHEET l l ADDITIONAL INFORMATION NO: Q 3.0-6 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS LCO 3.0.4 CTS 3.0.4 (All FLOG Fiants) DOC 1-02-LS1 l Comment: The markup of CTS 3.0.4 does not agree with the markup of STS LCO 3.0.4. The markup of STS LCO 3.0.4 is correct. Revise the CTS markup. i FLOG RESPONSE: The FLOG has re-examined the CTS markups for LCO 3.0.4. The actual markups vary slightly although the Comanche Peak markup is essentially identical to the Diablo l Canyon markup, and the Wolf Creek markup is essentially identical to the Callaway markup. All ) four markups were found to mean the same and all four markups were found to be consistent l with the iTS. The markup is slightly different but the meaning is identical. i l ATTACHED PAGES: None l l.. l t
ADDITIONAL INFORMATION NO: TR 3.0-001 APPLICABILITY: CA, CP, DC, WC REQUEST: Incorporate NRC-approved traveler TSTF-122 to eliminate confusion in the ITS LCO 3.0.2 Bases that discuss inoperability of redundant equipment. ATTACHED PAGES: Attachment 6, CTS 3/4.0 - ITS 3.0 Enclosure SA, Traveler Status Sheet Enclosure 58, page B 3.0-2 l l I f
INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.0 TRAVELER # STATUS DIFFFRENCE # COMMENTS TSTF 06. Rev. 1 Incorporated 3.0 01 Approsed by the NRC.
)
TSTF 08. Rev. 2 Incorporated NA Approved by the NRC: SR 3.0.1 i g Bases change only. 2 TSTF 12. Rev. 1 Incorporated 3.0 02 Approved by the NRC. , Incorporated a 2.4.H : TSTF52, fey,/ NA SR 3.0.2 Bases change only. 7 7,3 ::
- TSTF 71; gev,.2 Not incorporated NA To be addressed via SFDP. g-y,g-ee n.
-TSTc 103 ";t ircer pr:ted %Ir- I;r' erred 3.0.4 .;trix. 7R-7,d-oon j. , TSTF 104 Incorporated 3.0 03 Approved by the NRC. TSTF-122 -Net [ncorporated NA {diteri:1 LCO 3.0.2 Deses
-ch=g eccupied by the TSTF
- fter cur trr;;1er cut-cii 8#N k r:'
tte. bffrwed by -lLe AWC. i fi TSTF-136 Incorporated 3.0-02 /jffnved /y -//c A//C, ,2_y,g jgg / TSTF 165 Incorporated NA LY37(.IBdefcha%$'only. 7E-7,s-osa 1 1 TSTF 166 Incorporated 3.0 04 Appnvel /y +4e N#c , TE-3.o-oon j ; N ta
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i n. F. MARK UP 0F WOG STS REV 1 (NUREG 1431) 5/15/97
}
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i l LC0 Applicability B 3.0 l l BASES LC0 3.0.2 measures that permit cor:tinued operation of the unit that is not (continued) further restricted by the Completion Time. In this case, compliance with the Required Actions provides an acceptable level of safety for continued operation. Completing the Required Actions is not required when an LCO is l met or is no longer applicable, unless otherwise stated f n the l individual Specifications. t l The nature of some Required Actions of some Conditions l necessitates that, once the Condition is entered, the Required p Actions must be completed even though the associated Conditions no longer exist. The individual LCO's ACTIONS specify the ! Required Actions where this is the case. An example of this 1s l l in LC0 3.4.3, "RCS Pressure and Temperature (P/T) Limits." ( The Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally. l AMT#86*II/'J i The reasons for intentionally relying on the ACTIONS include, but l fn./,,4%, / eg are not limited to, performance of Surveillances, preventive ; l /d, Acr:roA/f maint=; s, Torrective m enance, or investigation of j l
/ operational problems. Enterin ACTIONS for these reasons must be 4 l - done in a manner that does not ompromise safety. Intentional i
entry into ACTIONS should not b made for operationai convenience. MtcMi'!ct tbt would et-result in redundant 7g-E.gf equipment being inoperablejshould be used instead. Doing so '
) a l+cm4five.r limits the time both subsystems / trains of a safety function are inoperable and limits the time ether conditions exist which rnap A result in LCO 3.0.3 being entered. Individual Specifications may
'.( specify a time limit for performing an SR when equipment is removed from service or bypassed for testing. In this case, the Completion Times of the Required Actions are applicable when this time limit expires, if the equipment remains removed from service or bypassed. When a changeg i n MODE or other specified condition is required to l comply with Required Actions, the uni.t may enter a MODE or other l specified condition in which another Specification becomes l applicable. In this case, the Completion Times of the associated l Required Actions would apply from the point in time that the new l Specification becomes applicable, and the ACTIONS Condition (s) are entered. l
- (continued) i MARK UP OF NUREG 1431 BASES B 3.0 2 5/15/97
_. . - . - . . . .-. . . -- - = - . - . - - . - . - . . - . - . - . . - . _ . - - - . . . . - . . . . = - - _ . l ADDITIONAL INFORMATION NO: TR 3.0-002 APPLICABILITY: CA, CP, DC, WC REQUEST: Revise Traveler Status Sheet to reflect NRC approval and latest revision number of travelers TSTF-71 Rev. 2, TSTF-136, TSTF-165, and TSTF-166. Deleted TSTF-103 from the Traveler Status Sheet as this traveler has been rejected by NRC. There are no changes to any CTS mark-ups, ITS mark-ups, DOCS, or JFDs. l l ATTACHED PAGES: Attachment 6, CTS 3/4.0 - ITS 3.0 Enclosure SA, Traveler Status Sheet i-i i t l d 1
l i INDUSTRY TRAVELERS APPLICABLE To SECTION 3.0 TRAVELER # STATUS DIFFERENCE # CDMMENTS i TSTF 06, Rev. 1 Incorporated 3.0 01 Approved by the NRC. ; TSTF 08. Rev. 2 Incorporated NA Approved by the NRC: SR 3.0.1
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Bases change only. 3 TSTF 12 Rev. 1 Incorporated 3.0 02 Approved by the NRC. ! 0 2. 4. /-l, 7 2,30:2 [i i TSTF 52ger, / Incorporated NA SR 3.0.2 Bases change only. , TSTF 71; gey, /2 Not incorporated NA To be addressed via SFDP. Tg-7.4-een_ , l. -TS" 103 t t ir,corpcrated fiA- Pciformed 3.0.4 matri.:. TR-7.d-oon k , I-TSTF 104 Incorporated 3.0 03 Approved by the NRC.
-Editeri:1 LOO 3.0.2 Se5e5
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t TSTF 122 -Not[ncorporated NA N'# #l . .$
-ch:r.;; occq.-ted by the TOTF
-after cur tr:vcler cut vii- 6 hte. bffrwed by -/Le NXC. ?
TSTF 136 Incorporated 3.0-02 Apfnvedly -//c A/IC, - Ly,g_ggp ,
# c LY37[.IBalefcNes'oniy. T/-7.4-002 i TSTF-165 Incorporated NA TSTF 166 Incorporated 3.0 04 Appoved /y f4 e NA C , TE-J.4-don 1
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f HARK UP OF WOG STS REV 1 (NUREG 1431) 5/15/97
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