ML20153E266
| ML20153E266 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/24/1998 |
| From: | TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20153E262 | List: |
| References | |
| NUDOCS 9809280035 | |
| Download: ML20153E266 (200) | |
Text
{{#Wiki_filter:. _ _ -- .- - - - . - - -_. _ _ _ - Pressurizer Safety Valves 8 3.4.10 i BACKGROUND The consequences of exceeding the American Society of l (continued) Mechanical Engineers (ASME) pressure limit (Ref.1) could include damage to RCS components, increased leakage, or a requirement to perform additional stress analyses prior to resumption of reactor operation. APPLICABLE All accident and safety analyses in the FSAR (Ref. 2) at SAFETY ANALYSES require safety valve actuation assume operation of ree 0 3~4' Gen 1 pressurizer safety valves to limit increases in RC pressure. The overpressure protection analysis (Ref. 3) is also based on operation of three safety valves. Accidents that could result in overpressurization if not properly terminated include:
- a. Uncontrolled rod withdrawal from full power
- b. Loss of reactor cociant ficw Feedline. break;
- c. Loss of external electrical load:
- d. Loss of normal feedwater:
- e. Loss of all AC power to station auxiliaries; and
- f. Locked rotor, Detailed analyses of the above transients are contained in Reference 2. Safety valve actuation is required in events b. e d, c :nd f (abovc) to limit the pressure increase. Compliance with this LC0 is consistent with the design bases and accident analyses assumptions.
Pressurizer safety valves satisfy Criterion 3 of the NPs0 Policy Statc;cnt;10CFR50;3Mc)DMD)2 LCO The three pressurizer safety valves are set to open at the RCS design pressure (2500 psie M85;psig). and within the ASME specified tolerance, to avoid exceeding the maximum design pressure SL, to maintain accident analyses assumptions, and to comply with ASME requirements. The upper and lower pressure tolerance limits are based on the i 1% tolerance requirements (Ref.1) for lifting pressures above 1000 psig. 9809280035 980924 DR ADOCK 050004 5 CPSESMark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-46 8/28/98
- - - . - ._ ~ . _ _ _ -.--- .- -
Pressurizer PORVs B 3.4.11 l BASES (continued) SR 3.4.11.2 i SR 3.4.11.2 requires a complete cycle of each PORV. Operating a PORV through one complete cycle ensures that the PORV can be manually ated for mitiaation of an SGTR. The . Frequency of ontns is based on a typicai re dinv
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! 0 3.4.en 1 H cycle and in ry accepted practice. ThelNote modifies this:SR~,to?alloRentrffntoland operation;in.iMODE 3Tpr,1orito performingithe;58GThislanowsitheJsutve1 Hance lto;be 0 3.4.11 2 l l performed;in ~eny;M00E13 :unden; operating: temperature:end l pressure;conditionsuprjor to~ent.ering e M00E;11orl2.-behw M8BIH5 In;accordance with References 4E5'and;6 "a_dministrative control sirequireithisitest : be? performed : in~.. MODES L3,E4 or. 5 to adequately;simu.l. ate; operating temperature.and pressure effects on PORV operation.'
I a a Opcratira w'.,cicncid air control valvcs and ched valves on the air accuma ctors ensures the POP" control system actuates picpcrly when called upon. Thc Ircqucacy of [18] months is based on a typical refueling cycic and the Ircqucacy of the other Surveillances used to dc . castrate POP" OPEIaBILI"/. en , , , , , _ av i s.7. AA.7 This Survciliance is act rcqt ired for plants with pcr;anent 1C powcr supplics to the vains - Thc survciliance dc; castrates that c;crgcacy powcr can be providcd and is perforacd by transferring powcr fic; nor;;l to
; ;rgency supply and cycling the valvcs. The frequcacy ;f [10]
acnths is based on a typical refueling cycic and industry accepted pract:cc. REFERENCES 1. Regulatory Guide 1.32, February 1977.
- 2. FSAR,ChaptetSection15
- 3. ASME, Boiler and Pressure Vessel Code, Section XI.
i; GeneticiLletter190106fg.nesolution^oEGenerMIssue;70; TowetioperatediRelie.fEalve2and BlockFValve"Reliabiljty,1 andigenetic]f ss_ue194728dditional iLW Temperatute Overpressure 1forj LightJWater 3 React.orsMursuant ito 1.0CFR50.Si(f)gj9unel2W11990j SR CPSE51 License ~Amendmergl'11Mulf15E1992 0 3.4.11 2 6l NUREG0797ASupp]ementi25ES.eptember2199a CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-56 8/2888
LTOP System B 3.4.12 BASES BACKGROUND With minimum coolant input capability, the ability to (continued) provide core coolant addition is restricted. The LC0 does not require the makeup control system deactivated or the safety injection (SI) actuation circuits blocked. Due to the lower pressures in the LTOP MODES and the expected core decay heat levels, the makeup system can provide adequate flow via the makeup control valve. If conditions require tha n<a of more than m.m _.,..m,s
..,j m . .. ,,,.. p p Gad g - 0 3.4. Gen 1 two inven (tory,ging, men pumps pumps]ormakeupintneeventorivaut can be made available through manual actions.
The LTOP System for pressure relief consists of two PORVs with reduced lift settings, or two residual heat removal (RHR) suction relief valves, or one PORV and one RHR suction relief valve, or a depressurized RCS and an RCS vent of sufficient size. Two RCS relief valves are required for redundancy. One RCS relief valve has adaquate relieving capability to keep from overpressurizingahm thefCSjfor the required coolant input capability. PORV Reauirements As designed for the LTOP System, each PORV is signaled to open if the RCS pressure approaches a limit determined by the LTOP actuation logic. The LTOP System; actuation logic monitors both RCS temperature and RCS pressure and determines when a condition not acccptabl; in the PTLR limits are 4s-approached. The wide
- range RCS temperature indications are auctioneered to select the lowest temperature signal.
The lowest temperature signal is processed through a function generator that calculates a pressure limit for that temperature. The calculated pressure limit is then compared with the indicated . RCS pressure from a wide range pressure channel. If the l indicated pressure meets or exceeds the calculated value, a PORV l is signaled to open. The PTLR presents the PORV setpoints for the LTOP System. The setpoints are normally staggered so only one valve typically opens during a low temperature overpressure transient. Having tha setpoints of both valves within the limits in the PTLR ensures that the Reference 1 limits will not be exceeded in any analyzed event. CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-58 828/98
LTOP System B 3.4.12 l BASES l APPLICABLE Heat Inout Tvoe Transients ! SAFETY ANALYSES l (continued) a. Inadvertent actuation of pressurizer heaters:
- b. Loss of RHR cooling: or
- c. Reactor coolant pump (RCP) startup with temperature asymmetry within the RCS or between the RCS and steam generators.
The following are required during the LTOP MODES to ensure that mass and heat input transients do not occur, which either of the LTOP overpressure protection means cannot handle:
- a. Rendering all but onc "PI safe.ty;; injection pumps and_one charging l pump incapable of injection;
- b. Deactivating the accumulator discharge isolation valves in their closed positions: and
- c. Disalicwing Pregluding start of an RCP if secondary i temperature is more than 50*F above primary temperature in any one loop. LC0 3.4.6, "RCS Loops-MODE 4," and LC0 3.4.7, "RCS Loops-MODE 5, Loops Filled," provide this protection.
The ilcfercacc 4 analyses demonstrate that either one RCS relief valve or the depressurized RCS and RCS vent can maintain R pressure below limits when only onc [llPI] pu;;;p [andM wo harging pumps arc] is [are actuated. Thub the LC0 f 0 3.4. Gen-1 l ows only [cncj i;;;uj pu;p Lanc cac twg@arging:pumfp OPERABLE during the LTOP MODES. Since neither one n u relief valve nor the RCS vent can handle the pressure transient need-from accumulator injection, when RCS temperature is low, the LC0 also requires the accumulators isolation when accumulator pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed in the PTLR. The isolated accumulators must have their discharge valves closed and the valve power supply breakers fixed in their open positions. The analyscs show the effect of accu;;;ulatcr discharge (continued) CPSES Mark-up ofNUREG-1431 Bases - ITS 3.4 B 3.4-61 8/28/98
LTOP System B 3.4.12 BASES APPLICABLE RCS Vent Performance (continued) SAFETY ANALYSES The LTOP System satisfies Criterion 2 of the NRC Policy Stotc; cat. 10CFR50 M (c)(2)J11); LCO This LC0 requires that the LTOP System is OPERABLE. Thc LTOP System is OPEPXLE Whcn the mini;;;u;;; cociant input and pic;sure relief l capabilitics era OPEPX LC. Violation of this LC0 could lead to the I loss of low temperature overpressure mitigation and violation of the Reference 1 limits as a result of an operational transient, i T limit the coolant input capabilit . the LC0 require I ero Q fety;injec h pumps an a; maximum _o 0 3.4. Gen 1 chargpiv.puuv3peyapauie of injecting into the RCS; and l ali auuumulator discharge isolation valves be closed and 1 immobilized. 'Jhca;lwhenjaccumulator pressure is greater than or I equal to the maximum RCS pressure for the existing RCS cold l leg temperature allowed in the PTLR. j Ou N The. LCO isMifjediby;aJoteistatingathatithelac.cumulator i301oti;[iCO Elis4G[mayibe?unjsolat.edyhenithe;accumulatot pressure 51s;]essithannalthan3rXthe; maximum RCS; pressure]for thelexisting;temperatureEas;;al] owed bylthe;P/T;11mit:curyvesaThis Note permi.tslthela'g_gueuilatorldischarge; isolation;yalve;Surveill.ance to;be' performed onlyihnderit.hese pressurefanditemperature;conditjons: The elements of the LC0 that provide low temperature overpressure mitigation through pressure relief are: l G. IWO RCS rCliCf ValVc3. 03 foll0W3; 0-3.4.12-1 l l a3. Two OPERABLE PORVs: or l A PORV is OPERABLE for LT0P when its block valve is open, its lift setpoint is set to the limit required by the PTLR and testing proves its ability to open at this setpoint, and motive power is available to the two valves and their control circuits, b2j Two;0PMLEJ_RHRisdction;rel ie_fj va] ves ilor AniRHRIsuction;te11efdalve;j s;0PERABLEiforA L MMenjits; RHR suctjogijsolationyalves end4ts R"R suctica al w are open',! its:setpoint31Catforibetween336. 5'psig . andJ63.52 psig,Iand testi_ng;has;provenlitsMilitylto;operat;tJ11sisetpojnt) (continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 8 3.4-64 8/2888
LTOP System B 3.4.12 BASES (continued) ACTIONS Gd (continued) mass input transient reasonable during the applicable MODES. This action is needed to protect the RCPB from a low temperature overpressure event and a possible brittle failure of the reactor vessel. The Completion Time considers the time required to place the plant in this Condition and the relatively low probability of an overpressure event during this time period due to increased operator awareness of administrative control requirements. l SURVEILLANCE SR 3.4.12.1. b 3r4:12:23 and SR 3.4.12.3 A ^ 0 3mnd REQUIREMENTS To minimize the potential for a low temperature ; overpressure event by limiting the mass input capability, a ' maximum of ene zero HP1 safety; injection pumps andl,a(maximum of one-two; charging; pumps are verified ecapable of injecting into the RCS and the accumulator discharge isolation valves are j verified closed and locked out. Verifjcationithatle.ach ! accumulator;jsjisplatedjjs"onlyirequired whentaccumulator I isolation;is Iequiredj,asistated;jn1Notell;to;the~ Applicability; I The-HP1 safety 11njectjpgpumpsandchargingpumparerendered incapable of injecting into the RCS, for[ example;' through removing the power from the pumps by racking the breakers out under administrative control orfy;isolatingitheldischarge"ofithe-Pump brelosedlisojationyalyes;Wititpoweniremovedifromithe operators 1oriby:ajanuanisolatipntvalveJecuredin;thefclpsed 2 pos_itionj An-aAlternate methods of LTOP control ptevention may be employeu cing at icast two indepcadent oc;n: to prevent a pump start such that a single failure or singic Oction will not i result in an injection into the RCS. This c:y bc ;;co;;;plished through the pucp controi witch being picccd in pull to lock :nd at icast one v;1vc in the dischargc ficw path being cic:cd.] PIo?jdtnOMyslaTgendetedjincapableiofJnjectjnfinto3heLRCS]
@ey'may;)eltJ!ergized;forp0_rposesisuchJsjesting:orjforaffiling ac_cumulators]
The Frequency of 12 hours is sufficient, considering other indications and alarms available to the operator in the control room, to verify the required status of the equipment. (continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-68 8/28/98
RCS Operational LEAKAGE B 3.4.13 BASES (continued)
- e. Primary to Secondary LEAKAGE throuah Any On,q_SG The 00 allons per day limit on one SG is based on the umption that a single crack leaking this amount would not propagate to a SGTR under the stress conditions of a LOCA or a main steam line rupture. If leaked through many cracks, the cracks are very small, and the above assumption is conservative.
APPLICABILITY In MODES 1, 2, 3. and 4, the potential for RCPB LEAKAGE is greatest when the RCS is pressurized. In MODES 5 and 6. LEAKAGE limits are not required because the reactor coolant pressure is far lower, resulting in lower stresses and reduced potentials for LEAKAGE. LC0 3.4.14. "RCS Pressure Isolation Valve (PIV) Leakage," measures leakage through each individual PIV and can impact this LC0. Of the two PIVs in series in each isolated line, leakage measured through one PIV does not result in RCS LEAKAGE when the other is leak tight. If both valves leak and result in a loss of mass from the RCS, the loss must be included in the allowable identified LEAKAGE. 1 l ACTIONS AJ Unidentified LEAKAGE, identified LEAKAGE. or primary to secondary , LEAKAGE in excess of the LC0 limits must be reduced to within i limits within 4 hours. This Completion Time allows time to l verify leakage rates and either identify unidentified LEAKAGE or I reduce LEAKAGE to within limits before the reactor must be shut down. This action is necessary to prevent further deterioration of the RCPB. J l l B.1 and B.2 If any pressure boundary LEAKAGE exists, or if unidentified LEAKAGE, identified LEAKAGE, or primary ec secondary LEAKAGE l cannot be reduced to within limits within 4 hours, the reactor 4 v 4 (continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-75 8/287)8
RCS PIV Leakage B 3.4.14 BASES ACTIONS degraded the ability of the interconnected system to perform (continued) its safety function. A.1 and A.2 The flow path must be isolated by two valves. Required Actions A.1 and A.2 are modified by a Note that the valves used for isolation must meet the same leakaoa renirements -- 0 3.4. Gen 1 as
- PTVs and must be within the RCPB3r3he;hig Qressure; portion oLtheisystesf Required Action A.1 requires that the isolation with one valve must be performed within 4 hours. Four hours provides time to reduce leakage in excess of the allowable limit and to isolate the affected system if leakage cannot be reduced. The 4 hour Completion Time allows the actions and restricts the operation with leaking isolation valves.
Required Action:A.2 specjfieGhat;theidouble:Jsolationibarrier of;twolvalves;be; restor.ed .by cl_os.ing;some;other, valve, qualified for'jsolation, ordrestoring onc ica'ing the RCS PIVm tc;within limits UlThe172 ;houriCompl etion; Time;af ter Lexceeding ;the_ limit allows:for thefestoration'ofuthe; a leaking:PIV.itoiOPERABLE<sta.tus; Thisjt.ine frame: considers 1the31me1 required.to; complete;the Action and;the;1ow;probabil.ityJfla,s_econd 2 Valve;failing during this;timegr_iodf er The 72 hour Completion Ti;c oftcr cxcccding the li;;;it 2110ws for the-restoration of the ic; king PI'! to OPERABLE status. This ti cfr;;c considcr3 thc tiac required to co;;;pictc this Action and the icw probability of a seccad valve failing during this period. (Revicwcr Notc. Two options arc provided for Rcquired Action A.2. The second optica (72 hour rcstcration) is approprietc if isciation of a seccad valve would place the unit in on unenclyzed condition.) B.1 and B.2 _ E 4. Gen.1 If leakage cannot be reducedhsystemljsolated; r the other Required Actions accomplisnea, um A..t .~a be brought to a MODE in which the requirement does not apply. To achieve this (continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-81 8/28/98
RCS PZV Leakage B 3.4.14 BASES SURVEILLANCE SR "3:4714.2"and SR 3.4.14.3 (continued) REQUIREMENTS beyondWyfjtsidesign; pres.su.re of 60_0apsigg1The: 2 interlock setpoirgithat; prevents 1the:yalves f. ing opened;is; set so'the? actual'RCS~ pressure ~must be 2:'psir;to 'open tMM{552%ihisisetpoiiitlensufesl:i 0 3.mn 1 m _ ,aes3grc pressure wilknotibe exceeded andithe RHRlrelieGyalves:willinot liftETheJ8; month Frequency;1.s;basedion;;the;needito perform the Surveil]ance unde $ conditions;that; apply (during a:p1 ant . outage. Thejl8Jeonth1Frequencytislalso; acceptable: based.on consideration of.,the"designJeliability (and conf.irming operating experience) of_the; equipment; Thc;c SR; cre nodified by Notc; clicwing thc RllR autoclesure functica to bc di;; bled This SR;is;notfapplicabl_e;when using the RHR System suction relief valves for cok overpressure protection in accordance with SR 3.4.12.7. REFERENCES 1. 10 CFR 50.2.
- 2. 10 CFR 50.55a(c).
- 3. 10 CFR 50 Appendix A. Section V. GDC 55.
~
- 4. WASH-1400 (NUREG 75/014). Appendix V, October 1975.
- 5. NUREG 0677, May 1980.
- 6. TechnicaLRequitemer]tsJanual
- 7. ASHE. Boiler and Pressure Vessel Code, Section XI.
- 8. 10 CFR 50.55a(g).
CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-84 8/28/98
l RCS Leakage Detection Instrumentation l B 3.4.15 i B 3.4 REACTOR COOLANT SYSTEM (RCS) B 3.4.15 RCS Leakage Detection Instrumentation BASES BACKGROUND GDC 30 of Appendix A to 10 CFR 50 (Ref.1) requires means for detecting and, to the extent practical, identifying the location of the source of RCS LEAKAGE. Regulatory Guide 1.45 (Ref. 2) describes acceptable methods for selecting leakage detection systems. Leakage detection systems must have the capability to detect significant reactor coolant pressure boundary (RCPB) degradation as soon after occurrence as practical to minimize the potential for propagation to a gross failure. Thus, an early indication or warning signal is necessary to permit proper evaluation of all unidentified LEAKAGE. Industry practice has shown that water flow changes of 0.5 to 1.0 gpm can be readily detected in contained volumes by monitoring changes in water level, in flow rate, or in the operating frequency of a pump. The containmant sump used ~ 0 3.4. Gen 1 ptm"^ t "nidentified LEAKAr#fs-e( and airicooleC
/ condensate; flow' rate annitor:are pmumentea w alarm for increases or u.o to 1.0 gpm in tne normal flow rates. This sensitivity is acceptable for detecting increases in unidentified LEAKAGE.
The reactor coolant contains radioactivity that, when released to the containment, can be detected by radiation monitoring instrumentation. Reactor coolant radioactivity levels will be low during initial reactor startup and for a few weeks thereafter, until activated corrosion products have been formed and fission products appear from fuel element cladding contamination or cladding defects. Instrument sensitivities of 104 C1/cc radioactivity for particulate monitoring and of 104 gC1/cc radioactivity for gaseous monitoring are practical for these leakage detection systems. Radioactivity detection systems are included for monitoring both particulate and gaseous activities because of their sensitivities and rapid responses to RCS LEAKAGE. An increase in humidity of the containment atmosphere would indicate release of water vapor to the containment. Dew point l temperature measurements can thus be used to monitor humidity j levels of the containment atmosphere as an l l l CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-85 8/28/98
RCS Leakage Detection Instrumentation B 3.4.15 BASES ACTIONS C:1:13C?l:29C:211 rand Ct2:2:fcontinued) are the ;;ntain;;nt x;p eenitor Containment!SumplL;eyel'iand 0-3.4.15-4 FloCMonjtoting:Syhten :andithe'contaj_nnentiatmosphere par),1culateiradjoactjve';noniter2 This Condition does not provide all. the required diverse means of leakage detection. With;both; gaseous?lcontainmentIatmosphere; radioactivity; nonitorj ng and1 containmentiaiKcooler30ndensatejflowiratelsoni.toring instrumentationchannels2 inoperable,? alternative:actionjis d required;EEitherigrabisamplesiof the; o containment; atmosphere must beJakencandianalyzedsoC; water , inventory balances,f:in;accordance with SR;3[4.:13,ilf;mustibe; performed to;proyideialternate; periodic z information; The followup Required Action is to restore either of the inoperable required monitors to OPERABLE status within 3.0 days to regain the intended leakage detection diversity. The 30 day Completion Time ensures that the plant will not be operated in a reduced configuration for a lengthy time period. Alnotelisiadded.allowingLt.hatSR.3:4.13.liis.not required toibe peCformedluntil:12 hoursiaftetestabljshing_ stea.dy state operation (stable.;RCSL press.ure;Gtemperature;7 power leveli pr.essurizer3nd:nakeupitank 11 evel s .7 makeup ;and ..l etdown ;1and _ RCP seal.linjectionland; return flowsMEThe;12_ hour allowance prov. ides sufficient l; time ;to: col l ectiand , processf.necessary; data iafter st_abl e; pl. ant 1condi ti on.siar.e_e_stabl i s.hed ; E0.1 and EL2
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0 3.4. Gen 1 If a Required Action of Condition A. B or e 4 cannot be met, the plant must be brought to a MODE which the requirement does not apply. To achieve this status, the plant must be brought to at least H00E 3 within 6 hours and to MODE 5 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. EIL1 With all required monitors / systems inoperable, no automatic means of monitoring leakage abe~available, and immediate plant 0-3.4.15-4 shutdown in accordance with LC0 3.0.3 is required. 4 CPSES Mark-up ofNUREG-1431 Bases - ITS 3.4 B 3.4-90 8/28/98
1 ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.1-1 APPLICABILITY: CA, CP, DC, WC REQUEST: Difference 3.4-38 l Comment: TSTF-105 has been rejected by the NRC. l FLOG Reeponse: The July 27,1998 industry traveler status reports indicate the status of TSTF-105 as rejected by the NRC with the TSTF considering. The FLOG has reviewed the traveler and is withdrawing the traveler from the conversion application. For Diablo Canyon, the CTS will be used which does not require a specific method for measuring RCS flow. This difference from the STS is justified by revised JFD 3.4-38. ATTACHED PAGES: Attachment 8 CTS 3/4.2 ITS 3.2 Encl. 2 3/4.4-12 Encl. 3A 8 and 8a Encl. 3B 7 Attachment 10 CTS 3/4.4 ITS 3.4 Encl. 5A Traveler Status page ,3.4-3 Encl. 6A 7 Encl. 6B 5 l i l
l 1 POWER DISTRIBUTION LIMITS : l 3/4.2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION l I 3.2.5 The following DN8 related parameters shall be maintained within the stated limits:
- a. Indicated "eactor Coolant System T m s 592*F gg
- b. Indiat;d Pressurizer Pressure t 2219 psig* ggyg'.g
- c. Indi;eted Reactor Coolant System (RCS) Flow 2 403,400 gpe** for Unit 1 [05f01!10 t 408,000 gpm** for Unit 2 APPLICABILITY: MODE 1.
ACTION: With any of the above parameters exceeding its limit, restore the parameter to within its limit within 2 hours or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 4 J hours. . LO5h06iLS). i WjthlRCS2flW meacutementiperlSpecification;4;2.514, not!meetingJimitEdoinot 305fli$ilj gggpj A SURVEILLANCE REQUIREMENTS 4.2.5.1 Each of the above parameters (RCS,3 T1assutizerlPresyte2 P 605j$$j!j - $31jpated3CS1 flow) shall be verified to be w1 thin its limits at least once per 12 hours. 4.2.5.2 The RCS tot:1 flow rate ;h:11 b; verified tc b; within it: li;it et 1;=t ;,;; per 31 ty; by p1=t s ,, uter indiction Or ==ur;&r,t of th RCS $$ $ $
;1b;w tap diff;rentisi' pr;=ure traxitter ' cutput volt;ge.
mmmmmmmmmm-M$rR??JilelRCS119Wiflgttf("Jgigatorfaha_1W7stgleggett(TMNRE_G 05 12 A MWLNJpt Re4Eontg]3pfj$hisiiK4. 2. 5. 3 The RCS leep fl:W rete CP 3.2 001 fndMters _m_ : Mil_u__,_
,u_ be subjec,ted
_u_ , t; e_____u u_ 0".'.'_5L _; CALIO"__'T!0'_; u___; u ore :tn1G-t en; p;r 10 _. . g g iter;ir.: tion of Surv; illa;; C; uir;Zat !. 2.5.4. 05 03 LG CP 3.2 001 4.2.5.4 -The RCS total ate shall be deter;ind by preci:i= h=t - M1;nce ;;nur;nat M L m ed iu e g aon imiE E gMU tik.i - == ~' ^k """-- after each fuel loading and prior to opefhtivn etcvs 05t eT -^TED n MERMAL "05 04 LG POWER. The feedwater pr;- ur and t; gr ture. th; ;in :t;= pre sure. =d 0 3.4.1 1 f;;i;ter flow differential prasure irstrunats :h:11 be ;;11brated within -
^0 t y: Of perfor;ing the ;;1crintric flow =nur;nat. 50f @ j
- Limit not applicable during either a THERMAL POWER ramp in excess of 5%
l of RATED THERMAL POWER per minute or a THERMAL POWER step in excess of 10% of RATED THERMAL POWER.
.I=1 sis e 1.0t fi;W ;;nur;nat uncrteinty. @$IO_1E
~CPSESMark-up ofCTS 3N.2 3N 2-12. 8/28/98
CHANGE NUMBER EllC DESCRIPTION 04 07 A Not applicable. See conversion comparison table (enclosure ! 38). i 04 08 Not used. l l l 04 09 A Not applicable. See conversion comparison table (enclosure 38). 04-10 LS-14 Notused.Zeppicabic. Sc; conycrsica comparison table (caciosurc 33). 0 3.2 6 04111 A Not; applicable.2Seefconversionicomparison table _,(enclosure 3BU3 1 05 01 LG The designation of how instrument uncertainties are treated (nominal. in the analysis, or in the development of the TS limit) is moved to the Bases. The movement of this level of detail out of the specification is consistent with NUREG 1431 and is an example of removing unnecessary details from the TS in accordance with 10 CFR 50.36. 4 l 05 02 LS 7 The requirement to verify that the total RCS flow is within limits using the plant computer or elbow tap output voltage on a monthly basis is deleted. This action was included in the TS based on the potential drift of the RCS flow indiution. The essence of this activity is performed on a quarterly basis through the Channel Operability Test performed in accordance with the Reactor Trip System surveillances. 05 03 LG Consistent with iUREC 1431. the rcquirc;;at to CP 3.2 001 perfor; a C".'f:!SL C^LISR",TIO" on the RCS ficw ;cters at 1 cast once pcr 10 ecaths and The requirement to normalize the 13CShflogate3ndifatotsIchenrel3 are is moved to the Bases for the RCS ficw icw reactor trip function in ITS Section 3.34.1. s 05 04 LG , ocasistent with industry travcicr TSTI 10S thi 0 3.4.1 1 l
,. cxplicit requirc; cats that the RCS ficw bc ;casured -
through the use of a precisica heat balance , meastrement and that the instru;catation used in the ;
/ perfor;;nce of the colori;ctric ficw ;casurc; cat bc !
eaFib ated within a spccified ti;re pcriod of perfor;ing t+e l
;;;sur;;;at is ;cved to a liccascc controlled docu; cat. The
{ ! requirc; cat to verify that the RCS ficw is within li;its rc;; ins within the Technical Specification. This is an 1 i CPSES Description of Changes to CTS 3N.2 8 8/28/98 l 1 l
1 CHANGE NUMBER RSBC DESCRIPTION l cxampic of reacving unacces;;ry details from the TS 0 3.4.1 1 and is acceptabic based on the guidance providcd in - 10 CT", 50.30. LS SRcI4 215 1 pro 11deside,scrjptjve det.a1EofitMimethottforXtheidelerminatfonXRCS totanriwrate:dulin!cXsutye111ance!;2Thicdetainisimoyed to;thelESRW424 BasesZlheseIdetailstatinotnece.ssary l t61ensurerthgCs3gtanjlowltatelfs31 t thin;tequited111mits21 , The;tequitementxofnTs:sgi4;1/EareladequateJIorzensurjpg l the;RCS30talmdrygte:1s;11thfntequjred]jaitsZ1These details 3te;not;pecessaryltoibelinith(JS;to'ensugthe RCS totarflottate;isZdthin;tequftedilimits;2Moying;this i nformationl;maj ntlins"consi stency y1 th1NUREGf1431 Zany '.ch ange to3his;descrjptiveji.nformation will.belmadelin;acqordance withfthe; Bases 1Contro1LProgramidescribed;in'ITSllSection 5;5'.14; 05 05 LG Not applicable. See conversion comparison table (enclosure 38). l l CPSES Description of Changes to CTS 3/4.2 8a 8/28/98 l l
CONVERSION COMPARISON TABLE - CURRENT TS 3/4.2 Page 7 ef 8 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 05-03 The requirement to perfom ; 0".'""El CALF 0nATIO" at ica;t VesNo ..Not in CTS Yes VesNo,-;Not:in; CTS VeshoM _ N otiin CTS LG cr.cc pcr 10 ; cath; and the rcqu;.ca nt to normalize the RCS loop flow rate indicators,chenrel; em is moved to the l. Bases for thc ;uricillancc rcqui,cu -t; for thc RCC fir;.; CP-3.2-0( 1 hw rcactor t-ip functica '- ITS 3.34.1.
- ~t ~ -
05-04 ~ 7;istent wit' indu;try travcicr TCTI 105. th; caplic. c' No - Requirement Yes Yes Yes H 0-3.4.la B: rcquirc; cat;thattheRCSficwbcscr.uredthcr~ghthcuh not in CTS. [/ LG of a pccci; ion hc;t bokn:c sc .;u. c c;.t and that the
'n:tru..c..tetica u;cd '- the pcrfor;;ncc of the co brisctric fkw sc;;urcKat bc calibrotcd wit; ; spccificd ti;ae pcriod of pccfor;ing The;detailsiregarding;theltiming _of calibrationtof the;instrumentatiortused;1n1the,perfermanc i
_the,calorimetricJ_lowmeasurement+sare,movedtot B 05-05 The Wolf Creek required actions would be modified to move No No Yes No LG details regarding identification of the cause for low flowrate to the Bases. 05-06 The time to reduce power to less than St RTP would be Yes Yes Yes Yes LS-8 revised from within 4 hours to within the next 6 hours. 05-07 This surveillance is modified to require that it be No - See ITS No - See CN 5-11-A Yes Yes H performed within 7 days of achieving 952 RTP. Section 3.4. CN 3.4-51. 05-08 Not used NA NA NA NA 05 09 The requirements for inspecting and cleaning the feedwater No - Requirement No - Requirement not tes to USAR Yes, to FSAR LG flow venturi would be moved to licensee controlled not in CTS. in CTS. Chapter 16. Chapter 16. documents. 05-10 The requirement to verify RCS flow rate within limits prior Yes No - Requirement not No - Requirement Yes A to operation above 75% RTP after each fuel loading and at in CTS. not in CTS. least every 31 EPFDs would be eliminated from the SRs for DNB parameters. CPSES Conversion Comparison Tame - CTS 3N.2 8f2&98 -b
l INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.4 TRAVEI FR # STATUS COMMENTS ' DIFFERENCE ( TSTF 26 Incorporated 3.4 32 Approved by NRC. TSTF 27. Rev.3, O Incorporated 3.4 33 Approved 1bylflRC 0 3.4.2 1 h TSTF 28 Incorporated 3.4 22 Approved by NRC. TSTF-54, Rev. 1 Incorporated NA Approyed;by1NRC m.3.4 009 TSTF 60 Incorporated 3.4 15 Approved by NRC. TSTF 61 Not incorporated NA Minor change that is adequately addressed in the Bases. TSTF 87, Rev. 21 Incorporated 3.4 31 Approved.by;NRC. m 3.4 oc4 TSTF 93. Rev. 31 Incurporated 3.4-17 Approved by NRC. 03.4.9: l TSTF 942Rev.1l Not incorporated NA Retained current TS. m.3.4 0C s
, ~
TSTF-105 Incer crated 3 + 38 z - o.3,4,1 1 TSTF 108, Rev. 1 Not incorporated NA LC0 3.4.19 does not apply. TSTF 113. Rev. 4 Incorpora'.ed 3.4 39 0 3.4.11 : 3 TSTF 114 Incorporated NA Approved by NRC. TSTF 116. Rev.2 Incorporated 3.4 36 a.3,4,1g i TSTF 136 Incorporated NA ApprovedibyJRC m.3,4.on TSTF 137 Incorporated NA Appr_ovedibyJRC l g.3,4.oos TSTF 138 Not incorporated NA Inconsistent with RCS loops requirements of ITS 3.4.5 and 3.4.6.
RCS Pressure, Temperature. and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure is 12 hours WB-RSu$
> fG20G}2219 psig.
SR 3.4.1.2 Verify RCS average temperature is s {581-}592*F. 12 hours " B-PS "1 SR 3.4.1.3 Verify 7.CS total flow rate is 12 hours 2 [204.000] 9F 8-PS m 403l300;gmJ.for;Vnjt11 408,0001gniforJUnit 2. SR 3.4.1.4 -
- - NOTE - - - - -
Not required to be performed until-04-heues ; 3.4-34 1 after 2 [00]t "T.". afte texceeding 85% RTP after each m lef_uel.ing: outage; je "" i; ;r::' '^' ' at a= t's V -
% 11 o recision: heat' balance';;that S total 18 months tiow rate is 2 L=4.gvuj gp 403J400lgpalforlUnitli SRBEd 408;000;gpm2for;Unjtm wcB PS q 4
4 CPSES Mark.up ofNUREG-1431 -ITS 3.4 3.4-3 8/2888 l
CHANGE NUMBER JUSTIFICATION 3.4 36 SR 3.4.13.1 and ACTIONS for LC0 3.4.15 are revised with the addition of a note per TSTF-116. The note addresses the concern that an RCS water inventory balance cannot be meaningfully performed unless the unit is operating at or near steady state conditions. The note added to the surveillance provides an exception for operation at less than steady state conditions. The RCS water inventory balance will only be allowed to be deferred for 12 hours l after re establishing steady state conditions. l 3.4 37 Not applicable to CPSES. See conversion comparison table (enclosure 68). 1
- P l 3.4 38 ocasistent with TSTF-10S. the dctoils on thc ccthod by l which the RCS ficw rate arc vcrified is covcd frce the SR l 3.4.1.4 to the S;;cs. Moving thi: infon;;ation to the Se:cs, ellows thc u;c of precision heat balonces. cibow taps, and other acceptabic ccthod; in order to perfore this verification and is consistent with the NURSC- 1 1431 philc;;phy of ecving ci;rifying inforcotion ;nd 0 3.4.1 1 dc;;riptive details cut of the TS to the Bascs. Not applicableitoJCPSES. JSee conversion comparison table (enclosure 68)2 l l
3.4 39 The shutdown requirements of ITS 3.4.11 would require the plant to reduce T,, to <500'F within 12 hours, rather than 4 MODE 4. to address the concern of entering [LTOP] LC0 3.4.12 Applicability with inoperable PORVs.hNew l jnitial3egired Actionsiareladded,toiConditjons;DJE 0 3.4.11 6 ! andl toli_usediately;injtia_telactionsifor; restoration of,the;inoperab]e;PORV(s);(andforJPORY block yalves) to;0PERABLEistatus,72Theselimmediatejactions:willl ensure expedientineasures~ areltaken:to;r.e;esta.blj.sh ~the OPetabilit,EoL@RV(sM andf0RVibl ock ;yalye.s)fwhil.e maintainigplantIconditions 'abovC!0 DEI 4;but?] es_sjthan 500T; For consistency, the shutdown requirements of ITS 3.4.16 are also revised to allow 12 hours to reduce T.., to
<500 F. This change is consistent with TSTF 113.
1 3.4-40 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 3.4 41 Not applicable to CPSES. See conversion comparison table (enclosure 68). 1 l 3.4 42 Not applicable to CPSES. See Conversion Comparison Table (enclosure 68).
, 3.4 43 Not applicable to CPSES. See Conversion Comparison Table CPSES Differencesfrom NUREG-1431 -ITS 3.4 7 8/28/98
_ _ -m
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431 - SECTION 3.4 5 or6 DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.4-38 /ca;istcat wit' TT 105 the dctcil; on tre ;cthod by w'.ich the RCS m Yes Yes No Ves No Yes No
~
flow rotc i; scrificd crc scucd frc; thc SR 3.4.1.4 to the ",0;c;. Consistent iwith;DCPP; CTS;SR;4,2.3v3&the; details;on,the: method by which theJCS1 flow n ratejjsMified js2emovedifront. i SIS 5@.3.4;1.4' text ' 1 s Yes 3.4-39 The snutdown requirements of ITS 3.4.11 would require the plant to Yes Yes Yes reduce To to <500Y within 12 hours, rather than H0DE 4 to address the concern of entering [LTOP] LCO 3.4.12 Applicability with inoperable PORVs. For consistency, the shutdown requirements of ITS 3.4.16 are also revised to allow 12 hours to reduce Tmto <SG0Y. This change is consistent with TSTF-113. 3.4-40 The Note to SR 3.4.1.4 would be modified to specify a plant specific No - See CN No - See CN Yes Yes power and to p* ovide additional time to perform an RCS precision flow 3.4-51 3.4-34 rate measurement. 3.4-41 LCO 3.4.1 is revised to reference Tables 3.4.1-1 and 3.4.1-2 for RCS Yes Allowance No No No total flow rate limits for DCPP Units I and 2 respectively. added per Amendment 60/59. 3.4-42 An exception to SR 3.4.14.1 frequency to leak test PIVs 8802A 8802B Yes No No No I and 8703 has been added. This change is consistent with the DCPP current TS. 3.4-43 A new Condition C is added to LCO 3.4.1 to reflect the current TS of No . No Yes No Wolf Creek for RCS flow rate. 3.4-44 Steam generator levels for Modes 3. 4 and 5 are specified to ensure SG No No NeYes Yes tubes are covered. The Cci h.cy current TS did not ensure tube Q 3.4.5-2 coverage. Q- 3.4.5-3
.I p CPSES Conversion Comparison Table -ITS 3.4 8/2&98
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.1-2 APPLICABILITY: CA, CP, DC, WC REQUEST: Difference 3.4 40 Comment: WOG-99 has not yet become a TSTF. FLOG Response: WOG-99 has been designated TSTF-282 which is currently under NRC review. No changes to the ITS mark-ups were made in the process of assigning this traveler a TSTF number. As explained in Enclosure 6B to Attachment 10, JFD 3.4-40 does not apply to CPSES or OCPP. Those plants are retaining their CTS, as explained under JFDs 3.4-34 and 3.4-51, respectively. Callaway and Wolf Creek continue to pursue the changes proposed by thic traveler. ATTACHED PAGES: EnctSA Traveler Status Sheet
TRAVELER ( STATUS DIFFERENCE # CONINIENTS l l TSTF 151 Rev?ll Incorporated NA m 3.4 00s TSTF 153 Incorporated 3.4-01 Approved _ by'NRC m-3 4 005 l l TSTF 162 Incorporated NA Approved.byNRC2 m 3.4 Oc6 WOC 51. Rcv.1 Incorporated 3.4 45 & See also CNs 3.4 18 and 0 3 4 12-2 TSTFf285 3.4 0352 3.4 20. WOG-60 Incorporated 3.4 35 TSTF-288 0 3.4.11 2 WOC-07. Rev. 1 Incorporated 3.4 10 Approved by NRC. DCPP TSTF 233 only. m 3.4 009 WOG 87 Rev _~2 Incorporated 3.4-47 0 3.4.11 4 A Incorporated 3.4 40 Applicable to Callaway and [WOG-99 STF1282 Wolf Creek only. 0 3.4.1 2
- = = - - - - - - -- --
hiX: 100TSTF;280 Incorporated 3.4 49 0 3.4.12 1 l i l j
l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.21 APPLICABILITY: CA, CP, DC, WC l
- REQUEST Difference 3.4-33 l
l Comment: TSTF-27 Rev. 3 is still pending NRC approval. I FLOG Response: The July 27,1998 industry traveler status reports indicate the status of TSTF-27, Rev. 3 as approved by the NRC. The proposed wording in TSTF-27, Rev. 3 was modified from TSTF-27, Rev. 2, and these modifications have been incorporated into the ITS. The FLOG continues to pursue the changes approved in TSTF-27, Rev. 3. ATTACHED PAGES: Encl.5A Traveler Status page Encl. 58 B 3.4-9 Encl 6A 6 l
-r . + + - * - --E - -4 -
INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.4 l l TRAVELER # STATUS DIFFERENCE # COMMENTS 1 l TSTF 26 Incorporated 3.4 32 Approved by NRC. l TSTF27.Re.3D Incorporated 3.4 33 7 f hr_oyed_by}JRQ = 0 3.4.2 1
- x TSTF 28 Incorporated 3.4 22 Approved by NRC.
TSTF 54, Rev. 1 Incorporated NA Approved _ by NRC m 3.4-009 TSTF 60 Incorporated 3.4 15 Approved by NRC. TSTF 61 Not incorporated NA Minor change that is adequately addressed in the Bases. TSTF 87, Rev. 21 Incorporated 3.4 31 Approv_ed by.NRC. g.3,4.oc4 TSTF 93, Rev. 31 Incorporated 3.4 17 Approved by'.NRC. 03.4.9: TSTF 94 ERev'1; Not incorporated NA Retained current TS. m.3.4 0c5 TSTF 105 Incorporated 3-4-38 0 3.4.1 1 TSTF-108 Rev. 1 Not incorporated NA LC0 3.4.19 does not apply. TSTF113,Rev.4 Incorporated 3.4 39 0 3.4.11.: 3 TSTF-114 Incorporated NA Approved by NRC. TSTF 116 Rev.2 Incorporated 3.4 36 a.3,4,13.; 1 TSTF 136 Incorporated NA Approved.byJRC m.3,4. cog I l TSTF 137 Incorporated NA Approvediby:NRQ m.3.4 00s TSTF 138 Not incorporated NA Inconsistent with RCS loops i requirements of ITS 3.4.5 and 3.4.6.
RCS Minimum Temperature for Criticality C 3.4.2 BASES ACTIONS L1 l If the parameters that are outside the limit cannot be restored. , the plant must be brought to a MODE in which the LC0 does not i apply. To achieve this status, the plant must be brought to MODE 2ffith%gM110 3-within 30 minutes. Rapid reactor shutdown can be readily and practically achieved within a 30 minute period. The allowed time is reasonable, based on operating experience, to reach MODE 21WithLig;0 3-in an orderly manner and without challenging plant systems. SURVEILLANCE SR 3.4.2.1 REQUIREMENTS RCS loop average temperature is required to be verified at or i above541551*Fevery3J230urs:30 minute wh0n Tm -T,,, deviation, i 10w low m T :1:r: not rc 0t :nd :ny RCS 100p T m 5475017. h Not; acdifics the SR. ;'.'h;n any RCC loop avcrogc ts.pcroture
+s ' Si7551*F :nd the T m T,,, deviation,10w 10w Tgalarm is ;
clarming,RCS loop averag; '.capcraturcs could fall bc.cw the LC0 i requirc. cat without additional warning. The SR to verify operatg{1nnn averaae temperatures every 30-m4mttesjG hours ~ ,,y.s_,.. .....,,,.r,m.s.,,
,,,_ ,,,. .s, es,. -
0 3'4'2 1 . v; .ation of the LCO. takes ~.into? account?iindicationstand ' ' alarms:that arelcontjpously;atallableltolthe; operator;10 I the; control!roomiandl11sicon)f st.entWithiotherj routine Suryeill ances;whichiareltypic_ ally; perfprmedionce; per, shi{t 213 ' additionTIoperator,slare;3ralDedito;belsensitiyeito RCS temperatute.;dutingiappr_o,ach.lto:ctiticality;and Wil_liensureithat thelmi nimumlemperatu_re3fotLcriticalitygsyt Js " critical ity a proached? L . REFERENCES 1. FSAR.Section[15.0.3EhaggerZ15. CPSESMark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-9 8/28/98
CHANGE NUMBER JUSTIFICATION l l 3.4 33 The Frequency of SR 3.4.2.1 to verify operating RCS loop i average temperature at or above (551]'F is changed to "12 hours" from the current surveillance frequency of 30 minutes. The SR to verify operatina 1000 average temperatures every 12 hours M3 .~,,. . ..m., ..#... 0 3.4.2 1 I Qc picvcat indvertant vfolatica of the LCO and l wnuaers indications and alarms that are ! continuously available to the operator in the control room. This change is based on industry traveler TSTF 27. 3.4 34 The current CPSES licensing basis, which does not require that the precision RCS flow measurement be current until after exceeding 85% RTP following each refueling outage, is retained. As discussed in the Bases, the analyses supporting this requirement are predicated on the performance of a gross flow measurement prior to entry into Mode 1 and the maintenance of a reduced power range neutron flux high reactor trip setpoint until the RCS flow has been verified. Through the use of the Transit Time Flow Meter and other precision instrumentation which has been installed by TU Electric, a sufficiently accurate RCS flow measurement may be made prior to 85% RTP. This capability allows for the use of a single power plateau below 85% RTP for performing required surveillances during the post refueling power ascension. It also allows the plant to remain below 85% RTP following a refueling outage until the RCS flow is verified to meet the required flow. ! This change affects the Conditions (a separate condition is required for the precision flow measurement prior to exceeding 85% RTP). and the note and frequency associated with SR 3.4.1.4. 3.4 35 This change adds a note to SR 3.4.11.1 and SR 3.4.11.2 stating that the SRs are only required to be performed in Modes 1 and 2. The Actions Note "LC0 3.0.4 is not applicable" is intended to allow Mode changes for testing purposes (per Bases). This allowance is properly presented as an SR Note. A properly placed exception j (i.e. an SR Note exception) would not allow the SR to be ! considered to be met until the appropriate conditions were available for it to be performed without entering the actions. The Note to these SRs would allow startup in Mode 3 if the SR had not been performed during the required frequency, but would limit the exception to prior to entering Mode 2. The change is consistent with traveler TSTFl288 WOG-60. 73,4,112 l l CPSES Differencesfrom NUREG-1431 -ITS 3.4 6 8M888
l l ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: Q3.4.3-1 APPLICABILITY: CA, CP, DC, WC l REQUEST: ITS 3.4.3 Bases References Comment: WCAP-14040-NP-A, Rev. 2 January 1996, has replaced WCAP-7924 A, April 1975. Please summarize the differences / applicability to the FLOG. FLOG Response: WCAP-14040-NP-A, Rev.1 was NRC approved as an acceptable reference for" Methodology Used to Develop Cold Overpressure Mitigating System Setpoints and RCS Heatup and Cooldown Curves" by SER dated 10/16/95 with minor comments which did not affect the SER. These comments were incorporated and the WCAP-14040-NP-A was issued as Revision 2 in January 1996. NRC acceptance of this WCAP as a reference was based upon the following key elements:
- 1) The WCAP incorporates state of the art fast neutron radiation transport.
- 2) The WCAP cold overpressure mitigating system satisfies SRP Section 5.2.2 and BTP RSB 5-2.
- 3) The WCAP fracture mechanics calculation conforms to 10CFR50, Appendix G and SRP Section 5.3.2.
- 4) The WCAP conforms to Reg. Guide 1.99, Rev. 2 in calculation of the adjusted reference temperature.
- 5) The WCAP conforms to 10CFR50, Appendix G for methodology for calculating minimum temperature in the P-T limit curves.
- 6) The WCAP satisfies the provisions of the draft generic letter published in the Federal Register for comment of June 2,1995.
These items are consistent with the STS reviewer's Note on STS 5.6.6. Plant Soecific Discussion: The CPSES-specific RCS pressure and temperature analyses were last revised to support CTS Amendment 14 for Unit 1 and the originalissue for Unit 2. As such, these analyses predate WCAP-14040, however, they were performe d in a manner generally consistent with the bases of WCAP-14040. As described in ITS Section 5.6.6, the CPSES RCS Pressure and Temperature Limits (ITS 3.4.3) were developed in accordance with 10CFR50 Appendix G and Appendix H Regulatory Guide 1.99, Revision 2, NUREG-0800 Section 5.3.2, and ASME Code Section 111, Appendix G. Because the CPSES licensing basis does not currently include WCAP-14040, the reference in ITS Section 3.4.3 will be revised accordingly. ATTACHED PAGES: Enci 58 B 3.4-10 and B 3.4-16. l l l I
RCS P/T Limits l 3.4.3 B 3.4 REACTOR COOLANT SYSTEM (RCS) B 3.4.3 RCS Pressure and Temperature (P/T) Limits BASES BACKGROUND All components of the RCS are designed to withstand effects of cyclic loads due to system pressure and temperature changes. These loads are introduced by startup (heatup) and shutdown (cooldown) operations, power transients, and reactor trips. This LC0 limits the pressure and temperature changes during RCS heatup and cooldown, within the design assumptions and the stress limits for cyclic operation. The PTLR contains P/T limit curves for heatup, cooldown, inservice leak and hydrostatic (ISLH) testing, and data for imum rate of change of reactor coolant temperature s 0 3.4.3 1 Each P/T limit curve defines an acceptable region for normal operation. The usual use of the curves is operational guidance during heatup or cooldown maneuvering, when pressure and temperature indications are monitored and compared to the applicable curve to determine that operation is within the allowable region. The LC0 establishes operating limits that provide a margin to brittle failure of the reactor vessel and piping of the reactor coolant pressure boundary (RCPB). The vessel is the component most subject to brittle failure, and the LC0 limits apply mainly to the vessel. The limits do not apply to the pressurizer, which has different design characteristics and operating functions. 10 CFR 50, Appendix G (Ref. 2) requires the establishment of P/T limits for specific material fracture toughness requirements of l the RCPB materials. Reference 2 requires an adequate margin to brittle failure during normal operation, anticipated operational occurrences, and system hydrostatic tests. It mandates the use of the American Society of Mechanical Engineers (ASME) Code. Section III, Appendix G (Ref. 3). l The neutron embrittlement effect on the material toughness is reflected by increasing the nil ductility reference temperature (RTm) as exposure to neutron fluence increases.
- The actual shift in the RT, of the vessel material will be established periodically by removing and evaluating the irradiated reactor vessel material specimens, in accordance with ASTM E 185 (Ref. 4) and Appendix H of 10 CFR 50 (Ref. 5). The operating P/T limit curves will be adjusted, as necessary, based CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-10 8/28M8
RCS P/T Limits B 3.4.3 BASES reasonable in view of the control room indication available to monitor RCS status. Also, since temperature rate of change limits are specified in hourly increments, 30 minutes permits , assessment and correction for minor deviations within a l reasonable time. Surveillance for heatup, cooldown, or ISLH testing may be discontinued when the definition given in the relevant plant procedure for ending the activity is satisfied. This SR is modified by a Note that only requires this SR to be performed during system heatup, cooldown, and ISLH testing. No SR is given for criticality operations because LCO 3.4.2 contains l a more restrictive requirement. REFERENCES 1. [ 14040 NP A. Rev. 2, Jar,uary 1006. Not used 0 3.4.3 1
- 2. 10 CFR 50 Appendix G.
- 3. ASME, Boiler and Pressure Vessel Code, Section III, Appendix G.
- 4. ASTH E 185 82. July 1982.
- 5. 10 CFR 50 Appendix H.
- 6. Regulatory Guide 1.99, Revision 2. Hay 1988.
- 7. ASHE, Boiler and Pressure Vessel Code, Section XI, Appendix E.
(continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-16 8/28/98 l
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.4-1 APPLICABILITY: CA, CP, DC, WC . I REQUEST ITS 3.4.4 Bases l i Comment: The Bases refer to the DNBR limit in the safety limits. Where is it? (this appears to l be a problem with the STS, as well as these conversions). FLOG Response: As described in the Applicable Safety Analyses Bases for ITS Section 2.1.1, the DNBR limit is: "There must be at least 95% probability at a 95% confidence level (the 95/95 l DNB criterion) that the hot fuel rod in the core does not experience DNB." The actual numerical l value is specific to a given DNBR correlaticn and analytical methodology. The correlations and l i methodologies are NRC-approved. More than one correlation or methodology, as generally I documented in the FSAR, may be used depending on core design and the particular transient being analyzed. For this reason, a more general term such as "DNBR limit" is used. This convention has been used throughout the Bases for ITS Sections 2.0,3.1,3.2,3.3, and elsewhere in 3.4. In the process of responding to this RAl,it was noted that all FLOG plants except DCPP and CPSES have a markup methodology error in the second to last paragraph of the Applicable Safety Analyses Bases for ITS Section 3.4.4. The acronym "SL" should have been struck-through; this is addressed under Comment Number 3.4. Gen-1. I ATTACHED PAGES: None i l l l l l l
t ADDITIONAL INFORMATION COVER SHEET . ADDITIONAL INFORMATION NO: Q3.4.5-4 APPLICABILITY: CP i REQUEST: ITS SR 3.4.5.2 (Comanche Peak) Comment: It should read "SR" rather than "Sr". FLOG Response: The "Sr"in the " clean" version of ITS SR 3.4.5.2 has been corrected to be "S R". ATTACHED PAGES: Attachment 19 - IT3 Specifications (clean) Page 3.4-9 l l i I l l 1 l l i
RCS Loops-HODE 3 i 3.4.5 l I SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation. 12 hours l 3.4.5.2 Verify steam generator secondary cide water 12 hours g,3,4,5,4 l l levels are a 10% for required RCS loops. y l l SR 3.4.5.3 Verify correct breaker alignment and indicated 7 days I power are available to the required pump that is not in operation. l l l l l l l l l COMAh".HE PEAK ITS 3.4 9 August 28, 1998
I l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.6-1 APPLICABILITY: CA, CP, DC, WC REQUEST: Difference 3.4-02 l l Comment: The difference states that the STS doesn't cover all possible configurations and the I language of the STS is potentially confusing. Please explain the basis for these comments. FLOG Response: The STS wording for Condition A, "One required RCS loop inoperable M Two RHR loops inoperable", and for Condition B, "One required RHR loop inoperable M Two required RCS loops inoperable",is confusing. This confusion arises from the fact the LCO
- allows any combination of two RCS or RHR loops, including one RCS loop and one RHR loop, l to satisfy the OPERABILITY requirement yet Conditions A and B are worded as if either two RCS loops or two RHR loops, exclusively, were the required loops.
By way of illustration, the following scenarios are presented. Assume the LCO's OPERABILITY requirements are satisfied by one RCS loop and one RHR loop. These loops are serving as the
" required" loops, if the RCS toop becomes inoperable, Condition A does not apply because it is "ANDED" with "Two RHR loops inoperable" yet one RHR loop remains OPERABLE in this scenario. Conversely,if the RHR loop becomes inoperable, Condition 8 does not apply because it is "ANDED" with "Two required RCS loops inoperable" yet one RCS loop remains OPERABLE. In fact, the wording of STS Condition B is at odds with the LCO since Condition B requires three loops to be OPERABLE (one RHR and two RCS loops).
The FLOG considered this wording to be a potential source of error for plant operators. Since the corresponding CTS specification is not confusing it was adopted in lieu of the STS wording. This confusion also led to the WOG creating a traveler, WOG-109, which was subsequently withdrawn and superseded by TSTF-263 which is currently under NRC review. TSTF 263 presents a very similar approach to that used by the FLOG to correct STS 3.4.6; however, TSTF-263 has not been incopated by the FLOG. TSTF-263 was not issued until several months after the FLOG submittals. The changes incorporated in ITS 3.4.6 are based on the CTS which has less rigid logic connectors than the STS. ATTACHED PAGES: None
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.8-1 APPLICABILITY: CA, CP, DC, WC REQUEST: Difference 3.4 48 Comment: it is unclear why TS 3.0.4 would not apply. If this change is to be considered it should be done on a generic basis. FLOG Response: A Reviewer's Note in STS LCO 3.0.4 states: "LCO 3.0./. has been revised so that changes in MODES or other specified conditions in the Applicability that are part of a shutdown of the unit shall not be prevented. In addition, LCO 3.0.4 has been revised so that it is only applicable for entry into a MODE or other specified conditions in the Applicability in MODES 1,2,3, and 4. The MODE change restrictions in LCO 3.0.4 were previously applicable in all MODES. Before this version of LCO 3.0.4 can be implemented on a plant-specific basis, the licensee must review the existing technical specifications to determine where specific restrictions on MODE changes or Required Actions should be included in individual LCOs to justify this change; such an evaluation should be summarized in a matrix of all exist;ng LCOs to facilitate NRC staff review of a conversion to the STS." Based on this Reviewer's Note, a matrix of this evaluation was placed in the NSHC LS-1 in Enclosure 4 of the Section 3.0 package (Attachment No. 6). JFD 3.4-48 has been revised to incorporate additional justification from NSHC LS-1 in Enclosure 4 of the Section 3.0 package (Attachment No. 6). JFD 3.4-48 has been revised to include:
"LCO 3.0.4 has been revised so that changes in MODES or other specified conditions in the Applicability that are part of a shutdown of the unit shall not be prevented. In addition, LCO 3.0.4 has been revised so that it is only applicable for entry into a MODE or other specified conditions in the Applicability in MODES 1,2,3, and 4. The MODE change restrictions in LCO 3.0.4 were previously applicable in all MODES. ITS LCO 3.4.8 is modified by a Note stating: "While this LCO is not met, entry into MODE 5 Loops Not Filled from MODE 5 Loops Filled is not permitted." The transition from MODE 5 (loops filled) to MODE 5 (loops not filled) removes the steam generators as a decay heat removal system while the RHR System is potentially degraded. Therefore, the Note ensures that the transition is precluded if LCO 3.4.7.b (two SGs) were chosen (in lieu of the second RHR loop) to ensure decay heat removal capability prior to draining the RCS."
It should be noted that the Applicability Bases for ITS 3.4.8 already provides a similar discussion. ATTACHED PAGES: Encl. 6A 8a
m _ . _ . _ _ _ _ _ _ _ . _ . . _ .. _ _____ _ _ _ _ ) j CHANGE NUMBER JUSTIFICATION i status;WithjEtjge.ltJf17.2Aours?allowsithe'plantno a 3~4 n.4 l M11.Condit1ogsz ttaggetw. _erel.notitestotettitne l bloctrvalventithir41meF1heH!erIktteloDIConditiog ' C;mu j A3pslWIatadinand3nggitjeG3s!nMXJigtered; 51511933gg@ls1DTCASMM29QhCtglationh1p tp!!tgeg[Cgn#1tjgpg13qdETif3qogitjgp1Eltfthe70r_1ginal l Cond111#2Me!nid28httells roothwnbe;gainedIbi i RegottKoc11 MIN 3sn(angutted;gtigr2wth j satisfieQ1thlblocKW4]1elpohlerlggmoy!dM121E;2;not 8Atjsfied2Rygtted2ctioMG230GJdItequitOthelplantito , he]in R E1371butJRequite CActjon1E1 Q oul QhaveZalready ! haditheiplagt;ifMDE13 (two~ houtsle.arliet? This change is , j con.mtent with traveler WOG-87. I i i 3.4 48 A note is added to ITS 3.4.8 ACTIONS, indicating that entry into MODE 5 Loops Not Filled from MODE 5 Loops i- Filled is not permitted while LC0 3.4.8 is not met. The addition of this note is based on the performance of a i plant specific LC0 3.0.4 matrix (see CN 1 02 LS 1
- of the CTS 3/4.0 packw=M3.0Jd;hasJeewnM ^ ;
j gnat.;, changes 11ILMODES;orlotherlspecifiediconditions 03.4.81 l
- in;the:Applicabilitfithatlar.efpart;)fXshutdownlof i i thelunitishallinotibgpreventedatn; addition LC0 1 2
3.0L41hasibeeCteVfgedjolthatlitlisionlylapplicablelfor ! , entrylintoXHODEXCotherlspectiledicogditions]n3he Appl tcabilityj g; MODES $3223 Zand 3Mhe]0DEichange i testtictions Jin'LC0 ~3.0;iwereiprevipus]ylapplicableJin ~ all;MODESMTS3001314.811simbdiffeOflalNoteistating( Dih110thfs;LCo;isgaotimet sentry;in,to:MODEi51 Loops 1Not
- E11 Led _lttomlH00EE(o@slE1]leQQotipe f atttedMIha
- tranitti@lftge]ODEi51(lo(ps1fj]lgdlitoJSDEt5;Qoopsinot l filledutemovesIt!tels.tenCoeneratots"aslaldecaylheat remova11systemlwhjtle21he J MRISystealisJp_otentially degradedETMtefo]EthCNote31tDresithatitheltran~sition islptec]LRied11flCg2L4Z b3tgo]LGsMeteichosen3.in111 hfithelsie&ndiRI]grpEto egstreldgy hestyte. m_ ova]
capa._b111ttptjor2tdIdraining1theJBCS{ 3.4-49 LC0 3.4.12 "[LTOP] System", provides fJur different methods for pressure relief. Any cf the four dethods may be used. However, Sur eillance Requirement 3.4.12.5 requires testing whether or not the equipment is being credited to meet the LCO. The proposed change adds the words " required" to the Surveillance to exempt its performance if the equipment to be tested is not being used to meet the LCO. In addition, two editorial changes were made. The LC0 requirement presentation was cla."ified. Also, the Note to SR 3.4.12.8 was revised to replace " required" to be met" with " required to be performed" since the " performed" nomen:lature is appropriate here, consistent with the CTS. This change is consistent with traveler ISIE1280 W00-100. 0 3.4.12 1 CPSEE Differencesfrm NUREG-1431 -ITS 3.4 8a 8/28/98
l l l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.9-1 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 3.4.9 Comment: Does 92% (90% for Diablo Canyon) in the pressurizer ensure that t'on an inadvertent Si that the pescurizer will not overfill before the operator is assumed to take action? Other plants have lowered this limit (Robinson) or qualified the PORVs for water (Millstone 3). FLOG Response: ITS Surveillance Requirement 3.4.9.1 requires the pressurizer water level to be less than 92% (90% for Diablo Canyon). This requirement is not related to the assumptions used in the inadvertent Safety injection analysis. The basis for this requirement is given in the ITS Bases for the SR (as clarified by NRC approved TSTF-162), which states that it is to ensure provision of a minimum space for a steam bubble which is an assumption in the safety analyses l (i.e., the pressurizer must not be water solid). This maximum pressurizer level is not assumed in any safety analysis. ATTACHED PAGES: ' None I i 4
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.9-3 APPLICABILITY: CP, DC, WC REQUEST: Difference 3.4.17 (Wolf Creek, Diablo Canyon and Comanche Peak) Comment: TSTF-93 Rev. 3 was approved with a reviewer's note whic . c /s that for non-dedicated safety-related heaters which normally operate the frequency is 18 months and for dedicated safety-related heaters which normally don't operate the frequency is 92 days. Each of the plants is asking for the 18 month frequency but it is unclear from the submittals if they j meet the criterion. Please provide information demonstrating consistency with the TSTF. i FLOG Response: DCPP and WCGS have two-groups of non-safety related pressurizer backup heaters. The pressurizer heaters together with the pressurizer spray valves are used to l control RCS pressure. This change is consistent with TSTF-93 and the added Reviewer's note. For Diablo Canyon, the NRC recently approved (6/5/98) changing DCPP current Technical l Specification 4.4.3.2 from 92 days to " Refueling interval" in LA 126/124. j i For Comanche Peak, the pressurizer heaters used to satisfy the pressure control function are ! comprised of one proportional control group and three backup groups. The design and operation is consistent with the basis for an 18 month surveillance described in Section 6.6 of NUREG-1366 (which was the basis for TSTF-93). The heater groups are normally connected to { the emergency pcwer supplies (two to each Class 1E train of emergency power) and normally ) operate. CPSES will revise the 3.4.9 BASES to reflect the NUREG-1366 basis for the 18 month } frequency. i l ATTACHED PAGES: Encl SA Traveler Status page l Enci58 B 3.4-43 and B 3.4-44 l l
~
1 INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.4 TRAVEI ER # STATUS DIFFERENCE # COMMENTS TSTF 26 Incorporated 3.4 32 Approved by NRC. TSTF-27. Rev.3 2 Incorporated 3.4 33 Approved lbfl,NRC 0-3.4.2-1 TSTF 28 Incorporated 3.4 22 Approved by NRC. 1 1 TSTF 54, Rev. 1 Incorporated NA Approved by1NRC m 3.4 009 i TSTF 60 Incorporated 3.4 15 Approved by NRC. l TSTF 61 Not incorporated NA Minor change that is adequately , addressed in the Bases l TSTF 87 Rev. 24 Incorporated 3.4-31 Approved.by NRC. m 3.4 0C4 l j i TSTF 93, Rev Incorporated 3.4 17 Approved A Vby.;NRD __ o.3,4,9. TSTF94jRev.1 Not incorporated NA Retained current TS. m 3.4 ocs TSTr-105 Ixcrprated 3 4 -38 0 3.4.1 1 TSTF 108, Rev. 1 Not incorporated NA LC0 3.4.19 does not apply. TSTF 113 Rev. 4 Incorporated 3.4 39 0 3.4.11 2 3 TSTF-114 Incorporatted NA Approved by NRC. TSTF 116, Rev.2 Incorporated 3.4 36 l 0 3.4.13 2 1 TSTF 136 Incorporated NA Approved by JRC l m-3.4 00s l TSTF 137 Incorporated NA Apprpved.by NRC m.3.4 005 TSTF 138 Not incorporated NA Inconsistent with RCS loops requirements of ITS 3.4.5 and 3.4.6. l
l l Pressurizer BASES B 3.4.9 ) l l C.1 and C.2 If one requir.edjgroup of pressurizer heaters is eee-inoperable and cannot be restored in the allowed Completion Tine of Required ' Action B.1, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to MODE 3 within 6 hours and to MODE 4 within 12 hours. The albed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. SURVEILLANCE SR 3.4.9.1 REQUIREMENTS This SR requires that during steady state operation, pressurizer level is msintained below the nominal upper limit to provide a minimum space for a steam bubble. The Surveillance is performed by observing the indicated level. The Frequency of 12 hours corresponds to verifying the parameter each shift. The 12 hour interval has been shown by operating practice to be sufficient to regularly Csess level for any deviation and verify that ! operation is within consistent with the~ safety analyscs assumptions of! ensuring _thet a steam' bubble exists in the l pressurizer. Alarms are also available for early detection of l abnormal level indications. SR 3.4.9.2 ___ pressurizer, heaters,used to , satisfy the pressure controllfunction~are comprised _of one; proportional: control O'3 " 3 I j group and.three... backup; groups Theiheater, groups..Lare / normally;connectedito the; emergency power; supplies;(two;to;eac Class 1E trainlof; emergency; power)land;normally:operaty Tk L 1s 5dT.1di seu writti use pvwei suppi les or e ucmunau ateu T.o be capable of producing the minimum power and the associated pressurizer heaters are verified to be at their design rating. This may be done by testing the power supply output and by l performing an electrical check ca heater element continuity and l resistance. This;may31solbe"donelbylenergizing the[heate.rs;and l seasuring'circuiticurtentQThe Frequency of 18. months 02 days is considered adequate to detect heater degradation and has been shown by operating experience to be acceptable.?The heater: design andl operation.is2 consistent with the basis _for.an 18. month surveillance; described 11n Section 6.610f,Ref.T3. > CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-43 8/28/98
=
Pressurizer BASES B 3.4.9 l l l en , a n , av i v.T. s.v 1 vLe_ en 2_ __. ___,2_.L,_ a s tu. L_ t.__ .__ _______&,.. __..___a l
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._ .: uw 1, cycic and is consistent wit', si-ilar verifications of =^rgency yvvvv i wuyyI iwJ REFERENCES 1. FSAR, Section:15.
- 2. NUREG 0737, November 1980.
m
- 3. NUREG 1366,; Improvements to Technical Specification 0-3.4.9 3 Surveillance-Requirements.
J CPSESMark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-44 8/2888
l l ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: Q3.4.10-1 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 3.4.10 Bases Applicable Safety Analyses Comment: What justifies the differences between the ITS Bases and the STS Bases and l between the plant Bases (especially Callaway and Wolf Creek) of the lists of possible over , pressurization events? FLOG Response: These Bases changes reflect each plant's licensing basis as expressed in their respective versions of FSAR Chapter 15. Plant Soecific D;scussion in the.CPSES Applicable Safety Analysis Bases for ITS 3.4.10, changes were made to item "b" to replace the loss of reactor coolant flow with the feedwater line break because the FSAR Section 15.2.8 analysis of feedwater line break shows the primary and secondary side safeties willlift. The loss of reactor coolant flow does not cause the safeties to lift. ATTACHED PAGES: 4 , None
I ADDITIONAL INFORMATION COVER SHEET ADDIY!ONAL INFORMATION NO: Q3.4.11 1 APPLICABILITY: CA, CP, DC, WC REQUEST: Change 444 LG Comment : The requirement is in the CTS and the STS. The justification for not putting it in the j ITS is that automatic actuation to open is not required. However, proper calibration also ensures that the PORV does not prematurely open creating as stated in the Bases "in effect a small break LOCA." l FLOG Response: There are two CTS LCOs (3.4.9.3 (3.4.8.3 for CPSES) & 3A.4) and l corresponding ITS LCOs (3.4.12 & 3.4.11) controlling pressurizer PORV operability. One of ; these, CTS 3.4.9.3 (3.4.8.3 for CPSES) and corresponding ITS 3.4.12, governs their cperability 1 as part of the LTOP/COMS system. Both the CTS (SR 4.4.9.3.1.b or 4.4.8.3.1.b for CPoES) 1 and the ITS (SR 3.4.12.9) require CHANNEL CAllBRATIONs of the LTOP/COMS PORV actuation channels every 18 months to support this function. The second of these, CTS 3.4.4 i and ITS 3.4.11, govems the operability of the PORVs and their block valves as isolable relief l valves. While the ability te open the PORVs manually and to isolate a stuck open PORV using its block valve are considered safety-related capabilities, the ability of the PORVs to act as automatic relief valves in MODES 1,2, and 3 is not a safety function in the current licensing ! basis. The pressurizer safeties fulfill both the RCS Code overpressure protection function and , the automatic pressure relief function assumed in the accident analyses. For this reason, STS 3.4.11 does not have a CHANNEL CAllBRATION surveillance requirement. SR 4.4.4.1.b is i therefore moved out of the technical specifications by DOC 4-04-LG. This is appropriate since automatic actuation of the PORVs is not a safety function in MODES 1,2, or 3. Requirements ! that are not needed to support the safety analyses are moved out of the Technical , Specifications, reflecting the philosophy and content of NUREG-1431. l The premature opening of a PORV is considered to be a small break LOCA. A LOCA is an unisolable leak or break in the RCS. A stuck open pressurizer safety valve would constitute a LOCA. One of the design functions of the PORVs is, however, to reduce the risk of a stuck j open safety by having actuation set points below those of the safeties. As stated in the STS Bases for ITS 3.4.11, LCO, a stuck open PORV could be isciated by closing its safety-related block valve, thus avoiding a LOCA. The automatic actuation of a PORV at a pressure lower j than its nominal design set point is not desirable, but is not outside the safety analysis. ATTACHED PAGES: None j l l l 1 I
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.11-2 APPLICABILITY: CA, CP, DC, WC REQUEST Change 4-08 LS 34 and Difference 3.4-35 Comment: WOG-60 has not yet become a TSTF. FLOG Response: WOG-60 has been approved by the TSTF and is designated as TSTF-288. This traveler has been submitted to the NRC and is under review. The proposed wording in TSTF-288 was modified from WOG-60, Rev.1, and these modifications have been incorporated into the ITS (editorial Bases note changes). The FLOG continues to pursue the changes proposed by this traveler. ATTACHED PAGES: Encl. 3A 8 Enci 3B 5 Encl. 5A Traveler Status page Encl. 5B B 3.4-52 & B 3.4-55, B 3.4-55a and B 3.4-56 Encl. 6A 6 i 1 l l
- . _ _ . -- -_ ~ - . . . .- - - . .-. . - - - - - - -
. CHANGE NUMEER ESE DESCRIPTION
- ' l 4 08 LS 34 Consistent with travelerhbTST.E the O.3.4.11 2 requirement to perform the w un - m lance of the pressurizer PORV block valves and the 18 month ]
1 surveillance of the pressurizer PORVs (i.e., perform one compl,ete cycle of each valve) is revised to indicate that the surveillance is only required to be performed in H00ES 1 and 2. This is consistent uith the recommendations of Generic Letter 90 06, " Resolution of Generic Issue 70,
' Power 0perated Relief Valve and Block Valve Reliability,'
and Generic Issue 94, ' Additional Low Temperature Overpressure Protection for Light Water Reactors ' Pursuant to 10CFR50.54(f)," June 25, 1990. 4- , LS 36 The requirement to perform the 92 day surveillance of l pressurizer PORV block valves (i.e., perform one complete cycle of each block valve) is revised such that it is not required if the block valve is closed to meet ACTION a of the current TS LC0 3.4.4. This change is acceptable because no credit is taken for the automatic actuation of l the PORV in Modes 1, 2, or 3. Credit is taken for manual operation of the PORVs during the Steam Generator Tube Rupture (SGTR) accident. However, the capability to l manually cycle the PORVs will be unaffected by this change. This change will not affect the ability of the block valve to open, if closed to meet ACTION a, in the mitigation of an SGTR. Deferral of the block valve cycling surveillance will not diminish the design capability of the block valve to open against differential pressures that would be present after an SGTR since the block valves are capable of opening against 2485 psig, the safety valve lift pressure, whereas 0 3.4.11 4 presmrizer pressure decreases after an SGTR. In additionnaLNoteMsladdedito1ACLIONi[d]istating3 hat jtidoeslgotlapply.3heftithe:bl6cklyalyejsEateligoperable solelEasla2esultronttcpowerzbeingItemorg: pet:ACIIONS [bMc]I4_sfaIregeltdoflaginopptable20RVislMnithis scenjr107ACTIONI[bMc]Jts!ege_redlajlaTresultlnCag joo@@b]e3PORV($1Mf&,jelPORVillerellnopefablelajid incapablemt!bein.3rsawual_1y3ycledMper;the: change dis _coisjegodgr;gLc31923sig)pAII0g3[b]meldib,
- entLredM11pwat,ygCT10N gb] mould 7c16;elthe ajgateEblettalycandiremoVeitsIponet;withinitime;t, t ErhootgIma:sla2esultrofabl6ctvalto pogrztemogangen ACUON_:[b]MCUE[d]NetelthenientetedMCUON;[d])ould tequite'1helassociated20RVito'beIplayedij nlaandal icontrol within~tjmelt T21hoursEHoweipMtheitea]onl[ot i
ot19tnallylentetXACTIONT[b]HsithatJthe3ssociated PORV L is;inoperAle:andican;t3oan.ual]y3ycjedathusithete11s CPSES Description of Changes to CTS 3N.4 8 8/28/98
CONVERSION COMPARISON TABLE - CURRENT TS 3/4.4 regeSep3 TECH SPEC CHANGE APPLICABILITY I
, NUMBER DESCRIPTION DIABLO CANYON l COMANCHE PEAK WOLF CREEK CALLAWAY 4-04 This change moves the requirement to perform channel Yes - Moved to the Yes - Moved to the Yes - Moved to the Yes - Moved to the LG calibration of PORV actuation instrumentation to a licensee FSAR. TRM. USAR. FSAR.
controlled document. 4-05 The shutdown requirereent of CTS 3.4.4 would require the Yes Yes Yes Yes LS-31 plant to go to reduceT , to <500*F within 12 hours, rather than go to MODE 4. to address the concern of entering [LTOP] LCO Applicability with inoperable PORVs. For consistency the shutdown requirements of CTS LCO [3.4.7] would be similarly revised. 4-06 This change provides a 72 hour completion time to restore an Yes No - Already part No - Already part No - Already part LS-32 inoperable block valve, with the PORY placed in manual of CTS. of CTS. of CTS. control mode. The current TS requires the block valve to be restored within one hour, or remove power from the solenoid. 4-07 This change provides a two hour completion time for Yes No - Already part No - Already part No - Already part LS-33 restoring an inoperable block valve when more than one block of CTS. of CTS. of CTS. valve is inoperable, and 72 hours to restore the remaining valves. The current TS requires the block valve to be restored within one hour for one or more valves inoperable. N 4-08 Consistent with travele F-288W9G-6j0the requirement to Yes Yes Yes Yes LS-34 perform the PORY and bl va..m u saing surveillances is revised such that the surveillances are only required to be %
" Q -3.4.11 - 2 performed in MODES 1 and 2.
4-09 Consistent with traveler WOG-87, the requirement to perform Yes Yes Yes Yes LS-36 the 92 day surveillance of the pressurizer block valves O.e., perform one complete cycle of each block valve) is Q-3.4.11-4 revised such that it is not required if the block valve is closed to meet ACTION a of the current TS LCO 3.4.4. In addition.;a Notet sladded,to i ACTION [d];;to, prevent (entry solely,due mtoiinoperable;PORV(s)ignder Actions,[b or,c]g 5-01 This change moves the Steam Generator Tube Surveillances to Yes No - Same as CPSES Yes Yes A SR 3.4.13.2 and the Administrative Controls 5%tions 5.5.9 change 1-14-A for and 5.6.10. CTS Section 3/4.0. CPSES Conversion Comparison Table - CTS 3N.4 8/2838
TRAVELER # S.T.AI.ES DIFFERENCE # COMME 5"TS
~~
TSTF 151 Rev;~;1 Incorporated NA m 3.4 00s TSTF 153 Incorporated 3.4-01 Approved by'NRC TR 3.4 005 TSTF 162 Incorporated NA Approved by NRC* TR 3.4 0C6 WBC 51. Rev.1 Incorporated 3.4 45 & See also CNs 3.418 and 0 3.4 12-2 TSTFf285 3.4-2352 3.4-20. M Incorporated 3.4-35 ( TSTFi288 _ _ ...,-- _ o 3.4.11 2 WGC 57. Rev 1 Incorporated 3.4-10 Approved by NRC. DCPP . TSTF-233 only. m 3.4 009 j WOG 87 Revi~2 Incorporated 3.4-47 0 3.4.11 4 WOG-99 Incorporated 3.4 40 Applicable to Callaway ar.d TSTF-282 Wolf Creek only. o 3.4.1 2 WL100TSTF;280 Incorporated 3.4-49 Q 3.4.12 1 l 4
Pressurizer PORVs B 3.4.11 BASES ACTIONS Note 1 has been added to clarify that all pressurizer PORVs are treated as separate entities, each with separate Completion Times (i.e., the Completion Time is on a componan* hasis), The avanHnn for LCO 3.0.4. Note
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.m a.. ,ar.n. . , l entry into nucES 1, J, uns u tc g. rc . cycong ct tac ;wh or block valvcs to verify their 0"E"ASLE status. Testin; '- - ' ;
; r' =rin icwcr "00EMntry;dnto;;n0 DES 3 2 dant 3.;to;petfor_q TyclingtofitheJORVsior;b. lock"Nalyesito;yetify;theit:0PEMBLE status GEtheleventathatitestj ngya_s; nog,satisfactorjly rformedlin.7owerTN0D.ES!
u With the PORVs may;bejinoperable and capable of being manually cycled (eMEexcessivelseat11eakage)EInithisfLconditi_on,' either the PORVs must be restored or the flow path isolated within 1 hour. The a_ssociatedjblock valvcs should 1s; requited lto_be closed, but power must be maintained to the associated block valves, since removal of power would render the block valve inoperable. Although a POP 3 ;cy bc designated inoperabic, it ;cy be abic tc be manually opened and closed, and thereforc, abic to perfora its function. "0"3 incpcrobility may bc duc tc-seat 1;;kogc, instru;^ntationprobic 3, automatic contr-1 probicas, or othcr causcs that do not prevcat manual use and do not create a possibility for a small brcak LOCA. Por thcsc reasons, the block valve ;ay bc cicscd but th; Action rcquires pcw r bc maintained to the valv . This-Gend+t4cn is only intendcd to permits operation of the plant for a limited pcried of tiac not to exceed untj,1jthe next refueling outage (MODE 6) so that maintenance can be performed on the PORVs to eliminate the problem condition. No selly, the "0"3s should be availabic for automatic mitigatica of ovcipicssurc cvents and should bc returncd to OPEPXLE status prior to catering startup ("00E 2h-Quick access to the PORV for pressure control can be made when power remains on the closed block valve. The Completion Time of 1 hour is based on plani. aperating experience that has shown that minor problems can be corrected or closure accomplished in this time period. B.1. B.2. and B.3 If one er-two PORVs is inoperable and not capable of being manually cycled, it must be either restored, or isolated by closing the associated block valve and removing the pwer to the associated block valve. The Completion Times of 1 hour are (continued) i 1 CPSESMark-up ofNUREG-1431 Bases -ITS3.4 B 3.4-52 8/28/98
Pressurizer PORVs B 3.4.11 BASES (continued) system during this time and provide the operator time to correct the situation. ThKgpquired.341gEargaodified 0'3 4 11'4 by?KNotej)tatjngittpGlMtfjequirgCAGl.190aWoWot2 ppg 1 Lit theIsolffgeson forJAhe@lecitvalveDipGggiated inoperabigMasla mesvitaf1poweribelns2tnoveDolcomplyA1th othetiRequired;ActicosBg],ttnisfeyegtRthe2Regd ted;ActiggEfor inoperab]emns);0$1cKtequitelthelblgcQtalye:powerito' be teamediencellt?is closed)lateladeguateltolddresEthe3:ondition; G.1 and G.2 If the Required Actions of Condition F are not met, then the plant must be brought to a H00E in which the LC0 does not apply. To achieve this status, the plant must be brought to at least MODE 3 withJ T9007 within 6 hours and to "00E 4 within 12 hours. Adhtionallactionaisf required.; tol beEj emediately injtiateditoirestoreitheginoperabl.e;valye(s)1to'0P.ERABLE status;j This ~will: ensure; expedient:measuresjareitakenitoire; establish OPERABLE LPORV.sland iblock1 valves lwhileimai ntaini ngl pl ant conditions.;above1MODEL4;butJ1esslthan:500Tj The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. In MODES 4end5anf6;(witKtheMactoriyesselfheadlon), automatic maintaining PORV OPERABILITY may be required. See LCO 3.4.12. SURVEILLANCE SR 3.4.11.1 REQUIREMENTS Block valve cycling verifies that the valve (s) can be ope _ned and;,Cl osed ,-_
,ma _ _yy _ .%...w.. mu.m_-6, _ _ . .. . wy,yu , .,_ i _ , - .,m.m_ _, _m
. ,_2 ~, _ o 3.4.11 4
_ _ _ _ _ u-a m i . . u . _ _u _ _ _4 ,31..
,__m %,
u __~o __ n- - 2, DYW"NY%n"e.A Y.'.AN?w??N".!W".SN.'* A.Y ?k" ?*me ""?S". ,AN.%#NNU.'6, *e 'I n=ded. The basis for the Frequency of 92 days is the ASME Code Section XI (Ref. 3). If the block volve is closed to isolat; ; PORV th;t is capabic of bcing manually cycicd, the OPERA 3ILI"I of the blak valve is of i;portancc, because spaning the block volve is necessary to pcrait the PORV to be used for manuel control of rcoctor picssure.
,_____m,_
If the bicck v;1ve is closed
._2__,... __ _mu__a__ ,mnm. m. .,_~_x___u,_ m bv iJVaWbw uns v b e sw a vv i sw i 4 Ivyb t WWsL g vi)y g gtg..guyuw , w .y g _.
tbg bh 0b 'O NO 'NNN ONp'O 00 ' N'C O UO OIb 'O PORV ; d open the bisck valve is 72 hours. t.ich is well within the allowebic limits (250 to extend the bicck valv; Frcqucacy nf 02 days. Furth m c, thcsc test rcquirc; cats would b^ ce;plet
- by the respcnh # 3 rcccatly closed bicck volvc upon restoratica of 9 ."RV to OPERASLE status. (i.c. , completica of the Rcquired Ac ".sas fulfills the SR).
_a - , (f This:SRiismodifiediby2two: Notes 7< SR by su ting IN8t t is not required to be metpe.cformed Note 1; modifies this o.3.4.11 2 with the block valve closed, in accordance with the Required o.3,4,11 4 1 l CPSES Msrk-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-SS 8/28M8 4
l Pressurizer PORVs I B 3.4.11 BASES (continued) l Actions'of thi.siLC0/ Eend4 tic . A.this LCO. [ Opening the 0 3.4.11 4 block valvelin thisicondit' ion increases'the risklof an unisclabidjleak;from the'RCS since thef0RViis already inoperable::.'. Note;2fmodif,iesithis SR tolailow entry into and operation in: MODE.3; prior,to performing _the SR. .This all the serveillance to be performed irmy Muut o.. unum 0 3.4.11 2 perating temperature ana pressure conditions.' prior..to entering MODE;11or,2. 'belca; "00E 2. In accordance with References 4;f 5f and 6,!administrativeLcontrols require this test be performed .in; MODES;3.f 4 or 5 to adequately simulate operating temperature;and.pressuref. effects ~on PORV operation. l t l L CPSESMark-up ofNUREG-1431 Bases -11S 3.4 B 3.4-55a 8/2&98
Pressurizer PORVs l B 3.4.11 l l BASES (continued) l 1 l SR 3.4.11.2 l SR 3.4.11.2 requires a complete cycle of each PORV. Operating a PORV through one complete cycle ensures that the PORV can be manually actuated for mitigation of an SGTR. The 0 3.4. Gen 1 Frequeno of IQ :nonths is based on a typical refueling cycle and industry accepted practice. The~ Note modifies this SRT.to~311orentry~dntoland operation'in,M6 dei 3fprjor t ' perforajng'the'SRPThisTallows'the: surveillance to be - 0 3.4.11-2 ' l perfwddilenyjiuuta menoperayms wuperature and - ressure; condition.s;yprjcrjtolenter.ing MODE;1'orJ2.'-below
/
"00T,% Inlaccordancellwithf References;4,7;,5:and 6Zadministrative controls?tequire;thisite_stibel performed;1n M00ESl3,14;or;5 to adequatelyAimulate; operating'_ temperature..and pressure; effects on PORV,operat W
_ 1 # _._
~
sn s. ,. .ii.s Opcrating the solcacid air control volvcs and check volves on the air accumulators casures the POR" control system actuates procerly whcn cdicd upon. Thc frequency of [18] months is bas ^d on ; typical refueling cycic and the frequency of the other Surveillances used to dcmonstretc POR" OPERASIU"/. e f'1 S A 11 A _ si s s.T. AA.7 This Survcillanc; is not rcquired for plants with pcrmancnt IE powcr supplies to the valves. The survciliancc dcmonstretcs that cacrgency powcr con be provided and is pcrformed by transferring powcr frca normal to cacrgency supply :nd cycling thc valves. The frequcacy of [IS] months is based on a typical refu^1ing cycic ;nd industry accepted practice. REFERENCES 1. Regulatory Guide 1.32, February 1977.
- 2. FSAR, C, hapt _ej Section 15,
- 3. ASME, Boiler and Pressure Vessel Code, Section XI.
42 Geneticitetteir190iO6 M reso]ution'of;Generjc2 Issue 20l iPoweri0perai;_ediRelieGValve[andl Block!Valge;Reliab1]ity,3 and;geneticitssGeM2]Additiona];Lowflemperat.ure Overpre.s_sureifor2 1ghtiWater2 Reactors M ur,suantito 10CFR50.53Q)2"iJune35Z19902 - 52 CPSES;Lic_ ens _eDndme_ntA1lTJulyil5,51992 ^ Q 3.4.11 2 6] NUREG 019UgEupp]ement1253 Sept _ ember;1992 CPSES Mark-up ofNUREG-1431 Bases - ITS 3.4 B 3.4-56 8/28/98
CHANGE NUMBER JUSTIFICATION l l 3.4 33 The Frequency of SR 3.4.2.1 to verify operating RCS loop ) average temperature at or above [551]'F is changed to "12 ' hours" from the current surveillance frequency of 30 minutes. The SR to verify operating loop average - l temperatures every 12 hours is sufficiently frequent l 0 3.4.2 1 , to prevent inadvertcat violation of the LCC cad I considers indications and alarms that are continuously available to the operator in the control room. This change is based on industry traveler TSTF 27. l 3.4 34 The current CPSES licensing basis, which does not require that the precision RCS flow measurement be current until after exceeding 85% RTP following each refueling outage, is retained. As discussed in the Bases, the analyses supporting this requirement are predicated on the performance of a gross flow measurement prior to entry into Mode 1 and the maintenance of a reduced power range neutron flux - high reactor trip setpoint until the RCS flow has been verified. Through the use of the Transit Time Flow Meter and other precision instrumentation which h.. been installed by TV Electric, a sufficiently accurate RC" > measurement may be made prior to 85% RTP. This cai - .ty allows for the use of a single power plateau below 85% RTP for performing required surveillances during the post refueling power ascension. It also allows the plant to remain below 85% RTP following a refueling outage until the RCS flow is verified to meet the required flow. This change affects the Conditions (a separate condition is required for the precision flow measurement prior to exceeding 85% RTP), and the note and frequency associated with SR 3.4.1.4. 3.4 35 This change adds a note to SR 3.4.11.1 and SR 3.4.11.2 stating that the SRs are only required to be performed in Modes 1 and 2. The Actions Note "LC0 3.0.4 is not applicable" is intended to allow Mode changes for testing purposes (per Bases). This allowance is properly presented as an SR Note. A properly placed exception (i.e., an SR Note exception) would not allow the SR to be considered to be met until the appropriate conditions were available for it to be performed without entering the actions. The Note to these SRs would allow startup in Mode 3 if the SR had not been performed during the required frequency, but would limit the exception to prior to enterin Mnda 9 The change is consistent with traveler 1 28@ - ~ 0 3.4.11 2 CPSESD]fferencesfrom NUREG-1431 -ITS3.4 6 8/2888
- - . - . _ . .- _. . - . = . . .
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.11-3 APPLICABILITY: CA, CP, DC, WC REQUEST: Change 4-05 LS 31 and Difference 3.4-39 Comment: TSTF-113 (presently Rev. 4) has not yet been approved by the NRC staff. FLOG Response: TSTF-113 Rev. 4 revises the shutdown requirements of ITS 3.4.11 tc allow the plant to reduce T,, to <500 F within 12 hours, rather than MODE 4, to address the cencem of entering LCO 3.4.12 Applicability with one or more inoperable PORVs. The shutdown requirements of ITS 3.4.16 are also revised, for consistency, to allow 12 hours to reduce T,y to
< 500'F. ITS 3.4.11 Condition B and C Bases changes have been made to the Callaway submittal to reflect Rev. 4 of the traveler; no changes are required for any other plants' submittals. The FLOG continues to pursue the changes proposed by this traveler.
ATTACHED PAGES: EnctSA Traveler Status sheet l l l l l l t i j
i INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.4 TRAVELFS.g STATUS DIFFERENCE # COMMENTS TSTF 26 Incorporated 3.4 32 Approved by NRC. TSTF 27, Rev.3 0 Incorporated 3.4 33 Approvedjby;NR_C T3.4.21 TSTF 28 Incorporated 3.4 22 Approved by NRC. TSTF 54. Rev. 1 Incorporated ' o. Approvediby_.NRC m.3.4 009 TSTF 60 Incorporated 3.4 15 Approved by NRC. TSTF 61 Not incorporated NA Minor change that is adequately addressed in the Bases. 1 TSTF 87, Rev. 21 Incorporated 3.4 31 Approved by NRC. g.3,4.ac4 TSTF 93, Rev. 31 Incorporated 3.4 17 Approved;by..NRC. 03.4.9: TSTF-94,iRev.1; Not incorporated NA Retained current TS. m .3.4 0C5 ; i TSTF-405 Ir.ccrporated 3-4-38 o.3.4.1 1 TSTF-108, Rev. 1 Not incorporated NA LC0 3.4.19 does not apply. TF 113. Rev 3 I Incorporated 3.4 39 n,3,4,11. j 3 x ( .. l TSTF 114 Incorporated NA Approved by NRC. TSTF 116. Rev.2 Incorporated 3.4 36 a.3.4.13.; 1 t TSTF-136 Incorporated NA Approvediby;NR.C m 3.4 00s l
}
'~
TSTF-137 Incorporated NA Approted,byLNRC 73 3,4 005 TSTF 138 Not incorporated NA Inconsistent with RCS loops requirements of ITS 3.4.5 and 3.4.6.
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.11-4 APPLICABILITY: CA, CP, DC, WC l REQUEST Change 4-09 LS 36, Difference 3.4-47, Change 3-04 and Difference 3.4-31 Comment: WOG-87 has not yet become a TSTF. FLOG Response: As discussed during a telecon with NRC Staff on July 30,1998, the ! above references to DOC 3-04 and JFD 3.4-31 apply to NRC-approved traveler TSTF-87 and were not intended to be questioned here. Additional changes have recently been added per Revision 2 of WOG-87 and are included in the attached pages below. The addition of the Note to the block valve Action Statement is considered to be administrative in nature as it reflects current plant practice. WOG-87, Revision 2, has been opproved by the TSTF group and is expected to be submitted to the NRC expeditiously. Given the nature of the Notes added to the PORV block valve Required Actions and Surveillance Requirement, the FLOG continues to pursue the changes proposed by this traveler. ATTACHED PAGES: Enct2 3/4 4-11 Enci 3A 8 and 8a Enct 3B 5 Enci 4 68 and 69 Enc!SA Traveler Status Sheet and pages 3.4-24 thru 3.4-26 Enct5B B 3.4-53,8 3.4 55, and B 3.4-55a Enci 6A 8 and 8a Enci 6B 6
REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES l LIMITING CONDITION FOR OPERATION 3.4.4 Both power operated relief valves (PORVs) and their associated block valves shall be OPERABLE. APPLICABILITY: H00ES 1. 2, and 3. l NoteMSgtate.LConditjon;entryii s3110wedjforieach;yal ve; {44t-u @ J ACTION: . 1
- a. With one or both PORV(s) inoperable because of cx;csaiv; ; cat ic;kage imuM]
andicapable;ofibeing'maguallLcycled, within 1 hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) with power maintained to the block valve (s): otherwise, be in at least HOT STANDBY within the next 6 hours and reduce.T.,to3500T-4n ^mu q~
, ~ . _ , _ within the following 6 hours. ' '
- b. With one PORV inoperable duc to causc other than excessiv; cat (4.az-ul,Q ic;kag; and,;notlcapable;ofabeing: manually; cycled, within 1 hour either restore the PORV to OPERABLE status or close its associated l b'ock valve and remove power from the block valve: restore the PORV NM s .,
tc OPERABLE status within the following 72 hours or be in HOT STANDBY l within the next 6 hours and reduce 3.,to35007 in ll0T S "JT00'ai ! within the following 6 hours. Wuv, ~
- c. With both PORV(s) inoperable duc to c asc Other than excessive ; cat ic kage and.noticapab]e;ofjbeing'maguallyl cycled, within 1 hour smugd ~
either restore at least one PORV to OPERABLE status oc close its associated block valve and remove power from the block valve and be muky' in HOT STANDBY within thc .cxt 6 hours and te_duceJ,y to2500T in ll0T SliUT00Lil within the following 6 hours. 1(feufQ . _ .
- d. With one or both block valves inoperabibwithin 1 hour restore the block valve (s) to OPERABLE status or place its associated PORV(s) in manual control. Restore at least one block valv to OPERABLE status within the i next hour if both block valves are inoperab e: restore any remaining i inoperable block valve to OPERABLE status wi in 72 hours: otherwise.
[ be in at least HOT STANDBY within the next 6 urs andt edjiceL,to [q0rpj j M0_0T in ll0T Siil!"J0'JF within the following 6 ours. l L e. The provisions of Specification 3.0.4 are not applic 4 09 LS J 8CIIONJd;;doeCnot apply,when;blocKNalVf[sEisdnoperableisoje]y3s,u 0 3.4.11 4 TAsulEof,1 comp 1Dg yith,1ACT10NS2bJric] - l s 4 , CPSES Mark-up of CTS 3N.4 3M411 8/28/98
CHANGE NUMBER N2iG DESCRIPTION 4-08 LS 34 Consistent with traveler W96-MMIE 288, the 0 3.4.11 2 requirement to perform the 92 day surveillance of the pressurizer PORV block valves and the 18 month ; surveillance of the pressurizer PORVs (i.e., perform one complete cycle of each valve) is revised to indicate tnat i the surveillance is only required to be performed in MODES l 1 and 2. This is consistent with the recommendations of l Generic Letter 90 06, " Resolution of Generic Issue 70,
' Power 0perated Relief Valve and Block Valve Reliability,'
and Generic Issue 94, ' Additional Low Temperature l Overpressure Protection for Light Water Reactors,' Pursuant to 10CFR50.54(f)," June 25,1990. 4 09 LS 36 The requirement to perform the 92 day surveillance of l pressurizer PORV block valves (i.e., perform one complete i cycle of each block valve) is revised such that it is not i required if the block valve is closed to meet ACTION a of the current TS LC0 3.4.4. This change is acceptable l because no credit is taken for the automatic actuation of l the PORV in Modes 1, 2 or 3. Credit is taken for manual j operation of the PORVs during the Steam Generator Tube Rupture (SGTR) accident. However, the capability to ! manually cycle the PORVs will be unaffected by this change. This change will not affect the ability of the block valve to open, if closed to meet ACTION a, in the mitigation of an SGTR. Deferral of the block valve l cycling surveillance will not diminish the design capability of the P rk valve to open against differential pressures that woi Sa present after an SGTR since the
- block valves are ct., ile of opening against 2485 g l psig, the safety val .e lift pressure, whereas pressurime nraunre decreases after an SG 0 3.4.11 4 l 10 j1932alNp.t01sldded.itoALLun;LdEstating3 hat it
- doeEnotIapp]ylgrentbelbleicxalvetsDte2inopetable sq1elraraltesultiofitttpoweigbeingitemoled:perLACT l 0NS
[b2bric] asIe3y10ltJf(8n31Ddagtib]MVJs)ZIfthis scentirAcJ10Etb3me)11slegered;asiayesult onan jnopetabicmmtspne watempetableIafxl l i inapable;nnbefg!!g!aal]EcsleggtEchange discus _sgin)derggcmo.zit.sismACIIOjN [b] Mold bg entered;at7timEzen7mecLIE(brpuld closeit_hg i asJgjated21ggamendlteg321ttpoweetith1Etime;t, c11hourAIL9s a:tes!41tTorzblock:xa]1e~posetztemola]; l s t pet ACIIK[b]2ACIIO!C[d] McGhenienteted gfCLIONj[d];Would teqoirelhe?associat_ed~f0RVJtolbeIpiagedMaanuallcontrol wit.hin;timeltdW21hourr.3!oweXer7dthe2eason1f. or ot191na11rentenipgEIION;[blEls3thatithe7Msociat_ed;M sninopetab1Eand3aIn;ttbe;ma.nually;gyg]ed,ithus3hetG1s CPSES Description of Changes to CTS 3M.4 8 8/28/98
CHANGE I NUMBER ESifG DESCRIPTION
.. thing;toLb(galnediby;placingith. e;PORV31Mnua]
% l controlaIhe20REinopetab111tyimay,LbeIsuchlthetithe 0 3.4.11-4 3 i 15EVlennitibze placertaguajgogetGreg! Mown contrGIpodeFMalMp291 chase;neither;th1EMttionJ:of
&TK[d))!9t31BIGEelgregotatigcarbe;]!stzIn addition.;1thelp.9t4109303;T10_N iM}2gguf fjDglAlgk3alye testotatignrcanrbelsalt $11eCac1gng3s'powerlisaremoyed I tt9mitheibloce.altemestorinitheHEtol0N_RABi.E l statds31thinitjg.tggihoutsI8J1oWXthelplantitoleX1t i ACII0g;[b]21ff !gigr3ete3!ot;tes_toteditolthe31ockyalve atithisitime3thelgeCNote3DMCTJOEEd]swouldThave no standing;jnd3Cp0N;[d])ould be;; entered;1Simi, lag conclusions;;can;be[ drawn forithe~telatjonshipfbetween ACTIONSl[ciend;d]2If; ACTION;[c] Jsithe;orjginallACTION entered;1therelisigothing tolbelgainedjby placipg both PORVsIj n;manua];cpntrolland ,tha ^ blockivalvet can't :be l r,estorediwithitheirTpowerl emoved M ith ACTION [d]jpot I satisfiednthelplantinust;go toiH0DE13.;1butJCTION;[c]
s would hay.e[already3adithejplant11n: MODE;31two;; hours earlieraThereforeEthere;1sino: compensatory; action associat_ed_with: cascading to[the block; valve ACTI_0N [d: when]thelsole;inoperability(1siwithithe"PORVCs g c ang i: con:ictent "th treak wGGT7. 5 01 A Not Applicable to CPSES. See Conversion Comparison Table (enclosure 38). 5-02 A Not Applicable to CPSES. See Conversion Comparison Table
- (enclosure 3B). l 5 03 A Not Applicable to'CPSES. See Conversion Comparison Table (enclosure 38).
1 i 6 01 M Consistent with NUREG 1431. this change adds the requirement to perfor:9 an RCS water inventory balance every 24 hours when the [ sump level detector] is inoperable. This is a new requirement and is more restrictive than the current TS. CPSES Description of Changes to CTS 3N.4 8a 8/28/98 j
CONVERSION COMPARISON TABLE - CURRENT TS 3/4.4 rare 5 ef13 TECH SPEC CHANGE APPLICABILITY NUfBER DESCRIPTION DIABLO CANYON COMANCHE FEAK WOLF CREEK CALLAWAY 4-04 Thi.= change moves the requirement to perform channel Yes - Moved to the Yes - Moved to the Yes - Moved to the Yes - Moved to the LG calibration of PORV actuation instrumentation to a licensee FSAR. TRM. USAR. FSAR. controlled document. 4-05 The shutdown requirement of CTS 3.4.4 would require the Yes Yes Yes Yes LS-31 plant to go to reduceT , to <500*F within 12 hours, rather than go to MODE 4. to address the concern of entering [LTOP] LCO Applicability with inoperable PORVs. For consistency the shutdown requirements of CTS LCO [3.4.7] would be similarly revised. 4 06 This change provides a 72 hour completion time to restore an Yes No - Already part No - Already part No - Already part LS-32 inoperable block valve, with the PORV placed in manual of CTS. of CTS. of CTS. control mode. The current TS requires the block valve to be restored within one hour, or remove power from the solenoid. 4-07 This change provides a two hour completion time for Yes No - Already part No - Already part No - Already part LS-33 restoring an inoperable block valve when more than one block of CTS. of CTS. of CTS. valve is inoperable, and 72 hours to restore the remaining valves. The current TS requires the block valve to be restored within one hour for one or more valves inoperable. 4 08 Consistent with traveler TSTF-288 W96-60, the requirement to Yes Yes Yes Yes LS-34 perform the PORV and block valve cycling surveillances is revised such that the surveillances are only required to be perfc med in MODES 1 and 2. lQ3.4.11-2 ] 4-09 Consistent with traveler WOG-87, the requirement to perform Yes Yes Yes Yes LS-36 the 92 day sur*>eillance of the pressurizer block valves (i.e., perform one complete cycle of each block valve) is , revised such that it is not required if the block valve is 3.4.11-4 ll closed to meet FTinN a of the current TS LCO 3 a ~ (dion.ia Notelis,added;to;AQIION,[d];to, prevent; entry] solely.due:to: inoperable;PORV(s);underiActions.[b oric]i 5-01 This change moves the Steam Generator Tube Surveillances to Yes No - Same as CPSES Yes Yes A SR 3.4.13.2 and the Administrative Controls Sections 5.5.9 change 1-14-A for and 5.6.10. CTS Section 3/4.0. ' CPSES Conversion Comparison Table - CTS 3N.4 8n8/98 . . ~ _ _ . -
IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 36 10 CFR 50.92 EVALUATION FOR TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS Consistent with traveler WOG 87, the requirement to perform the 92 day surveillance of pressurizer PORV block valves (i.e., perform one complete cycle of each - block valve) is revised such that it is not required if the block valve is# o.3.4.n.4 \ clowd to meet ACTION a of the current TS LC0 3.4.4f rn.aaaltion,maJoteis m _ddedito ~ ACTION ,[d] topevempgy ssoiely;due,tojnoperable~PORV(s);..undet ActionsubotcU - This proposed TS change has been ev::luated 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 Commission 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 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 1 Involve a significant reduction in a margin of safety." 3. The following evaluation is provided for the three categories of the significant hazards consideration standards:
- 1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed change adds a relaxation to the surveillance associated with the pressurizer PORV block valves. The quarterly valve cycling will no longer be required if the block valve is closed per any ACTION of the LC0. No credit is taken for the automatic actuation of the PORV in Modes 1, 2, or 3. Credit is taken for manual operation of the PORVs during the Steam Generator Tube Rupture (SGTR) accident. However, the capability to manually cycle the PORVs will be l unaffected by this change. This change will not affect the ability of the ! block valve to open, if closed to meet ACTION a, in the mitigation of an SGTR. Deferral of the block valve cycling surveillance will not diminish the design capability of the block valve to open against differential pressures that would be cresent after an SGTR since the block valves are capable of opening against CPSESNo Signiflant Ha:ards Consideration - CTS 3N.4 68 8/28/98
V. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS-36 (continued) 2485 psig, the safety valve lift pressure, whereas pressurizer pressure decreases after an SGTR [ ]. The lack of quarterly block valve cycling, which could extend to a complete cycle since ACTION a allows continued operation with the block valves closed, doe! 7t decrease the likelihood of successful pressurizer relief since powei remains available to the block valve motor operator (s) and the surveillance frequency for the PORVs can be as long as 18 months (tested during each cold shutdown per the IST plan). Quarterly cycling could make PORV seat leakage worse; if the block valve were to subsequently be r;;411anca enuld unnococemrily challenga " _ and unable to PRT integrity.clos [e, th4e
~a dditiorf of_the Noteito1 ACTION [d] ~ stating ,that it 0 3.4.n 4 )
.not, apply.when the block 3valye(s);is~inoperabl_e sol.ely as a result of power 2being remov.ed. per3CTIONS}[blo.ric] .as;a; result.lof,an inoperable PORV(s)l eliminates operatotdistracti_on caused by the. required performance of activities;with;no safety;benefitUhisEchangelhas;no;effect;on the; successful mitigation,of a[SGTRisincelthejinitjalpremi_se is.that .the PORV(s) .is .
unavailable,' Elimination _ofco peratorlactions that have no safaiy hanam resul in 'anloveral_l; benefit to plantEsafetyylnerefore, the proposed change does not involve o ugniticant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
The only accidents that are potentially associated with this proposed change are those related to a loss of pressurizer relief function. This change does not introduce any new overpressure accidents and the existing analyses remain valid. Thus, the proposed change does not create the possibility of a new or different kind of accident from those previously evaluated.
- 3. Does this change involve a significant reduction in a margin of safety?
The proposed change does not affect the acceptance criteria for any analyzed event. The automatic actuation of the PORVs is not credited in the accident analyses for Modes 1, 2, or 3. The PORVs will remain capable of being manually cycled. The margin of safety established by the LCOs also remains unchanged. Thus there is no reduction in the margin of safety from that previously established. N0 SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION l Based on the above evaluation, it is concluded that the activities associated with 3 l NSHC "LS-36" resulting from the conversion to the improved TS format sa isfy the no J significant hazards consideration standards of 10 CFR 50.92(c): and accordingly, a no significant hazards consideration finding is justified. CPSESNo Significant Ha:ards Consideration - CTS 3N.4 69 8/28/98
~
I TRAVELER # STATUS DIFFERENCE # CO51NIENTS TSTF 151 Rev?1 Incorporated NA m-3.4 oos TSTF 153 Incorporated 3.4 01 Approved by NRC m.3,4.ogg TSTF 162 Incorporated NA Approyed byy'NRC.: m .3.4 Oc6 WOC 51. Rcv.1 Incorporated 3.4-45 & See also CNs 3.418 and Jr 3.4 12-2 TSTF;285 3.4 2352 3.4 20. - - l WOG-69 Incorporated 3.4 35 TSTFJ88 0 3.4.11-2 WOC 57. Rev. 1 Incorporated 3.4-10 Approved by NRC. DCPP TSTF-233 only. TR 3.4 009 WOG 87 ev;;2 Incorporated 3.4 47 0 3.4.11 4 WOG-99 Incorporated 3.4 40 Applicable to Callaway and TSTF-282 Wolf Creek only. 0 3.4.1 2 W^ m 100TSTF 280 Incorporated 3.4-49 l 0 3.4.12 1 1 l l l i l I 1 i l 1 J
Pressurizer PORVs 3.4.11 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve $=llDTE-x-w9 .- - -vt -:-b inoperable. R_equired 'Actiojglildo3]otilipp_]y it.en,lblockWaNelf,s3noper,able h 3,4,y solely asTarre~sultjg[cgap]ying o.3,4,11 4 l i githlequfred#tjons3;2;ot E;32 3.f.]5. . . . . .- . . . . . .=:.7. := t, .1 now e55vs.deu PURV in 1 hour manual control. AND C.2 Restore block valve to 72 hours OPERABLE status. D. Required Action and D.1 Initiat.elaction9.to restore Immediately associated Completion PORV(s)],~andjblock Nalvelto 03!439Gl Time of Condition A, B, OPERABLEistatus or C not met. 8HQ D.12.(BeinMODE3. 6 hours AND D.23, Sc k "00E 12 hours Bedyce'T,gtoI5500%. l l I CPSESMark-up ofNUREG-1431 -ITS3.4 3.4 24 S/1587
Pressurizer PORVs 3.4.11 CONDITION REQUIRED ACTION COMPLETION TIME E. Two [cr thrcc] PORVs E.1 Initiatelactionito Immediatel.V !!3Mf393j inoperable and not ristorie onelPORJito capable of being OP,ERABLElsta1;us VBMj manually cycled. M E.12 Close associated block 1 hour valves. E.23 Remove power from I hour associated block valves. M E.34 Be in MODE 3 6 hours M E.45 Sc in tiOCE 4.fseduce 12 hours :3.4439I1 T,gfo~5500T. rT -- W -N01E E f = = i f [R_equLredl6ctionsIdqino,tlapp]y F. More than one block n 3 valve inoperable. @enZblock19alve~1sjnoperable L n'4 0 4 3.4.11 soleKasiresultfoficomplying o RLth3eA01t@jec_tfon.s1Bj2Iod Y ? ?..=. ~ ..=.2.a =.. ,.. J F.1PlaceassociatedPORVsin 1 hour manual control. M F.2 Restore one block valve to 2 hours IBiPSj OPERABLE status [if three bicek valvc; cre inopercbic].
-8 P.3 P,c tore rc:cining 7;'. hour; iBiPSj block vcivc(s) to opera LE :tatus.
I CPSES Mark-up ofNUREG-1431 -ITS 3.4 3.4 25 S/1S M
Pressurizer PORVs
'4 a 11 CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and associated Completion G.1 .Initiatelactionlto restor 6? ode]blocEvalvq Lamediately ggg'g
^
Time of Condition F not to~0PERABLE3tatuji. met. 8El G .-12 Be in H0DE 3. 6 hours AND G.23 Sc in "00E 4.;l: educe 12 hours T,gto ~<500*F. SURVEILLANCE REQUIREMENTS SURVEILLANCE FRE0VENCY m SR 3.4.11.1 -- --- - ---
-NOTES-- ----
1.;Not required to be metperformed with block valve closed in accordance wit the Required 03'4-%'3' Action of Conditio LQO.T M 3 cr E. 3,4,47
~
0 3.4.11 4 210njy; required _tobe; performed;in;H00.ES21]
...................................... l323.5M Perform a com)lete cycle of_each block valve. 92 days cgggay e
--= .m... .m m __ m,__.. . . , . . __ _ ,___2 _ .m m a rr r Li nam a n m _a r o v .t.r at h Dw j0jejhj IA }-{Cl S its i.N $ 5 U 9 M ,
N 3.4-47 Nireta r!-v Q 3.4.11 4
~~.-n=2 .-Y -- :.::puLLk---r-t -X-n~ ::1-1 *3;g"3"5) 8 Op]1Tfequj tq[dito* beWtfoL1Ljed E1p_H0D_ES 35*G and3 -. .
-. .. . . _ ~ - - _
- :s:: z .= :::n n -- - 2:s u r r u a u :
SR 3.4.11.2 Perform a complete cycle of each PORV. 18 months %Bj{@ Sil 3.4.11.3 i'crfc ;; a cc;;;pletc cycic of cach scicacid [18] i;;cnth; IBMA cir control valvc cr.d check valvc on the air acca;;;ulator; in I'0l1" control cy; ten. CPSES Mark-up ofNUREG-1431 -ITS 3.4 3.4-26 S/15/97
. _ _. .~ _ _ __. ___ _ _ _ . . _ . _ _ _ _ _ _ . Pressurizer PORVs B 3.4.11 BASES reasonable, based on challenges to the PORVs during this time period, and provide the operator adequate time to correct the situation. If the inoperable valve cannot be restored to OPERABLE status, it must be isolated within the specified time. Because there is at least one PORV that remains OPERABLE, an additional 72 hours is provided to restore the inoperable PORV to OPERABLE status. If the PORV cannot be restored within this additional time, the plant must be brought to c "00E in which th LC0 docs act app @- atlleistJ! ODE l3Mth_;TJ<1500TZas required by Condition D. C.1 and C.2 If one block valve is inoperable, then it is nMessary to either . restore the block valve to OPERABLE status wiJdn the Completion i Time of 1 hour or place the associated PORV in manual control. i The prime importance for the capability to close the block valve j is to isolate a stuck open PORV. Therefore, if the block valve - cannot be restored to OPERABLE status within 1 hour, the Required Action is to place the PORV in manual control to preclude its automatic opening for an overpressure event and to avoid the potential for a stuck open PORV at a time that the block valve is inoperable. The Completion Time of 1 hour is reasonable, based on the small potential for challenges to the system during this time period, and provides the operator time to correct the situation. Because at least one PORV remains OPERABLE, the operator is permitted a Completion Time of 72 hours to restore the inoperable block valve to OPERABLE status. The time allowed to restore the block valve is based upon the Completion Time for restoring an inoperable PORV in Condition B, since the PORVs see say;not'be capable of mitigating an :=rprcssura event if;the31noper_able block ya]velisinotifu1]y,'ppejE.Nhcn picced in un=1 control. If the block valve is restored within the Completion Time of 1 72 hours, the power will be restored and the PORV restored to OPERABLE status. If it cannot be restored within this additional time, the plant must be brought to c "00C in which thc LC0 docs not cpply, htllegjlt"MIDEure thUC500*FJ as -- required by Condition D AgiBeguwWtjonsgrejaodifjgd 103.4.114 \
. Apotelstat1Dgithat3WXegigteQg11gsidoInotfgpp]y11f )
thelso]CteasoCfg3 tmh 8;b3Rlye,M1XdeQlared I inoperablemsagnssamiM!Kne.1gtemoteditComplfMth otMrsRequited1Act10nsMGhigyeg3he? Requited _AclienEfos inoperablel'ORV15KWh1Mgl@tplthQ}ockIval velpowerit0],be __ VedionC021t35310$$Mr[Q)deqlletQo3addr,e5$lt!H![Cogdttj D.1 and D.2 If the Required Action of Condition A, B, or C is not met, then the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to at least MODE 3 91th:T.4<500% within 6 hours cad to "00E 4 within 12 hours. Additjonal TactiodiCregtfireditolbelin1tlates (continued) CPSESMark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-53 8/2888
Pressurizer PORVs B 3.4.11 BASES (continued) system during this time and 3rovide the operator time tV M correct the situation.flgeitequirea; Actions;are;nodifit:# 0'3 4 11~4 .l 2a2Not.ej statingJhatithe3eguited2ctionCdo:notlapp]L1i the;soleireasonfptithelblock;Malyelbein[decl ared inoperabl e7j sf asiai resultzoffpoqerlbeingiremoved;toicomp]yJrith othedequirediActions EInthisleVent 3;heiRequired1Actionsifor inoperablelR0rd(s);(whighltequireithelblockIvalve,'poweritolbe vedloncenit21sig]osed)lateladequateltoladdressit_heiconditi , G.1 and G.2 If the Required Actions of Condition F are not met, then the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least T<500"F within 6 hours and tc "00E 4 within H0DE 3 with T'dltilonaliagtion;isirequir.ed;to bei.jamediately 12 hours."~5d initiated to; 1 restore;the}in. operable; valve (s);toiOPERABLEistatus.; Thisiwill: ensure; expedient; measures:ateltakenjolrejestablish OPERABLE _P0Ryslandblockyalves;while; maintaining) plant conditions above_H0DEJ4)utiless;than~500*G The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. In H0 DES 4 end 5 and:6T(with:thelre_ actor;ves'se1~ head,on), automatic maintaining PORV OPERABILITY may be required. See LC0 3.4.12. SURVEILLANCE SR 3.4.11.1 REQUIREMENTS Block valve cyclina verifies that the valve (s) can ha nnaned a k se d cEcop1 W ;i 2 c Al.cc1 M ya'M.il sig c G i o.3.4.11 4
.g;crde;;r tith"the RccuirtiAction:~cf Con;itionT;r C.' if ,
nccdcVThe basis for the ireauency of 92 cays is the AS Loae. Section XI (Ref M -4; t.x t;;cc;c va;vc is f i--Mc a ruw.' that is capable of bcing manually cyc'.cd. the
.PEPXIL:" of th bicck valva is of i;;;portancc becausc cpenin the block valvc is nccessary to pen;;it th; "0RV to bc used for
;;;anual control of rcactor pressurc. If thc bicck valvc is c1csc to isciate an othcrwisc inoperabic PORV~t:ict;;isqfitgpa)][cf befag';;;tatellEcygics, the ;;;axi;;;um Cc;;;platica Tim t PORV and e xn the bicck valvc is 72 hours, which is wcll within the allowa:10 li;;;it; (250 to extend the bicck valv Prcqucacy of 02 days. Parther;;;;rc, thcsc test requircnnts would bc ce .pleted by the reopening of a reccatly cicscd block valvc upon restoration of the PORV to OPEPELE status. (i.c., completion ,
tM=uired Actions fulfills the SR'. - This_SRjis;m_odjfjed:by;.tiolNotes]Mhe-Note limodifies this o.3.4.11 2 SR by stating that it is not required to be getoevor with the block valve closed, in accordance with tie Require o-3.4.11-4 l CPSES Mark-up ofNUREG-1431 Bases - ITS 3.4 B 3.4-55 80888
i Pressurizer PORVs B 3.4.11 BASES (continued) Ac of this:LC0JCor,diti;G.this LC0_) Opening the g,3'4'11,4 ock'valvelin;this:2 condition ~ increases the; risk of. an unisolablelleak: frow -theRCS ~since the PORV-is 'alrea i 1noperables; note 2. modifies:.thi,s:SR.to_ allow entry into'and I I operation;,inl MODE 3~priorstol performing the SR. This La1. lows theJsurveillance;toibe_ pe.rformed.in eny MODE 3:under o.3,4,11 2 operating temperature and. pressure conditions," prior.to entering..H0DEXor;2. ; belev "00E. 2. In accordance with References A,;,51and 6,~ admini_strative controls require .this test be performed.in. MODES 3.2.4 or 5 to adequately simulate operating temperature and pressure, effects'on PORV' operation. l l l l i i CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-55a 8/28/98
-- - = - - - . - - - - . . _ - - _ . - - . _ - - --. . .
CHANGE NUMBER JUSTIFICATION 3.4 46 Consistent with current TS 3/4.1.1.4. " Minimum Temperature for Criticality " ITS LC0 3.4.2 and its Condition A and SR 3.4.2.1 are modified to refer to " operating" RCS loops. Adopting the current TS wording is acceptable since valid 2 T.,, measurements are not obtainable for a non operating loop. 3.4 47 ITS SR 3.4.11.1 contains a Note which exempts the cycling of tM block valve when it is closed in accordance with Required Actions of Condition B or E of LC0 3.4.11. However, Required Action A.1 also directs closure of the block valve when one or more PORVs are inoperable and capable of being manually cycled. The SR Note should also , exempt performance when tha block valve is closed in ' accordance with Required Action A.1 as the block valve l should not be opened when the PORV is inoperable. This change is consistent with NUREG-1430 and NUREG-1432 in as much as the block valve cy'= 9 exemoted under ; CondiHane A a =ad r-4 Since pcwcr to the bloc - l (Tilic(s' is ;;;einteincd in "cauired Action A.1 T 0 3'4 11'4 Note to SR 3.4.11.1 will be revised to not require I the surveillwa nerformance if the block valve (s) is k closed nedhe Since powcr to nc ' Sk V; hie;Lpsm.m L i; e nd inn ";quir;d A.1. Action; S.2 ond E.3, the ;urveillerce can act bc ;;;ct. Civen the wording change
%t" to "perfered" in th; Netc. the wording of S" 3.4.11.1 i; revised to exe...ed tc the Conditica 3 :nd
;XGPti;n. IRiadditiogZNotesI6rgladdedito"C,ondi,,tions;C andiFistating2t M hesejtequiredjhettonsTdon_'tlapply;when DLelbLoc_idalv!ggEis2nostablOoleEAs3pirasult%jls
- pogr2mtgeengriperlRequ1M3ctigslB123irygn;s]
resultrofranlimpetable3)RVQQILIn_lthisiscen,atio 3 G99G1MG!OEarl15"enteredlaslaltesultIqfjtrilnoper_abj e
- NRKEf1EenENEMrtetnopetabicanosagbmet M1Hg31!!aB11MiggaConditicatuoutsewntelglat M8BBM&BB!tWM3ctioWN33ndXUlpidIclotejlbs i
EBGMatBTAlmslBlf.93 rid tremyelitsgegglithidiigelt, EDialEstifJmristoltMf7bl#cKEVAM38!gEttg@lal@c i - BIRElE03!iul!!13EiE90dition%3Jtet#M213end)
- M!3!11BL'BCttetGR ER1d3tegG1t#3he~2 REB 8;lB_edRVlts
- 1812plE2020mmDuttrA131th1EtiWDLt,ggLhgutsj
' BiltH12BhlDitM8_s@3fetlot191glifientattggTJgidit1on;BXs
- thetjthe"85s0ciated11LOBVas"1gopptAbJeland?can'tibg Mhd4DmME4tisl$he]'el1Ggtthfr!QMMIjainidibf pla_c1DgithCPORV;jllrplanuallco!gtojgIMM~1gopetab1]ity
! GD3DORh3h&t3he]ORVicanitibCPMedjl[mahual ! M!$t91]IeK'EbjpgicQgtpJl iggerifugETirCWhichic~asej t BentitedwtfortsIC113hdI2;garmbeJiatzgritaddition] 4 8tentedTActionicf2Htestqte2Dlock?ValV6300PERABLQ
- statuggaralwantisfied3saancangemsIr3so1 rom. 'thelblo~ckIValve5 Restor 1Dg~;t_he20BVlto10RERABL l CPSES Differencesfrom NUREG-1431 -ITS 3.4 8 8/28/98
- . - _ _ - . .- .- _ - - . - - . - . . . - - . -- . - - - - ~. -
CHANGE NUMBER JUSTIFICATION
- ~
..atusNithin? time;t/072 hours;allowscae:p]agt2to g,3, 11,4 l 88113gDditicrcBMf;ponrlierEnot?restpfyd_1tolthi blockIFRvot3his31oe3thelleOcte;MiQgnflition Clfgt1GaiR31Estetingland,Condit1ertMioi8dibel!!gt.ered]
S14118@tlGglggggt34DMdta@Xofithe3elationship between;cogittchCEIandflIflondjtje[EfJs thelorfginal Condittern.iis.. mere;!s3tothiggitEble gained;by llettuitedfMidE!!Kand;R_equiredMetterl182;gnitibe saltsfled Mitt DJockitalvelpowerittagted2313EE12;not e satisfiedattstrerAction:s.12you]dyequitelthe; plant;to ) be2tn1 MODE 23?lttutilleguired;ActionJXWouldihavellre had;thelplagt11n~MODEn3;tWo;hourslearJiepis change is woustent wuir-W;h "0C C7 3.4 48 A note is added to ITS 3.4.8 ACTIONS, indicating that ! entry into MODE 5 Loops Not Filled from MODE 5 Loops Filled is not permitted while LC0 3.4.8 is not met. The addition of this note is based on the performance of a I i plant specific LCO 3.0.4 matrix (see CN 1 02 LS 1 l of the CTS 3/4.0 package). LC0 J.0141has2been;r_eyis.ed i spithatichangesij nLHODESlorlotherispeci fjediconditjons 0-3.4.8-1 inithe3ppli_cabflity;thatiarel par,tMfia?shutdownlof the" unitishallinotibelptevented .WInladdftignZj.00 3.0XbasIbjegIteVjs,edisg;thatiitlisioglylappljcablelfot l en_ tty 2ttltgle]LODEIotiotherispecified ~ conditions 10'the App]icabilitniq1M. ODES 3;1223Eandl.3IhelMODE3hange i testrjitions11ri1LC0j3iOi4iwere' pre 11ous]ylapp]icable in l alllMODES2DI53.C0;3M;821 simodi fjed; bylalNoteIstatingi [Wjh JelthjslLC0lis:gotiset,ientry310tojp0DE151LoopsJot E1]ledif_tpsiM00Ei51LoopslEilledlislgotlpetuitledHSKi te transjtipCitp.s_(MODE [51(loopsiffiled)lto]LODEL5lQoops'not ff]ledEteeMCthelsteaCgegetatorsEaDIde_ cay; heat ! ~ tenovalisys_t_eQhjle?the:RHRjSysten11s2 potent.jally degradedMIlgttfpl11thCNoteZensuresltilatlth~e3tansition 181PtecluMLi.fi(C023142&l(two;5GsERtelchosegX193feu ofsthelteMDdlBHR366pMtolensUrfdecayiheaEremoval I capebilityJpt10Ctoldtain_ing Jhe;RCM l 3.4-49 LC0 3.4.12 "[LTOP] System", provides four different methods for pressure relief. Any of the four methods may be used. However, Surveillance Requirement 3.4.12.5 l requires testing whether or not the equipment is being credited to meet the LCO. The proposed change adds the words " required" to the Surveillance to exempt its performance if the equipment to be tested is not being used to meet the LCO. In addition, two editorial changes were made. The LCO requirement presentation was clarified. Also, the Note to SR 3.4.12.8 was revised to replace " required" to be met" with " required to be performed" since the " performed" nomenclature is appropriate here. consistent with the CTS. This i changeisconsistentwithtravelerTSTE280Wes-40s. o.3.4.12 1 CPSES Differencesfrom NUREG-1431 - ITS 3.4 8a 8/2888 j
CONVERSION COMPARIS0N TABLE FOR DIFFERENCES FROM NUREG-1431 - SECTION 3.4 6er6 DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.4-47 ITS SR 3.4.11.1 contains a Note which exempts the c; ling of the block Yes Yes Yes Yes valve when it is closed in accordance with Required Actions of , Condition B or E of LCO 3.4.11. However. Required Action A.1 also directs closure of the block valve when one or more PORVs are inoperable and capable of being manually cycled. The SR Note should . also exempt performance when the block valve is closed in accordance with Required Action A.1 as
- A1 " unlun chmlet not be opened when H 0-3.4.. 1-4 pFatoaw o ; i.9n, addition.1 Notes,are:added_to Condition C_ana, or Er i
prevent _ entry;solelyidue; tot noperable PORV(s) under, Conditions.B j \ ~ C 3.4-48 A note is added to ITS 3.4.8 ACTIONS. indicating that entry into MODE 5 Yes Yes Yes Yes Loops Not Filled from H0DE 5 Loops Filled is not permitted while LCO 3.4.8 is not met. 3.4-49 This change reorganizes the presentation of ITS LCO 3.4.12. adds the Yes Yes Yes Yes word " required" to ITS SR 3.4.12.5. and changes the word " met" to
" performed" in ITS SR 3.4.12.8.
3.4-50 This change is consistent with current TS SR 4.4.9.3.3. The 12 hour No - adopting No - adopting Yes Yes frequency applies to vent pathway (s) that are "not locked, sealed, or ITS format. ITS format. otherwise secured in the open position. The wording added to ITS SR 3.4.12.5 is also consistent with the format used in similar ITS 3.6 SRs. The 31 day frequency is also revised to be consistent with current TS SR 4.4.9.3.3. 3.4-51 The Note for SR 3.4.1.4 is removed. This is consistent with DCPP CTS Yes No No No DC C005 4.2.3.5. DCPP conducts a measured RCS total flowrate verification on the IB 24 month 3 frequency. 3.4-52 Consistent with traveler TSTF-285 WOG-51 the Note concerning No - See Yes No - See No - See accumulator isolation is rewordedLot f clarity,and is moved from the CN 3.4-45 CN 3.4-45 CN 3.4 45 APPLICABILITY to the LCO. 0-3.4.: 2-2 CPSES Conversion Comparison Table -ITS 3.4 8/2888
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.11-6 APPLICABILITY: CA, CP, WC REQUEST Difference 3.4-[39](Wolf Creek, Comanche Peak and Callaway) Comment: This difference does not address the addition of the "Immediately"in Required Actions D.1, E.1, and G.1 of ITS 3.4.11 FLOG Response: This RAI refers to JFD 3.4-49; it should refer to JFD 3.4-39., Difference 3.4-39 is revised with the addition of the following:
"New initial Required Actions are added to Conditions D, E and G to immediately initiate actions for restoration of the inoperable PORV(s) (and or PORV block valves) to OPERABLE status. These immediate actions will ensure expedient measures are taken to re-establish the operability of the PORV(s) (and PORV block valves) while maintaining plant conditions above MODE 4 but less than 500 F."
ATTACHED PAGES: Enc! 6A 7
, CHANGE MJMBER JUSTIFICATION 1 3.4 36 SR 3.4.13.1 and ACTIONS for LCO 3.4.15 are revised with the addition of a note per TSTF 116. The note addresses l the concern that an RCS water inventory balance cannot be l meaningfully performed unless the unit is operating at or l near steady state conditions. The note added to the l surveillance provides an exception for operation at less than steady state conditions. The RCS water inventory balance will only be allowed to be deferred for 12 hours after re establishing steady state conditions. 3.4 37 Not applicable to CPSES. See conversion comparison table (enclosure 68). 3.4 38 Consistent with TSTF 105, the details on th; ccthod by which the RCS fisw rate are verified is acved frc; the SR 3.4.1.4 to the Sascs. ticving this information to the Bases, allows the usa of precisica hcot balancca, albow taps, and other accptabic acthods in order to pcrform this verification and is consistant with the NUREC-1431 philosophy of acving clarifying info mation and 0 3.4.1 1 descriptivc details cut of the TS to the Bascs. Not used 3.4-39 The shutdown requirements of ITS 3.4.11 would require the plant to reduce T,,, to <500'F within 12 hours, rather than MODE 4, to address the concern of entering [LTOP] LC0 3.4.12 Annlicability with innnarablo DicVQNew
, _ t.1aXRequired3tionslareladdedito;ConditionsK E a 3.4.11 6 L andi.toammediatelylinitigelactions39r2 restoration ofithelgopetableJORV(sMandio6 PORVjb]pck tvalyes) to;0PERABLEigtatusl5jTJ!eseliamediateTactions Will: ensure expedlegt; measures 3rftakenitoire e~r stab 11shithe opetab_111tylf1P_0RHgMand f0RVlbjocklyal_ylesEwhile ma.intaining pl.antTennditionsiabovgM00EL41b0tpesCt 500T' consistency, tne souwvwn requirements of ITS
. 6 are also revised tr low 12 hours to reduce T.,, to
<500'F. This change is consistent with TSTF 113.
3.4 40 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 3.4 41 Not applicable to CPSES. See conversion comparison table (enclosure 6B). l 3.4 42 Not applicable to CPSES. See Conversion Comparison Table l (enclosure 6B). 1 3.4 43 Not applicable to CPSES. See Conversion Comparison Table (enclosure 68). CPSES Differencesfrom NUREG-1431 -ITS 3.4 7 8/28/98 1
.s
ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: Q3.4.12-1 APPLICABILITY: CA, CP, DC, WC REQUEST: Difference 3.4-49 Comment: WOG-100 has not yet become a TSTF. , FLOG Response: WOG-100 has been approved by the TSTF and is designated as TSTF-280. This traveler has been submitted to the NRC and is under review. The proposed wording in TSTF-280 was modified from WOG-100, and these modifications have been incorporated into the ITS (added "or" to LCO list and SR 3.4.12.5 Note was deleted). The FLOG continues to pursue the changes proposed by this traveler. ATTACHED PAGES: Encl. 5A Traveler Status page,3.4-28 and 3.4-32 Enci 58 B 3.4-64, B 3.4-65 and B 3.4-69 Encl. 6A 8a 1 l a
TRAVELER # STATUS DIFFERENCE # COSIN1ENTS TSTF 151 R_ev;21 Incorporated NA 7g.3,4 00s 1 1 TSTF 153 Incorporated 3.4-01 Approved;by NRC TR 3.4 005 TSTF 162 Incorporated NA Approved by;.NRC.' TR 3.4 Oc6 l L'00 51. Rev.1 Incorporated 3.4-45 & See also CNs 3.4 18 and 0 3.4-12 2 TSTFi285 3.4 2352 3.4-20. W96-60 Incorporated 3.4 35 TSTFf288 0 3.4.11 2 L'00 57. Rev.1 Incorporated 3.4 10 Approved by NRC. DCPP TSTF;233 only. TR 3.4 009 WOG 87 Revf 2 Incorporated 3.4 47 Q 3.4.11-4 WOG-99 Incorporated 3.4 40 Applicable to Callaway and TSTFf282 Wolf Creek only. o.3.4.1 2 q FE 100TSTF 28.0 Incorporated 3.4 49 ( _ 0 3.4.12 1 f l
. - - - . _ - . - .. . _~.-
i LTOP SYSTEM 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System l 1 1 LC0 3.4.12 An LTOP System shall be OPERABLE with a maximum of cac high ., ! pressure injectica ("PI) pump zero safetyjinjectio.njpumpsiand .B-PS/ l ene-twofcharging'.~ pumps capable of injecting into the RCS and the _ accumulators isolated and either a or b bcicw.one of, the 3.4-49< i following pressur.e: relief capabilitiesi
- 0. Two RCS rclicf volves. Os follows; ha. Two power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR. or 2-b: Two residual heat removal (RHR) suction relief valves with setpoints 2 436.5 psig and s 463.5 psig, or B bc; One PORV with a lift setting within the limits B specified in the PTLR and one RHR suction relief valve with a setpoint 2 436.5 psig and s 463.5 psi . . or 3.4 49 Q-3.4.12 1 b-d. The RCS depressurized and an RCS vent of 2 2-97 2.98 square inches
- B-PS
. . a . . . . . : 4 5. . (.= .y.3. 3. NOTE- . - { = - ~-' ~ - . :: - - - - ? -
Accumulator.1may~ be unisolatedica is caly- required when accumulatoripressure}is11essLthan!grcatcr than5cr ' 34jl22 3 equal to the . maximum RCS pressure forjthe. existing RCS co]dleg temperature allowed by.the;P/T limit curves provided11nithe PTLRi APPLICABILITY: MODE 4 when all RCS ccid icg temperature is > [275]"'- 3.4-05^ H0DE 5, MODE 6 when the reactor vessel head is on.
............................N0TE -- - -
Accumulator isolation is only rcquired when accumulatcr :3.4-52 1 pressure is greater than er equal to the maximum RCS pressurc for the cxisting RCS cold ic; temperaturc allowed by the P/T limit curves provided in the PTLR. The LC0 isinot . applicable when al_1 RCS cold, leg i temperatur_es;are7.320*F_ and the~following conditions are 3.4 met: a At least one; reactor coolant; pump .is in operation, and b! Pressurizer level 11s .< 92*,'and CPSESMark-up ofNUREG-1431 -ITS3.4 3.4-28 8/28/98
1 1 l LTOP SYSTEM l 3.4.12 SURVEILLANCE FREQUENCY 1314-08 d i SRf i g 12 3 Verify RHR suction isojatioq] valves 4s arefopen 7212 hours , l for each required RHR suction relief valve. I B-4-09 l B PS l Q-3.4.12-3 l l l l 3 4-49 l SR 3.4.1 "0TC 0 3.4.12 1 n_,.. ._ t_ ___,____;..u.s__. ____,.,2__ vi . . ,___.2_s_u;
.uyu i w uw r . i v. ...s m .. . ovii,y . g . . .
with LCO 3.4.12.db. J 12 hours for
\
iB:PS i Verify r.equired RCS vent 2 E-07 2.98 square unlocked open inches open. vent valve (s)3 . 3. 4.f 49,. . , ! eE 31 days for locked open vent valve (s) SR 3.4.12.6 Verify PORV block valve is open for each 72 hours required PORV. SR13Z4]122 Not3 sed.J^rify ass ^ciated "J " sucti^- 31 days isciaticr. valve i; locked oper, with opcretor 0 3.4.12 3 powcr rc;;;cved for cach requircd "J:" sucticr. relief volyc. CPSES Mark-up ofNUREG-1431 -ITS 3.4 3.4 32 8/28/98
- l. . _ _ -
LTOP System B 3.4.12 BASES I APPLICABLE RCS Vent Performance (continued) SAFETY ANALYSES The LTOP System satisfies Criterion 2 of th NRC I;1 icy StetG~nt.1EFM0;36[cM2M1DJ LC0 This LC0 requires that the LTOP System is OPERABLE. Thc LTOP Sy;tes l i; TEPXLE 2.cn the mini;um ce;1ent input end pic;;urc rclicf l cep;bilitic; erc TEPXLE. Violation of this LC0 could lead to the loss of low temperature overpressure mitigation and violation of the l Reference 1 limits as a result of an operational transient. l To limit the coolant input capability, the LC0 requires one W zero safety; injection pumps and one almaximum ofitwo 0 3.4. Gen.1 charging pumps be; capable of injecting into the RCS,' and all accumulator discharge isolation valves be; closed and immobilized. L'hca;$,whenlaccumulator pressure is greater than or l equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed in the PTLR. 0 3.4.12-2 The LC0;is_modifjed;byza Note: stating;thatitheiaccumulator i i;il:ti;G;Z;;1G;;; Red:saylbelunisol ated;whenithe;accumul atot ptessure:J s11ess;thanI;;;r;3h;at ;;rJtlthelmaximum;RQSJpressure;foc t.he,existjng: z temper,atureJEas: allowed;by thef/T211mit' curve _s;5This Note. petsjtsithelaccumul atorldi.schatgelisol ation: val ye:Surveill_ance to;be..performedlonly;under;the_se pressurelanditemperature:gondition.s] The elements of the LC0 that provide low temperature overpressure j
- t. mitigation through pressure relief are:
TWO RCS relicf v;1vc;. as follow 0 3.4.12-1 all. wo OPERABLE PORVs: or A PORV is OPERABLE for LTOP when its block valve is open, its lift setpoint is set to the limit required by the PTLR and ! testing proves its ability to open at this setpoint, and motive power is available to the two valves and their control circuits. b2.; Two;0PERABLE~RHRisuption;reljefiValles;ior, I l V AAMisuctign;teltet.aal.ye'jsLOPERABLEifot;LTOP;when11ts~ e RHB suctioqlisolation~ valves end it; PJlR suction velve arelopen,1 itsIsetpointIls'atioribetween1436.5"psig:and;463;5Jpsig,Iand I testjng~hasIproven31ts3bflitylto'#nn:atithfs!setpojnt) (continued) l CPSESMark-up ofNUREG-1431 Bases -ITS3.4 B 3.4-64 8/28/98 l - -
LTOP System B 3.4.12 BASES LCO c[.' One10PERABLE20RVJndM0JP RABLEM}uctioh (continued) teliefIi/alyeEot 0-3.4.12-1 db NA depressurueu RG anu on KL5 # vent. An RCS vent is OPERABLE when open with an area of a 2-07 2198 square inches. Each of these methods of overpressure prevention is capable of mitigating the limiting LTOP transient. APPLICABILITY This LC0 is applicable in MODE 4 when any RCS ccid leg temperaturc is m [275]'r, in MODE 5, and in ,00E 6 when the reactor vessel head is on. The pressurizer safety valves provide overpressure protection that meets the Reference 1 P/T limits above 075 3_20 F. When the reactor vessel head is off, overpressurization cannot occur. LC0 3.4.3 provides the operational P/T limits for all MODES. LC0 3.4.10. " Pressurizer Safety Valves," requires the OPERABILITY of the pressurizer safety valves that provide overpressure protection during MODES 1, 2, and 3, and MODE 4 above 075 320*F. Low temperature overpressure prevention is most critical during shutdown when the RCS is water solid, and a mass or heat input transient can cause a very rapid increase in RCS pressure when little or no time allows operator action to mitigate the event. Thc Applicability is acdified by ; Note stating that accumulatcr isolation is only required when thc accumulatcr 0-3.4.12-2 pressurc is acrc than or at the maximum RCS prcssurc for the ensting tempcraturc, as alicwcd by the "," limit curves. This Note permits the occumulator dischargc isciation v&te Surveillancc to be pcrforacd caly under thcsc pressurc and tc;perature conditions. TheApplicabilitfjfmodifieLbylalNoteEstatingithatithe:LC0iis n.otlapp]1gabl. e ~aboyd2.0*F,iybe[at3eastionergeagtoricoolantjpump is210 operationNptessurjzerJeyellis39212andithelplantiheatup tate 11 s;11mited3E60 *FlirCanyloneiho_utfpetiod.'7JTheseil conditions are11ncludedjjn1heLLTO_P,iana]ysis31[wlDg L10%tolbelnoperable aboye320'Fj (continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-65 808/98
LTOP System B 3.4.12 BASES (continued) SURVEILLANCE REQUIREMENTS SRr3:4112r4 (Continued) Each: required l_lHtsuqtion:rehenvalye:shalkbe! demonstrated OPERABLELWwerifyjng1tsfJ:R suction volve en(RWsuctior) isolatign: valves 3reiopen:and;byitesting?jt;1n;6&is&v,c.e;with the; Inservice 7Mtpg;Pfogr_as.0%(Rcicr to SR 3.4.12.7 for the PJ:R suctica iscictica volv; Survciliencc.) This".Surye111ance;is; only required;toibe; performed;1fithe RHRIsuction'; relief 1 Valve;isibeing usedioi,eetLthjsLLC0j t s The;RHRlsuctiorf21 solation: valves hiare yetifiedito;be;, opened every 3R72; hours 7mThefrequency;j s: considered ; adequate;in ; view of;other;adeinistrativeicontrols suchlas; valve:statusiindications available;to.the~operatorfi nithe; control roosithat; verify;theJHR suctionivalveirenainsiopen! The ASHE Code, Section XI (Ref. 8), test per Inservice Testing Program verifies OPERABILITY by proving proper relief valve mechanical motion and by measuring and, if required, adjusting the lift setpoint. SR 3.4.12.5 The RCS vent of 2-247-2.98 square inches is proven OPERABLE by verifying its open condition either:
- a. Once every 12 hours for a valve that c;nnot bc is _not locked.fsealed20tiotherwisej,ecuredJn;the!open position.
- b. Once every 31 days for othera ventipaths),(e.g M a valve that is locked, sealed, or oth_erwisejsecured in position). A .
removed pressurizer safety valve orlope.nloa.nwayl;alsojfits this category. The-An.yDassi e vent path] arrangement must only be open (1Rien: rec J1reo;t PERABLE. This Surveillance is 0 3.4.12 1 requirec? bc scrfor %if the vent is beino used to satisfy t ressure relief requirements of the LC0 3.4.1 SR 3.4.12.6 The PORV block valve must be verified open every 72 hours to
- provide the flow path for each required PORV to perform its function when actuated. The valve must be remotely verified open
{ 2 (continued) CPSESMark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-69 82888 4 g -
..,p .I
l CHANGE NUMBER JUSTIFICATION l
- slatQs31thi$ltf(tem 22hp.utsiallows;ttgpl ant;t 0 3.4.1 M 881t;CondjtfomB7ilfjpMLerLWeteJotirestotedI_tolt_he l bloclGvalve
- at3his',timeZtheIneWJiote;og1 Condition
?I@dE havernontaridig:abd;ConditionM(onldibe:ent_e.redJ SinflaKcoccitision~ s itarrbe: drawn 1(orjthitelationshjp
! betweeKCogd_ition' s 'f E?arld:FMIf!ConditioKE11s2theToriginal l Cgrgitiorcentered2thefEislDptbing ito;be3algeCby Beguited~Act1KPJiaggeguiled?6ctiinZF12;canit1.be satisfied 31thrbloeglyalverpiowet;temoyed: With r ainot satjftfled718equitedlActjpn;G12 WodidIr_equjtelthe:plaptjto beliO0 LEX butlR!tquiredl Action 1E ~4 .,Woul dj havela_l ready hatth[pl ante 1[ MODE!3jtwo~ hourslearl ier; This change is consistent with traveler WOG 87. 3.4-48 A note is added to ITS 3.4.8 ACTIONS, indicating that entry into MODE 5 Loops Not Filled from MODE 5 Loops Filled is not permitted while LC0 3.4.8 is not met. The addition of this note is based on the performance of a plant specific LC0 3.0.4 matrix (see CN 1-02 LS 1 of the CTS 3/4.0 package). LCO 3.'0.4 haslbeenitevised so.ithatichanges;j nl_HODES;oriother ;speci fiediconditions 0 3.4.8 1 initheiApplicab1]jtylthat are;partfoflaisilutdown;of the :unitishal];notl,be; prevented;2IrCadditiona LCO 3,0 i41hafbeepitevisedisp;thatjitilslon]ylapplicable;for entrylintfalM. ODErot[ot_het specf fjed., cogditionslin;the ApplicabilityiiniMOD_ES3E223Eand;4[,rdThe:MODEighange restrictionsljnlLC023.0:4 wereJprevjpu_s]y~appligablelin all;N00ES;EDIS;l.C0 ~3j41811s'. modi fiedfjyZalNotOtatingi Whjleithis1LC0lis%timetg_en_tryJintpf, MODE 551LooRs;$t E1Ue[ftom; MODE 251L_oop]slF111djd is!notlpe.tsitted2&The transitiogifrom'M0DElSlQoopsif1]fled)J10' MODE 551(l oopsingt fillesi)ltem6Verthejste'amigepefatotslas'a ' decay; heat tenoyallsys_t_emlWhileithe:RHRiSystemlisIpotenti.a))y degrided 3Ih(tefdteZt_h_e;NotelerjsuresithatIth_e;trartsj tjon isIpreclgded3fiLC0Kilb.3two75Gs)Jerelchoseg-{jan;]ieu gffthylsgpdOlfEl@p)ltoiens;0teMecaflhiatir_emoval papab_ilityJptioritoldrNining}}helRCS] 3.4 49 LC0 3.4.12 "[LTOP] System", provides four different methods for pressure relief. Any of the four methods may be used. However, Surveillance Requirement 3.4.12.5 requires testing whether or not the equipment is being credited to meet the LCO. The proposed change adds the words " required" to the Surveillance to exempt its performance if the equipment to be tested is not being l used to meet the LCO. In addition, two editorial changes were made. The LC0 requirement presentation was clarified. Also, the Note to SR 3.4.12.8 was revised to replace " required" to be met" with " required to be performed" since the " performed" nomenclature is appropriate here, consistent with the CTS. This change is consistent with traveler 80 WOC 0 3.4.12 1 CPSES Differencesfrom NUREG-1431 -ITS 3.4 8a 808/98
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.12-2 APPLICABILITY: CA, CP, DC, WC , REQUEST: Differences 3.4-23 and 3.4-45 Comment: WOG-51 Rev.1 has not yet become a TSTF. FLOG Response: WOG-51, Rev.2 is designated as TSTF-285. This traveler has been submitted to the NRC and is current!y under review. The proposed wording in TSTF-285 was modified from WOG-51, Rev 2, and these modifications have been incorporated into the ITS. The FLOG continues to pursue the changes proposed by this traveler. ATTACHED PAGES: Enct5A Traveler Status sheet,3.4-28 Enci5B B 3.4-64 and B 3.4-65 Encl 6A 9 Encl 68 6
~
. . . . . -. ~. . . _ .-
l TRAVELER # STATUS DIFFERENCE # COMMENTS l I i TSTF-151 gev.21 Incorporated NA 7g.3,4.gos TSTF 153 Incorporated 3.4 01 Approved _by NRC n 3.4 00s
=:
TSTF 162 Incorporated NA Approved by,_NRC TR 3.4 0C6 m Incorporated 3.4 4 See also CNs 3.418 and 0 3.4 12- 2 [STF;285 w 1-,-e35 3.4-20. [ W96-60 Incorporated 3.4-35 TSTF}288 0 3.4.11 2
'400 57. "cv.1 Incorporated 3.4 10 Approved by NRC. OCPP TSTF 233 only. TR 3.4 009 WOG-87 Rev..2.' Incorporated 3.4 47 0 3.4.11 4 WOG-99 Incorporated 3.4 40 Applicable to Callaway and TSTF.;282 Wolf Creek only. 0 3.4.1 2 '400 100TSTF-280 Incorporated 3.4 49 0 3.4.12-1
LTOP SYSTEM 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LC0 3.4.12 An LTOP System shall be OPERABLE with a maximum of cac high pressur; injectica ("PI) pump ze.roisa.[ety11njection' pumps 3nd NEN ene-twoj$argtng]pumpj capable of injecting into the RCS and the accumulators isolated and either c or b below.onefofithe E3l4f49] followinCptessuteRelieEcepabiljtiesj
- c. Two RCS relief valvcs. as fcilows.
1-a] Two power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR, or B-b; Two residual heat removal (RHR) suction relief valves with ._
~ setpoints 2 336;5 psig and s 463;5 psig. or RB!,id 3-c.? One PORV with a lift setting within the limits BB Mi specified in the PTLR and one RHR suction relief valve with a setpoint 243615 psig and s 163.5 psig-Hor 3.4-49 Q 3.4.12 1 b-d] The RCS depressurized and an RCS vent of a B-07 2.98 square inches. 2BjPSf4
. .c.=u=_==.:.
~ .- := ..~. .~; NOTE +R -~~ n
- - --- , -- m"when~
Jirc.,~ m ; =.a Accumulato yTheTur isolamdicr. Tis'ccirrc 3.442 accusl aio...h...i.p_re_ss_ureds71es s"thanreh1 Q.3.4.12 2 Cracl Rthrmax_inus1RCS;pressuteJoGthe;existigGCS o GRlil893!W!!Entutelallowedibyltjelf!IllinjEc4tvej pro 3.ideGLtheRILR] iii M d d i!:x : z & % c L E w :u 5 5=? I2 2i M Tiii APPLICABILITY: MODE 4 wh;n all RCS ccid ic; temperature is 2 [275] F. MODE 5, F~3 @'.0.51d HODE 6 when the reactor vessel head is on. l . . . . . . . . . . . . . . . . . . . . . . . . . . . . N 0T E - - - Acca ulater isciation is caly required when occumulator {3W52M pressur; is grcater than or aquel to the maximu; RCS I pressurc for the cxisting RCS ccid leg temperaturc clicw;d l by the P/T limit curvc3 provided in thc PTLR.- l The1LC0;is?not" applicable 1whenJalllCS3oldlleg tempefatuteCare21320fF.5an.dithelfoJ10wjpg3onditions are ..3,TO053 t: metj CPSES Mark-up ofNUREG-1431 -ITS 3.4 3.4 28 8/28/98
LTOP System B 3.4.12 BASES APPLICABLE RCS Vent Performance (continued) SAFETY ANALYSES The LTOP System satisfies Criterion 2 of the N"C Policy Stat .~nt.10CFR50P361cl(2)111)] LC0 This LC0 requires that the LTOP System is OPERABLE. The LTOP System is 0"C"#LC whcn the minimum cociant input and presourc relief capabilitic; arc OPE"#LE. Violation of this LC0 could lead to the loss of low temperature overpressure mitigation and violation of the Reference 1 limits as a result of an operational transient. To limit the coolant input capability, the LC0 requires one HPEzero safety' injection pumps and one a maximuniof. two 0 3.4. Gen.1 charging pumps apable of injecting into the RCS ' and all accumulato scharge isolation valve , losed and immobilized. " hen,'When,: accumulator pressu s greater than or equal to the maximum . -- e e = for the exist RCS cold leg temperature allowed in the PTLR. 0-3 m The;LC0ifsimodjfiedlby;a3otelstatingith_at the_accumula. a tor 140141;nli;'.;ElfEWiG4;may;be;unisol..ated then.:thejacgueulat . _ pressureJs31essithan3.or;;.thonicrict;the maximum;RCSfpres.sur_effor i thelexistingitemperatur.ezaslall. owed byithef/jT ljuftigurveslaThis Note;permitsithetaccumulatoridischargeli solation: val ve:Survejllang.e I to;be;performedJnJLunderjthese;pressurelandit_emperature;condjtjo The elements of the LC0 that provide low temperature overpressure mitigation through pressure relief are:
- a. Two "CS relief valves as folicws.
0-3.4.12-1 a3. Two OPERABLE PORVs: or A PORV is OPERABLE for LTOP when its block valve is open, its lift setpoint is set to the limit required by the PTLR and testing proves its ability to open at this setpoint, and motive power is available to the two valves and their control circuits. b2j ICOPERABLE;MBls'uction7 t e]ieLValvestor Ajn RHRTsuction:reliefjvalve;jsLOPERABLEiforjl. TOP2 wheglits1RHR suctioRisolation;yalyes and it: PJlP, suction valve are;openl,4 its';setpo19t;;1 rat 3ribetweenJ3#;5;psjg andj63Epsjgl Zand te.s11.pg;has ptoveplit_s3bilityito;open"atithis e.setpojnt! (continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-64 8/28/98
LTOP System B 3.4.12 BASES l LC0 g3] OMERLELPORyla.qdione10PE!@Blf1@Fisu_ctfod _ i (continued) telieffelyellof 0-3.4.12-1 ! 1 1 db. A depressurized RCS and an RCS vent. l l An RCS vent is OPERABLE when open with an area of a M7 2 Q square inches. l Each of these methods of overpressure prevention is capable of mitigating the limiting LT0P transient. 1 APPLICABILITY This LCO is applicable in MODE 4 t; hen any RCS cold lag tcaparaturc is ; [275] F, in MODE 5, and in MODE 6 when the reactor vessel head is on. The pressurizer safety valves provide overpressure protection that meets the Reference 1 P/T limits above B75 320*F. When the reactor vessel head is
~
I off, overpressurization cannot occur. I l LC0 3.4.3 provides the operational P/T limits for all MODES. LC0 3.4.10. " Pressurizer Safety Valves," requires the OPERABILITY of the pressurizer safety valves that provide overpressure protection during MODES 1, 2, and 3, and MODE 4 above 275 320 F. Low temperature overpressure prevention is most critical during shutdown when the RCS is water solid, and a mass or heat input transient can cause a very rapid increase in RCS pressure when little or no time allows operator action to mitigate the event, licability is acdified by a Nott stating that 7 eccumulater isolation is only rcquired when the acca;;;ulator 0-3.4.12-2 P picssure is ;;rc than er at the ;;;;xi;;;u;;; RCS pressure for the l existing te;grature, as alicwcd by the "/T li;;;it curvcs. This Note greits thc acca;;;ulater discharge is;1atica valvc Surveillance to bc perferned only under these picssurc and isparature conditions. The.7ApplMabilitf31s;nodifjedibyla}No_te3tati1Dg;thatItheiLC0;is gotiapp1tcableiabove320Niwtjenf at aeastlionelteactoricooj ant; pump is3DIopetatjog a!pCessucjzetdev_enis ire 2MandithezplantTheatyp rate 21snimitedlto601F21g[any3ne hout3etiodisiThe_se: conditions am; included 11g3hej.10 Plana}ysis; allowing 3.IOP,f, tom,1gopetable above2320*fJ (continued) CPSESMark-up ofNUREG-1431 Bases -ITS3.4 B 3.4-65 80888
CHANGE NUMBER JUSTIFICATION 3.4 50 Not applicable to CPSES. See conversion comparison table (enclosure 68). 3.4 51 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 3.4 52 Consistent with traveler TSTE285;W96-51, the Note o.3.4.12 2 concerning accumulator isolation isErewordet;fot clarityJnd is moved from the APPLICABILITY to the LCO. CPSES Dsfferencesfrom NUREG-1431 -ITS 3.4 9 g/28j98
CONVERSION COMPARIS0N TABLE FOR DIFFERENCES FROM NUREG-1431 - SECTION 3.4 6 or6 DIFFERENCE FROM NUREG 1431 APPLICABIt.ITY NUPEER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CAllAWAY 3.4 47 ITS SR 3.4.11.1 contains a Note which exempts the cycling of the block Yes Yes Yes Yes valve when it is closed in accordance with Required Actions of Condition B or E of LCO 3.4.11. However, Required Action A.1 also directs closure of the block valve when one or more PORVs are inoperable and capable of being manually cycled. The SR Note should also exempt performance when the block valve is closed in accordance with Required Action A.1 as the block valve should not be opened when the PORV is inoperable. In; addition,1 Notes.are;added to Condition C and R 0-3.4.: 1-4 I F;to prevent; entry; solely due,tokinoperablef0RV(s);under_ Conditions B or;Ei 3.4-48 A note is added to ITS 3.4.8 ACTIONS. indicating that entry into MODE 5 Yes Yes Yes Yes Loops Not Filled from MODE 5 Loops Filled is not permitted while LCO 3.4.8 is not met. 3.4-49 This change reorganizes the presentation of ITS LCO 3.4.12, adds the Yes Yes Yes Yes word " required" to ITS SR 3.4.12.5. and changes the word " met" to
" performed" in ITS SR 3.4.12.8.
3.4-50 This change is consistent with current TS SR 4.4.9.3.3. The 12 hour No - adopting No - adopting Yes Yes frequency applies to vent pathway (s) that are "not locked. sealad or ITS format. ITS format. Otherwise secured in the open position. The wording added to ITS SR 3.4.12.5 is also consistent with the format used in similar ITS 3.6 SRs. The 31 day frequency is also revised to be consistent with current TS SR 4.4.9.3.3. 3.4-51 The Note for SR 3.4.1.4 is removed. This is consistent with DCPP CTS Yes No No No 4.2.3.5. DCPP conducts a measured RCS total flowrate verification on l DC C005 l the 18 24_ month frequency. 3.4-52 Consistent with travele , -2l8 WBG-Si b Note concerning No - See Yes No - See No - See accumulator isolation i rdedifor2clarityzand is ved from the CN 3.4-45 CN 3.4-45 CN 3.4-45 APPLICABILITY to the LCO. R 0-3.4.: 2-2 l i CPSES Cenersion Comparison Table -ITS 3.4 8/2888 i
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.12-3 APPLICABILITY: CA, CP, DC, WC REQUEST: Difference 3.4-09 Comment: The difference does not adequately justify not adopting STS SR 3.4.12.7. The SR is intended to apply to valves besides manual valves. Performing SR 3.4.12.4 does not verify the same status as that verified by SR 3.4.12.7. FLOG Response: JFD 3.4-09 is not applicable to DCPP. JFD 3.4-09 provides an incorrect justification for not adopting SR 3.4.12.7. The Surveillance Requirement to verify the RHR suction isolation valves are locked open every 31 days (when the RHR relief valves are being used for cold overpressure protection) was removed from the CTS as part of a license amendment implementing the Generic Letter 88-17 recommendation to delete the RHR autoclosure interlock (ACl). The 31 day surveillance was determined to be no longer necessary since removal of the ACI eliminates the single failure that could have isolated both RHR suction relief valves. ACI removal also reduces the probability of closure of the RHR suction isolation valves when power is available. Also, SR 3.4.12.7 is bracketed in the S1 S. NUMARC 93-03, " Writer's Guide for the Restructured Technical Specifications" indicates that brackets are used in the generic Technical Specifications and Bases to indicate where plant specific input is needed. As identified in the
" Methodology for Markup of NUREG-1431 Specifications"in Enclosure 5A, changes to bracketed information involve the insertion of plant specific information which is presently located in the current TS. The methodology applied by the FLOG was that a JFD was not required if the bracketed requirement /information was not in the current TS. Therefore, no justification was provided since the STS SR 3.4.12.7 was not in current TS. SR 3.4.12.4 is abo bracketed in the STS. The changes being made to that surveillance involve plant specific wording changes (i.e., " isolation valves are"), which require no justification per the FLOG methodology, and the SR Frequency as discussed in JFD 3.4-08 (not applicable to DCPP).
Based on the above, JFD 3.4-09 is no longer necessary and will be replaced by "B-PS" in the Enclosure SA markup. JFD 3.4-09 will be shown as "not used" in the Enclosure 6A and 6B markups. Plant Soecific Discussion ACI deletion and elimination of the subject surveillance requirement was approved for CPSES in OL Amendment No. 4 dated October 21,1991. ATTACHED PAGES: Enci5A 3.4-32 Encl 6A 2 End 6B 1
1 LTOP SYSTEM l 1 3.4.12 ' SURVEILLANCE FREQUENCY SR I3 4 12.4 Verify RHR suction isolationjvalves 4s are;open 7212 hours for each required RHR suction relief valve. 3-4-09
.n.ps Q 3.4.12 3 SR 3.4.12.5 -
NOTE 3449 0 3.4.12 1 Only required to be performed when cc; plying with LC0 3.4.12.db. l
'2 i hours for :B-PS j l
Verify required.RCS vent 2 2-07 2.98 square unlocked open inches open. vent valve (s)S -
,3.47493 1 6E 31 days for locked open vent valve (s)
SR 3.4.12.6 Verify PORV block valve is open for each 72 hours required PORV. r SR,1314J12.7 No[Used;'!crify associated PJ:Ps suction 31 days { isciation valvc is iccked cpcn with operator 'u.a.4.12 3 powcr rc;;;cved for cach required PJlPs suction , relicf valva. CPSES Mark-up ofNUREG-1431 -ITS 3.4 3.4-32 8/28/98
QiANGE NUMBER JUSTIFICATION and does allow injection from [two] charging pumps. The changes are made consistently in the LCO, ACTIONS and SUR C LLANCE REQUIREMENTS. 3.4 07 Not applicable to CPSES. See Conversion Comparison Table (enclosure 68). i l 3.4 08 The existing licensing basis as contained in the Technical Specifications requires performance of this surveillance on a frequency of 72 hours. The Westinghouse STS used to develop the plant specific TS did not address the use of RHR relief valves. The requirement in the current TS was developed as part of an LAR to remove the autoclosure interlock which, in part, proposed 72 hours as it was consistent with the SR for the pressurizer PORV block valves. The 72 hours was found to be acceptable in the SER which was enclosed iri the license amendment. Plant experience has not indicated that the existing requirement I is unsafe or unacceptable. The surveillance frequency does not require reduc
- to 12 heurs.
3.4 09 The plant docs not havt ;;nual Rl R suction isciation 0 3.4.12 3 valves. The ;ctor-cpcrated suctica isolatica valvc3 (2 per relief volvc linc) arc survcilled in eeeeedance with SR 3.4.12.4. Thereforc this survcillance requircccat is not used. Not used 3.4 10 Not applicable to CPSES. See Conversion Comparison Table (enclosure 68). 3.4 11 The plant does not have the RHR autoclosure portion of the RHR System interlock as the system was deleted from the plant design. However, the portion of the interlock which prevents the valves from opening when system pressure is in excess of the setpoint has been retained. As such the note referring the autoclosure interlock has been deleted from improved TS 3.4.14 Condition C and SR 3.4.14.2 [and SR 3.4.14.2 is modified to be consistent with LC0 3.4.12]. SR 3.4.14.3 is not used. 3.4 12 In conformance with the current TS, the RHR Isolation Valves which are RCS PIVs are excluded from being retested following an extended period of operation in MODE 5. The valves are tested on an 18 month frequency which is acceptable based on valve type, interlocks, position indication and system alarm functions. These valves meet j the criteria for testing at least every 18 months but do not require additional testing based on when the unit is l in cold shutdown or based upon being moved from a closed position. CPSES Differencesfrom NUREG-1431 -ITS 3.4 2 8/28/98 l l
CONVERSION COMPARIS0N TABLE FOR DIFFERENCES FROM NUREG-1431 - SECTION 3.4 1 or6 DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 3.4-01 Clarifies intent of wording for the allowance to remove pumps from Yes Yes Yes Yes operation by changing "de-energized" to " removed from operation" consistent with TSTF-153. 3.4-02 This change revises Condition A of ITS 3.4.6 to cover any required Yes Yes Yes Yes loop's inoperability and adds Required Action A.2 indicating that cooldown to MODE 5 is only required if an RHR loop is OPERABLE. Condition B is deleted. 3.4-03 The current technical specifications allow I hour for the de- Yes Yes Ye Yes energization of all RHR pumps. [ ] 3.4-04 The symbol ">" in DCPP LCO 3.4.8 Note 1.a.. is replaced by the words Yes No No No "at least" 3.4-05 This change is being made consistent with the current assumptions used No. These Yes No-Similar No-Similar in the analysis. The analysis credits three operatimal restrictions operational analysis analysis below 350*F, to ensure that the reactor vessel h prcteted. restrictions are assumptions assumptions not part of the not contained not contained current TS. in CTS. in CTS. 3.4-06 Plant specific safety analyses do not allow injection from safety Yes - DCPP Yes - CPSES Yes - WCNOC Yes - Callaway injection pumps but do allow CCP injection analysis assumes analysis analysis analysis one CCP only. assumes two assumes one assumes one CCPs. CCP only. CCP only. 3.4 07 The word "all" in the DCPP LCO 3.4.12 APPLICABILITY is replaced by the Yes No No No word any. 3.4-08 The current licensing basis as containad in the Technical No - DCPP LTOP Yes Yes - See Yes - See OL Specifications requires performance of this surveillance on a frequency design does not Amendment No. Amendment NO. of 72 hours. use RHR relief 49. 42 vai vt 3. - 3.4 09 Thc plant doc not ha.c c ucl id".'..cuctic . i clatica valvc . ,2._.s_.,, 'hc No DCPP LTOP Ves NA Ves NA Ves NA
~ ...z__
.~. .___.. .. ..i...__ ,,, ___ __,
.m. m.s.
. . _ , . . _ ___ 2__=__ 2___ __. 0- 3.4.12-3 ]
..~m. mr . . _ 2.. .m m r. ....m . . ..s. mm . 3 . mmm .~,
surv-i"cd in accc.-dancc -it'. SR 3.4.12.4. Not used u c R"R cclicf ~ vetves- NA -_ CPSES Converswa Cun.1, .nv., Tu;>;c - aa J.4 8/28/98 9
l l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.12-4 APPLICABILITY: CA, CP, WC REQUEST: ITS Bases 3.4.12 Applicability (Comanche Peak, Wolf Creek, and Callaway) Comment: The intent of the addition to the end of the first paragraph of the Applicability Bases l is unclear. The LCO applies if the head is on. The added discussion essentially states LTOP l (COMS) protection is not needed with the head on and the bolts fully detensioned. If that is the argument then rather than adding it to the Bases discussion, the case should be made for modifying the LCO Applicability. FLOG Response: This comment is not applicable to Comanche Peak as this information was not in the CPSES ITS Bases. The Applicability for ITS LCO 3.4.12 includes MODE 6 when the reactor vessel head is on. With no fuel in the reactor vessel the plant is not in MODE 6. The statement was placed in the ITS Bases to indicate that low temperature overpressure prciection (LCO 3.4.12) is not required to be OPERABLE with no fuel in the reactor vessel. There may be some plant conditions when the reactor is defueled that warrant placing the reactor vessel head on the vessel for radiological concerns. In these situations, the requirements of LCO 3.4.12 are not required to be met. The inserted Bases words are being deleted and plant procedures will provide the appropriate guidance for the plant conditions when no fuelis in the reactor vessel. ATTACHED PAGES: None
.- .- _ _ .. . - . ~ - .. . .-. .- . . .-_ . ..-.
l l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.12-7 APPLICABILITY: CP l REQUEST ITS 3.4.12 Required Action D.1 (Comanche Peak) Comment: Is there an approved analysis that demonstrates that this new action is sufficient l protection from an accumulator discharge? l FLOG Response: The additional actions in Condition D are equivalent to depressurizing the accumulator to less than the maximum RCS pressure for the existing cold leg temperature as ; allowed in the PTLR; instead of depressurizing the accumulator, the cold leg temperature is increased to the point where the maximum allowable pressure is greater than the accumulator pressure. Because the maximum allowable pressure is greater than the accumulator pressure, i any accumulator discharge transient has no significant adverse effects; therefore, this condition is not explicitly analyzed. The additional actions are consistent with CTS 3.4.8.3. l AHACHED PAGES: l None i t f 9 y I
l l ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.12-8 APPLICABILITY: CP REQUEST: ITS 3.4.12 Required Action D.2 (Comanche Peak) l Comment: What RCS temperature has to be greater than 350 degrees F7 Tave (enter Mode ! 3)? One or more cold leg temperature (s)? , 1 FLOG Response: The RCS temperature > 350 F refers to T., for the purpose of entenng ; Mode 3 and thus exiting the Applicability of the specification. For CPSES,in order to exit the l Applicability by satisfying Required Action D.1 (raising RCS cold leg temperature to 320 F), it is also necessary to satisfy the three additional requirements of RCP operation, pressurizer level and heatup rate. Because of these constraints and because of the close proximity of RCS cold leg temperature requirement to the Mode 3 temperature requirement, Mode 3 may achieved before all cold legs are above 320 F. New CPSES Required Action D.2 specifies this option. Required Action D.2 is revised to refer to RCS average temperature. ATTACHED PAGES: 1 Enci5A 3.4-30 I I l l
__ ._ _. . . ___ ..__ . _. _ . . _ _ _ ~ . . _. _ . _ _ . _ _ _ . _ LTOP SYSTEM 3.4.12 l
- CONDITION REQUIRED ACTION COMPLETION TIME l
D. Required Action and I associated Completion Time of Condition C not D.1 Increase RCS cold leg temperature to > 075 320*F. 12 hours gg met. E Yetiffjlllt3,eastlegg 33i4!06
- 5 l Citasto,GeoolanUpoup;1g l J,gfpper8tiorg 7 dale P.E!tssuriz_erlevellis3 92*J E'E The.Tplantiheatupyate M11mitettol601Flin ,
an. cone 2h.our; period; QB , l D12 IncreaseJCS vera 12 hours 3.4 05 temperature;to _ O'FJ g.3.4.12 8 DB D.3 Depressurize affected 12 hours accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR. E. One required RCS relief E.1 Restore required RCS relief 7 days valve inoperable in valve to OPERABLE status. MODE 4. F. One required RCS relief F.1 Restore required RCS relief 24 hours valve inoperable in valve to OPERABLE status. MODE 5 or 6. i CPSES Mark-up ofNUREG-1431 -ITS 3.4 3.4-30 8/2888
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.13-2 APPLICABILITY: CA, CP, DC, WC REQUEST: Change 6-26 LS 30 and Difference 3.4-36 (Diablo Canyon, Callaway and Wolf Creek) Comment: TSTF-116 has not yet been approved by the NRC. FLOG RESPONSE: TSTF-116, Rev. 2 is currently under NRC review. This change provides assurance that the RCS water inventory balance will provide meaningful results. The proposed ' wording in TSTF-116, Rev. 2 was modified from TSTF-116, Rev.1, and these modifications , have been incorporated into the ITS. The FLOG continues to pursue the changes proposed by l this traveler. l This comment is also applicable to CPSES based on the applicability of JFD 3.4-36. ATTACHED PAGES: Encl. 5A Traveler Status page Encl. 58 B 3.4-76 , t
l l INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.4 TRAVELER # STATUS DIFFERENCE # COMMENTS l l TSTF 26 Incorporated 3.4 32 Approved by NRC. l TSTF 27. Rev.3 2 Incorporated 3.4 33 Approvediby.;NR.C 0 3.4.2 1 TSTF 28 Incorporated 3.4 22 Approved by NRC. TSTF 54. Rev. 1 Incorporated NA Approyed by:NRC m 3.4 009 TSTF 60 Incorporated 3.4 15 Approved by NRC. TSTF 61 Not incorporated NA Minor change that is adequately addressed in the Bases. TSTF 87. Rev. 24 Incorporated 3.4 31 Approved by_NRC. m 3.4 0c4 TSTF 93. Rev. 31 Incorporated 3.4 17 Approved,by NRC. 03.4.9: TSTF942Rev.1; Not incorporated NA Retained current TS. m 3.4 0c5 TSTr 105 Incorporated 3-4-38 n.3,4,1 1 TSTF 108. Rev. 1 Not incorporated NA LC0 3.4.19 does not apply. TSTF 113. Rev. 4 Incorporated 3.4 39 0 3.4.11 : 3 TSTF-114 _ Incorporated NA Approved by NRC. T , Ra g Incorporated 3.4 36 a.3,4,13.; TSTF 136 Incorporated NA ApproVediby;NRC m 3.4 009 TSTF 137 Incorporated NA Approyed_by NRC m.3.4 005 j TSTF-138 Not incorporated NA Inconsistent with RCS loops ! requirements of ITS 3.4.5 and 3.4.6.
RCS Operational LEAKAGE B 3.4.13 , BASES l
\
ACTIONS B.1 and B.2 (continued) l l l must be brought to lower pressure conditions to reduce the , I severity of the LEAKAGE and its potential consequences. It I should be noted that LEAKAGE past seals and gaskets is not l pressure boundary LEAKAGE. The reactor must be brought to MODE 3 1 within 6 hours and MODE 5 within 36 hours. This action reduces the LEAKAGE and also reduces the factors that tend to degrade the pressure boundary. The allowed Completion Times are reasonable, based on operating l experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging i plant systems. In MODE 5. the pressure stresses acting on the RCPB are much lower, and further deterioration is much less likely. l SURVEILLANCE SR 3.4.13.1 REQUIREMENTS Verifying RCS LEAKAGE to be within the LC0 limits ensures the l integrity of the RCPB is maintained. Pressure boundary LEAKAGE would at first appear as unidentified LEAKAGE and can only be positively identified by inspection. It should be noted that LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE. Unidentified LEAKAGE and identified LEAKAGE are determined by performance of an RCS water inventory balance. Primary to secondary LEAKAGE is also measured by performance of an RCS water inventory balance in conjunction with effluent monitoring within the secondary steam and feedwater systems. The RCS water inventory balance must be met with the reactor , at steadv state operating conditiorp/Ustable] temperature
- 0-3*4*13 2 WaeMevel a pressuruetpna_mpseup , tank.Gevel s 2 makeup;and letdownriand;RCPds.eal*inMiontandfreturn' flows) ;nd nw 9mtinc Drc=r >Therefore, a Notedsjaceo;anowJngith_at this SR is not required to be performed in tiO0ES 3 and 4 until 12 hours of af_t_eriestaMj]Lhing] steady state operation near operating pressure. have ba n establishcd. 521he32thout allowancCpMVides2suffteteyt3timeltoIco]1ectIandjprocess necessary;1atalaf_terlstable31 ant 1 conditions 3re' established]
Steady state operation is required to perform a proper inventory balance since calculations during maneuvering are not useful and c Note rcquires the Surycillance to bc ;;;ct .; hen stcody state-u
- established. For RCS operational LEAKAGE determination by water i
I (continued) CPSESMark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-76 8/28/98
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.13-3 APPLICABILITY: CA, CP, WC REQUEST: ITS 3.4.13 Bases LCO c. (Wolf Creek, Callaway, and Comanche Peak) Comment: How is the addition of what does not constitute identified leakage consistent with the definition in ITS Section 1.17 FLOG Response: The three categories in the definition of identified leakage do not include leakage outside containment. The added text in the ITS 3.4.13 LCO Bases on what does not constitute identified leakage is unnecessary and will be removed. ATTACHED PAGES: Enci5B B 3.4-74 2
RCS Operational LEAKAGE l B 3.4.13 l 1 BASES l l No pressure boundary LEAKAGE is allowed, being indicative of material deterioration. LEAKAGE of this type is unacceptable as the leak itself could cause further deterioration, resulting in higher LEAKAGE. Violation of this LC0 could result in continued degradation of the RCPB. LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE.
- b. Unidentified LEAKAGE One gallon per minute (gpm) of unidentified LEAKAGE is allowed as a reasonable minimum detectable amount that the containment air monitoring and containment levci monitorin;; cquip;;nt Conta,inment. Sump levella.ndBow 0-3.4.15-4 Monitoring'Syst.es can detect within a reasonable time period. Violation of this LC0 could result in continued degradation of the RCPB, if the LEAKAGE is from the pressure boundary.
I Identified LEAKAGE c. Up to 10 gpm of identified LEAKAGE is considered allowable because LEAKAGE is from known sources that do not interfere I with detection of identified;unidentifiediLEAKAGE and is well within the capability of the RCS Hakeup System. Identified LEAKAGE includes LEAKAGE to the containment from specifically known and located sources, but does not ! include pressure boundary LEAKAGE or controlled reactor coolant pump (RCP) seal lqakoff (a normal A j function not ennddered LEAKAGMeeg;jn;dA+ 0 3 4 13 3 ] CcNNN5b55555NNES $$NN I
- rmam+m.ma:eeemm:ms" E'n' M S'd" S ui S "'eTimi"3""2EM'24'lET:3 m"""Z:"kt22" eu m.-u-ww nth ~w -72DWG2. 2+3W"'"'1on of '
- - - - - - . I li: LCO ~"%un. In continued degradation of a component or system.
- d. Primary to Secondary LEAKAGE throuah All Steam Generatarji (SGs)
Total primary to secondary LEAKAGE amounting to 1 gpm l through all SGs produces acceptable offsite doses in the l Ste-accident analysis. Violation of this LC0 could exceed I ! the off' site dose limits for this accident. Primary to l l secondary LEAKAGE must be included in the total allowable
- limit for identified LEAKAGE.
(continued) l CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-74 8/28/98
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.13 4 APPLICABILITY: CP, DC , REQUEST: ITS 3.4.13 Bases SR 3.4.13.1 (Comanche Peak and Diablo Canyon) Comment: The Bases for SR 3.4.13.1 define steady state as Tavg changing by less than 5 degrees F/hr (Comancht: Peak) and Tavg changing by less than 5 degrees /hr and stable RCS ' pressure etc. (Diablo Canyon). The text for Diablo Canyon then goes on to define steady state as changing less than 5 degrees /hr and for Comanche Peak ITS Bases 3.4.15 Required Action B.1.1 and B.1.2 and B.2 defines steady state in terms of stable RCS pressure and then refers back to SR 3.4.13.1. Which statement or statements define steady state? l FLOG Response: The te m " steady state" is defined as " stable RCS pressure, temperature (Tmchanges less than 5'F per hour), power level, pressurizer and makeup levels, makeup and letdown, and RCP sealinjection and return flows." The Bases are revised to consistently use ' this definition. ATTACHED PAGES: Encl. 5B B 3.4-77, B 3.4-88 and B 3.4-89
l RCS Operational LEAKAGE B 3.4.13 BASES SURVEILLANCE SR 3.4.13.1 (continued) REQUIREMENTS inventory balance, steady state is defined as stable RCS. , pressure, temperatureGT Jc ung1ng;Dydess2 t nanygnourb l power level, pressurizer anc makeup cans ievm, m-uy and 0 3.4.13 4 1etdown, and RCP seal injection and return flows. An early J warning of pressure boundary LEAKAGE or unidentified LEAKAGE is l provided by the automatic systems that monitor the containment ! atmosphere radioactivity and the containment sump level. It should be noted that LEAKAGE past seals and gaskets is not I pressure boundary LEAKAGE. These leakage detection systems are specified in LCO 3.4.15, "RCS Leakage Detection Instrumentation." The 72 hour Frequency is a reasonable interval to trend LEAKAGE and recognizes the importance of early leakage detection in the prevention of accidents. A Note under the ficqucacy column l stctc:, thct this Sl1 ir required to be pcifor cd during steady state operction. Whenl.nordsteadyistate operation pregludes i sutve111ance:perfgraancelithelsurye111ancelshoul.dibe ! performed;1niay,teasonablegtieelperjodicommensurateyithithe surveillanceJperfotaance11eDgth',1onceisteadyistateloperation o.3.4.13 4 has' been"achievedgprovidedjpteatetithg;72 ' hours;have __f elapsed 7since:the' list;pePformancap Sem,7.m ,,3 mm m 2;D219;NL2;;3R;LXilh;;G SR 3.4.13.2 This SR provides the means necessary to determine SG OPERABILITY in an operational H00E. The requirement to demonstrate SG tube integrity in accordance with the Steam Generator Tube Surveillance Program emphasizes the importance of SG tube integrity, even though this Surveillance cannot be performed at normal operating conditions. DisIsurje111anceIdoey~notltig directly1to3nrpf;LhellMMiM[ct1tetjaMalth_e;LC0;or]onths CONDITIONSSthetelotelG_11greltgeeetEthisisurje111angeMg comideteddallure'tolmeetahenntegrity;goli1mitheltc_0;gd;LC0 3!0 T app 11esf1 REFERENCES 1. 10 CFR 50, Appendix A GDC fl ed 30.
- 2. Regulatory Guide 1.45, May 1973.
- 3. FSAR, Section 15.
41 ESWdect19E32 51 NtEGI10jlRoliamELHolenbey119842 6] 101Cf010_0J CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-77 8/28/98
_ ___ ~. __ __ _ _ _ _ _. _ . -._ _ _ _ _ ._ RCS Leakage Detection Instrumentation B 3.4.15 BASES ACTIONS Actjons; arf so#1fie#;byIalNote;thatilgdicates 3ha. tlthelptoyj sfolg of;LC013103;atelgotlappMcablL36s; Result,1*alMODEXhagge islallowedJhen;theJtequ1_redi;.y.Ae1. ..E x.;,itc;; Containment SumpAleyeEand *FloGongprigg @ystepJitheMr3A o.3.4.15-4 atso_spherje:particu]atelacgitot,"Rheltequired fataospheric gaseousimonitorlorithe.irequir.ed;airicooleticonde.nsatelflow ratet sonitor2Eate11goperableWJhisla]lowanceltstproy_ided becauseloth_er110strument.atioCis2availab]eitoisonitor RCS z leakage] l A.1 and A.2 Withtherequiredcontain; cat;cnitorContainment; Sump;Leyel o.3.4.15 4 and;FloKMonitoring; System inoperable, no other form of sampling can provide the equivalent information: however, the containment atmosphere radioactivity monitor will provide indications of changes in leakage. Together with the atmosphere monitor, the periodic surveillance for RCS water inventory balance, SR 3.4.13.1. must be performed at an increased frequency of 24 hours to provide information that is adequate to detect l leakage. Anote,lis;addeda))owingithat(SR:324.131isfnot i 4 ! requi. redL tolbeiperfnemad until312Jhours;after. establishing' steady stata 'nnaMaatas.;defi,ned,An3neyasesz ,onW3;4x13.1h et;UIC3CEEI545IC$ A==v;UI;T5i.$ECW;i.$$CVCIEr[e;;;INI 0-3'4'13-4 00d;;;kc; Plt BKlisiels;1;;E;.;P ;od lotdo ;i LTi "C" 3:01 " ' injcction~;ndJrc - .. . m ,. m 12ihour allowance,proviaes y sumclenplmegocotrecta1 process d l;necessaryidatalaf_tet stable; pl an_t; conditions;are;establi sh_ed] l Restoration of the required sump acnitor Conta1_nsentiSump Level anGlowjHonitorjing; System to OPERABLE status within a 0-3.4.15 4 l l Completion Time of 30 days is required to regain the function after the monitor's failure. This time is acceptable, considering the Frequency and adequacy of the RCS water inventory balance required by Required Action A.1.
"cquired Action A.1 i; modified by a Note that indicates that the provisions of LCO 3.0.4 are not applicabic. As a rcsult. O tiODE
! change is alicwcd when the s[quj;;;;; contain;cnt sump monitor is incperabic. This 011cuanc; is providcd because other ! instrumentation is availabic to acnitor "CS icakagc. l l B.1.1. B.1.2. 8nd B.2.1. and B.2.2 l With both gascous and the particulate containment atmosphere radioactivity monitoring instrumentation channels inoperable, alternative action is required. Either grab samples of the
- containment atmosphere must be taken and analyzed or water inventory balances, in accordance with SR 3.4.13.1, must be performed to provide alternate periodic information. l With a sample obtained and analyzed or water inventory balance performed every 24 hours, the reactor may be operated for up to 30 days to allow restoration of the required containment CPSESMark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-88 8/2888 i _.
RCS Leakage Detection Instrumentation i l B 3.4.15 ' BASES 1 ( atmosphere ____.u_ J. radioactivity
.,,_.._J J, &L_monitors. J_ __
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vys a u b vii sa u i i vvvw u sa birw w ii hvv i w a hvi russ saw bw s a vvy a u bu _._J&._J__ ....&m_ J- nnen An, e ___..JJ.J __.u ..__,m. ._- L .u. iruvi s a bvi esty dJ a b wiss sa viEsviv6be yavvsusu yi uu suusy s w a us % burNUIs _ . . _ , na L.... j L vUI J k7 s ivus a e i The 24 hour interval provides periodic information that is adequate to detect leakage. ALnoteMs;added allowing;thatiSR 3l."4213W1Finotirequiretto2be:per.formedluntil712 hours afterrestabitshinoisteady"stateToperation"Ds defined ,1n;the s
- ---- '~ ---^- -
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hout: allowance _ provides; sufficient: time sto; col lect Tand . process l necessary;dataiaftetstabl.e:p.lantjconditions are1 established: The 30 day Completion Time recognizes at least one other form of leakage detection is available. n._..J_ J A &J _ n 1 ._J nm_..J_m) Am&J _ D 9 ._- __JJ#JmJ L., . sswqu ii su nw b s vs s w.. u n su asuqu a i su n w b ivis u.6 us w suvu s a svu uJ u kf m & m &L.& J JJ..& . LL.& LL. __m..J.Ja_. *# f f*n 9 n A ._. & riv b s 6 su b i, tu i wu 4L J bitu b hesu ya v v i a a vs ud vi 6vv w.u.7 us w I sv b
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wnub 0.1 and 0.2 CFl?1 7Cf1?2.TCr2717and Cl2:2 1 With the required containment atmosphere gaseous radioactivity monitor and the required containment air cooler condensate flow rate monitor inoperable, the edy means of detecting leakage 4s t l l r 1 I t CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-89 8/:8/98
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.14-1 APPLICABILITY: CA, CP, WC REQUEST: Difference 3.4-13 (Callaway, Wolf Creek and Comanche Peak) Comment: What is the justification for restricting the testing to check valves with the addition of the term " check"in three places in SR 3.14-1 and its Bases? All PlVs at a plant may be check valves however, the addition is not consistent with the "or isolation valve" part of the first sentence of the SR Bases or with the words of required Action A of ITS 3.4.14. For Callaway and Wolf Creek simple deletion (sic] of" check" causes a problem with CTS 4.4.6.2.2.d and 4.4.5.2.2.d for Comanche Peak. FLOG Response: CTS 4.4.5.2.2 for Comanche Peak requires surveillances be performed on each RCS PlV listed in Table 3.4-1. The valves listed in this table are not all check valves. All the valves listed are subject to the testing frequency of items SR 4.4.5.2.2.a, b, c, and e. In addition, testing of the .ChtGk valves within 24 hours of actuation was specifically addressed in item d. This CTS surveillance does not contain a 24 hour test requirement for non-check valve PlVs. The STS equivalent of 4.4.5.2.2 for Comanche Peak is SR 3.4.14.1. However the STS SR does not appear to limit the 24 hour test requirement to check valves only. Therefore that portion of the STS surveillance was modified to be consistent with the CTS. The Bases were similarly modified. CTS 4.4.6.2.2.d for Callaway and Wolf Creek is similar to CTS 4.4.5.2.2.d for Comanche Peak. However, CTS 4.4.6.2.2.d for Callaway and Wolf Creek does not specify check valves only (as does the Comanche Peak counterpart). Nevertheless, all the valves subject to CTS 4.4.6.2.2.d
- in Table 3.4-1 for Callaway and Wolf Creek are check valves, given that the CTS SR wording i excludes the RHR suction isolation valves. It was decided that the STS wording should be revised consistent with the wording for Comanche Peak to reference only check valves rather 4 than bring forward the CTS list of PlVs and the RHR suction isolation valve exclusion.
ATTACHED PAGES: None 1 l l
l ADDITIONAL INFORMATION COVER SHEET 1 ADDITIONAL INFORMATION NO: Q3.4.14-2 APPLICABILITY: CP, DC, WC REQUEST: Change 6-11 LS-11 (Wolf Creek, Diablo Canyon and Comanche Peak) Comment: The change justifies isolation by a single valve within 4 hours and the use of check valves as isolations. However, the change does not justify the practice of using a second isolation valve. FLOG Response: Change 6-11-LS-11 for Comanche Peak and Diablo Canyon is modified to include the bracketed information from NSHC LS-11. DOC 6-11-LS-11 provides justification for isolation by a single valve within 4 hours, the use of check valves as isolation valves, the use of using a second series isolation valve within 72 hours to isolate a leaking PlV. Comanche Peak and Diablo Canyon take credit for a second series isolation valve to isolate a leaking PlV. The Enclosure 3A description for Comanche Peak and Diablo Canyon of 6-11-LS-11 (in part) provides:
"This change in conformance with NUREG-1431 Rev.1, allows for the flow path to be isolated by one valve within 4 hours and (by a second in series valve] within 72 hours.
This change is less restrictive and is acceptable because the first valve has been surveilled as meeting the same leakage criteria as the inoperable PlV and the small probability of a failure during the 72 hour period.. " For Comanche Peak and Diablo Canyon Enclosure 4 NSHC LS-11 provides additional justification for use two series valves which has been added to DOC 06-11-LS-11 as follows:
"The valve used to isolate the inoperable PlV will be leak tested in accordance with the surveillance requirements. With the successful completion of this leak test requirement, there is sufficient assurance that a single valve can provide adequate isolation for the following 72 hours. (The requirement to employ a second series isolation valve within 72 hours restores the two valve isolation required by the current TS.] The interval during which only single valve isolation of high-to-low pressure interface is provided, is sufficiently short so as to not involve a significant increase in the probability or consequences of an accident previously evaluated."
l Wolf Creek has evaluated this issue further and determined that the design of the plant is such that the Reactor Coolant Pressure Boundary only contains two qualified pressure isolation valves in series. Therefore, the bracketed STS Required Action allowing the use of a second series isolation valve to isolate a leaking PlV is not required. ATTACHED PAGES: None
.- ~
. - - _- .. . - ._ . .. , _ - = _ _ _ _ . = - _ - .-_ -.
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.14-3 APPLICABILITY: CA, CP, DC, WC l 1 l REQUEST: ITS 3.4.14 Actions Notes 1 and 2 Comment: The adoption of the STS notes (especially #1 which is a less restrictive change) is I not discussed / justified. FLOG Response: A new DOC (6-29-LS-38) has been added to include ITS 3.4.14 Action Note 1 to the CTS markup. This note allows separate Condition entry for each pressure isolation valve (PlV) flow path made inoperable by an inoperable PlV. Also new DOC 6-30-A is added to include ITS 3.4.14 Action Note 2 which specifies entry into applicable Conditions and Required Actions for systems made inoperable by an inoperable PlV. ATTACHED PAGES: Enct2 3/4 4-15 Enci 3A 13 and 13a Enci 3B 9 EncI 4 1,72 and 73 i l
BEACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION l ACTION (Continued) I iE(b2contJ} Wjth,1RCDseallinjection:f]ow!greatefithan;thelabove31mitZyerMyj ,.. 2;100! ; flow; equivalent;tolais1Dgle;0PERABLEJECCS; charging ;tra11,j s M" .M, l ayail able31 thin 142oursland ireduc_e;$heHlottatelto'Within11mits M-u# within}72thoursEorjbelinjat21 east [H0TiSTANDBY1Within;1heJexti62 houts - and;in1H0T2 SHLIIDOWN;within $helfollowing 6; hours]
- c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion 'f $114s gq the affected system from the low pressure portion within 4 hours i- - -
use of at least two one/ closed manual,+ er deactivated automatic @'* MN vehes, or' check valve" andLwithin 72 hours;by;the;use;of;a second 4 closed manual,Jdeactivated automaticCor'chec4Lvalve#: Tor be in at 6 30 A least HOT STANDBY within the ne 6 rs and in COL (LSBUIDOWN 0 3 4 14 3 within the following 30 hours *** (New) With the~ RHR. suction; isolation valve;interlockLfunction =6 29 Ls 0 3.4.14 3 inoperabl.e ; isolate;the affected. penetration;by:usefofjone c1gsed manua.1;orl deactivated ,a.u. tomatic - valve wit. h.in '.4.-- ho. urs; SURVEILLANCE REQUIREMENTS 4.4.5.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of 1 the above limits by: i c. tionitoring th: Reactor Ccciant System Lcckagc Octcetion Systc @.tpisy( rcquircd by Spccification 3.4.S.1 at least once pcr 12 hours,
- b. Measurement of the CONTROLLED LEAKAGE to the reactor coolant pump fiidgj seals when the Reactor Coolant System pressure is 2235 i 20 psig at least once per 31 days with the modulating valve fully open. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4:
- c. Performance of a Reactor Coolant System water inventory balance at least within 12 hours after achieving steady state operation
- and at least once per 72 hours thereafter during steady state operation, except j that no more than 05 hours shall clapsc betw;ca any two successive @ts-tsy inventory balances. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 or 4; and M1& MIS _
- d. gn{gring the Reactor ll cad Flangc Lcakoff Systc; at icast once per
,,~w.
gg
- being changed by ic33 than S=F/ hour.
T EEh1Valvelusedsto,: satisfy;thisllac.tjon;must Aave.beenlyerif,teddo_ meet 6 30 A N 0 3.4.14 3 surveil l a nce " requirement t4.4. 5 : 2.'2.1 (M tm;ertapp 11 cad LeJonom ons _and;Requi redlActio.ns Igrlsystemimade inonerabl eu b v " anti nocerabl e ' PI V .* - 6 29 Ls I S_eParatejconditionientty2s;a]lowedforjeachjPIVJ]o(pat $[N # o.3.4.14 3 J CPSES Mark-up of CTS 3N.4 3N 4-15 8M8/98
l l CHANGE NUMBER HSHC DESCRIPTION 1 remaining charging flow (with some inoperability in the l charging system) is greater than or equal to 100% of the l assumed post-LOCA charging flow, 72 hours is allowed to restore Operability. This change is consistent with traveler WOG 84. l l 6 22 H This change adds a new ACTION to isolate the affected RHR penetration within 4 hours if the RHR suction isolation valve interlock function is inoperable. The function of the RHR suction valve interlock is to protect the RHR system from an intersystem LOCA by preventing the RCS hot leg suction isolation valves from inadvertently opening when the RCS pressure exceeds the interlock setpoint. Upon failure of the interlock. the current TS permits continued operation for 72 hours for restoration of the affected subsystem. The improved TS requires action within 4 hours to isolate the affected RHR subsystem. Thus the new ACTION decreases the probability of an intersystem LOCA upon the failure of the interlock. This is a more restrictive change and the new ACTION is in LC0 3.4.14 Condition C of the improved TS. 6 23 LS 25 Not Applicable to CPSES. See Conversion Comparison Table , (enclosure 3B). 6 24 H Not Applicable to CPSES. See Conversion Comparison Table (enclosure 38). 6 25 LS-26 Not Applicable to CPSES. See Conversion Comparison Table (enclosure 3B). 6 26 LS 30 Not Applicable to CPSES. See Conversion Comparison Table (enclosure 38). 6-27 A Not Applicable to CPSES. See Conversion Comparison Table (enclosure 38). 6-28 LG Not Applicable to CPSES. See Conversion Comparison Table (enclosure 3B). , s 6f29 LS-38 Qonsjstentwith1NUREG,1431EseparateiCondition'e_qtry 1s; allowed:for~each? flow path'with"excessivejleakage
\
fromSS;P5Vsl.lAltho^ug(this3pecidcadon[provijfes l03.4.143j aj idt;oni all owabl e2IVAe.akageirateMts ' main purposej s_to ' pteyentioverpres sure; fail ure ~ o f;thell ow i pressure ~ portions; oLgonnecting Jy. stem _sl2Th_elleakage J imit i i sf auj ndigation .: thatithe2IVs ~ betweenJhe;RGS 'an[the gonne_cti ng; systems ;a re ' degraded _orldegrading .~ I Ea ch,1fl oW CPSES Description of Changes to CTS 3N.4 13 8/2888
I l CHANGE l l NUMBER HSjiG DESCRIPTION - 1 path;is;allowea separ_ t ate;Condjtjon entryibas,ed.upon l the;functjonalAndependencejohthef cv paths (1That 1 0 3.4 14 3 1sathelreguf tediactionsitomol ateithelhjghlpressure Portions;;ofatheIaffected flo(paths;;jnAr_ der;to Protectithe q nectjng:JoWpressuresystems18re;not'affected j by;1eaking2IVs;iniotherflowpaths; [' 6 30 A IT5:3;414f; Action; Note"2 which;specifie_sientryjnto l appligable;Condjtions:and Required Actions lfor 0 3.4.14-3 systems made:; inoperable _by:an11noperablefIV isiadded tothe;CTSHIhisais"an; administrative: change;because it;.only.'make.s; explicit:a. general requirement.that 1s_ 3 alr.eacly licitTlInithe: CTS.j 7 01 R This change in conformance with NUREG-1431 Rev. 1. removes the reactor coolant system chemistry specification from the Technical Specifications. The limits and required actions on reactor coolant system chemistry is being relocated to a licensee controlled document. l l l CPSES Description ofChanges to CTS 3/4.4 13a 828/98
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CONVERSION COMPARISON TABLE - CURRENT TS 3/4.4 Page 9,f13 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 6 25 The Operational Leakage LC0 has been modified to change Yes No - Leakage limit Yes No - Already part LS-26 allowed limit for RCS pressure isolation valves. of 5 5 gpm is of current TS per already part of Amendment 66. current TS. 6 26 The CTS surveillance requirement for performing an RCS water Yes No - Already part Yes Yes t LS-30 inventory balance is modified to allow deferral of the water of the CPSES inventory balance such that it would be performed within 12 current TS. . I hours after achieving steady state conditions. 6-27 RCS leakage detection system descriptions are revised for No - Current No - Current Yes Yes A consistency with current TS LCO 3.3.3.1 and FSAR Sections systems are systems are 5.2.5.2.2 and 11.5.2.3.2.2. applicable. applicable. 6-28 The current TS definition of controlled leakage is deleted. No - Retaining No - Retaining Yes - Hoved to USAR Yes - Moved to FSAR LG The RCP seal water return flow limit is moved to a licensee CTS. CTS. controlled document. d9 Separate Condition;entCy11 stallowed,each, flow path with.; . Yes Yes Yes Yes LS 38 excessive;1eakageJrosjtCSLPIVsel l Q-3.4.14-3 h 6-30 ITS13.4.14. Action _ Note:2;whichsspecifies:entryxinto Yes Yes Yes Yes A applicable Conditions and.Reautred Actionsfor; systems.made inoperable by;an inoperable _PlV,is;added to the CTS. l0-3.4.14-3 l )
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/
7-01 This change relocates the reactor coolant system chemistry No. Amendment 98/97 Yes - To be No - Amendment 89 No - Amendment 103 R specification from the Technical Specifications ;o a relocated to relocated TRM. relocated to USAR relocated to FSAR licensee controlled document. Equipment Control Chapter 16. Chapter 16. Guidelines (ECG). CPSES Conversion Comparison Table - CTS 3N.4 8/2888
1 I l NO SIGNIFICANT HAZARDS CONSIDERATIONS (NSHC) i l CONTENTS l I. Organization ........................................ 2 i II. Description of NSHC Evaluations. . . . . . . . . . . . . . . . . . . . . . 3 III. Generic No Significant Hazards Considerations "A" - Administrative Changes......................... 5 "R" Relocated Technical Specifications. . . . . . . . . . . . . 7 "LG" Less Restrictive (Hoving Information Out of the Technical Specifications) . . . . . . . . . . . . . . . . . . 10 "H" More Restrictive Requirements. . . . . . . . . . . . . . . . . 12 IV. Specific No Significant Hazards Considerations "LS" LS 1................................................ 15 LS 2................................................ 17 LS-3................................................ 19 LS 4................................................ 21 LS 5................................................ 23 LS6................................................25 LS 7. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 8................................................ 27 LS 9................................................ 29 LS 10 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 31 LS 11. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 3 LS 12............................................... 35 LS 13 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 7 LS 14 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 9 LS 15 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 41 LS 16 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3 LS 17 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 5 LS 18 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 7 LS 19 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 9 LS 2 0 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 51 LS 21. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3 LS 22. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 2 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 5 LS 24. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 25. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 26. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . N ot Appl i cabl e LS 27. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 2 8 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 7 LS 2 9 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 9 LS 30. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 31. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 61 LS 32. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 33. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not Appl i cabl e LS 3 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 64 LS 3 5 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 6 LS 3 6 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 8 i LS 37- .. ..... . m.70 328 u .m.e. .:.._ ..u e . x.n-- . n,i na. ne .. =m nn mmm.a,, . m ._. 2-
- y. -~ _ nre q un m. .,. ...,u u,,,... n u m u .~ -, e
_ _ _ ,. . ..TR" 0 3.4.14 3 TR 2 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 724 TR 3 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 746 1 CPSES No Signi)icant Hazards Consideration - CTS N4.4 1 8/2 M 8
i l IV. SPECIFIC NO SIGNIFICANT HAZARDS.. CONSIDERATIONS NSHC1LS;38 10 CFR 50;92' EVALUATION g.3,4,14 3 F08 g m y % D TECHNICAL: CHANGES,THAT11MPOSEiLESS; RESTRICTIVE LZJ..CC.5 ' tREQUIREMENTS;WITHIN;THE; TECHNICAL SPECIFICATIONS Consistentiwith NUREG;1431,1separateJction_ entry;is.;all.o.wed,for each. flow path _with . excessiveleakage from3CS;PIVs;iAlthough.;this2specifjcationjprovides:aflimit on allowable.PIV.;1eakageirate;?jts main ~ purpose ~1.sito prevent;overpressureifailure of the lo(pressure._ portions __of connecting systems;7The;1eakage;11mit,is an indication that;the^PIVs'between the'RCS:and the; connecting' systems lare degraded or degrading. Eachiflow path is Lallowed separate _ Condition; entry; based upon.the functional independenceiof the flow pathsEThat isT;thefrequired. actions to jsolate:the high pressure _ portions _of the affected flow paths, .in order tojprote;t the connecting low pressure. systems are not affected by leaking'PIVs 'in other flow paths. This proposed TS change has been_ evaluated.and it has been. determined that.it involves no significant hazards consideration. JThis determination has been performed in accordance with the criteria. set forth in 10 CFR 50.92(c) as quoted below:
"The Commission 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) or150.22 or .for aLtesting facil_ity involves _no significant hazards consideration, Lif operation of the _ facility lin accordance with the proposed amendment would not:
- 1. Involve a significant increase in the. probability or consequences of an accident previously; evaluated; Lor
- 2. Create the possibility _.of a new or djfferent kind.of accident from any accident previously, evaluated;1or 3! Involve a significantir. eduction;in a. margin.of saf,ety." ,
The .following evaluatio.n Lis.provided,forithe:three, categorie_s.of the significant haz a rds [consi deration;standa rd s t 12 Doesithe change l involve;,a"signjficantlincreaselin;the probability or consequences;of an;acc_ident;prevjously3 valuated? The~propo. sed _ change" adds l a; rel axati on;to;the LLC 0_byla1.] owi ng ;sepa ra te :Condi ti on entry;forZeach PIV'flowpathUAlthough'this specifjcation.,provides, a limitfon allowableiPIV_le.akage ratedjts; main;purposelis;to_preve.nt oyerpressure failure ofithe low pressuref. portions;of;connectjng.. systems.l;The21eakage? limit.is,,an indication that the;PIVs_,between._the RCSTand thelconne.cting_ systems;are degraded orldegradig. J Ea ch ;fl ow ; path "i s;all owed _ sepa rate,C_ondi tj on ;ent ry . ba sed . uponithe functional _ independence;of;the. flow; paths.3hus thelequited actions,' to isolate the;high; pressure lportionsLof,the affected_ flow l paths;Iin; order.;to.. protect the] _ s CPSES No Significant Ha:ards Consideration - CTS 3N..I 72 8/28/98
l l IVC SPECIFICJ10,.SIGNIFICANTijlAZARDS CONSIDERATIONS 0 3.4.14 3 L (continuedl < connecting: low; press _ure systensfare;notlaffected,bylothet2qaking'PJVsh Thereforel1the proposedichange;doesJot&tnvolye;a.:signi_ficantlincteasejin_the probab11jtyi.or3 consequences 3f;atacej_dentjpteylouslylevaluatedi 21 Doesithe: change; create;the:possib111tyloffalnewlocidifferentJindof accident fromianylaccident;preyjouslyleyaluated_?. Ihe;only; accidents;that1are: potentia]1y_ associated withithjs: proposed change,;are tho.se;related to;theipotentjallfoq[an"jnterfacingisystessiLOCA; causing a, failure of;the9ow;pressur.e: portion lofiaisystes outside;of _. containment .with thelresulting esp. ape;offadioactive~materialEThe: Required Actions 1forithis1LC0;provjde forithe isol_ationfo_f,the f] W, path;withjya]vesithatineeti he t same:1eakage requirements as the1P,IV.sland.whichLaust;be.within:the.RCPB:or:for DCPP and_CPSES'ithe:high, pressure,portionf ofitheisystem;ZThe protection provjded for mthe;]ow pressure . systemicontinues;tolbe;maintainedland,ils;1ndependentioff,the^actionsirequired to Ptot_ect;other: fl owpathsithatimayfal so;be;aff_ected;"1This;changeldoes;not introduce.;any newLoverpres.surelagcjdentslandithalexisting;a.nalyses remain valid. Thus athe proposed; change;does:not:cre.atejthe po.ssibility;of.;a new or different kindlof; accident;from those previous.ly; evaluated.' 3: Does this change;inyolvela significant;r. eduction;in a; margin ofisafety? The.; proposed changeldoesinot f affect 1.the; acceptance;crjteria for any_ m analyzed event;E0y,erpressure; protection:ofgach affected_ low pr_essureisystemicontinues,to be.1 provj ded ,byjealCt.ested;isolatiortyalleslwhichiar_elindependentlof ~ other;fl ow pathsEThe: margin of; safety:establjshediby;the;LC0 temainslunchanged;3Thus"there 1sino;teduction;inJthe;marginJfisafety;from;that previously[ established; ENFEEEEN01SIGNIFICANT; HAZARDS' CONSIDERATION DEIERMI.NAIION Basediog;thelabove eva,]uationZit11siconcludedithatithe2ac_tivitieslass_ocjat_ed31th
!!SHCfLS;38"3resul ting 1from_;thelconvetsloI[tolthelimptoyed3S2formatisatisfyltheino signjfgant;hazardsiconsideratjon;standardslofS0;C_FR _50M2(cMand_accordingly,7a DCsjgnjfjcant1 hazard.sEconsidetation'fjndigg;isgustified]
CPSES No Significant Hat:ards Consideration - CTS 3N.4 73 828/98
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q3.4.15-4 APPLICABILITY: CP, DC . REQUEST: ITS 3.4.15.3 (Comanche Peak and Diablo Canyon) Comment: The SR requires a Channel Calibration of the sump monitors. However, ITS LCO 3.4.15.a only requires one monitor (level and discharge flow) (Comanche Peak) or one monitor system [Diablo Canyon] to be operable. What other monitor (s) is the SR referencing? FLOG Response: For Comanche Peak the CTS title of the subject monitor is the " Containment Sump Level and Flow Monitoring System." The ITS markup for the sptem title is not quite accurate and will be revised to reflect the verbatim CTS title. The revised SR 3.4.15.3 will become " Perform CHANNEL CAllBRATION of the required Containment Sump Level and Flow Monitoring System." Also the Bases will be revised to better describe the system. For Diablo Canyon, each of the three containment sumps into which unidentified leakage can flow has its own monitor. The sump monitoring system is made up of the three individual monitors. The surveillance requirement applies to each of them. ATTACHED PAGES: EnciSA 3.4-40 and 3.4-43 Enci5B B 3.4-74, B 3.4-87, B 3.4-88 and B 3.4-90
RCS Leakag@ Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation t LC0 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:
- a. 0 'ein cr1 su;;;p (levci or and disch;rgc -0 3 4.15 4 anitor Containment.; Sump;Levellandflow Monitorjng System:
- b. One containment atmosphere particulate radioactivity 3.4f14M monitor (ga:ccus or particulate'; and
- c. One containment air cooler condensate flow rate monitor or one_lcontainmentiatmospher_e radioactivity monitor
$34s141j i
(gaseous); APPLICABILITY: MODES 1. 2, 3. and 4. l l l ACTIONS HIEi-;idi-3 NOTE-jXiHHHi-; . LC0;3.0j4;is.;not , applicable; 13i4?l53
==.= =:=:. :::. = .=
CONDITION REQUIRED ACTION COMPLETION TIME A. RemH raAcat;in; cat NOT[- PS eu;;;p ;;;cnitor Containment LCO 3.0.4 is not applicable- 0 3.4.15 4
~
Sjajip312eEanU.5c5 "m-*< System ' R33915M inoperable. A.1 E-y,'ZE-MEIEEis51Y5 NotZreguj_redJntjE121hou.rs after_,Jestablisheent~of (Si4336j$ steady 3 tate; operation!
-i =' < .cg 25 Perform SR 3.4.13.1. Once per 24 hours b.NQ A.2 Reitore Icnt ; ump 30 days PS (cnitorContaWent'hSump LevellandYlo#Noiiit 0 3.4.15 4 Syst_egtoOPERABLEstatus.
CPSES Mark-up ofNUREG-1431 -ITS 3.4 3.4-40 8/2888
RCS Leakage Detection Instrumentation 3.4.15 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.15.1 Perform CHANNEL CHECK of the required 12 hours containmentatmosphereparticulate2and; gaseous 13'.~4K4hl radioactivity monitors. SR 3.4.15.2 Perform COT of the required containment 92 days atmosphere particul_ ate;and, gaseous !3/4-714 11 radioactivity monitors.
#B'fi SR 3.4.15.3 Perform CHANNEL CALIBRATION of the required 18 months ntainment; sump,LeVe Landflow Monitor2 1ng 1 p3 Systeg containa ,t su;;;p r,cnitees. o.3.4.15-4 2374342 l l 3115;ji SR Perform CHANNEL CALIBRATION of the required 18mmonths Ed containmentatmospherepajigulateland; gaseous radioactivity monitors _.
R3 ~@fil l SKjT3;(;353 Perform CHANNEL CALIBRATION of the required 18; months $j l containment air cooler condensate flow rate monitor, l CPSESMark-up ofNUREG-1431 -ITS3.4 3.4-43 8/28/98 l i
RCS Operational LEAKA".E B 3.4.13 BASES No pressure boundary LEAKAGE is allowed, being indicative of material deterioration. LEAKAGE of this type is unacceptable as the leak itself could cause further deterioration, resulting in higher LEAKAGE. Violation of this LC0 could result in continued degradation of the RCPB. LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE.
- b. Unidentified LEAKAGE One gallon per minute (gpm) of unidentified LEAKAGE is allowed as a reasonable minimum detectable amount that the enntainment air monitnMnn anzhn::: cat kvc; (fitoring cqug;; cat Containment %nnnlevel ~and F1 0-3.4.15-4 Monitoring'Systepfcan armt within a reasonable time period. vloiation of C LLO could result in continued degradation of the RCPB, if the LEAKAGE is from the pressure boundary.
- c. Identified LEAKAGE Up to 10 gpm of identified LEAKAGE is considered allowable because LEAKAGE is from known sources that do not interfere with detection of id ntified _un' witified; LEAKAGE and is well within the capability of ths RCS Makeup System.
Identified LEAKAGE includes LEAKAGE to the containment from specifically known and located sources, but does not include pressure boundary LEAKAGE or controlled reactor coolant pump (RCP) seal leakoff (a normal function __ ~ not considered __,.u.-,_. LEAKAGE). !dcati'iciV.!YJ.CE m__- ,___~___ ,___ _ , u _-r._ ,__, l03.3.133 "ES"Wi31"ES"E"EM"Mi"r"IMidErI"TII"!
" zee """MI"It NIE",,%"*"O!difY"',"ll""C"ITII" IE"MOl'E"d' ICE"1?IIO15"2""Mi'+I' fSEII"'3. d
' ' d "'"2" I'"'"i" "ki*iCM&CIIC2d"T" 'i""f,:~~ Violation ym-reamy-a-awymm ~uw.uvvu
~-
of this LC0 could result in continued degradation of a component or system. Primary to Secondary LEAKAGE throuab All Steam Generators (SGs) Total primary to secondary LEAKAGE amounting to 1 gpm through all SGs produces acceptable offsite doses in the Ste-accident analysis. Violation of this LC0 could exceed the offsite dose limits for this accident. Primary to secondary LEAKAGE must be included in the total allowable limit for identified LEAKAGE. (continued) CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-74 8/28/98
_ _ . - _ _ _ _ _- _ _. . ._ _ __ _ . . ~. RCS Leakage Detection Instrumentation B 3.4.15 i BASES APPLICABLE The need to evaluate the severity of an alarm or an indication is l SAFETY ANALYSES important to the operators, and the ability to compare and verify l (continued) with indications from other systems is necessary. The system response times and sensitivities are described in the FSAR (Ref. 3). Multiple instrument locations are utilized, if needed, to ensure that the transport delay time of the leakage from its source to an instrument location yields an acceptable overall response time. The safety significance of RCS LEAKAGE varies widely depending on its source, rate, and duration. Therefore, detecting and moritoring RCS LEAKAGE into the containment area is necessary. Quickly separating the identified LEAKAGE from the unidentified LEAKAGE provides quantitative information to the operatcrs, allowing them to take corrective action should a leakage occur detrimental to the safety of the unit and the public. RCS leakage detection instrumentation satisfies Criterion 1 of the NilC "clicy Statc cat.10CFR50.36(c)(2)(ii). LCO One method of protecting against large RCS leakage derives from the ability of instruments to rapidly detect extremely small leaks. This LC0 requires instruments of diverse monitoring principles to be OPERABLE to provide a high degree of confidence that extremely small leaks are detected in time to allow actions to place the plant in a safe condition, when RCS LEAKAGE indicates possible RCPB degradation. The LC0 is satisfied when monitors of diverse measurement inam -= available. Thus.JLtEntain: cat acnn-- 0-3.4.15-4 60ntainsegSump_i.evehana FJoW Monitoring:Syste[in m . . m . v. , ,, nc. o . . .. cr particulate raoicactivity monitor end;eithetDEcont.ainmentyair,7 cooler'condensatelflow rate monitor 3nta gagtourradjoactfvitymmonitog provide an acceptable minimum. APPLICABILITY Because of elevated RCS temperature and pressure in MODES 1,
- 2. 3, and 4 RCS leakage detection instrumentation is required to be OPERABLE.
In MODE 5 or 6, the temperature is to be s 200'F and pressure is maintained low or at atmospheric pressure. Since the temperatures and pressures are far lower thar. those for MODES 1, 2, 3, and 4, the likelihood of leakage and crack propagation are much smaller. Therefore, the requirements of this LC0 are not applicable in H0 DES 5 and 6. CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-87 8/2888
RCS Leakage Detection Instrumentation l l B 3.4.15 BASES ACTIONS Actionrar0modifjed; byXNote :thatMndicatesithatrthe;ptoyi sjo!1s of3C0f310Melnotiapplicab' eNa'resultarMODEtchange iW- ? --t-i ?TXi;lii6t;i. 4.. . -.a; contal-my^ l 7 Levelland ;FjoOogitoting Jysten@uwwrea o.3.4.15-4 I aMwmermuims6.. ,Aw1redfatmospheric gaseousimonitorjonthelrequirediai ricooleticondensate;f]ow ratr monitornare;1nopetableMThista]10wanceits.;provided because;ottlerlinstrumentation;js;availabl_ejto;nonitor;RCS leakage! A.1 and A.2 With tha reauir~d fain; cat acnitor Containment $ Sump 3eM 0-3.4.15-4 f dFlow Monitorina'Svstem invperauie, no o wer Torm or sampling can provide the equivalent information: however, the containment atmosphere radioactivity monitor will provide indications of changes in leakage. Together with the atmosphere monitor, the periodic surveillance for RCS water inventory balance, SR 3.4.13.1, must be performed at an increased frequency of 24 hours to provide information that is adequate to detect leakage. A note 21siadded; allowing thatl.SR!3:4;13;111sEnot requiredito;beJperformed;until?l2; hours _after estab11shing: steady state ;operationMlasidefinedlin;.theJas.es;of SR 14.13l.1) .1 9I;D1;SCEpf50^uisiUt_=r;i.5 tut; .N;Ia l;M;lCpE;;;4EN;I 0-3'4'13-4 OK;;k;;pDi43;E;DC;;4;;plifl;td;W GoGCC;;;l ' injccticalendl;tuta ;fi cwslsiThe;12 ; hour, allowance; provides sufficientitimeito:collectiand process necessary data;after stabl e _ pl antigonditionsIar,eAstabl i shed i Restcratinn of the raMd.p monitor ContainmantM (Ciivel:and Flow Monitoring' Systema CRnXDLL status within a 0-3.4.15-4 completion ilme or 30 days is required to regain the function after the monitor's failure. This time is acceptable, considering the Frequency and adequacy of the RCS water inventory balance required by Required Action A.1. Required Action A.1 is ;;dificd by : Note that indicates that the provisions of LCO 3.0.4 crc not opplicabic. As ; rr.sult, ; ."00E changc is allowed whcn the i;;3jrgy contain cat sump acnitor is inoperabic. This clicwcacc is provided becausc cthcr 4nstru :catation is availabic to acnitor RCS ic;kagc. B.1.1. B.1.2. and B.2.1. and S.2.2 With both gascous and the particulate containment atmosphere radioactivity monitoring instrumentation channels inoperable, alternative action is required. Either grab samples of the containment atmosphere must be taken and analyzed or water inventory balances, in accordance with SR 3.4.13.1, must be performed to provide alternate periodic information. With a sample obtained and analyzed or water inventory balance performed every 24 hours, the reactor may be operated for up to 30 days to allow restoration of the required containment CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-88 8/2888
RCS Leakage Detection Instrumentation B 3.4.15 : BASES ACTIONS CT17C?1723C?271?and C^2 2Mcontinned) I are thohtain;;nt ;;;;; r,mnit;r ContainmentitSURD7LevelrpfEF 0-3.4.15-4 McW Mont:orina'Svsh e mmem;ahyng;al:EgspiEj3 patticula<:ezadloacDe'monitorj This Condition does not provide al]. the required diverse means of leakage detection. With:both_.gaseonsicontainmentfatmosphere2adioactjvity:monjtoting and; containment 31 ricoo]ericondensatelflow Iateleonitoring
.instrumentatjon: channel s;1_noperable rialternatjve ~ action.11s f required. & Eitherigrabisamplesjof.the;containmentLatmosphere_sust be:taken;and: analyzed:orJwateriinvent. pry;bal ances ;;1n ~accordance
! with SR;3;4.13;1,7,must;be; performed ,to; provide;alternatef petjodic i l information. l l Thefo]lowupRequiredActionistorestoreeitherofthe l
- inoperable required monitors to OPERABLE status within 30 days to l regain the intended leakage detection diversity. The 30 day i Completion Time ensures that the plant will not be operated in a reduced configuration for a lengthy time period.
l A note ~js.!added; allowing;that SR;3.4.13eljs_not required to be performed.,unt11 12; hours afteriestablishing steadyjstate operation 3st_able:RCS;pr.essurentemperaturejpowerl lev _e)l pressuriz_erland makeupjtankilevels'1makeupland;)etdown2and;RCR sealiinjectionlanpfeturnjflows), dThejl2 houriallowance:provides suf ficient, timelto: coll ect ;and; processinecessary;da_ta;after stablef plant; conditions 'arelestablished.: ED.1 and E[L2 h 0 3.4. Gen 1 f If a Required Action of Condition A, B ot C ee-O cannot be i met, the plant must be brought to a H0DE in which the l requirement does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours and to MODE 5 within 36 hours. The allowed Completion Times are reasonable. l based on operating experience, to reach the required plant it conditions from full power conditions in an orderly manner and without challenging plant systems. r L EfL1 o st L. l With means all required of monitoring monitor leakage [a:em[ and 09ailable, inoperable, immediate plant no automatic 0-3'4'15-4 ' l shutdown in accordance with LCO 3.0.3 is required. l l CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 8 3.4-90 8/28/98 I
l ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: Q3.4.16-1 APPLICABILITY: CA, CP, DC, WC REQUEST: Difference 3.4-39 Comment: TSTF-113 has not yet been approved by the NRC staff. l FLOG Response: See response to Comment number 3.4.11-3 ATTACHED PAGES: . l l None 1 i I 1 l l l I l r t l l l i l
~
ADDITIONAL INFORMATION COVER SHEET i ADDITIONAL INFORMATION NO: Q3.4.G-1 APPLICABILITY: CP REQUEST CTS 3.4.8.2 and Change 9-05-R (Comanche Peak) Comment: The CTS Cross Reference Table shows this specification is relocated to the FSAR. Since this is an operational requirement shouldn't it be in the PTLR or a plant procedure? FLOG Response: The Cross Reference Table was in error. The correct location is the TRM as indicated in enclosure 3B. The TRM contains operational requirements and is the appropriate location. The Cross Reference Table will be revised accordingly. ATTACHED PAGES: Enct 1 4 (Sorted by Current TS) ~ l l
J l l Page 4 Table 4.41 ITEM 4.a 3.4.16 ACTION A.1 Table 4.41 ITEM 4.a 3.4.16 CONDITION 8 Table 4.4-1 ITEM 4.a 3.4.16 ACTION B.1 Table 4.4-1 ITEM 4.b 3.4.16.2 SR 3.4.8.1 LC0 3.4.3 LC0 3.4.8.1 LC0 Relocated PTLR 3.4.8.1 ACTION 3.4.3 CONDITION A 3.4.8.1 ACTION 3.4.3 ACTION A.2 3.4.8.1 ACTION 3.4.3 CONDITION B 3.4.8.1 ACTION New 3.4.3 CONDITION C 4.4.8.1.1 SR 3.4.3.1 SR 4.4.8.1.2 SR Relocated FSAR Figure 3.4 2 Relocated PTLR Figure 3.4 3 Relocated PTLR Table 4.4 2 Relocated FSAR 3.4.8.2 LLv Relocated FSAR;TRM 3.4.8.2 ACTION Relocated FSAR-TRM U% Q 3.4.G 1 4.4.8.2 SR Relocated FSAR-3.4.8.3 LCO 3.4.12 LC0 3.4.8.3 LCO a 3.4.12 LC0 3.4.8.3 LC0 a Relocated FSAR 3.4.8.3 APP 3.4.12 APP 3.4.8.3 ACTION a - 3.4.12 CONDITION E 3.4.8.3 ACTION a 3.4.12 CONDITION G 3.4.8.3 ACTION b 3.4.12 CONDITION F 3.4.8.3 ACTION b 3.4.12 CONDITION G 3.4.8.3 ACTION c 3.4.12 CONDITION G 3.4.8.3 ACTION d 3.4.12.5 SR 3.4.8.3 ACTION e Not Used 3.4.8.3 ACTION f 3.4.12 ACTION Note 3.4.8.3 ACTION New 3.4.12 CONDIT0N B 3.4.8.3 ACTION New 3.4.12 CONDTION G 3.4.8.3 ACTION New 3.4.12 CONDTION C 3.4.8.3 ACTION New 3.4.12 CONDITION D 3.4.8.3 ACTION New 3.4.12 CONDTION G 3.4.8.3 ACTION New 3.4.12 CONDITION G 4.4.8.3 SR New 3.4.12.3 SR 4.4.8.3.1 SR a 3.4.12.8 SR 4.4.8.3.1 SR b 3.4.12.9 SR
- l. 4.4.8.3.1 SR c 3.4.12.6 SR
! 4.4.8.3.2 SR a 3.4.12.4 SR 4.4.8.3.2 SR b 3.4.12.4 SR 4.4.8.3.2 SR c 5.5.8 l l 4 l l I L
a . . + - e - a, -a .: ~ - - - m +-A a A 2 ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: CA 3.4-004 APPLICABILITY: CA, CP, DC, WC REQUEST: This item covers the following changes:
- 1. Revise ITS 3.4.14 (and corresponding CTS mark-ups) to reflect that the RHR suction isolation valves from the RCS are remote-manual, not automatic. (Not applicable to DCCP, WCGS and CPSES)
- 2. Define an OPERABLE RCP in ITS 3.4.4 LCO Bases as defined in ITS 3.4.5 and 3.4.6 LCO Bases.
- 3. Revise the ITS 3.4.9 Bases for Required Action A.3 to n~.'/.::h the Bases changes made for ITS 3.4.5 Required Action C.2 per approved traveler TSTF-87 with regard to ways to make the Rod Control System incapable of rod withdrawal.
- 4. Revise the Applicability Bases for ITS 3.4.10 to reflect the change to the Note in Enclosure SA under JFD 3.4-18, i.e., the Note allows entry into MODE 3. MODE 4 should be struck-through as it was in Enclosure SA since the pressurizer safety LCO is not applicable in MODE 4. (Not applicable to DCCP, WCGS and CPSES)
ATTACHED PAGES: Enci 5B B 3.4-19 and B 3.4-42 l l
1 RCS Loops-MODES 1 and 2 B 3.4.4 BASES (continued) APPLICABLE The plant is designed to operate with all RCS loops in operation SAFETY ANALYSES to maintain DNBR above the 1_init;value, during all normal 1 (continued) operations and anticipated transients. By ensuring heat transfer i in the nucleate boiling region, adequate heat transfer is ! provided between the fuel cladding and the reactor coolant. ' RCS Loops-MODES 1 and 2 satisfy Criterion 2 of the NRC Policy Statc; cat. 10CFR5_0.36(c)(2)(ii)] LC0 The purpose of this LC0 is to require an adequate forced flow rate for core heat removal. Flow is represented by the number of ! RCPs in operation for removal of heat by the SGs. .To meet safety ! analysis acceptance criteria for DNB, four; pumps are required to i be;in . operation at reted-power. 1 i An OPERABLE RCS loop consists of an OPERABLE RCP in operation i providing forced flow for heat transport and an OPERABLE SG in accordance with tho etn2= r^r-?^- Tuha Surveillance s ' Procram >'An RCPfis .0PERABLE11fritlis; capable;ot Deing CA 3.4 004 l ) { power _edf and isiableito:providej, forced flow; j j j APPLICABILITY In MODES 1 and 2, the reactor is critical and thus has the potential to produce maximum THERMAL POWER. Thus, to ensure that 4 the assumptions of the accident analyses remain valid, all RCS l loops are required to be OPERABLE and in operation in these MODES , to prevent DNB and core damage. The decay heat production rate is much lower than the full power heat rate. As such, the forced circulation flow and heat sink requirements are reduced for lower, noncritical MODES as indicated by the LCOs for MODES 3, 4, and 5. j Operation in other MODES is covered by: 1 LC0 3.4.5, "RCS Loops-MODE 3"; LC0 3.4.6 "RCS Loops-MODE 4"; l LC0 3.4.7, "RCS Loops-MODE 5. Loops Filled": LC0 3.4.8, "RCS Loops-MODE 5. Loops Not Filled": LC0 3.9.5, " Residual Heat Removal (RHR) and Coolant Circulation-High Water Level" (MODE 6); and LC0 3.9.6, " Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level" (MODE 6). l l 1 i (continued) CPSESMark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-19 828/98 J
Pressurizer BASES B 3.4.9 cooldown to avoid rapid pressure rises caused by normal operational perturbation, such as reactor coolant pump startup. In H0 DES 1, 2, and 3, there is need to maintain the E-3'4 002 availaMlity of pressurizer heaters, capable of being powered from offsiteEpoweriorZan emergency power supply. In the event of a loss of offsite power, the initial conditions of these MODES give the greatest demand for maintaining the RCS in a hot pressurized condition with loop subcooling for an extended period. For MODE 4, 5, or 6, it is not necessary to control pressure (by heaters) to ensure loop subcooling for heat transfer when the Residual Heat Removal (RHR) System is in service, and therefore, the LC0 is not applicable. ACTIONS A.1 and A.2 ?A~.3~and'A 4 Pressurizer water level control malfunctions or other plant evolutions may result in a pressurizer water level above the nominal upper limit, even with the plant at steady state conditions. Normally the plant will trip in this event since the upper limit of this LC0 is the same as the Pressurizer Water Level-High Trip. If the pressurizer water level is not within the limit, action must be taken to restorebring the plant to aiH00E71nyhich the LC0idoes;nottapplygoperation within the bour.ds of the safety analyscs. To achieve this status, within:6 hogs the unit must be brought to MODE 3. Withr a llTrodsefullrinserted~and in_c_apable 2of Withdrawal /Fe,;.gNideenergize_al
- t. Mums,Dy CA 3.4 004 ropen1ng tne uitss or.oe enerairinn the motor generatorMHG sets J aaj nopa,ijy gthelunjtjmust be L b.rougnt Inc , cr m ip brackers open, within 5 hours and to MODE 4 within 12 hours.
This takes the unit out of the applicable MODES. and restorcs the unit to cpcration within the bounds of the safety analyscs. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. IL1 If one required group of pressurizer heaters is inoperable, restoration is required within 72 hours. The Completion Time of 72 hours is reasonable considering the anticipation that a demand f0Cimor,e;tharEone: group;ofiheaterscausedbylossofoffsite pcwcr would be unlikely in this period. Pressure control may be maintained during this tiac using normal station powcred heateft CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-42 8/28/98
ADDITIONAL INFORMATION COVER SHEET ; I ADDITIONAL INFORMATION NO: CP 3.4-004 APPLICABILITY: CP REQUEST: Revises the Bases discussion of SR 3.4.1.4 to clarify the meaning the SR note conceming " not required to be performed until...". ATTACHED PAGES: Encl. SB B 3.4-6
RCS Pressure. Temperature, and Flow DNB Limits B 3.4.1 BASES todicationifocithirpatame_terji_ndicatesiinipercenti(3) .3.The value in;*1thatM]Eassure;compljance3rithithelgjpjeumfotal floc 11mit21rCthe:SRiis; determined; based;on;;the )easured1RCS totaLf1EfromlSRW41114'.3Followjngieachlrefueling cutage:and PClottoltheicompletionlofxSR13:4.1;4,1thelyaluelinLitused to assure. comp 11anceMth:thelminimum'.RCSJtotallfloQsbased:upon the;measutediRCS2totp1] floc (SR;3 t411:4);'fton_;the; prev.1ous operating; cycle:grllanJalternat.eimeasurementiandiassessmentigf i actual:RCSitota]Zflow] SR 3.4.1.4 Heasurement of RCS total flow rate by performance of a precision calorimetric heat balance once every {48318 months (afterjeach r.efueling) allows the installed RCS flow instrumentation to be calibrated norma]jzed and verifies the actual RCS flow rate is greater than or equal to the minimum required RCS flow rate. The Frequency of {4B} 18 months reflects the importance of ; verifying flow after a refueling outage when the core has been altered, which may have caused an alteration of flow resistance. This SR is modified by a Note that allows entry into MODE 1, without having performed the SR, and placement of the unit in the best condition for performing the SR. The Note states ttat the SR is~nct -H " he cerforr? "ilInot.Jequireh - o.be performed;unti1^after exceedina 85% RTP after'!each j CP 3.4 004 refuelina'outagera hours n'tr f00tl"T" g,scA y ilpr;Rprior ;c cacccCin; 05: "7 Mtcr'c;ch~Tcf # ing /
.ui; cxcepica is oppropr etc sincc tnc ncet 0;;;nce ry o ss thc pl:nt to bc at ; mini;;;um of [00!] "T" to obtain the stated "CS fl;w occuracies. The Surveillance :h:11 bc grfor;;;cd within 24 hours aftcr reaching [00!] ",T".;Usinf ptecision instrumentatjonNjtEmul tiple'indicationQt_he: stated ECSiflow accuracy;may_belattained at3powettlevelsIs.1gnificantly;below15*
RTP 2asidesctibedlinJthe runcettaj ntyJanalysesEiRequi ting ?the preci sionfflow; measurement 3tolbe; performediptiorito;85t"RTP allowsiforzalsingle te_ sting;plateaulto~t(usjgLtolpetformithe3CS , flow measurement 3mtvatiotts.*other; tests;desettbedzin i S,ection1312?Jftecedure_s2 teguj re;that$t.heHHERMAL1 POWER l i available11nstrumentationzandicaljbrattonlintety_alsihe sufficiegtito" ensure),that 3he; stated.;RCS3floWaccuracy11s attained 2fforffeedwaterjpre.ssure3ndjt_mperatuteRthe;mainfsteam e . pressureZand ~ fee'dnaterjfl anrdi ffetentia:1Jpressure; instruments l are:caljbrated31.thjn190; days of!perfigraingithe;galorjmetrjgifloW I measurementi REFERENCES 1. FSAR Section 15. CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-6 8M8/98
i l ADDITIONAL INFORMATION COVER SHEET l l ADDITIONAL INFORMATION NOs: TR-3.4-004 APPLICABILITY: CA, CP, DC, WC TR-3.4-005 TR-3.4-006 TR-3.4-009 l REQUEST: Revise the Traveler Status Sheet to reflect that TSTF-54 Rev.1, TSTF-87 Rev. 2, i TSTF-136, TSTF-137, TSTF-153, TSTF-162, and TSTF-233 (was WOG-67) are approved by NRC. Add Rev.1 to TSTF-94 and TSTF-151. ATTACHED PAGES: Encl. 5A Traveler Status pages (2) Encl 6A 5 ( Encl 68 4 l. l 4 f f
- . . - - - . . - . - . . . - - ~ - . _ ._
INDUSTRY TRAVELERS APPLICABLE TO SECTION 3.4 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF 26 Incorporated 3.4-32 Approved by NRC. TSTF 27. Rev.3 0 Incorporated 3.4 33 Approved;byJRC 0 3.4.2 1 TSTF-28 Incorporated 3.4 22 Approved by NRC. TSTF 54. Rev. 1 Incorporated NA pprov_ed;by;NR b m 3.4 009 TSTF 60 Incorporated 3.4 15 Approved by NRC. TSTF 61 Not incorporated NA Minor change that is adequately addressed in the Bases. TSTF 87 Rev. Incorporated 3.4 31 [ Approved;by;N m .3.4 oc4 TSTF 93, Rev. 31 Incorporated 3.4 17 Approved by;NRC. 03.4.9: TSTF-9cRev;(_ Not incorporated NA Retained current TS. j m 3.4 Oc5 TSTF 105 Ir.ccrporated &:448 0 3.4.1 1 l TSTF 108, Rev. 1 Not incorporated NA LC0 3.4.19 does not apply. TSTF 113. Rev. 4 Incorporated 3.4 39 0 3.4.11-: l v - TSTF 114 Incorporated NA Approved by NRC. TSTF 116, Rev.2 Incorporated 3.4 36 03.4.132 1 TSTF 136 Incorporated NA 4 Jyediby ig.3,4.gog l TSTF 137 Incorporated NA h"rovedibyJR m.3.4-005 l l l l TSTF 138 Not incorporated NA Inconsistent with RCS loops requirements of ITS 3.4.5 and 3.4.6.
TRAVELE.Rf S.IAII!S DIFFERENCE # COSINIENTS TSTF151_evgh Incorporated NA TR 3.4 00$ TSTF 153 Incorporated 3.4-01 oved,by:NRC - TR 3.4 005 k TSTF 162 Incorporated NA proved.by;NRCd TR 3.4 0C6 A WOC 51. Rev.1 Incorporated 3.4 45 & See also CNs 3.418 and 0 3.4 12-2 TSTF 285 3.4 0352 3.4 20. WOG-60 Incorporated 3.4 35 ,, TSTFi288 o 3.4.11 2 ) [57.Rcv Incorporated 3.4 10 only. byNRC)DCPP l TSTF,:233 TR 3.4 009 C / WOG 87 Rev.l2 Incorporated 3.4 47 Q 3.4.11-4 WOG-99 Incorporated 3.4 40 Applicable to Callaway and TSTFf282 Wolf Creek only. a 3.4.1 2 WOG-100TSTF 280 Incorporated 3.4-49 0 3.4.12-1 I 1
)
l 1 J
i' l CHANGE NUMBER JUSTIFICATION gross specific activity limit is added to LC0 3.4.16 Condition B rather than its first reference being in SR 3.4.16.1. This is also consistent with the treatment of DOSE EQUIVALENT I-131. 3.4 26 Not applicable to CPSES. See Conversion Comparison Table (enclosure 68). 3.4 27 Not applicable to CPSES. See Conversion Comparison Table (enclosure 68). 3.4 28 Not applicable to CPSES. See Conversion Comparison Table (enclosure 6B). 3.4 29 Not applicable to CPSES. See Conversion Comparison Table (enclosure 6B). 3.4-30 An exception is added to the Actions for LC0 3.4.12 This is consistent with the current licensing basis. Additionally, circumstances could arise where increasing MODE would reduce the risk of a low temperature overpressurization event. In these cases it would be unwise to maintain the plant in a lower MODE configuration. Increasing plant MODE may also be the expedient way to exit a low temperature over pressurization potential when operating within a Condition. This option should be retained as exist in the current Technical Specifications. 3.4 31 These ACTIONS in ITS 3.4.5 and 3.4.9 are modified to reflect their LCO. The position of the reactor trip breakers and the power supply status of the CRDMs are not LC0 requirements; therefore CONDITIONS and ACTIONS are revised. As worded in NUREG 1431 Rev 1, these ACTIONS could preclude certain testing in MODE 3. A more generic action, which assures the rods cannot be withdrawn, replaces the specific method of precluding rod withdrawal. The specific methods are added to the Bases as examples. The revised ACTIONS still assure rod withdrawal is precluded and this detail is not required to be in the TS to provide y .3,4.ao4 adequate protection to the public health and safety. No technical changes result from this e.Thesej changes are consistent with TSTF-8 . l 3.4 32 In accordance with industry traveler TSTF 26, the ACTION would be changed to specify taking the plant to a MODE for which the LC0 is not applicable. This change maintains the consistency between the Mode of Applicability and the Required Action which requires the Mode of Applicability to be exited. i CPSESDifferencesfrom NUREG-1431 -ITS3.4 S 8/28/98
~l
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431 - SECTION 3.4 4 or6 DIFFERENCE FROM NUREG-1431 APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON C0HANCHE PEAK WOLF CREEK CALLAWAY 3.4-27 Applicability for LCO 3.4.12 H0DE 6 is revised to include an additional Yes No No No qualification if the head closure bolts are not fully detensioned, per DCCP CTS. 3.4-28 This change adds a DCPP specific description of a secured open valve. Yes No No No 3.4-29 The use of Channel Functional Test (CFT) would be retained from the Yes No No No current DCPP TS to the improved TS. 3.4-30 An LCO 3.0.4 exception is added to the Actions of LCO 3.4.12 No - This change Yes Yes Yes is out of scope for DCPP 3.4-31 Condition C and REQUIRED ACTION D.1 of ITS 3.4.5 and Condition A of ITS Yes Yes Yes Yes
-3. N 3.4.9 are modified to reflect generic wording to assure that the rods are fully inserted and cannot be withdrawn. This change is consistent with TSTF-8 M r 3.4-32 In accordance with industry traveler TSTF-26. the ACTION would be Yes Yes Yes Yes changed to specify taking the plant to a H0DE for which the LCO is not applicable.
3.4-33 The Frequency of SR 3.4.2.1 is changed to "12 hours". This change is Yes Yes Yes Yes based on industry traveler TSTF-27. 3.4-34 Retains CPSES current TS which requires that the precision RCS flow No Yes No No measurement be performed prior to exceeding 85% RTP. 3.4-35 Adds a note to SR 3.4.11.1 and SR 3.4.11.2 stating that the SRs are Yes Yes Yes Yes only required to be performed in Modes 1 and 2. 3.4 36 SR 3.4.13.1 and ACTIONS for LCO 3.4.15 are revised with the addition of Yes Yes Yes Yes a note per TSTF-116. 3.4-37 The primary to secondary leakage limits are revised per Callaway OL No No No Yes Amendment No. 116 dated October 1. 1996. CPSES Conversion Comparison Table -ITS 3.4 808/98
ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: WC 3.4-001 APPLICABILITY: CP, WC REQUEST: ITS LOC 3.4.8, Note 1.a. is revised to "at least 10*F" consistent with CTS 3.4. i.4.2. Note 1.a. is a bracketed ([]) note in NUREG-1431, therefore, this change is incorporating CTS inside the brackets. ATTACHED PAGES: Encl. 5A 3.4-17 i I i
RCS Loops-MODE 5. Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops-MODE 5 Loops Not Filled LC0 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.
............................N0TLS -- - - - .
- 1. All RHR pumps may be dc cacrgiced removediftonioperation s3&02]
for s 15 ;;;inutes when switching frc;;; onc loop to cacthcr 1 hout provided: ?3.4039
- a. 'coref outlet 3emperaturelis;maintal at [B M
...eas . 0%i.bels:saturationitempera g.3,4. oat
- b. No operations are permitted that would cause a reduction of the RCS boron concentration: and
- c. No draining operations to further reduce the RCS water volume are permitted.
- 2. One RHR loop may be inoperable for s 2 hours for surveillance testing provided that the other RHR loop is OPERABLE and in operation.
APPLICABILITY: MODE 5 with RCS loops not filled.
;====m_w_.
_mm ::= ._,._==,,N_ OLE. _=.n_=_=., w.r==:== =:=: Wh.11eitttisfL_C0;isIgotleetTAgtry11ntoJ!0DEj 53ooMlNot2111ed fromJ0DEigggpffjl]M21 s*%tIpermittedj 23'
^ W$
ilL.x55 55125E~31=EDi k :55215 M z2d:1EE5il ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop inoperable. A.1 Initiate action to restore Immediately RHR loop to OPERABLE l status. i-l 4 (continued) l CPSESMark.up ofNUREG-1431 -ITS3.4 3.4-17 8/2888 i i l .
1 l ADDITIONAL INFORMATION COVER SHEET l ADDITIONAL INFORMATION NO: WC 3.4-002 APPLICABILITY: CA, CP, DC, WC l REQUEST: Clarify ITS 3.4.9 Applicability Bases to state the pressurizer heaters are capable of being powered from either the offsite power source or the emergency power supply. ATTACHED PAGES: Encl. 5B B 3.4-42 l l l l l-l l l l
l Pressurizer BASES B 3.4.9 cooldown to avoid rapid pressure rises caused by normal operational perturbation, such as reactor coolant pump startup. In H00ES 1, 2, and 3, there is need to maintain the wc.3'4 002 availability of nrautiri7ar heaters, capable of being / powered from6ffsite~poWr4crgn emergency power supply. In the event of a loss or orrsne power, the initial conditions of these MODES give the greatest demand for maintaining the RCS in a hot pressurized condition with loop cubcooling for an extended period. For H00E 4, 5, or 6, it is not necessary to control pressure (by heaters) to ensure loop subcooling for heat transfer when the Residual Heat Removal (RHR) System is in service, and therefore, the LC0 is not applicable. ACTIONS A.1 end A.2J"A;3 and'A.4 Pressurizer water level control malfunctions or other plant evolutions may result in a pressurizer water level above the nominal upper limit, even with the plant at steady state conditions. Normally the plant will trip in this event since the upper limit of this LC0 is the same as the Pressurizer Water Level-High Trip. If the pressurizer water level is not within the limit, action must be taken to restorebring the plant to aLH0DErin whichithe LCO,doesinot applyRcperation within the bounds of the safety analyscs. To achieve this status, within;6: hours the unit must be brought to MODE 3,1[ tith?allirods5 fully 3 inserted;and incapablelof Sithdrawa) (e!g;n defenergize alliCRDHs_by CA 3.4 004 opening;theJTBslor ~;defenergizingithelmotor[ generator ,(MG), sets).MdditjonallyZ.theJunit;mustibe, brought the reactor trip brcakers opca, within 5 hours and to MODE 4 within 12 hours. This takes the unit out of the applicable MODES. and restorcs the tmit to operation within the bounds of the safety analyscs. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. Ed If one required group of pressurizer heaters is inoperable,
. restoration is required within 72 hours. The Completion Time of 72 hours is reasonable considering the anticipation that a demand fot;nore;thanloneigroup'ofiheaters caused by loss of offsite powcr would be unlikely in this period. Prcssure control may bc
- maintained during this tiac using-f crmal station pawcred heatcrs.
l l CPSES Mark-up ofNUREG-1431 Bases -ITS 3.4 B 3.4-42 8/2888
_ .. __._ . _ _ .- .___. _ _ - . ~ . . _ . _ . . _ _ . _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ ..-_ _ _ Attachment 2 to TXX-98208 Page 1 of 4 l - i JLS CONVERSION TO IMPROVED TECHNICAL SPECIFICATIONS CTS 6.0 - ADMINISTRATIVE CONTROLS ITS 5.0 - ADMINISTRATIVE CONTROLS RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION AND LICENSEE INITIATED ADDITIONAL CHANGES i
. - - . . . - . - . - - . - . - . . - - . - . _ . _ ~ ~ . _ - _ . _
l
- Attachment 2 to TXX-98208 Page 2 of 4 l -
INDEX OF ADDITIONAL INFORMATION , ADDITIONAL INFORMATLQN APPLICABILITY ENCLOSED NUMBER 5.1-1 CA NA 5.2-1 CA, CP, DC, WC YES 5.3-1 CA, DC, WC NA 5.5-1 CA,DC NA 5.5-2 CA, CP, DC, WC YES 5.5-3 CA, CP, DC, WC YES 5.5-4 CA, CP, DC, WC YES 5.5-5 CA NA 5.5-6 CA NA 5.5-7 WC NA 5.5-8 CA, CP, DC, WC YES 5.5 CA, DC WC NA 5.5-10 CA,WC NA 5.5-11 DC NA 5.5-12 WC NA 5.5-13 DC NA 5.5-14 CP YES 5.6-1 CA, CP, DC, WC YES 5.6-2 DC NA 5.7-1 CA, CP, DC, WC YES CA 5.0-002 CA NA
- CA 5.0-003 CA, DC, WC NA CA 5.0-004 CA NA CA 5.0-005 CA NA DC 5.0-ED DC NA DC 5.0-001 DC NA DC 5.0-002 DC NA DC 5.0-003 DC NA DC 5.0-004 DC NA TR 5.0-003 CA, CP, DC, WC YES TR 5.0-005 CP YES l TR 5.0-006 CA, CP, DC, WC YES i
WC 5.0-ED WC NA WC 5.0-001 WC NA WC 5.0-002 WC NA WC 5.0-003 WC NA WC 5.0-004 WC NA WC 5.0-005 WC NA WC 5.0-006 WC NA
Attachment 2 to TXX-98208 Page 3 of 4 JOINT LICENSING SUBCOMMITTEE METHODOLOGY FOR PROVIDING ADDITIONALINFORMATION The following methodology is followed for submitting additional information:
- 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 encicsures 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 !ncluded in the additional information for the licensee to which the
- change does not apply, as the changes are only for consistency, do not technically l 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.
i i
Attachment 2 to TXX-98208 Page 4 of 4 JOINT LICENSING SUBCOMMITTEE METHODOLOGY FOR PROVIDING ADDITIONALINFORMATION (continued) 1
- 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 section number. nnn = a three digit sequential number
ADDITIONAL INFORMATION COVER SHEET j ADDITIONAL INFORMATION NO: O 5.2-1 APPLICABILITY: CA, CP, DC, WC REQUEST: STS 5.2.2 b and Difference 5.2-2 Comment: TSTF-121 has been withdrawn for modification, combination and resubmission. Use current ITS. FLOG RESPONSE: Traveler TSTF-258 has been submitted to the NRC for review. This traveler superseded travelers, TSTF-86, TSTF-121, and TSTF-167. TSTF-258 is based on the recommendations in the April 9,1997 letter from C. Grimes (NRC) to J. Davis (NEI), with some exceptions. The FLOG submittals have been revised to incorporate TSTF-258. The latest industry status on TSTF-258 is that the NRC has requested changes to Section 5.7, High Radiation Area. See response to Comment Number 5.7-1 for how the FLOG has addressed the NRC comments on TSTF-258. ATTACHED PAGES: Encl. 2 6-2,6-3,6-7,6-11 and 6-15 Encl.3A 2,2a,4,4a,6 and 7 Encl.3B 2,2a,5, Sa and 8 Encl. 4 1,19 and 20 Encl. 5A Traveler Status sheet, 5.0-4, 5.0-5, 5.0-6, 5.0-11, 5.0-31, 5.0-39 thru 5.0-44 Encl.6A 1, i a, 2, 3, 4 and 5 Encl.68 1, 2,4, 5 and 6 i l
M OLS 6.2.1 ONSITE AND OFFSITE ORGANIZATION (Continued)
- d. The individuals who train the operating staff and those who carry out the radiation protection and quality assurance functions may report to the appropriate manager onsite: however, they shall have sufficient organizaticial freedom to ensure their independence from operating pressures.
6.2.2 UNIT STAFF The unit organization shall include:
- a. An Auxiliary Operator shall be assigned to each reactor containing fuel and an additional Auxiliary Operator be assigned if either unit is operating:
With,both: units 1 shutdown orLdefueled,Taitotaliof_three Auxiliary 1-igg operatorsifor atheltwo; units;are requited.-
- b. At least onc licensed Opratcr for cach unit shall bc in the control e l-05-A'
- room when fuci is in eithcr rcactor In addition, while cither unit is in "00E 1. 2. 3. cr 4. at 1 cast onc liccased Senior Oprator shall ,
bc in the control raca:
- c. A Radiation Protection Technician
- and a Chemistry Technician
- shall i~t.u-A? M be onsite when fuel is in the reactor **:
- d. ? site "rc Brig:dc cf :t least five ec=bers' shall bc maintaincd on ~ 1-os-w; M site at all tiacs. The Tira Srigade shall not include the Shift Suprvisor and the two other ;c bars of the minimum shift crew necessary for safe shutdown of the unit and any grsonnci rcquircd for othcr essential functions during a fire c:crgency;
- e. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions (e.g.,
licensed Senior Operators, licensed Operators, Radiation Protection Technicians, auxiliary operators, and key maintenar.ce personnel). T!E a; cunt of cycrti;c worked by unit staff ;c;bers grforming safety related functicas shall be limited in accordancc with the Nl1C 1093
]
." clicy Statc; cat on working hours (Cencric Letter No. 0212) The o.5.2 1
/ conttol sZshallitgel_udeIguidel jneslonyorkingihouts;thatJensure adequate 3hifKcovetagejshallibelmaintalgedylthout toutine: heavy;use T i of 4ovettimeZAny; deviation;from 3helabovelguidelinesZshal.l!be authotizedMnladvancelbylthe EPlant$anaget;3;otithe:f;Pjant3tanagerls'3 designeeg.iniaccordanceNithlapp_ roved; administrative;ptocedur,esZandyith documentation;ofithelbastsiforigrantingithe"deytation3Routwhi_ati from the"wrkingihour;guideljneslshall*notibe;authotizpnd
- f. The Shift bhrations Manager shall hold a Senior Reactor Operator license.
- The Radiation Protection and the Chemistry Technicians and fire Brigade .
composition may be less than the minimum requirements for a period of time 11gLG 3] not to exceed 2 hours, in order to accommodate unexpected absence, provided immediate action is taken to fill the required positions.
- dita',1si ngl e; Radi ation_ . Protection *Jechni cian 'andia;si ngl.elChemj st ryiT_echni ci an 1"1-u AT'Q canlul0 ltth1Erequj rement;fotJx)thlunits !
CPSES Markup of CTS 6.0 64 8/28/98
~
1 1 l l ADMINISTRATIVE CONTROLS l 6.2.2 UNIT STAFF (Continued)
- g. 6 h.^ Shift 'r '-'- ' "rhor 'STA) An7jndiVjduball orovida 1 15 3 Ladvisor Ciana@y o.5.2 1 in technical support thermalto the7unitroperationsDshift reactor engineering,crew and SMTEr l the areas of hyarauiics, plant analysis with regard to the safe operation of the unit. -4he Shift Tcchnical Advhor shall havc a bachelcr's degrce or cquivalent www in a scientific or cngineering disciplinc and shall have received '
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wuyuu1 5 4bIwJ vs 5 4 4 d l. 3 ts.ssws s b u b 4 vi s uliu vvi s k t vsJ isi bi sw wulikt vs _--_vvill . 3 NEWNShift crew ' compositions say be~onelless1than;the minimum requirement 1 13-A - of 10 CF8 50.54(m)(2)(1)2and.6.2.2:a:for 'a: period.of; time not to l exceed.2; hours;jn_orderstoL. accommodate; unexpected. absence of on-duty shift crew members lprov.ided11mmediate7actionjis;taken'to restore the shift. crew composition;to withinithe minimum, requirements. 6.3 UNIT STAFF OVALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, Revision 2, 1987. I L 6.4 NOT USED 6.5 NOT USED 6.6 NOT USED . I TUTT 1f Ynt A T T n11 6.7 t* A f"f"TV vru 6i LAiIA r v A v s n i A v11 M[,b h.: s'8
.j 6.7.1 Ihc folloWing actions shall bC tak^n in the evCnt a Safety Limit is
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- b. A L'cchscc Event "cport shall bc prcpared in accordancc with
,ncenen ,,
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- c. The Licenscc Event "seport shall be submitted to thc Commission in
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If that organizational position is assigned 1 l l CPSES Markup of CTS 6.0 6-3 8/28/98 t i 3
ADMINISTRATIVE CONTROLS , 1
- 10) Limitations on the annual der e- h m=itment to any
' 8 member of the publicMnd;the; site bounday,' oue to '[
releases of radioactivity anu m .-i mn irom uranium fuel - cycle sources conforming to 40CFR190.
- 11) The1 provisions of'Technicaljspecification 4,0.2'and;4.0.3 are ,2-22 A applicable 1to;the.Radi.ologicall Effluent: Controls Program: 0 5.2 1
- f. Not used
- g. Containment Leakaae Rate Testina Procram A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50 Appendix J, Option B. as modified by approved exemptions.
This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, " Performance Based Cantainment Leak-Test Program, dated September, 1995" The peak calculated containment internal pressure for the design basis loss of coolant accident, P, is 48.3 psig. The maximum allowable containment leakage rate, L., at P,, shall be 0.10% of containment air weight per day. Leakage rate acceptance criteria are:
- a. Containment leakage rate acceptance criteria is 5 1.0 L,.
During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are 5 0.60 L, for the Type B and Type C tests and 5 0.75 L, for Type A tests;
- b. Air lock testing acceptance criteria are:
- 1) Overall air lock leakage rate is 5 0.05 L, when tested at 2 P,.
- 2) For each door, leakage rate is 5 0.01 L, when pressurized to 1 P.,
The provisions of Specification 4.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program, with the exception of the containment ventilation isolation valves, which is specified in specification 4.6.1.7.2 and 4.6.1.7.3. lhe provisions of Specification 4.0.3 are applicable to the l Containment Leakage Rate Testing Program. j2-11 g g j TI'~E NEW 7 Technical 'Soeci fications" (TS) ' Ba ses ' Control Proaram CPSES Markup of CTS 6.0 6-7 8/28/98
1 ADMINISTRATIVE CONTROLS ANNUAE RADI0 ACTIVE EFFLUENT RELEASE REPORT" . M MI 6.9.1.4 The Annual Radioactive Effluent Release Report covering the operation of l the unit during the previous year shall be submitted prior to May 1 of each year ir! , accedance'with:10C.FR5.0136a. The report shall include a summary of the quantities l of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCH and PCP and (2) in conformance with 10CFR50.36a and Section IV.B.1 of Appendix I to 10CFR50. MONTHLY OPERATING REPORTS 6.9.1.5 AnnH np reports of operating statistics and shutdown experienc 3 18 LS t 0-5.2 1 bcludingdocumcatationGT0;; challenges 9ty valves /57 Fat i be submitted to the pic:;surizcr on a monthly basis to tnc;u;;vs or picssurjzcr U.L. auca Regulatory Commission. Occu;cnt Control Ocs, 'Jashington. 0.C. 20555. with a copy , to the Regional Administrat;r of the Regional Office of the NRC. no later than the . 20th of each month following the calendar month covered by the report. l l CORE OPERATING LIMITS REPORT l 6.9.1.6a Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each reload cycle or any remaining part of a reload cycle for the following: 1). Moderator temperature coefficient BOL and E0L limits and 300 ppm surveillance limit for Specification 3/4.1.1.3. 2). Shutdown Rod Insertion Limit for Specification 3/4.1.3.5. 3). Control Rod Insertion Limits for Specification 3/4.1.3.6. 4). AXIAL FLUX DIFFERENCE Limits and target band for Specification 3/4.2.1.. 5). Heat Flux Hot Channel Factor. K(Z). W(Z). F/". and the F/(Z) allowances for Specification 3/4.2.2 6). Nuclear Enthalpy Rise Hot Channel Factor Limit and the Power Factor Multiplier for Specification 3/4.2.3.
- 7) SHUTDOWN MARGINS values in Specifications 3/4.1.1.1, 3/4.1.1.2.
3/4.1.2.2. 3/4.1.2.4. and 3/4.1.2.6. 8)I"ge fueling;B_oro[ Concentration;11m1ts ;1.n; Specj ficatjon:3/4.9.1 J nttu - 6.9.1.6b The following analytical methods used to determine the core operating limits are for Units 1 and 2. unless otherwise stated, and shall be those previously approved by the NRC in:
** A single submittal may be made for a multi unit station. The submittal shou k ,
'N, l shall combine these sections that arc common to all units at the station:
h5ie'v'er, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit. CPSES Markup of CTS 6.0 6-11 8/28/98
+
ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA qualified in radiation protection procedures (e.g., Radiation Protection Technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with dose rates equal to or less than 1000 mrem /h, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device which continuously indicates the radiation dose rate in the area; or
- b. A radiation monitorirg device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and individuals have been made knowledgeable of them; or
- c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the RWP.
3 11 A 6.12.2 In addition to the requirements of Specification. 6.12_L areas accessible 0 5.2-1 to individuals with radiation _ levels creater_tMcMequal= to 3100 mrem /h at 30 in.) tut icss than 500 rods in onc nour at onc ;nctgr_fr ;; lac radiction y' __.._'12 __ __ <___ -__ .. t.__
. " ' ^ "iction C-Mshall burov iueu with lockad doors or continuously guarded to prevent _= authorized unauthoh.
6nedvertenCieTJy, ana the keys shall be maintained unTei" Lhe adiffinTsTf3t17e ' N control of the Shift Manager on duty and/or radiation protection supervision. 0 5.2 1 Doors shall remain locked except during periods of access by individuals under an approved RWP which shall specify the dose rate levels in the immediate work areas and the maximum allowable stay time for individuals in that area. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by individuals qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area. For isolated high radiation areas accessible to individuals with radiation levels of greater than 1000 mrem /h at 30 cm but less than 500 rads in one hour at one meter that are located within large areas, such as PWR containment, where no enclosure . . exists for purposes of locking or gannot'_.belcontinuously;guardedj, and where no : mu $, z enclosure can be reasonably constructed around the isolated area, that isolated area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device. 6.13 NOT USED 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCH) Changes to the ODCH: l
- a. Shall be documented and records of reviews performed shall be l sto sj l '
CPSES Markup of CTS 6.0 6-15 8/28/98
CHANGE NUMBER ESliC DESCRIPTION
'Nct =cd.
l 01 09 A The~ CTS 2equirementsicqncerningiolettime 05.27 \ l being;inlag_cordance31thithe NRC;Pollgy; Statement 31s ! tePlaced,)frefeArngitoJdelgistrative3tpcedutes; tor the~cogLrollCLwotMgg~j!au._rs3ThCRopos_ ed3hange prpyides2easonableTassuta!ce3hatrsafgIplant5 operations f wil11not be; jeopardized 1bnimpsited.:pettotmance: caused _by excessive]vorkingLhours'd" oecifjeIcontrols;forlivorking houtsioffreactorlplantistaffiate;desettbed]Drocedures thattequitelaideliberate31 cision' making: process ~to minimize;the~potentiaE[orjimpair_ed;personneUperformance ; and_that testa _bl i shed: procedure;gontrol ' processes;will. provide; sufficient! control s;forichanges;to;that; procedure. Repl acement ~ of_the;CTSireference;;toireferring 30 administrative controls;doennot'ghangelthefrequirements associated Jithl wor _ king hours;and11sitherefore~ cons.idered l anjadministratiye: change;fTheseTchangeslarelconsi. stent' / (with..the NUREG;1431 asimodified;by TSTE258) <,.-
;9 - - - - -
01 10 M Adds requirement for three Auxiliary Operators for the two unit sites with both units shutdown or defueled. This change is consistent with NUREG-1431. Although more restrictive, this change is consistent with current plant practice. 01-11 A For clarity, a note is added to state that one Radiation Protection Technician and one Chemistry Technician can fulfill the staffing requirements for both units. 01 12 A Deletes the shift technical advisor (STA) qualifications. The additional NUREG 1431 requirement that the STA shall meet the qualifications specified by " Policy Statement of Engineering Expertise on Shift" was not inserted because this requirement is redundant in that it is embedded in RG 1.8, Revision 2 (see section on Unit Staff Qualifications). 01-13 A Adds new statement to accommodate unexpected absences of on duty crew member. This change is consistent with NUREG 1431. This criteria was in the CTS but was subsequently moved to the Final Safety Analysis Report (FSAR). The criteria is consistent with current practice and 10 CFR 50.54(m) and, as such, reinsertion in the TS is considered administrative only. ! 01 14 A Not applicable to CPSES. See conversion comparison table l (enclosure 38). l l l CPSES Description of Changes to CTS 6.0 2 8/2888
CHANGE NUMBER HSt!C QESCRIPTION DEIS A ThisIchangelrevises1the;CTSitofeljninatelthe_ title:pf 0 5.2 1 %i IShift3TechnjcAllAdvlspfl(STA13.JIACatelnotIusediat /j alliplants3thelfunction;marbe;1(ulfiUed, bylone:offthe .- i othet;_onishif_t1]ndividpals)2J_his1Section3s2reyisediso thatlitidoesLnot]japlyithatithe;ETAlanditheJhj ft Supervisotinustibe:~dj flerentiind1VjdualsE0ptionllfofithe commissio[PolicKSta_tementlgEEngi_neerinflExpertiselon Shiftlisisatjsfied bflassjgnjggian3ndjyjdualD11th x specifjedleducationaliqualifications'to*each oper,ating i crewiasIoneIof;thelSR0s3prefethblyltheiShift; Supervisor) required; bE103FR150 ;54(mM2M1) Jofprovideithe fechnical_ expertiselpnishift:XEliminatj0g the; title;of STAfis c considered.:anladmini strative: change; since;thelrequ1 rement fotengineetingiexpertiselonlshiftLis1mainta.ined!:LThis j change 11siconsistentwithNUREG-1431'usmodifiedby;TSTFj 258# 0.1316 LG A; generic; tit 1.eLhas replaced thel plant _ specific TR 5 0 005 utility;titlelforithelcorporat_e, officer _having responsibiljtylforioyetall~,plantisafety: The plant specific;titlelisimoyedito.the.1FSAR Thisll change is consistent _with;TSTFj65 02 01 A Not applicable to CPSES. See conversion comparison table (enclosure 3B). 02-02 LS 4 CTS Section [6.7], " Safety Limit Violation," requirements to notify the NRC within 1 hour following a violation of a safety limit (SL), submit a Safety Limit Violation Report and not resume plant operation until authorized by the Commission are being deleted. These requirements are a duplication of 10 CFR 50.36(c)(1),10 CFR 50.72 and 10 CFR 50.73.[ ] Since the plant must meet the applicable requirements contained in the regulations, sufficient regulatory controls are maintained to allow removing these duplicate regulatory requirements from the current TS. The notification requirement to management and the review committees is an after the fact notification and is not necessary to assure safe operation of the facility. As such, this requirement is not necessary to be included in CPSES Description of Changes to CTS 6.0 la 8/28/98
. - . - . - = - _- .. _- .- . - - . . . .. . _ . .
CHANGE NUMBER RSBC DESCRIPTION i 02 11 M New program requirements. " Safety Function Determination Program" and " Bases Control Program" would be added, consistent with NUREG 1431. Although these new programs reflect current plant practice, delineating them in the l ITS would be more restrictive. 02-12 LG Not applicable to CPSES. See conversion comparison table (enclosure 38). 02-13 LG Revises Section 6.14 item b to move the requirement that 00CM (or similar programs and procedures) changes require review and acceptance by onsite review committees to the 00CM. The onsite review of ODCM changes is currently required per [ procedures]. This change is consistent with NUREG-1431. 02 14 M Not applicable to CPSES. See conversion comparison table (enclosure 38). 02 15 A Not applicable to CPSES. See conversion comparison table (enclosure 3B). 02-16 A Not applicable to CPSES. See conversion comparison table (enclosure 3B). 02-17 LS 1 Not applicable to CPSES. See conversion comparison table (enclosure 3B). - _ 02 18 A mt applicabic to C"SES. Scc corciersica co;;; pari;cr' 0 5.2 1 I\ tabic (caciosurc 30) Revises ~the; Radioactive Effluent -), Contro]ji PfpgtaalDoseTtate21Jejts;re] gas _ed.,tolate_as l benhdit@~ sit (boundarXto;terlectineC101CFR f artj20 rpqoltenentsnf.tegisaancelot;Geneticj.ettet 89J01E10 CEg0wfupdated =Nh0RCMth'edXdrjftiGenetic Lettetzs32ETyptistosg3hames;to2sI51NUREGEbased.pg.] theltjeO0lCfB3052lCptDp6MCchang6s18teIcoDsistent s gitEtgIgramtg11etterELhCApf1719fi1997J1ett.ef t
- froCCfA1m!LsitmutelsmtEsomelageptions1;mThe ptoposedIchangesisA1gaiGhejianeiovetallileyelzof effilleYjtX6htf61NfDeTret81n1Nithe[operdtional D.eg!b111tylttatreglst.inth30rtent]llunderlthe; previous i 103fB120ft Th ete~thangerate'intendedito311minat.e 96ssible3onfusjonJon1sproper21mpl_emejtatjon of2the tevisedMCER.120.;renitementg%Ihejtoposedichanges;are consistentmith.;ggE_G314311as3odj fledibyiTSIF-258H For DCEPiendlCESE5Jip6fitionslofjISTE2.58)erefadopted;that t
gerinotlalte.ady;1n~corpotated11ntolthe;CTSJased;oq PteRousHicenneIaaegdments. CPSES Description of Changes to CTS 6.0 4 8/28/98 l
CHANGE NUMBER HSHC DESCRIPTION 02 19 LS-2 Not applicable to CPSES. See conversion comparison table (enclosure 3B). 02 20 A Not applicable to CPSES. See conversion comparison table (enclosure 38). 02f21 A Ngt'; applicable 30LCPSESE2See convetsionicomparison E 5.0 0M tab]eI(engipsure3B)] N - 'm 02:22 A The,.neuantvgJnluemuun6mi s ytogramiisirevised ;to incl udeiciarificationZstatements~denotipg ;th.at ;the
@ l provisions"oftCTS 3 0;2 andX04:are; applicable to these:activitiesLThes.elstatements!gfiappligability clarifyltheiallowance;for surve11]ance" frequency extensi onsland_al l owanc.eitol performini.ss_ed.:survi el l ances .
Genetig: Letterj 8910MImpl ementation_offrogrammatic Control s;for; Radiol,ogica11Effl uent; Technical. Specifications"andithelRelocationlof Details lof;.RETS to t_he 0ffsite1 Dose _ Cal _culation_ Manual;orithe; Process Control Program"; allowed 3fcenseesl;toyelocatethe; Radiological EffluentJTechnica]Jpecifjcation_s,7andf establish. the RadioactiveiEffluents~ Control ; Program ;1n ithe Adminj strativelConttol s ~ Sectionlof_the;Techni. cal Spegj fications aThisIchange ieffectivelylimpl ements . the CTS l.requirementsJhat;were; rel.ocated_per;Generip; Letter 89: 01;5Thi sichangeli_s.: consider _edian iadmi ni st rative ' .nge since'thelchanges~arelin3he_ptesentat.ionimet . nly.] Thi sichangelj s;;consi,s. tent;with_NUREG; _ podified,by TSTF2258; 03 01 A Revises " Routine Reports" section to be consistent with NUREG 1431. The method for submitting all reports is revised to be in accordance with 10 CFR 50.4. Since this change merely makes the TS consistent with the regulations, it is considered administrative. 03-02 A Not applicable to CPSES. See conversion comparison table
- (enclosure 38).
l CPSES Description of Changes to CTS 6.0 4a 8/28/98 l
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_. l l CHANGE NUMBER liS11C DESCRIPTION 03 08 A CTS Specifications [6.9.1.5, 6.9.1.6 and 6.9.2] are revised to delete the reference to submittal location for l the monthly report, core operating limits report and special reports. The requirements related to report submittal are contained in 10 CFR, Since conformance to 10 CFR is a condition of the license, specific identification of this requirement in the TS would be duplicative and is not necessary. Since the plant requirements remain the same, the change is considered an administrative change. This change is consistent with NUREG 1431. Rev. 1. 03 09 LG The record retention requirements are moved to the FSAR and implementing procedures. The removal of this detail . from the CTS is consistent with NUREG-1431. The l requirement for retention of records related to activities affecting quality is contained in 10 CFR 50 Appendix B, Criteria XVII and other sections of 10 CFR 50 that ace applicable to the plant (i.e., 50.71, etc.). Post-completion review of records does not directly assure operation of the facility in a safe manner, as the activities described in the tocuments have already been performed. By retaining these requirements in plant procedures and licensee controlled documents, any changes in these record retention requirements will be adequately controlled under the provisions of 10 CFR 50.59 and the applicable regulations. 03 10 LG Not applicable to CPSES. See conversion comparison table (enclosure 3B). 03 11 A Radiatica Arca is revised to bc consistent with 0 5.2 ) t?UREC 1431 ;nd the acw I;rt 20 rcquir ; cat;. Changc; are non technical to add clarification and confor; with tiUREC 1431 :nd RC S.30. C_TS,6l12))Rhichlprovfde_slhjgt} tadiationTarealacces.s];onttollalternatlyesipur_suhntito_10 CFR"20.72031c)J2)ihalbeenIrevisediasIaire_sultlofAhe changeltol103FK20~ arid theiguidanceljniR_e'gG]atoryiGui_de n 8_l3;82ESinc_elthe;plantir_equj r_ements!r_emainItheIsame; [ ekgept?.as3f dentffiddlin]peci fic"Descrj ptiori!ofichanges? t thelchangeli s~considereradministrative aThiXchangeli consistentyith3UREGi1431"as.
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modified by;TSTE. 2r58' _m_ i 03-12 LG Not applicable to CPSES. See conversion comparison table ! (enclosure 38). i L 03 13 M The following report [ ] will be added to the ITS Administrative Controls section: " Reactor Coolant System i (RCS) Pressure and Temperature Limits Report (PTLR)" [ ]. 1 CPSES Description of Changes to CTS 6.0 6 8/2888
' CHANGE l
NUMBER RSBC DESCRIPTIDH l l 03 15 H Refueling boron concentration limits will also be added to l the COLR. The addition of these limits to the COLR is considered to be more restrictive. 03 16 A Deletes one of the allowed ECCS evaluation models for l CPSES Unit 2 which is no longer used. Although this l change is more restrictive with respect to the TS (the model may no longer be used), there is no impact on current operations. 03 17 A Deletes the methodology section references in the COLR. These references are adequately defined by the analytical methods themselves as approved bu the NRC and it is redundant to repeat the information in the ITS. This change is consistent with NUREG 1431. 03 18 ALS 5 tiot applic;ble to CPSb Scc conversica comparison ~ 0 5.2 1 t ble (cnclosurc 3S). The; CTS; requirement 1tolprovide documentatjon~,ofiall;challengesito;thelPORV'sforisafety valns;iEdeletedZ2Theltepotting'of; pressurizer; safety anditeljef Eval.velfajluresTand challenge _slisibas.edfon_the guidarice;in.JEREGiO694NTMIMelated Requirements;for New Operatjnglicensees DJiThelguidange; of;NUREGiO69[ states :
"Assuteithat3mylfajJuteZofsa20RV~orlsafety; f valve,to close;Wjllbeleporteditolthe NRCfptomptlyJM1]
challengeftolthe20RVs;orJsafety;valgsishouldibe documentedl11the:argtualitepottfiMNBC2 Generic 3.etterR orrigelinLedsontentgofithe1Mo_qthly;opetat.ing:Beport; teque:sts;3heLstenittalIofilescirlformation31[the; monthly opetatingleL2ttfdJhelge@rjc;1etteritde!1t_1fDE@at needs3to:boeposedlt, oisuppottithelNRCletfotaance IndicatoflPE}gragag avjjlab111tyIandfcapagity 2 statisticWHhe:genettele_ttendgernorspecifically identify 2hemeeditetepodIchallengesitolthelpress_urizet safetylarlitgletWaMsTIh_tEchangelsynisisteDt31t t!UBEEL13Eartt811(1Mibybmz:C
/ 3 03 19 A NotIDsed'Tihe ter; "uncuthorized" is changcd to "inedv;rtent" in the lligh Radiation Are; section. The picvation of inadvertat catry is discussed in section t 1.S of 30 0.30. This RC reficcts the tiRC's position regarding physical barriers for high radiation arcos.
Radiation cras within the limits listed shall bc lockcd ! cr continuously gu;rdcd to prcvat inadvertat entry as i discussed in 30 0.30. Further; crc. the distinction l betunn uncuthorized versc+-tnacertent is important based t ca a fictice of Vici tion that ^_lb;y rccived on this , interpictation of tcras.
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CPSES Description of Changes to CTS 6.0 7 8M8/98
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1 Page 2 of 8 CONVERSION COMPARIS0N TABLE - CURRENT TS 6.0 TECH SPEC CHANGE APPLICABILITY l NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY i 01-07 Revises Section 6.2.2a. Unit Staff Organization, to reflect No No Yes Yes LG the non licensed operator staffing requirements for a DCPP is a multi- CPSES is a multi- moved to USAR moved to FSAR single unit site. The minimum shift crew composition as unit plant unit plant , Chapter 13 described in Table 6.2-1 has been moved to a licensee controlled document. 01-08 Moves the fire brigade requirements to a licensee No Yes Yes Yes LG controlled document. These requirements can be found in LA 75/74 Move to FSAR Move to USAR Hove to FSAR BTP ASB 9.5-1 and their duplication on the ITS is not required. 01-09 ( a d The CTS; requirements concerningiovertime being W Yes NA-Yes M-Yes M-Yes in accordance:with2 the,MtC,Poljcy Statement1 1sfeplaced,by l 0-5.2-1 & referri ng .to; administrative; procedures Jor;the,controkof
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- ~ ^ ~ = - = - " f Q ng hours; _- _ - - -
01-10 Adds requirement for three auxiliary operators for the two No Yes No No M unit sites with both units shutdown or defueled. Already DCPP Wolf Creek is a Wolf Creek is a requirement single unit site single unit site 01-11 For clarity, a note is added to state that one radiation No Yes No No A protection technician and one chemistry technician can DCPP procedure and Wolf Creek is a Wolf Creek is a fulfill the staffing requirements for both units. operational single unit site single unit site requirements , differ. 01-12 Deletes the Comanche Peak STA qualifications based on use No Yes No No A of RG 1.8. Revision 2. 01-13 Adds new statement to accommodate unexpected absences of No Yes No No (1 on-duty crew member. already in CTS already in CTS already in CTS 01-14 Deletes the shift supervisors and operating supervisor from No No No Yes A section 6.2 as required to hold a senior reactor operator DCPP procedure and Not in CTS Wolf Creek has license. operational different requirements requirements differ. CPSES Conversion Comparison Table - CTS 6.0 8/28/98
Page 2a of 8 CONVERSION COMPARIS0N TABLE - CURRENT TS 6.0 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY r 01 15 This:changelrevisesithe; CTS to: eliminate;the; title,of i Yes Yes Yes Yes A l Shift Jechnical # vjsor;(STA) G l 0-5.2-1 E! 01 16 A generic; title lhasireplaced;the plant; specific utility No . Retained CTS Yes No- Retained CTS Noe L.G titlefor._the; corporate.offjcer_having.responsibjlityfor Retained H TR-s.o-i'os R overa]Lplantisafetytand;the,plantLspecjfjg. title 2smoved 1 CTS toithe;Fl5AR; CPSES Conversion Comparison Table - CTS 6.0 8/18M8
Page 5 of 8 CONVERSION COMPARISON TABLE - CURRENT TS 6.0 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 02-16 Change the Diesel Fuel Oil Testing Program description for No No Yes Yes A sampled properties of new fuel oil from "within limits" to Not in CTS Not in CTS
" analyzed" within 30 days following sampling and addition of the fuel oil to storage tanks. This wording more clearly defines that within 30 days following the initial new fuel oil sample, the fuel oil is analyzed to establish that the other properties specified in table 1 of ASTH D975-81 are met. This change is consistent with the Bases for SR 3.8.3.3.
02-17 " Reactor Coolant Pump Flywheel
- is being revised Yes No - see Section No Yes LS-1 consistent with TSTF-2374 WOG The proposed changes 3/4.4. CN 10-03-LS LAR submitted provide an exception to the examination requirements in 12/3/96 TR-5.0-006 l Regulatory Guide 1.14. Revision 1. "Reactcr Coolant Pump Flywheel Integrity." g -
02-18 Revise the Radiological Effluent Controls Prog No.Yes No.Yes Yes Yes A f aircady in CTS Q-5.2-1 limite tcr cr.d tn reflect
. w cd changes trovclcr to 10 CFR Party m af ,
t Ccacc.,(aircedyir. CTS y 02-19 The surveillance interval for verifying that other No No Yes Yes LS-2 properties are with limits for ASTM 2D fuel oil is changed addressed in 3/4.8 addressed in 3/4.8 from "within 30 days" to within 31 days" after obtaining a (CN 01-60-LS24) (CN 01-60-LS24) sample. 02-20 Add the provisions of Specifications 3.0.2 and 3.0.3 are No No Yes Yes A applicable to the Diesel Fuel Oil Testing program. This not in CTS not in CTS change is consistent with TSTF-118. 02 21 Amendment;No c106 2 forJ olhCree kincorporatedr afl ootnote_to No No Yes No A allowxtheyolumetrjg;and surfacelexasjnatiort,of 1 the;.RCP 2 f "D" potor;flywheehfocithe;ff.1rst110 year;ISkintervalibe WC-5.0-004 l delayedt forione operating cycleaThe; examinations were completed _during;theininth; refuel _1ng outage & Sincetthe footnote 1s;a one timetexceptionfand:has,beeni. satisfied; the; footnote;1s no longer:; applicable:and_can be: deleted. CPSES Conversion Comparison Tame - CTS 6.0 8/28/98
CONVERSION COMPARIS0N TABLE - CURRENT TS 6.0 Page 5a of 8 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK lWOLFCREEK CALLAWAY i 2.
/ 02722 The RadioactivetEffluents; Control.s. Program;.is revised;to Yes Yes Yes Yes f A include ;clar.i fication;statementsidenoting ; that ;the l0-5.2-1 \l prov1;1ons_of CTS 4.0.2iand;4;Q.3,are; applicable 3t o these 1
7 k activities; a 03-01 The method for submitting all reports is revised to be in Yes Yes Yes Yes A accordance with 10 CFR 50.4. i i d CPSES Conversion Comparison Table - CTS 6.0 8/2&98
Page 8 of 8 CONVERSION COMPARIS0N TABLE - CURRENT TS 6.0 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 03-16 Deletes one of the allowed ECCS evaluation models for CPSES No Yes No No A Unit 2 which is no longer used. 03-17 Deletes the methodology section references in the C08R. No Yes Yes Yes A References do not exist in DCPP CTS j d03-18 .".cyc; th; cpartin;; ccgirc._..: for dec_..tstica of all NeYes NeYes Yes NeYeq ' ~% ( ALS-5 cholic..sc; to th; 03; or ;;fcty v;1vc; to thc ="0C l 0-5.2-1 M'
- l. ;'e..thly Ch etini; Rcport.@lCTS;tequirementitoiprovide documentatjon;ottaljichaljengesdtoltheiPORVis;orgsafety N_ yalveslis1de}et.ed!
..m m. ununariccd" i; chor.;,cd to "inadvertcat" 'n the Yc %"3 VesNA VesNA Yc;"A A ::if; C; diction frc; ;cction 'hc picventi m of ir.;d.crtcnt lQ-5.2-1 B.
catry i; discu;,cd i ;cction 1.5 cf "O 0.00. f.ot';used 03-20 The use of a continuous guard is provided as an additional Yes Yes Yes No LS-3 option for preventing inadvertent entry into high radiation Maintainir.) CTS areas that are accessible to individuals. CPSES Conversion Comparison Table - CTS 6.0 8/2888 ; i
N0 SIGNIFICANT HAZARDS CONSIDERATIONS (NSHC) CONTENTS I. Organization ........................................ 2 II. Description of NSHC Evaluations...................... 3 III. Generic No Significant Hazards Considerations "A" - Administrative Changes......................... 5 "R" Relocated Technical Specifications. . . . . . . . . . . . . 7 "LG" - Less Restrictive (Moving Information Out of the Technical Speci fications) . . . . . . . . . . . . . . . . . . 10 i
"M" More Restrictive Requirements................. 12 IV. Specific No Significant Hazards Considerations "LS" i l
LS 1. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i cabl e LS . 2. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Not a ppl i cabl e LS.3............................................ ... 15 LS.4. . .... ..... 17
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0 5.2 1 1 m l l CPSESNo Signipcant Hazards Consideration - CTS 6.0 1 8/28/09 4
IV. , SPECIFIC NO SIGNIFICANT_. HAZARDS CONSIDERATIONS 0 5.2 1 NSHC LS 5 a10 CFR 50.92_ EVALUATION FOR TECH _NICAllCHANGES THAT_ IMPOSE 1LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL 1 SPECIFICATIONS The. CTS"r_equirement to; provide. documentation.,oLall_ challenges to1the PORV's or safety; valves l,1_s . deleted.13he Ieporting ;of;pr.essurizer;.s.afety 'and . relief, val ve failures and challenges isibased_on the_guidanceJinfNUREG:0694, "THI.:Related Requirements'for New Operating'. Licensees;;"J1Thel guidance'of;NUREGe0694 states: [A.ssure thatLany failure off a1PORV~or safety valveito closeLwill .be' reported to the NRC; promptly. . All challenges. to _the PORVs.or safety valves"should be documented in the: annual report." LNRC _ Generic Letter 97 f02l:." Revised _ Contents 'of the Monthly Jperating Report" requests thel submittal of.less information in the monthly operating report. The~ generic letter identifies what needs to be reported to support the NRC Performance. Indicator l Program, and avai_ lability and capacity statistics. The generic letter 1does not.specifically identify the need to report challenges to the pressurizer safety and. relief valves. This change is consistent with NUREG-1431 as modified by TSTF-258. 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; Commission may make a. final determination, pursuant to.the procedures in 50.91 thatja proposed amendment to an. operating license for a facility licensed under 50.21; (b) or 50.22 or:for al testing faciljty; involves noJsignificant , hazards consideration;2if. operation:of the facilityLin accprdance with the proposed amendrnent would.not:
- 1. Involve;alsignificant; increase [in_ the probability;or' consequences of an acc ident .' pre vipus]Le va lua ted:;or
- 2. CreateJthe^ possibility;of a:new or;different kind of. accident fran any acciden t. pre vious 1T e ya lua ted;'or 3; In vo l ve~:ais ignLficantyreduct lon;in la. jna rgin' o f"sa fe ty. '
TheJfollowing evaluation is;provided_forithe thr_ee categories of the significant hazards; consideration 3 bndards:
- 1. Does the change, involve a_.significantiincreaselin the probability or consequences _ of an1 accident' previously evaluated?
- The proposed change would not; affect l.theimethod _of operation.of plant _ systems and involves only the. deletion of, reporting any challenges lto the PORVs or; l
i CPSES No Significant Ha::ards Consideration - CTS 6.0 19 8/28/09
IV;JSPECIEIEN0iSIGNIFICANEHAZARDS_C_0NSIDERATION 0ua NSHCiLS;5 , (conti.nu.ed) safetyival yes WiReportingiofIcha]Jengesitp ~theLPORyforlsafety3alves3asinot impact:onanyfageidentpreviously;evaluatedJ_ Therefore ithe; proposed chapge;would_notiresul.t;in"aisjgnLficant11ncreas_e:j_n_the Probability _or; consequences;.oEalpreyjouslyIevaluatediaccidenti
- 2. Doesithelchangeler_eateithe~;possjbilityioflainew'orldtfferentikindf of accident;fromf anylaccidentlprev. iou. sly; evaluated _?.
1 The.. assumptions [of thef,agcidentianalysesjar_ejunaffect_ed by thel proposed changeijNo newipermutations70r;eyentJjnitiatorsiare; introduced by..the ' deletion ofethisf reportjng requ.irement;73her.eforekthis proposed change would not create the possibility"oflainewlorldifferentikind;of; accident; 3 '. Does;thisl change;jnyolve_aisignificant reduction in a margin;of._ safety? The accident. analyses areiassused_toibe; initiated from conditions:which are . i consistentiWith;t.he TechnicallSpecifications; Limiting; Condition;forL0peration.
- The proposed change doesinot? affect (any LCO OT. h erefore,1there,is,no change in thefaccident analys_e_sjand,al1Jrelevan,t
- event l acceptance' criter.ja remain ~yalid.
Further;;theJproposed: change.;hasino; affect _onianyLactual;or;r.egulated failur.e Point. twhich 'is; protected _by;an;eyent"apcLeptance1 criterion. JBegause_there;is i no_ change 11nlanyifailure_pointinorjiin any; event? acceptance criteria,'there'1s no reduction; inia; margin;of safety;' ] i N0.;SIGNIFICANLHAZARDS; CONSIDERATION DETEP)[INATION Bas.ed ion.;thej aboveleva] uati on ,$1tii s :concl udedithat ~t heiacti vi tiesla s soci at_ed . with NSHCMLSiS"Zresu) ting from 3helconversionito3he:japrovediTSJformatisati sfylthef no l sjgnificant!hazardsiconsi.derationistandardslof310;CFL50.92(c);';and accordingly,{ a noisjgnificant .hazardsicon_siderationifjndinglis Tjustified. CPSES No Significant Ha:ards Consideration - CTS 6.0 20 8/28/09
I 1 1 Industry Travelers Applicable to CTS Section 6.0/ITS 5.0 4 i TRAVELER # STATUS DIFFERENCE # COMMENTS l TSTF-9, Rev.1 Incorporated B-PS NRC Approved. TSTF-37, Rev.1 Incorporated 5.6-2 DCPP only i TSTF-52, Revil Incorporated 5.5-4 Incorporated,dran Revi ( 3.6.1 6 ' 1 Per,Q3.6_.1-6z 1 TSTF-65, Rey.1 Not Incorporated NAS.2-9 Not NRC approved se+f 1R 5.0 005 tr;;;l;r ;;; cff de:;. TSTF-106, Rev.1 Not Incorporated NA Retain CTS 4
- TSTF-115 Not Incorporated NA Not NRC approved as of traveler cut-off date.
3 j TSTF-118 Incorporated 5.5-8 NRC _ Approved 1R 5.0 006 .l t a TSTF-119 No:Ir.cerpere: d NA Retair. CTS 1R 5.0 006 J TSTF-120,;Rev.1 Not Incorporated NA Retain CTS 1R 5.0 006 j TSTI' 121 Ir. ;rper;;;d Gr2-2 - 0 5.2 1 i C i TSTF-152 Incorporated 5.6-4 NR_CApproved 1R 5.0 006 1 x 7 [e TSTF-157 !acerpor;;;d Gn%2 ' ] A
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= 0 5.2 1
- "/OC-57,!!cv.1 Incorporated 5.6-5 1R 5.0 003
- M FJ2,33,1 WOG-72 Incorporated 5.5-13 4
WOG-85MJ37, Incorporated 5.5-14 0 5.5 2
" reps d Trave: r Incorporated 5 23fy-),5.23, 0 5.2 1 TS,TF-258 523-22 5.5-1,5.5-16] -
- 5. g 5.7,-l ,
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l l 1 1 l Organization < 5,2 l 1 l l l 5,2 Organization i 5.2.2 Unit Staff (continued) 5.2 3 de. Administrative procedures shall he devolnnad and implemented - 0 5.2 1 i i to limit the working hours oq(pirsonnel t ursit stal3rwno perform l safetyrelatedfunctions(e.g.'(i)licensedSeniorReactor c
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(continued) Organization i 5.2 CPSESMarkup ofNUREG-1431 -ITS 5.0 S.0-4 8/28/98
5.2 Organization 5.2.2 Unit Staff (continued) Controls shall bc included in the proccdurcs such that individual overtiac shall be revicucd senthly by the [ Plant Supcrintendcat] cr his designee to casurc that exccasive hours have not bcca assigned. Routin; deviatica frca the bov; guidclines is not authorized. fB s - The ;; cunt of ovcrtiac worked by unit staff ;c;5crs performing safety related functicas shall be li;;;ited and controlicd in 5.2 3 accordance with the "RC Policy Statc cat en working hours o.5.2 1 (Cencric Letter 8212).1he;q.ontrols:sha.1.liinclude guidelines op; working;houtsithat; ensure: adequate;shjft; coverage shal,1jbe main.tainedyithout1 routine:h_eavy_use_ofiovertimenAny deviatio.n from theiabove guideljne.s shal,11bejauthorizediin: advance _ by the E . Plant Manage,r* 3:or_the E: Plant; Manager's*1 designee 31n 7 acc. ordance. .T.w.ith appr.o.vec.T.. administrative proce.dures.Ta.n.d wi.th 4 documentation qfithe:ba.s,1slforigranting;the;dev.iation2 Routine ,j deviation 1from;theWorkjng. hour;guideljnes:shall;not be j uthorizedA y ef. The Shi.ft.0p.er_at.i_ons'M..an.ager. or Assistant Operations
.B-P"S zm.
"anager] shall hold an SR0 license. ~ '
'fg. Chc Sh'ft M-icci Advisor (STA) Antindividualshall
- r Mpg 2) provide advisory technical sunnnet to th p ;
Supervisor (SS)'5rew unit'ooerations7 shift'cr in the areas of ther hydraulics, reactor engineering, 5.2 6 0 5.2 1 and plant anal sis with regard to the safe operation of the unit. " c5 wheDieithehk[. e OTAiEshalllbe;as_sjgneditojkothIunits n"H00Ejl 22;M Zor2 "Z[hej.5B position may;belffile_d;bylthels.hif_t;managecocanzonishift SR0lpto11dingit.h,eMndlyjdua][meetit he;dualirgleJIti a addition, the STA shall ;cct qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift. __
- . . =
*2Dutiesimahbe; performedibylthe'Jige:Pte_sj.dentiofj Nuclea rj 0perations.;i fatha t (BfP'SM
~
! ofganizationallposition;is assigned) j CPSESMarkup ofNUREG-1431 -ITS S.0 5.0-5 8/2888
-. - - . . . . - _ = . - . _ _ - - - _ . . -- - . = __ - . _ .
l l Unit Staff Qualifications i 5.3 1 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications
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5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of Regulatory Gui_def.11;8;1 Revision 2,',1987. cr t,acrc raccnt revi;L ions, or ANSI en__..,.__.. e&-_;-_; .--__A e eu. ,uu s u uwwbreuvuw L,_ &_ Au-
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_ _. 1. u. & iTwyu 5.3.2 Forithef purposes;offl0CFR55.4,Ta;1icensed . Senior Reactor, Operator (SRO) and,'al..l. i. censed.,'r.eactor. ; operator. (RO)'.J.are ,those indi.v. iduals who,11n 5.3 2 addition;tomeeting.thelr_quirement.sfoLT.S15.3.10performthe; functions o.5.2 1 des _gribed in,10.CFR5.0.54.(m)J i i t CPSES Markup ofNUREG-1431 -ITS 5.0 5.0-6 8/28/98
Programs and Manuals 5.5 5.5 Programs and Marsals 5.5.4 Radioactive Effluent Controls Proaram (continued)
- f. Limitations on the functional capability and use of the liquid
- and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2t of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I:
- g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from'theisite to areas 5.5 1 at;or beyond the site boundary " '^ " -- '- - '--
/ 0 5.2 1 ec--iated . ith " "" ?c. App = dix 3. T2k " "-Hni h))M pg; shallibe Mn ? accordance; with :the; following:
- 1. Forl noble;.gasesr(to a dose rate'of:500 mrem /yr:.to the totallbodyian a Jose rate o. 000 mres/yr to theJskin',Ca_nd -
i
- 2. Foeiodinell31;1.foriiodine 133;;for tritiumRand for all' radionuslides;in; par iculate;formyith; half lives h 5.5-1
/5reaterathahT8 days; ; aldoseIrate~ f1500faremfyrj o.s.2 1 to anymorga_n; y
- h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I:
- 1. _n and ouarterly doses to a membpr_of- - _
Limitations nn
- annual 5.5 1 the publi .beyondthesite;boundarydfromiodine131. 0 5.2 1 iodine 13 , tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and
- j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
r ' l L k ." The provisionCof;SR .3 0.2:and_SR,3.0;3:are: applicable;to_the 5.5 16 R_adi oactive;Effl uent ,_Contr.ol s ~ programf,surye.111 ance; frequency. 0 5.2 1 (continued) CPSESMarkup ofNUREG-1431 -ITS 5.0 5.0-11 8/28/98
Reporting Requirements 5.6 5.6 Reporting Requirements ! consistent with the objectives outlined in the Offsite Dose Calculation Manual (00CM). and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C. The Annual Radiological Environmental Operating Report shall include the i results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the a ,B-PS-format l.Rsimil arJto3heltabl_e;j n:the: Radiological: Assessment; Branch Techn_1. cal Pos.ition,lRevision 1llNoyenberl1979. [The rcport shall idcatify the TLD results that rcpresent collocated dcsimcter; in rciation to the NRC TLD B-PS' program and the cxposurc pcried associated with cach result.] In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible. 5.6.3 Radioactive Effluent Release Reoort P *h ti'i d ? h ? !ii Hi HEE D.NOTEh M?ity u qi{& n y:5 = 91 ?ij &it % = B.pS':
~
A single submittal may be made for a multiple unit station. The submittal shou M shall combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
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The Radioactive Effluent Release Report covering the operation of the unit duri_ng,the;preygus;ye_ag shall be submitted pr,1.orito Mayl1 ~oleachlyear in t5;6i41 accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the 00CM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50. Appendix I. Section IV.B.1. 5.6.4 Monthlv Ooeratina Reoorts Routina reoorts of operating statistics and shutdown exoerience.#fludjng 8566 h;=; cat;$iMlf..;31J;U;U5nsoi30.jhccc::crizer3c;cioccatedTclicf 05.'21 J : cr cri.;;urizer~3;fety'V;1Vc; Wall be submitted on a monthly basis i no later thali the H 20th of each month following the calendar month I covered by the report. (5.641 9 l (continued) CPSESMarkup ofNUREG-1431 -ITS S.O S.0-31 8/28/98 l
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EI12SEEZE,NICECGZJs?dEErcer!L;mgh_ uw>.w:m r,,.=..nve ma- =a;nRadiation w :.L.s.27 Areaj w- .m.?wv& mmu.~_w Lx m rmw.mL akrr:a v? 5;0Z3D!!IMSMTIVEiCONTit0LS 5;7 2 11ghiRadiation;Areaj n w w m m m m w - m m m -cerm - v.en- r , n WE.dgm.w4Mh wn.r % wgwwwus deh Ad.4ha m.#gh,--m hMW m web ..my wn ar.Aa . ;.s.Alu AsJprovided jn paragraph _203601_(g)iof30,CFR_Partt20,lthe following; controls sha]llbelappljed.;toJ)igh.' radiationiareas'jniplaceiof;theicontrols. required by ' ,1 paragtaph;20.1601(a);and ~(b)~of;101CFRfart:20; i 517.1Z THiah~ Radiation ~ Areas'with Dose' Rates Not Exceedina liO rem / hour at 30 Centimeters ~fron 'the' Radiation ~ Source ~or from ~ any Surface ~ Penetrated by the Radiat1on:
~
. a. Each; entryway,toisuch;an;areafshall.'be. barricaded and conspicuously posted asia.._highiradiationfarea.1Such; barricades _may be_ opened as necessarylto permit. entry or. exit ~of.personn.el or equipment.
- c. : b. JAccess.toZand activities ~1n~ Jeach;such:areais. hall. be'. controlled by means of Radiation, Work fermit,(RWP) or m equiya)ent;thatlincludes specification of radiation; t dose _. rates]in the;jamediate; work area (s) and ,
other; appropriate radiation: protection ~equipmentland; measures; l1c ; Individuals qualified iniradiationJprotection; procedures _an_d personnel continuously.escotted.by.;such;individualsimay;be: exempted from'the requirement;for:aniRWPforiequivalentyhil.e_petforming the.ir_ assigned duties;providedithat_they,areotherwiseffo] lowing _p1 ant;. radiation protectionfprocedures:for. entry'.toZexit;from??and worklinisuch areas:
.w Z C.Td. ;Each indivjdualfot; group entetingisuch. fan?arealshall' possess:
GEllin Tradiation monitoring devicejthat; continuous)y:; displays radiation" dose: rates 51n!the7areaCot
. mare n.wL om.w.aJ G;%2"'.2. E.g Aitadiatiormonitorj ng;devicelthat Lgqntinuous]Dintegratesl.the radiatjonIdos_eltatesMnithela'tealand! alarms;when'the'. device',s do,s.e;al ar_m3etpoj ntii slir_ea.ched ,5yi thianJppropti ateial a rm setpointZot]
W3 E EH223'." _ ;;Aladiation; monitoring;devige that' continuously,itransmits_ dose tateiinformation;andicumulative; dose toX;remot.efre.geiver monitored:byyadiation.: protection; personnel;:responsibl e :for contro111ng'personn.eliradiation~exposureyith_theiarea;7.or i CPSESMarkup ofNUREG-1131 -ITS 5.0 S.0-11 8/28/98
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5;LJJ!igh Area RadiationArea
-mn-w --- nem-.~ rmm.v;ym ;y mm m- eme = ,
5.^7 ;17izj Hi ah Radi ation' Areas ' with ~ Dose ~ Rates ' Not Exceedi naT. 0 ~ rem / hour'at 30 Centimeters ~ from'the~ Radiation ~ Source or from~any' Surface ~ Penetrated 5.7-1 by the'RadiationTcontinued) 4 5.2 1 l E. l4. JAlself readingidosimeterde;gs.; pocket _jonization;chambetfor ele.ctronicidosimeter) land,"]
. i 2 '
;(1), ; Be.underithe;'surveill_ance,l as;specjfied in1the RWP or equivalent 7whilefin the; area',Tof;an z individualfqualified in radiation protection procedure _s.iequipped withfa radiation mon.itoringLdevjcefthat continuously displays i radiation doseiratesTin the' area.:iwho is; responsible for controlling personneliexposur.e' within;the _ area, Tor (ii) Be under, the; surveil]ance as'_specified in_ the RWP .or equiva].ent,"while;in thefareaf by means;of. closed circuit television,tof;petsonnel..; qualified Lin radiation protection procedures 2r.esponsibl.e,for,controlli.ng personnel l rad.fationi. exposure;inithe; area Tand_with the;means to i communicatedwithlindividualsiinitheareaLwhoarecovered by such~surve1] lance': .
~,~e, :Except foriind.ividuals; qualified _infradiationlprotection procedures, entry .intoisuch; areas:shall,'belmadelonly,afteridose_ rates.,in the; area have been determined and. entry personnellarelknowl.edgeab]e of, them ,
l l _.d 542_- . Hiah Radiation' Areas with' Dose: Rates ~ Greater'than 1.0~ rem / hour at 30 Centimeters from'the'RadiatiorFSource"or;from'any Surface" Penetrated by i l the' Radiation? but~less than~500 Tads / hour ~atTITMeter from~the~ Radiation Source ~or2from 'any ' Surface' Penetrated"by'the' Radiation: l H;X27 Each, entryway _to~su.ch;an areaTshall;be~conspfcuously; post _edl.as;a_high l Eadiation! area and sha].]~be:proy1_dedlMthX1odedlor;contjnuotas]y I guarded door'orlgate that; prevents 3nauthorizedient.ry;5and,Tjnladditi.on;
?E25 D EriH1. g ; Al]Isuch; door and.;gateikeys3ha));beimaintained . unde _ tithe administrative;contr.ol;ofatheJ[shjft3Mrf..~, . L,y, . y..
pr.c.t e ct i ct.; ma.n.ager] ," or; hi s 'ori.heridesi gnee .: ( ; 1 l l l CFSESMarkup ofNUREG-1Di -ITS S.O S.0-D 8/28/98 l l
i m M E ;J F m r a E 2 22 E r m D E m 2 E a I.!ijgh 3adiationfArea EEE25322L.:: !EE2XMWWGU12'.TilWEE!:511.R:1.52 SM1HighReaLRadjation1rea wmrnem~mw;mwmwer;rmww v.;vmrwenwn=~ vvmm SR.Trij Hiah ' Radiation ' Area s' with ' Dose ~: Rates
- Greater"than'1: 0 ' rem / hour 'at :30 5,7-1 Centimeters"from the~ Radiation
- Source ~orrfrom'anV' Surface
- Penetrated by the'RadiationPbutales's7tha~n~500* rads /hourrat TMeter'from'the 0 5.2 1 Radiation' Source *ortfrom'anrSurface' Penetrated'by'the' Radiation:
(continued) 7T, ' i2J " Doors and,gatesisha11Iremain; locked except during periods of Personnel lpr; equipment; entry;or ; exit]
,~g ;q IEXb. 3 Access,t.ogandiactjvitiesiin;;eachf,such area;.sha_1.1 be. controlled by '
means of;an RWPfor; equivalent thatlincludesl specification ~ of. radiation dose ratesiin the11mmediate; work; area (s) and other appropriate radiation protection" equipment and,measur.es.:
, Z c. . (Individual _s qualif.ied;jnfadiation_ protection procedur_e.s,may be_ exempted from1the: requirement forlan_RWPioriequjvalent whil.e" performing radiation surveys,inisuch; areas lprovidedithat theyf arelotherwiseifollowing plant radiation _protectionproceduresforlentrytoZexit.from,(andworkin c
such areas.: e, , a ,2 S;nd. .? Each individualLorfgroup;enterjng Lsuch;an;areaf shal.11 possess.:
..a b . 51_. l Afadiation monitoring; device that;continu.ously; integrates,the ra_diation rate.s jnithelareajand; alarms whenitheidevige'_s_ dose alarm;;setpointds~ reached 391thian appropriate alarm:setpoint,~.or l Z ;.3 2 2. JA:radiationfonitotiggidevicelthaticontinuouslyJransmits dose rate ~andTcumulative~ dose"information t.oialr. emote;receiv.et r
monitor.ed;byitadjation~prote_qtion persongeEresponsiblefifor controlling;personnejjfr.adiation;exposureMthjg ,the~ area'with:the meansito:communi_cate;Wi_thiandiconttpEevery; individual;inithe area, Tog HIG3.. M 6l sel fireadi ng;dq'sjmetegej ggpogketlj.oni zatj onighambetior electronic;do_sjmeter)3ndl E3!GQ7 1.(iH J Be3nderithe~s0rveill anceE;as3peci fiedl i n;the:RWPfor equjval entAWhile]j. nit _helarea 71ofian;indj vidual ,quali fied , in:Eadjation; protection:proceditesKequipped withfa . radiation 1 monitoring;devicelthat icontj nuou sly _displ ays radiationJd.oseltateslin~the area;7who~isirespo.nsibleifor cont tolj ing 7petsonnel;exposu re 'wi thi n;,the; a rea ,~, og CPSES Markup ofNUREG-1431 -ITS 5.0 5.0-43 828/98
~ -...- - - - - -._-. - - . .- .. . - .- -_ - .. . . - -. --
Ed3IM2ETJf2EEffi3IOTMUES.EdMLL'XMBYr2 High]adj at_ ton;Wea IEE22Ehm:&5TC.:n.dcJ2EDIREsmRGEmirE522 S 52Mijgh1 Area 3adiationfrea smcx m e-- m w~wrrmwmmew m x m nna m mrm~ry.m 577;20ffiCHioh Radiation' Areas?With' Dose'RaterGreater'2thanT0"ren/ hour'at 30 Centimeters fron'the'Radiai;1on' Source'or from any Surface Penetrated 5.7 1 45.2-1 M hvthe'Radiatiori.9butless"than~500rrads/hohr"atTMeter:from the: Radiation? Source'or:from"anVTSurfice Penetrated 7bV'the Radiationi (continued);
~"~
FZ :(ii)EBelunderf.the surveiljlancelasispecified;in;theLRWP_ or equivalent;1while;1n;the; area 2by;means;of; closed circuit tel evisionRoffpersonneliqual ifjed lin' radiation ~ protection Procedures 2 responsible;for controlling; personnel radiation; expo.surejin;thel area,";.and_with.the means to communicat.eiwithjand;controllevery'individualiin the area, or
!1 , ;47 min;those;casesiwhereioptions:(2) and;(3);;above,dare impractical ocidetermineditojbelinconsi,stentiwithithe Lowf As ,is Reasonably Achjevablei.prjnqiplelEa; radiation;'monitorjng device;that continuous]y displays; radiation ~ dose:latesiin_the. area ~
E Z.le.. l.~ Except forr.individualstaualified in' radiation' protection procedures Gr personnel: continuous _1y; escorted'by:such"individualsQntry.into _such areas sna1LDe_maae ogm aner_co_sem rates;1nyne_ area hav.e uwey determined;and entry;personnellatelkpow]edgeable:_ofithem; yygf. 7S*wWul" areas'thatiar#1rithjn;allarger" area Get-4s3 _ 6trc11ci:rO1;; redinier, ;I;ygupp as.$1R_ containment,1whereino - enc.iosure_ exists Jor2 tne, purpose _og locking ]ndiwher_e".po3 nclos.ure can reasonably;beiconsttucted;arourjdithelindividuallarealneed not,be pontrollediby;a;.J.ockedloorlorIgateinoricontinuously; guarded,1 bet shall;be barricadedEconspicuousVipostedKand;alcleatlyJtsible flashing 111ghtsshal,11be3ctjvated.Zat;the area"aslayarnjngidevice2 i CPSESMarkup ofNUREG-1431 -ITS 5.0 5.0-44 8/28/98
i JUSTIFICATIONS FOR DIFFERENCES FROM NUREG 1431 Section 5.0 This enclosure contains a brief discussion / justification for each marked up technical change to 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 plants may have plant specific information in that location. CHANGE NUMBER JUSTIFICATION 5.1 1 Not applicable to CPSES. See conversion comparison table (enclosure 6B). ; 5.1 2 Not applicable to CPSES. See conversion comparison table (enclosure 6B). l 5.2 1 This change revises Section 5.2.2a to reflect the current Technical Specifications (CTS). This change clarifies the application of the unit staff provisions to both units. 5.2 2 This change deletes Section 5.2.2.b since the requirement for the presence of a reactor operator (RO) or a senior reactor operator (SRO) in the control room is adequately controlled by 10 CFR 50.54(m)(2)(111) and 50.54(k). The ITS 5.2.2.b requirement that is being deleted will be ' met through compliance with these regulations an s required in the TS. This is consistent with traveler TSTF M258. 5.2-3 t d:3.19. pes.gon;5t 2.2dl(ISTS15.!2;2e);1samaudspecifjc 0 5.2 1
; working houG11mitEtoIndninistrativeJproceduresitoicontto130rking
' hoursaIbe:proposedichangesyjll;provfdeleasonab1f;as_surance;that
, safe; plant;operatiopsJillinptJbe3eoparddiz_ed ibylepalted; performance i caused 3yy3xcessigyottig3 puts 11 Specific stkjng;houtaisitatjonsfare n
! notiothentiseirequitgdltolbe3n3he;technica]#pec1(1 cations 3nderJ0,CFR 50;36(gM51:7ispecific]sperol s EforyotkjngihoarsTofarengtor.; plant istaff ateidesgrabedi1[ptsteektep3hatrequitcaldeJ1henteldecfsionlaakifg processity:minfaige3hgIpotentfarforfijspajMdMr~fgpgel"pettorEa.ncelland thattestablished_ptgge@teDontroWrocesseD1117etpyidle sofficient controuygrlchasesmhetatege@rrZ.Ihteelchnoges3re~ consistent wtth3_heltecommendAjgE333helAptil;939913Jeft tKt@3fiGtjaes;to?
DavisEJddition@lif23ht3STS' statement 2Gggtf01s3 hall &Eincludedlig the ptgcegresNenithstandividualloyectime7sha111beIreViewed noDthly_by the;[P]an,t1Superjntendent]Igrlhjsldesigneeltolenshteithatlexcessivelhours have:not beenzassignedaisibeingcdeletedsrhereJis no.guidancelin Generjc3etter;82f12ithatyscussesithese3dditional%conttolsGIhe addi tipna] [requf_resen,tatolhave3he,21 ant;.50petj nt.egdentf(or1hisIdes.ignee) review 11ndividuaEove#j_selonXmogthly& asis 33nnecessary;sjnce sufficientladsjnjstrattyelgontrois;and_po1JcieslexistH_asJell;as3he role of the 2 Individuals'superfisots11nzsuperyisjng:personnehptevent excessivelotJbuseloflovettime?3Jhese:ghangej!afelgonsj s.tentjtith ;T_SIF;i 258! CPSESDifferencesfrom NUREG-IDI -ITSS.0 1 8/2888
CHANGE NUMBER JUST!FICATION 5.2 4 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 5.2 5 Not used.
^
5.56 m i; chcagc revi;c; Sectica S.2.2f to dc;cribe the currcat [licen ing bc;i:] for tb Shift Technical A&i:cr (STA). This: change T L Cevises3TS Section;51R;2;.fd(ISIS ~Section,5.2.2.g)1toidesetjbeJhe la.s.21) current; [TS] Ia.nditole]ja_inatelthe; tit 1e;oflShi ftiT.echnicallAdvj sot (STA)."ISTAslare;notJlsediatialliplants (the; function [mayibeJfulfilled by onelof thelotherlojn shittlindlyiduals);iHhts:,Section;isTrevised so thatf.itidoes,not;jmply that;the'STA andf the ShiftiSupervjsor;must:be different:individualsE0ption llofithe; Commission?olicy;Statementlon Engineering ^ Expertise ~onlShiftlis; satisfied;bylassigning an;1ndividual withispecifiedi.educationalIgualjfications;toleach operating crew:as.:one of thef SR0s (preferably;the; Shift" Supervisor): required byL10;CFR 50.54(m)(2)(1)ito:proyideithe; technical:expertiseonishiftCHowever,the ISTS 5'2.2.g wordingiofGthe;ST_A;shalliprovide;..7supportitolthe Shift Supervisor;.~.1" dis' considered to~be; easily misinterpreted.to require separate; individuals 3Therefore ithe;, wording js revised so;that:the.STA function;may be provided byleither,La_s.eparate; individual .or;the individual wholaisoifulfill_s;another rolefinithe; shift command structure, s? change;1s consistentyith1TSTF-258. 5.2-7 This change revises 5.2.2c to add a note that a single Radiation Protection Technician and a single Chemistry Technician may fulfill the requirements for both units. This statement was added to clarify operational practices consistent with current licensing basis. 5~2i8 Not_a ppl i cabl ejo,_CPSESj."HSee_conversi onicompa rj son;tabl el(encl osurei68) . 0 0 002 5.2i9 A generjcjtitleihastreplacedithe; plant; specific utility:titlelfor thelcorporatelotfjerihaving :tesponsibiliti, forloverallipl ant m.5.0 005 safety: A"revienerls']!otelWasiad_dedidescribing:whenith.eluselpf gener,1c;11tles;j.slalloWedi?Kstatement was3alsp;addedlindicatjng that (theIpl antispeciffejtftiesJorlany t ' gener,1cititles;0sediwillibe provjdedjjn~ the:ESARJ Ihislchangelis consistentylthiTSTE!65; 5.3 1 This change revises Section 5.3.1 to be consistent with the current TS regarding plant staff qualifications and training.
- s New: paragraph 15!3:2iffiaddeditolensure'that'ithere;js not 05.21 1 misundetitanding) hen;cemplyingyithT10 ^ CFRl551direqui rements diThe Definitions;1n1101CFB;EfJslateEActively; pet ormi. f ng;the; functions ofian;operatorlodseniglr operatodmeans;thatlanlindjvidual;has~a po.sition~on JhelshjftIcteWithatJrequires;the]individualltoibejlicen_ sed a side finedli nit _heltacilityis;t_echnicallspecifi cati on s ,iand ithat.;gi". " j PJacinglthisjparagtaphjinithelITSptsitheIl0'CFR155:4 4requLrementifor defjnjng jn;thelfacjlitf10technica12specif,1cationgthe; function performed;by11.tcensedjndividuals'per;10 CFRi%54(m)Mddingithi paragraphjjs consisterMithithe~r_ecommendationslin'thefptil;9~; 92 gqcri.srimes;tpNZDayisland;TSIFi258; la 808M8 CPSESDifferencesfrom NUREG-1DJ -ITS5.0
! CHANGE NUMBER JUSTIFICAT10N 5.5 1 These changes revise Section 5.5.4, " Radioactive Effluent Controls Program." to reflect new 10 CFR Part 20 requirements and NRC letter dated _7/28/95 (Christopher I. Grimes to Owners renunc h ' b eler ie uu n .3 r vu. su wu ,ui.uuw ununce i wu n su . vi nom.u- 0 5.2 1 l 1431 tc be cor,;i;ter,t with 10CFR Nrt 20. AfterJssuance;ofmGeneric Letter L89 - 01310_CFR 20 ' wa sj, updated .HThe;NRCli ssu_edialdraft_ Generi c Letter &933 X 2on: proposed ^changesito,STS N.UREGS;basedlon2 theinewi10 l CFR: 20 GHhe)roposed ichangeslare e ;gonsi stentjWithithe;draftigeneric I letterJthe' Aprili921997))etter;from CCGrimes?.to2J.JDavis (withf some exceptions) and_traveleCTSTF-258f1The; proposed; change.simaintain,the samelover.all i l.evellof;effluenticontrol while: retaining thefoperational flexibility that exists:Withicurrent,TS ,under the previous;10.CFR 20. , These;changesiare; intended,tofelim_inate;possible confusion or im l implementation of_the revised 10 CFR 20. requirements:
, f' 5.5-2 This change revises Section 5.5.3 " Post Accident Sampling," to ensure capability to obtain and analyze radioactive " iodines" in lieu of
" gases." This change is consistent with the current TS and plant practices.
5.5-3 This change revises Section 5.5.8, " Inservice Testing Program." to delete "iricluding applicable supports." This change is consistent with the current TS. l 5.5-4 The Containment Leakage Rate Testing Program is added to the improved Technical Specifications (ITS) consistent with the current TS. The Containment Leakage Rate Testing Program is consistent with traveler TSTF 52. 5.5 5 This change revises Section 5.5.13. " Diesel Fuel Oil Testing Program," to l be consistent with the current TS. The details of the method applied to this test are discussed in the associated SR 3.8.3.3 Bases. [] l 5.5-6 Additional programs are added to the ITS (other than Containment Leakage Rate Testing Program discussed in CN 5.5-4). [This change adds new , Section 5.5.17. " Technical Requirements Manual," to the CPSES TS. A program description has been added to describe the licensee control of this licensing basis document and any changes to it. This program is subject to control by 10CFR50.59.] ( 5.5 7 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 5.5-8 A sentence is added to Section 5.5.9 ("The provisions of SR 3.0.2 are applicable to the Steam Generator Tube Surveillance Program test frequencies") and Section 5.5.13 ("The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test frequencies") to provide consistency with current application of these requirements. This is consistent with the use of current TS and alleviates potential confusion in the program descriptions. This change is consistent with traveler TSTF 118. CPSESDifferencesfrom NUREG-14.11 -ITS S.O 2 8/28/98
l CHANGE NUMBER JUSTIFICATION l 5.5-9 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 5.5 10 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 5.5-11 The documents referenced for the testing frequency for the VFTP do not provide frequencies for combined pressure drop tests or the heater power rating test. The CTS frequency is added for these tests. 5.5-12 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 5.5-13 This change revises Radioactiva Effluent Controls Program dose projections to meet original intent of TS prior to implementation of GL 89-01. GL 89-01 provided the wording for the STS (Section 5.5.4.e) which combined the requirements for cumulative and projected dose. This requires a plant to make projected doses for the quarter and year on a 31 day basis. It is only necessary and reasonable to make a projection for the next 31 days. A cumulative dose projection is still required for the current calender quarter and year in accordance with the ODCM. This is consistent with WOG 72. 5.5-14 Section 5.5.7 is being revised consistent with TSTF-237 WOG-85 [ ]. 0 5.5 2 The proposed changes to Section 5.5.7 provide an exception to the examination requirements in Regulatory Guide 1.14 Revision 1.
" Reactor Coolant Pump Flywheel Integrity." The proposed exception to the recommendations of Regulatory Position C.4.b would allow for an acceptable inspection method of either an ultrasonic volumetric or surface examination.
The acceptable inspection method would be conducted at approximately 10 year intervals. This change is consistent with the NRC Safety Evaluation Report associated with WCAP-14535. " Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination." 5.5-15 Not applicable to CPSES. See conversion comparison table (enclosure 6B). w - 5.Si16 The Radioactive _ Effluents 1Copttols1Programli.s;reyjsed,tojng]ude 0 5.2 1 I clarification _ statements;denotingithat3he;ptovisions'of SB;3.0.2 and_SR t3 0.3Lar_elappljgableitEthe_selagtiyftfesnTheselstatements of applicability;clarjfy;thela))oRancelforisutveil]ancEfrequency;extensfons and_al).owianceitolperform',missedjsutyjellancesEGenerjcitetter;89 017 1 Implementation"oflPrpgrammatj ciControl s]foriRa.diologigal LEffl dentJTechnical Spegifica_tfons an_d;the"Re]ocatjonlofA D etajKojiREI,Sito~theJffJ.ite; Dose Calcu]ationatanualzotme2tocess1ControllProgram v allowedlicenseesito telocatelthe Radjo]ogica]1EffluentLTechniggllSpecifjcationslandl estab]jshithe Radioactive:Effl uents."Controlltogram:j n;the1Admini strative;ControMSectJoq l i of,theHechnic_almSpecifJcations'.3Hjl sighangele.ffectively11mplementsithelCTS requi rementsithatyerf relocat_ed.,peirjGenerfciLettecl8910.1.XSince ithi s ichan adopts previous' CTS;re.qujtements',11t:is: considered;a:changelof'presentatjo method _ only.2This:changeli siconsi.s.tentj wi th "TSTFi258j 5.6-1 This change revises Section 5.6.4 " Monthly Operating Report " to reflect a revised submittal date. This change is consistent with the current TS. l 5.6 2 Not applicable to CPSES. See conversion comparison table (enclosure 68). CPSESDifferencesfrom NUREG-H31 -ITS5.0 3 8/28/98
CHANGE NUMBER JUSTIFICATION a 5.6 3 This change revises the report date in Section 5.6.2 " Annual Radiological Environmental Operating Report" to be consistent with current TS. 5.6 4 This change revises Sections 5.6.1 and 5.6.3. " Occupational Radiation Exposure Report" and " Radioactive Effluent Release Report", respectively, per l NRC letter dated July 28,1995. " Changes to Technical Specifications i Resulting from 10CFR20 and 50.36a Changes" (From Christopher I. Grimes to
- Owners Group Chairs). This change is consitent with TSTF 152.
1 ~ 5.6 5 [ ] PORV lift settings are referenced in PTLR section per "0C 57. TR.5.0 003 Rcv.1TSTE233. 4 1
~
5.6.6 The:ITSitequirementato ptgvide: documentation:offall; challenges. to 5 the, pressurizer _ power operated;r_e]jeflyalvesiotipressurizer safety valvestisidel_eteddTheirepotting of pressurizerdsafetyLand relief valve; failures'and:ghallenges;isibased onitheigujdancelin_NUREGt0694,1"THIf Related_R_equirementsifor;New;0peratingLicensees. Tithe _guidanceiofNUREGi 0694fstatesi2Assureithatlany;failutelof aLPORVIorJsafety~ valve tojclose:will be~ reported toitheiNRC:promptlyGll;challengesito the1PORVs or; safety valvesishould!be; documented,jn;the annua]irepott;2NRC;GeneticLLetter;97-02!
" Revised; Content.s'ofithe1Honthly;0perating Report"srequests the: submittal of less informati_onlinitheimonth]yloperating; report?5Jhelgenerjc1]etter identjfiesiwhatineeds'iolbe;repotted ito;suppottithe;NRQfetformance;Indjcatot Program. land availabilitylandicapacity;statistigsfMhe:generjc;1ettet;does not specifjcally;identifyltheineeditof report 1 challenges ^to;the' pressurizer safety 1and ~ re]iefyalves .iThi s;changeli s; consistent ) tith ;TSTF-258 l {
l 5.7 1 This changc rcvises "igh Radiation Area to incorporate changes con;i;t1 1 5 2-1 I Imammmme l with [the curr;nt TS]. Specifically, di;tonce; fic;; the radiaticn ;00 rec. Section;5;7;isitevised iniaccordance;withi10 CFR 20A601(c);andJpdates;the'aggeptable'alternat.elconttolsito~th seigiyen11n:10, 9 CFR120;1601&TMseIchagges:areiconsistentMth the! draft;GenetiplLetterI(933 i X R on ptoposedi?hanges!to;STSINUREGsibasedion;thernewl10 CFR;2.0 and;the D lett.erittom;CZjtimesT;_NR_G71to"JZDails EN_EIIdatedfApr1129,5199EThi s ghange21gcensjstent"withTTSJFl258 8ndienc_ompassesithelN_RC'"commentsion 6L11/9826dditionalltechnt?a];cha@esima.deltclSectioLS . tate:jdentifiedland justifjed] 5.7-2 This changc reviscs "un;uthoriccd" to "in;dvertant" in the "igh 0424 R; diction Arce ;ection to r;ficct 'RC's positica as st;tcd in RC S.38. Scction 1.5 Tcserding physical kiricts for "igh R; diction f Arass. This is consistcat with travcler TSTF 157. ITX52 2.;ejsjeVAed consj stent;withiCIS;6112;thatjalloiwslanylindiyidualiorlgrguplofdindivj duals to;enteria:highlhighitadiationiarea;(doseltat_esJgreaterithan11.0jremlhourlat 30;cm)1 accompanied;bylaEjindividua]Iquali.fiedjj[tadiatjon~ptotection c procedures;withlair_adiation doseTate~mofiitotigg deyjeelighe3ualified 10d ividuEisItMpon11bleIforlpto1Lding po_sitiyCcontrolland shall; perform periodicItadiationZsdrye1]Langes'atlthelequegcyjspecified dgitheJWPEJhe CTSltequitement_s3]lowlthe qualifiedlindividualito enter 2allockedihigh radiatioCareaTwith;plantHvor);ers3rithoutifjrstihavjng;to30terlthe;are~ 7 4 8/2888 CPSESDifferencesfrom NUREG-1431 -ITS 5.0
Cr%NGE NUMBER JUSTIFfCATf0N
- ~
termineido_s_e;ratesjandthen:exitthe;arealto;proy1deido_se2 i ate 0 5.2-1 T information;tolthelp] ant" workers k 2and;then7reenterithelarea Zjilhis fl exj bility;,ts11Ekeeping yttLtheXAs].ow;Ls]Leasonably,Achievabl e; i rincipleTh11e~najntaipg appropri; ate 2adiatjort1WorkerJpractices;; j 5.7 3 Not applicable to CPSES. See conversion comparison table (enclosure 6B). S
.7 .4 ITS;5.7.2.f 1sireyisediconsistent 3 with CTS _6.12.toldelete;the phrase 0 5.2 1 "thatfisicontrolledlasla highlradia. tion, area Ellhe proposed change r
would precludelhaving ,to.: post:an;:ar.ea aroundLthelhigh-high radiation area;asla'highladiation .arealwhen;theiarea;may;notimeet.the: definition of;a high; radiation; area; l l i 1 j
)
I i i i 5 8/2888 CPSES Differencesfrom NUREG-JD1 -ITSS.O
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 5.0 Page 1 of 6 TECH SPEC CHANGE APPLICABILITY DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY NUMBER DESCRIPTION No No Yes No 5.1-1 Revises Section 5.1.1 to maintain WCNOC current technical specifications (CTS). The Plant Manager does not currently approve prior to implementation each proposed test. experiment or modification to systems or equipment that affect nuclear safety. Revises Section 5.1.1 to maintain Callaway CTS that the No No No Yes 5.1-2 plant manager approves prior to implementation each proposed test, experiment or modification to systems or equipment that affect nuclear safety and are not addressed in the FSAR or TS. 5.2-1 Revises Section 5.2.2.a to reflect the CTS. This change Yes Yes No No clarifies the application of the unit staff provisions to Wolf Creek is a Callaway is a single unit site single unit site both units. 5.2-2 The requirement for the presence of a RO or a SRO in the Yes Yes Yes Yes , control room may be deleted from the ITS since this 0 5.2-1 requirement is adequately controlled by 10 CFR - 50.54( ). This change is consistent with_tIAyal " TSTF .258p , 5.2-3 C 5cd T kIection;5;2;2d;(ISTS;5;2;2ehi sgevj sed ,from NAYes NAYes NAYes NAYes specific; working _ hour;11mitsi t ofadministrative procedures to 0-5.2-1 ]
-JN a1 Q houts! __
5.2-4 Section 5.2.2.a describes the unit staff requirements for No No Yes Yes non-licensed operator staffing for multi-unit sites. This DCPP is a multi- CPSES is a multi-change reflects plant specific requirements for a single unit plant unit plant unit site and is consistent with the current TS. 5.2-5 Not Used NA NA NA NA CPSES Conversion Comparison Table -ITS5.0 8/28/98
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 5.0 Page 2 of 6 TECH SPEC CHANGE APPLICABILITY DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY NUMBER DESCRIPTION Yes Yes LA 50/36 moved Yes Yes 5.2-6 - ! .2.27 L d^ggibe the current [ licensing Revises p'er STA. and eliminate the u u e ui.j aip aecnnicoi m text to FSAR Q.5.2-1 basi . Section 13.1 which dvisor,(STA). permits on shift SRO to fill STA _ pu m iun Yes No No 5.2-7 Revises 5.2.2c to add note that a single Radiation No Protection Technician and a single Chemistry Technician may Not current Wolf Creek is a Callaway is a procedure or single unit site single unit site fulfill the requirments for both units. operational requirement Yes No No No 5.2-8 Revises 1 Sections;5.242.and 5.3.1?to reflect; License DC-5.0-002 Amendment 128/126; dated 4/11/98 which changed; requirements LA128/126 m for othe DCPP2 0per.ations;Directorg Yes No No 5.2-9 A1 generjc title;has; replaced;the;plantispecific utility No TR-5.0-005 titl_eifor;the, corporate;.off,1 cert h aving; responsibility,for overallcplant, safety 4 Yes Yes Yes Yes 5.3-1 Revises Section 5.3.1 to be consistent with current TS regarding plant staff qualifications and training. LA 43/42 7 - N Yes Yes Yes Yes 5.3 2 New paragraph 5.3.2;is;added.to; ensure thatythere_is not 0-5.2-1 T , nisunderstand'ing when complying.with:10 CFR. 55.4 requirements, j Yes Yes Yes Yes 5.5-1 Revises Section 5.5.4. ' Radioactive Effluent Controls 0-5.2-1
~ N t now in crR Part 20 requirema M Procram " +a .
lcttcr dctcd '/2^./05 corsutcr.t 7th p u R cd tro.Ilcr. Revises Section 5.5.3. " Post Accident Sampling." to ens Yes Yes Yes Yes 5.5 2 the capability to obtain and analyze radioactive " iodines" in lieu of
- gases." This change is consistent with the current TS and plant practices.
Revises Section 5.5.8. " Inservice Testing Program." to Yes Yes Yes Yes 5.5-3 delete " including applicable supports." This change is consistent with the current TS. CPSES Conversion Comparison Table -ITS5.0 8/28/98
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 5.0 Page 4 cf 6 TECH SPEC CHANGE APPLICABILITY DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY N'JMBER DESCRIPTION The documents referenced for the testing frequency for the No Yes Yes Yes 5.5-11 Ventilation Filter Testing Program (VFTP) do not provide See CN 5.5-12 frequencies for combined pressure drop tests or the heater power rating test. The CTS frequency is added for these two tests. No No No 5.5-12 The referenced frequencies for the tests listed in the Yes Ventilation Filter Testing Program (VFTP) were evaluated as part of the DCPP 24 month fuel cycle program (see LAR %- < 09). Yes Yes Yes 5.5-13 Revises Radioactive Effluent Controls Program dose Yes projections to meet original intent of TS prior to implementation of GL 89-01. (WOG-72) Yes Yes Yes 5.5-14 Section 5.5.7 is being revised consistent with TSTF_-237 e Yes WOG-65 [ ] The proposed changes to Section 5.5.7 provide an exception to the examination requirements in Regulatory l Q-5.5-2 l Guide 1.14. Revision 1. " Reactor Coolant Pump Flywheel t Integrity." No No 4 No Yes 5.5-15 This change provides a time interval of within 31 days after removal in which a laboratory test of a sample obtained from the charcoal adsorber must be tested. This change is consistent with the Callaway CTS. - Yes 41 TheRadioactive; Effluents 1 Controls;Progrands; revised.to Yes Yes Yes 0-5.2 1j ! (( i ncl ude tcl arMj estion : statements ,denoti ng ;that;the provisions;of x5R 3.0.2tand.SR,3A3,-.are appljcablef to.these activities! Revises Section 5.6.4. " Monthly Operating Report." to No Yes No No 5.6-1 Callaway CTS reflect a revised submittal date. DCPP CLB consistent LAR 94-14 Wolf Creek CTS with NUREG-1431 consistent with consistent with , NUREG-1431 NUREG-1431 Deletes the EDG Report to reflect the recormendations of GL Yes No - not in CTS No - not in CTS No - not in CTS 5.6-2 94-01 ' Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators." dated May 31 1994. CPSES Conversion Comparison Table -ITS5.0 8/28/98
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 5.0 Page 5 of 6 TECH SPEC CHANGE APPLICABILITY DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY NUMBER DESCRIPTION Yes Yes Yes Yes 5.6-3 Revises report date in Section 5.6.2. " Annual Radiological Environmental Operating Report" to be consistent with Consistent with See LA 42/28 current TS. original TS and LA 78/77. Yes Yes Yes Yes 5.6-4 Revises Sections 5.6.1 and 5.6.3. " Occupational Radiation Exposure Report" and " Radioactive Effluent Release Report." respectively, per NRC letter dated July 28,1995. " Changes to Technical Specifications Resulting from 10 CFR 20 and 50.36a Changes" (From Christopher I. Grimes to Owners Groups Chairs). This change is consistent with TSTF-152. Yes Yes Yes Yes 5.6-5 [ ] PORY lift settings are referenced in PTLR section per 1. HTR-5.0-003 ll TSTF-233 '.J00 57. Rcv N - n.
,r y
Yes Yes Yes yes
/5,6-6 The:ITS irequirementito; provide;documentationloftall 0-5.2-1 j challengestt olthe pressurizer:powerioperatedirelief, valves -
or pressuCizerisafetyivalves11sfiletedt i Yes Yes Yes Yes _ , , ,_
-1 Rcvisc; l'igh R; diction Arca to incorporst con;i; tent 0-5.2-1 chans ; .;is.. -. m m . ~. y .Sectioni5.7A i strevised jn accordancepith;10;CFR120;1601(c)iand; updates 1the; acceptable al ternateicontrol sito;those.gi ven;1ng0;CFR,2031601.
Yes Yes Yes 5.7-2 I Cheng; unauthoriccd to ;nad.crtcat" in the lligh Radiation Yes Arca acction to rcficct the ':RC'; p;;ition ;; :tsted i- RC 0-5.2-1/ l 0.30, 5cction 1.5 cc;;rding phy;ical bcrricr; for "igh Radiction " cas. This changc i; con;i;tcnt .;ith TSTF 157 ITS;5.7.2.e 1s; revised;consistentiwith CTS:6.12;thatiallows any;indivjdual;or; group.;ofaindfvidualsito; enter;a high.high radiation area 3(dose,ratesigreater,;thanal;0 fem / hour at.30
' cm)taccompanjed by,an2 i ndividuahqualified inJadiation protection. procedures <with a gadiation,dosetrate. monitoring vice; ,
CPSES Conversion Comparison Table -ITS5.0 8/2888
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 5.0 Page 6 cf 6 TECH SPEC CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY f - M4 ITS;5;7,2.f fis- revisediconsistent!with;C15;.6',12!to; delete the'phrasefthat;js controlled [asta;highiradiation; area *g-Yesi Yes! Yes '(es 0-5.2-1 ' l [ The; proposed,changeyould! preclude,.having1to. post;an area 1 around.the z high-high radiation area as.athigh radiation _ area ( when,the, area _may,not,meetithe; definition of,a high radiation area;
\
i CPSES Conversion Comparison Table -ITS5.0 8/28/98 a
.- -_ . . . - . . ~ . -
l t ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 5.5-2 APPLICABILITY: CA, CP, DC, WC REQUEST: Difference 5.5-14 Comment: WOG-85 has not yet become a TSTF. Use current ITS. FLOG RESPONSE: WOG-85 has been approved by the TSTF and is designated as TSTF-237. This traveler has been submitted to the NRC and is under review. The proposed wording in TSTF-237 was modified from WOG-85 and these modifications have been incorporated into the ITS. The FLOG continues to pursue the changes proposed by this traveler. l For Wolf Creek, this change was approved by the NRC in Amendment No.106 dated June 24, l 1997. Therefore, the wording in ITS 5.5.7 is consistent with Amendment No.106. l ATTACHED PAGES: l Attachment 10 CTS 3/4.4 l i Enct 2 3/4.4-33 ( Enci 3A 18 Enc! 38 13
- Encl 4 70 l
l Attachment 18 ITS 5.0 l Enci5A Traveler Status sheet and 5.0-12 l Encl 6A 3 4 Encl 6B l l l 1
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s.bmu a .- ...rm m u n e , e.c.m..s be . bo 2. s L a o_ 1.b. s. 1. o_o . sm._ J.. be wm m .rv. mm u e , fica service. SURVEILLANCE RE0VIRF,11ENTS 4.4.9 In addition to the requirements of Specification 4.0.5. each reactor coolant 31042M d ; pump flywheel shall be inspected per the recommendations of Regulatory Position lieu ~of? Position C.4.b of Regulatory Guide 1.14. Revision 1. August 1975. In:6 d he sol'unelfromI.****d. CfEb(IEand;C"4;b(2)Ra qualiflediin;placelVTJa*=ination% 1 thannner botof thetflywheeleto'the r cir:ler6ne halEof{he:outip raalus
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i l l 4 6 CPSESMark-up ofCTS 3N.4 3M 433 8/28/98
CHANGE NUMBER NSilC DESCRIPTION described above and the current individual Technical Specifications which contain the operability requirements for the required components or equipment that meet criterion 3, the RCS Structural Integrity specification is deleted instead of relocated. 10 02 A Consistent with NUREG 1431, the Reactor Coolant Pump flywheel inspection requirement has been moved to Section ITS 5.5.7. 10 03 LS 37 onsistent with travele SIF123,7_ the Reactor 0 5.5 2 Coolant Pump Flywheel Ins am is revised to provide an exception to the examination requirements in . Regulatory Guide 1.14 Rev 1. The exception (to Regulatory l Position C.4.b(1) and C.4.b(2)) allows for an acceptable inspection method of either an ultrasonic volumetric, or surfra anmination. The inspection would conducted at a ximat_ejten year intervals coinciding with the Inservice Inspection schedule required by ASME Section XI. , The acceptability of the proposed change is established in l WCAP 14535. Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination, with Limitations. The NRC's Safety Evaluation of the topical concluded that the inspections i should not be completely eliminated but should be conducted i during scheduled inservice inspections or RCP maintenance at approximately 10 year intervals. The proposed change is consistent with these recommendations. 11 01 R This change in conformance with NUREG 1431 Rev.1, removes l the reactor coolant system vents specification from the Technical Specifications. The requirements for the reactor coolant system vents will be relocated to a licensee controlled document as identified in the Conversion Comparison Table (enclosure 38). CPSES Description of Changes to CTS 3M.4 18 808/98 i
CONVERSION COMPARISON TABLE - CURRENT TS 3/4.4 rege13,f13 TECH SPEC CHANGE APPLICABILITY NUPEER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 10-02 The Reactor Coolant Pimp flywheel inspection requirement has No - Amendment Yes No - Amendment 89 No - Amendment 103 A been moved to Section 5.5.7 in the improved TS. 98/97_ relocated RCP relocated to USAR relocated to FSAR flywheel Chapter 16 and CTS Chapter 16 and CTS surveillances to 6.8.5b.. 6.8.5.b. CTS 6.8.4.1. 10-03 The Reactor Coolant Pump Flywheel Inspection Program is No - See CN-02 Yes No - See CN-02 No - See CN-02 LS-37 revised to provide an exception to the examination LS-1 in the ITS LS-1 ta the ITS LS-1 in the ITS requirements in Regulatory Guide 1.14. Rev 1. The exception Section 5.0 Section 5.0 Section 5.0 (to Regulatory Position C.4.b(1) and C.4.o(2)) allows for an package. package. package. acceptable inspection method of either an ultrasonic volumetric, or =fam examination. The inspection would conducted a (approxim Maten year intervals coinciding lQ5.5-2 l with the Inservice ins tion schedule required by ASME - Section XI. 11-01 Removes the reactor coolant system vents specification from No. Amendment 98/97 Yes - To be No - Amendmer 89 No - Amendment 103 R the Technical Specifications. The requirements for the relocated relocated to the relocated to.:JSAR relocated to FSAR reactor coolant system vents will be relocated to a licensee requirement to TRM. Chapter 16. Chapter 16. controlled document. Equipment Control Guidelines (ECG). CPSES Conversion Comparison Table - CTS 3M.4 S/158 7
IV. SPECIFIC NO SIGNIFICANT HAZARDS CONSIDERATIONS NSHC LS 37 10 CFR 50.92 EVALUATION FOR l TECHNICAL CHANGES THAT IMPOSE LESS RESTRICTIVE REQUIREMENTS WITHIN THE TECHNICAL SPECIFICATIONS l Consistent with travelerhF123Z;"0Ck the Reactor Coolant Pump Flywheel 0 5.5 2 l Inspection Program is rev neu a ,cevi e an exception to the examination requirements in Regulatory Guide 1.14. Rev 1. The exception (to Regulatory Position C.4.b(1) and C.4.b(2)) allows for an acceptable inspection method of either an ultrasonic volumetric, or surface examination. The inspection would conducted at ten year intervals coinciding with the Inservice Inspection schedule required by ASME Section XI. The acceptability of the propos2d change is established in WCAP-14535, Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination, with Limitations. The NRC's Safety Evaluation of the topical concluded that the inspections should not be completely eliminated but should be conducted during scheduled inservice inspections or RCP maintenance at approximately 10 year intervals. The proposed change is consistent with these recommendations. 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:
"iiie Commission 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 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 significant hazards consideration standards:
- 1. Does the change involve a significant increase in the probability or l
consequences of an accident previously evaluated? The safety function of the RCP flywheels is to provide a coastdown period , during which the RCPs would continue to provide reactor coolant flow to the l reactor after loss of power to the RCPs. The maximum loading on the RCP i l CPSES No Significant Ha?,ards Consideration - CTS 3N.4 70 8/28/98 l
l l l Industry Travelers Applicable to CTS Section 6.0/ITS 5.0 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF-9, Rev.1 Incorporated B-PS NRC Approved. TSTF-37, Rev.1 Incorporated 5.6-2 DCPP only TSTF-52, Rev.1 Incorporated 5.5-4 Incorporated draft Rev. (. 3.6.1-6 1 per,Q3.6.1-6z TSTF-65, Rev.' 1 Not Incorporated NAS.2-9 Not NRC approved aM 1R 5.0 005 tear;;;rcut-cifdate. TSTF-106, Rev.1 Not incorporated NA Retain CTS TSTF-115 Not incorporated NA Not NRC approved as of traveler cut-off date. TSTF-118 Incorporated 5.5-8 NRC Approved 1R 5.0 006 TSTF_;19 No:Ir. crpora::d NA "ctoinCIS 1R 5.0 006 TSTF-120, Rev.1 Not Incorporated NA Retain CTS qR 5.0 006 TSTF-121 !acorporated Sr2-2 0 5.2 1 TSTF-152 Incorporated 5.6-4 NRCApproved 1R 5.0 006 TSTF-157 !acorporated 577 -1 0 5.2 1 WOG-67, Rev.1 Incorporated 5.6-5 WOG-72 Incorporated 5.5-13 e m
"/OC-35TSTF .237 Incorporated 5.5-14
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.t CPSESMarkup ofNUREG-lui -ITS LO LO-12 8/28/98 1
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CHANGE NUMBER JUSTIFICATION 5.5 9 Not applicable to CPSES. See conversion comparison table (enclosure 68). 5.5 10 Not applicable to CPSES. See conversion comparison table (enclosure 6B). l 5.5 11 The documents referenced for the testing frequency for the VFTP do not provide frequencies for combined pressure drop tests or the heater power rating test. The CTS frequency is added for these tests. 5.5 12 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 5.5 13 This change revises Radioactive Effluent Controls Program dose projections to , meet original intent of TS prior to implementation of GL 89 01. GL 89 01 l provided the wording for the STS (Section 5.5.4.e) which combined the requirements for cumulative and projected dose. This requires a plant to make projected doses for the quarter and year on a 31 day basis. It is only necessary and reasonable to make a projection for the next 31 days. A l cumulative dose projection is still required for the current calender quarter and year in accordance with the ODCH. This is consistent with WOG 72. 5.5-14 Section 5.5.7 is being revised consistent with STFf237 [ ]. 0 5.5 2 l The proposed changes to Section 5.5.7 provide a .: = % .un o the - - - - - - examination requirements in Regulatory Guide 1.14. Revision 1.
" Reactor Coolant Pump Flywheel Integrity." The proposed exception to the recommendations of Regulatory Position C.4.b would allow for an acceptable inspection method of either an ultrasonic volumetric or surface examination.
The acceptable inspection method would be conducted at approximately 10 year
- intervals. This change is consistent with the NRC Safety Evaluation Report l associated with WCAP 14535, " Topical Report on Reactor Coolant Pump Flywheel l Inspection Elimination."
5.5 15 Not applicable to CPSES. See conversion comparison table (enclosure 68). 5,5-16 The;RadioagtjveJffluents Conttpls1rogramlis;revj sed;to lincl ude 0 5.2 1 clarjficationistatementsiden_ot1 @ atithe;provisionsrof_SR;3iO J t and SR,,310.33rgapp]fcablelto~itMseJactiyitiesZgThese; statements l priapplicabiljttc]atify;the;allgjn:cgfodsktail]anceiftequency'extegsjons ! andlalloRange~tolperfors;missedsetviellances2iGeneticletMtip9101; Eleplementattog;ofiPlogriammaticIControlslfo~clRadiologicaHEff]uentiTechniga], Specifj eationslandit_helelocatioef2 Deta1]s29fiRETS;tgitg0ffsite; Dose Ca] cul atigManda]Ioithe1Pr#gGonttolftpgtasZallowd 'licenseesito telocatelthe_RadiologicaEEffleetUechnical2 Spec 1[icationsiand: establish;t!g Radioa.ctiyel Effluents LControlJftgjraalinithe2Administ ratileiC,ontrols;Segtj611 ofithelechnical15pecifJcatio!Ls3Hhigchaggeleflectivelylimp]ementsl;theM l requireme!Ltsithat3ereEtelocatedlpenGenetfciLettet189101.HSincelthisichange adopts:ptevjous1CTsirequirementsrit;1s:conside. red.:a: change:of; presentation
- methodLonly.51This change;isIcon_tjstentAlthlTSTFJ2582 5.6 1 This change revises Section 5.6.4, " Monthly Operating Report." to reflect a revised submittal date. This change is consistent with the current TS.
5.6 2 Not applicable to CPSES. See conversion comparison table (enclosure 68). CPSESDifferencesfrom NUREG-1D1 -ITS5.0 3 8/28/98
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 5.0 Page 4 cf 6 TECH SPEC CHANGE APPLICABILITY DIABLO CANYON COMANCHE PEAK WOLF CREEK CAllAWAY NUMBER DESCRIPTION Yes Yes Yes 5.5-11 The documents referenced for the testing frequency for the No Ventilation Filter Testing Program (VFTP) do not provide See CN 5.5-12 frequencies for combined pressure drop tests or the heater power rating test. The CTS frequency is added for these two tests. No No Mo The referenced frequencies for the tests listed in the Yes 5.5-12 Ventilation Filter Testing Program (VFTP) were evaluated as part of the DCPP 24 month fuel cycle program (see LAR 96-09). Yes Yes Yes Yes 5.5-13 Revises Radioactive Effluent Controls Program dose projections to meet original intent of TS prior to implementation of GL 89 01. (WOG-72) Yes Yes Yes Yes 5.5-14 Secti .5.7 is being revised consistent wit TF. e [ ] The proposed changes to Section ., provitfe tion to the examination requirements in Regulatory 0 5.5-2 l Guide 1.14. Revision 1. " Reactor Coolant Pump Flywheel Integrity." No No No Yes 5.5-15 This change provides a time interval of within 31 days after removal in which a laboratory test of a sample obtained from the charcoal adsorber must be tested. This change is consistent with the Callaway CTS. Yes Yes Yes Yes 5,5p16 The_ Radioactive E1 ffluents1 Controls: Program 11sireyised to 0-5.2 1 l include; clarification,statementEdenoting;that the provisions of SR t3.0,2;and;SRl3,0i 3 are; applicable,to these activitiesA Yes No No 5.6-1 Revises Section 5.6.4. " Monthly Operating Report." to No Callaway CTS i DCPP CLB consistent LAR 94-14 Wolf Creek CTS reflect a revised submittal date. consistent with consistent with with NUREG-1431 NUREG-1431 NUREG-1431 1 Yes No - not in CTS No - not in CTS No - not in CTS 5.6-2 Deletes the EDG Report to reflect the recommendations of GL , 94-01. " Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators.* dated May 31. , 1994. 8/2&48 CPSES Conversion Comparison Table -ITS 5.0 i
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 5.5-3 APPLICABILITY: CA, CP, DC, CA REQUEST: ITS 5.5.4 b&g and Difference 5.5-1 Comment: Changes are based on a yet unnumbered traveler. Use current ITS. FLOG RESPONSE: Traveler TSTF-258 has been submitted to the NRC for review. This traveler superseded travelers, TSTF-86, TSTF-121, and TSTF-167. TSTF-258 is based on the recommendations in the April 9,1997 letter from C. Grimes (NRC) to J. Davis (NEI), with some exceptions. The FLOG submittals have been revised to incorporate TSTF-258. The latest industry status on TSTF-258 is that the NRC has requested changes to Section 5.7, High . Radiation Area. See response to Comment Number 5.7-1 for how the FLOG has addressed I the NRC comments on TSTF-258. 1 I ATTACHED PAGES: l l See markups associated with Comment Number O 5.2-1. l l 1 l l l 4 f l l
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 5.5-4 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 5.5.4 e and Difference 5.5-13 Comment: WOG-72 boa not yet become a TSTF. Use current ITS. FLOG RESPONSE: This change to ITS 5.5.4 e was prepared in accordance with WOG-72, Rev.1 which is currently under TSTF review. The change specifies that the requirement to determine cumulative dose contributions from radioactive effluents need be done on a current quarterly and annual basis instead of every 31 days. We believe there is a strong technical basis for this change to the ITS. We request that the NRC keep this as an open item under the assumption that the traveler will be approved prior to issuance of the SER. ATTACHED PAGES: None. J d 9
-- - _ _ - ._ , . _-- __ ._~ - -= . -
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 5.5-8 APPLICABILITY: CA, CP, DC, WC REQUEST: CTS 3.7.6 (3.7.5.1 and 3.7.6.1 - DCPP and 3.7.7.1 and 3.7.8 -CPSES) and Change 10-08-A Comment: It should be specifically noted as to which CTS requirements were carried over to the VFTP and which were deleted (as well as which section of what standard justified the duplication deletions). Provide explanation and justification. FLOG RESPONSE: Attached Table 5.5-8 describes where the CTS SRs for plant ventilation systems were moved to in the ITS. The following provides justification and clarification for those CTS SRs that were not moved to either the " Ventilation Filter Testing Program (VFTP)" in the ITS, or the ITS SRs: DOC 10-07-LG (Not applicable to CPSES) moves the requirement to verify Cor, trol Room temperature once every 12 hours to a licensee controlled document. This DOC nas been revised to include the fol owing additional justification: "The NRC has previously approved moving this type of detailed information or specific requirements to a licensee controlled document that is maintained in accordance with applicable regulatory requirements. This temperature is not an initial condition or controlled parameter for any licensing-based accident scenarios Also, its inclusion in the ITS is not necessary to adequately protect the health and safety of the public. The basic requirements for maintaining OPERABILITY are still retained in the technical specifications." Per DOC 10-17-A, the SR to measure ventilation system flow rate is not identified as a separate SR in the ITS because it is verified as part of the other in-place filter tests that are specified in ITS 5.5.11. The same DCC applies to CTS SR 4.7.6.1 b 3 for Diablo Canyon, CTS SR 4.9.13 b 3 for Wolf creek, and CTS SR 4.7.7 b 3 for Callaway for the same reason. DOC 10-08 A has been revised to show that some CTS SRs were rnoved to the ITS SRs. ATTACHED PAGES: Table 5.5-8 i Attachment 13 CTS 3/4.7 - Plant systems l Encl. 3A 12 Enci 38 11 e 4 1 I
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l MWCC. M CA% ECPAM ro ;lTS SR Licensee; I 3:iDCPPl~f QENFTP??*k M8N $$ S kiOW ' MI@$N MMNW TS$V N 'Gd ?<.EW$d @4 ,MPGIN IDTS dCTS SRl (CTS SR$ SCTS'SRiI l M$$l%,SN DocuinOnt l 4.7.5.1 a 4.7.6 a 4.7.6 a N/A X l l ! 4.7.5.1 b 1 4.7.6 b 4.7.6 b 4.7.7.1 a 3.7.10.1 1 4.7.5.1 b 2 N/A N/A N/A 3.7.10 Bases l 4.7.5.1 b 3 N/A N/A N/A 3.7.10 Bases l 4.7.7.1 b ITS 5.5.11 3.7.10.2 4.7.5.1 c 1 4.7.6 c 1 4.7.6 c 1 4.7.7.1 b 1 ITS 5.5.11a&b 4.7.5.1 c 2 4.7.6 c 2 4.7.6 c 2 4.7.7.1 b 2 ITS 5.5.11c 4.7.5.1 c 3 4.7.6 c 3 4.7.6 c 3 4.7.7.1 b 3 See DOC l 10-17-A l 4.7.5.1 d 4.7.6 d 4.7.6 d 4.7.7.1 c ITS 5.5.11 & 3.7.10.2 l 5.5.11 c ! 4.7.5.1 e 1 4.7.6 e 1 4.7.6 e 1 4.7.7.1 d 1 ITS 5.5.11d 3.7.10.2 l 4.7.5.1 e 2 4.7.6 e 2 4.7.6 e 2 4.7.7.1i 3.7.10.3 l 1 4.7.5.1 e 3 4.7.6 e 3 4.7.6 e 3 4.7.7.1 j 3.7.10.4 4.7.5.1 e 4 4.7.6 e 4 4.7.6 e 4 4.7.7.1 d 2 ITS 5.5.11e 3.7.10.2 l 4.7.5.1 f 4.7.6 f 4.7.6 f 4.7.7.1 e ITS 5.5.11 & 3.7.10.2 5.5.11a 4.7.5.1 g 4.7.6 g 4.7.6g 4.7.7.1 f ITS 5.5.11 & 3.7.10.2 5.5.11 b i 4.7.7.1 g ITS 5.5.11 & 3.7.10.2 5.5.11a 4.7.7.1 h ITS 5.5.11 & 3.7.10.2 l 5.5.11 b 4.7.6.1 a 1 4.9.13 a 4.7.7 a 4.7.8a 3.7.12.1 DC&CP 3.7.12.1 3.7.13.1 WC&CA Bases CP 4.7.6.1 a 2 N/A N/A N/A 3.7.12.1 Bases 4.7.8b ITS 5.5.11 3.7.12.2 4.7.6.1 b 1 4.9.13 b 1 4.7.7 b 1 4.7.8 b 1 ITS 5.5.11a&b 3.7,12.2 DC 3.7.13.2 WC&CA NA CP 4.7.6.1 b 2 4.9.13 b 2 4.7.7 b 2 4.7.8 b 2 ITS 5.5.11c 3.7.12.2 DC 3.7.13.2 WC&CA NA CP 4.7.6.1 b 3 4.9.13 b 3 4.7.7 b 3 N/A See DOC 10-17-A 4.7.6.1 c 4.9.13 c 4.7.7 c 4.7.8 c ITS 5.5.11 & 3.7.12.2 DC&CP 5.5.11 c 3.7.13.2 WC&CA 4.7.6.1 d 1 4.9.13 d 1 4.7.7 d 1 4.7.8 d 1 ITS 5.5.11d 3.7.12.2 DC&CP 3.7.13.2 WC&CA l i
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l CHANGE i NUMBER MillC DESCRIPTION 1 l 10 08 A The description of the ventilation filter specific testing requirements i and the required surveillances are moved to the Ventilation Filter l Testing Program (VFTP) as defined in the Administrative Controls of the ITS. No technical changes to requirements or test specifics except as noted by separate change numbers are made. A new SR is added that requires [CR ventilation and primary plant ventilation) system filter testing in accordance with the VFTP. The requirements o_f this specification are 1) moved to Section 5.5.11 of the TTM or
.. ved.to1IISiSR_sCor;2) deleted sir.cc they arc duplicated ir, Regulatory Cuidc 'RC) 1.52, revisicr. 2. [ ANSI N510 1950, 0-5.5 8 h
- A 11t* T 11 f" n A inon 9 vi ru w a n sus Asvu,J.
10 09 LS-27 Not applicable to CPSES. See Conversion Comparison Table (enclosure 38). 10 10 TR-1 The SR is revised to allow credit for an actual actuation, if one occurs, to satisfy the SRs. The identification of the initiating signal is moved to the Bases. 10-11 LS-19 The frequency of the surveillance requiring verification of the CR ventilation system capability to maintain a positive pressure is relaxed to [18] months on a STB, consistent with NUREG 1431. The new frequency requires one of the 2 DC ALL 001 trains to be tested every [18] months instead of both trains every [18] months. The most likely cause of a failure to achieve the required pressure is a failure of the ventilation pressure boundary. Thus when one train successfully demonstrates the ability to maintain the pressure, in all likelihood the other train will also. This results in less testing of the CR ventilation system than is required by the CTS. 10 12 LS-32 Not applicable to CPSES. See Conversion Comparison Table (enclosure 3B). 10 13 LG Not applicable to CPSES. See Conversion Comparison Table (enclosure 3B). 10 14 A Not applicable to CPSES. See Conversion Comparison Table (enclosure 38). 10 15 LG Not applicable to CPSES. See Conversion Comparison Table (enclosure 3B). 10 16 LG Not applicable to CPSES. See Conversion Comparison Table (enclosure 3B). 10 17 A The SR to measure ventilation system flow rate 4 not identified as a separate SR in the ITS because it is verified during the other in-place filter tests (see ITS 5.5.11). CPSES Description of Changes to CTS 3N. 7 12 8/28/98
CONVERSION COMPARISON TABLE - CURRENT TS 3/4.7 11*/16 TECHNICAL SPECIFICATION CHANGE APPLICABILITY NUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY 09-07 A note is added to the [SSW) surveillance that clarifies system NO: ASW only YES YES YES A operability requirements. Isolation of [SSW] flow to individual supplies CCW components does not render the system inoperable. heat exchangers. 10-01 The DCPP specific text description, definition of a ventilation YES NO NO NO LG train, is deleted from the LCO and moved to the Bases. 10-02 The APPLICABILITY and ACTIONS are revised to include *during YES NO: part of CTS. YES YES M movement of irradiated fuel assemblies." 10-03 The SR for the control room ventilation system is revised to NO: Plant YES NO: refer to NO: refer to LS-7 require the filtration units without electric heaters to be configuration 10-22 M. 10-22-M. tested for only 15 minutes instead of 10 hours. includes heaters. 10-04 An ACTION statement is added to require entering 3.0.3 if two YES YES YES YES A trains of the control room (CR) ventilation filter system are inoperable in MODES 1. 2. 3. or 4. 10-05 A new option is added to the ACTIONS by NUREG-1431 that allows YES NO: part of CTS. YES YES LS-18 the suspension of CORE ALTERATIONS or movement of irradiated fuel versus placing the ventilation system in the recirculation mode. 10-06 The details and description of the required actions and the YES NO: not in CTS. YES YES LG monthly SRs for train operability are moved to the Bases. 10-07 The surveillance that verifies control room temperature once per YES: moved to NO: not in CTS. YES: moved to YES: moved to LG 12 hours is moved to a licensee-controlled document. ECG. USAR. FSAR. 10-08 The description of the ventilation filter specific testing YES YES YES YES A requirements are moved to the VFTP. as d gerad " ..~ Adminktrate enntenh nf the ITS nrJoyedstoJTS_SRs. &4etegr M-ira dus;licatcd ir, thc applicabic '10 c- Storm.'A SR is i -Q-5.5-8 l added that requn n u.n venuiauun anu primary plant ver.tilation system] filter testing in accordance with the VFTP. CPSES Conversion Comparison Table- CTS 3N.7 8/2&98 _ _ ._ _ ._ __ = _ ._ -
. . . _ . . _. .. .. .-__._ _.. _ . . - . . . _ = .. . . . . , . . _ - _ _ _ _
i i I ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: Q 5.5-14 APPLICABILITY: CP l REQUEST: ITS 5.5.11.e and CTS 4.7.8.d.3 (Comanche Peak) Comment: The value for the ESF filtration unit is 100 plus or minus 5 kW in the CTS and 100 plus 5 kW in the ITS. Provide correction or justify change. l FLOG Response: The ITS value for the ESF filtration unit is corrected to be 100 plus or minus 5 kw. ATTACHED PAGES: l EnctSA 5.0-23 l l l 4 e
Programs and Manuals 5.5 I 5.5 Programs and Manuals (continued) 5.5.11 Ventilation Filter Testino Procram (VFTP) (continued) ESF Ventilation System Penetration RH ControlfRoom;EmergencyJ11tration unit 0.2% 70% Control Room Emergency' pressurization unit B-PSb 0.2% 70% Primary Plant: Ventilation. System - ESF 1.0% 70% ' filtrationiunit iteviewer's "ctc; Allowabic panctration - 100! methyl iodide efficiency for charcoal crcdited in-safety cvaluation/(safety factorb safety factor of - 5 for systems with heatees-
- [7] for systems without heater
- d. Demonstrate at least once per:18 months for each of the ESF n
.5.5-11
- systems that the pressure drop across the combined HEPA filters, the prefilters,and the charcoal adsorbers is less than the value specified below when tested in accordance with B-PS d Regulatory Guide,1.52, Revision 2, and ANSI /ASME N510_19801989 at the system flowrate specified below i 10%
ESF Ventilation System Delta P Flowrate Control Room;Ea rgency; filtration unit 8.0 in WG 8000 CFM Control Joom; Emergency; pressurization unit 9 5_.iniWG 800_CFM Prima rylPjan,t ; Ventil ationiSystemM ESF B-PS"9
~
8.511n'WG 15000_CFM filtration _ unit {
- n. Demonstrate at:1e.ast~once'per_18; months that the heaters for each of the ESF systems dissipate the value specified below ~5.5-111 t-1M when tested in accordance with ANSI /ASME N51019801989. 98-PSj ESF Ventilation System Wattage Control Room: Emergency:pressur,1zationiun.it 10 iT1 kW Primary Plant Vent 11ationiSys_temXESF , B-P'S1 filtration' unit.
100 g kW
% Q 5.5 14 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.
(continued) CPSESMarkup ofNUREG-1431 -ITS S.O S 0-23 8/28/98
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.11 Ventilation Filter Testina Proaram (VFTP,). (cont 1nued) ESF Ventilation System Penetration RH Contro11 Room; Emergency.Lfiltration '. uni.t 0.2% 70%
'B-PS 4
~
Control Room; Emergency; pressurization unit 0;2% 7.0% Primary PlantJentilation1 System ff ESF 1.0% 70% filtrationunit Rcvicucr's Note. Allow;bic pactration - 100 ;cthyl iodidc afficicacy for cherccal credited in safety cv;1uation/(sofety factor).
- afety factor of - 5 for sy;tc;; with heatcrs.
- [7] for systc;; without heater.
- d. Demonstrate at;1eastionce' peri 18 months for each of the ESF .5.~5-11%
systems that the pressure drop across the combined HEPA filters, the prefilters,and the charcoal adsorbers is less than the value specified below when tested in accordance with B-PS?j
' '~
Regulatory;Gui.de 1.52ERevision 2,f andLANSI/ASME- N510:1980F)89 at the system flowrate specified below ijl0* ESF Ventilation System Delta P Flowrate Control Room Emergency;f,ijtration unit 8.0;1n..WG 8000,CFM ,
^
Con _trolJoomiEmergencylp_ressurization_ unit 9.511n_WG 800_CFM eB-PSy"'
^~ '
Primary Pjant,JentilationiSystem3ESE 8.5;iniWG 15000_CFM i filtrationlun.it; i
- e. Demonstrateatje.ast:;onceperJ81monthsthattheheatersfor I525-11A each of the ESF systems dissipate the value specified below t-104 when tested in accordance with ANSI /ASME;N510 19801989. $BfPSjj ESF Ventilation System Wattage Control? RoemlEmergency;pressur,1zation~ unit 10;1"11kW (B-P'S3 "
Primary Pjant: Ventilation:Syst_emIESE 1_00 g kW fil_tr_at. _io_n .un.._it. .
% Q 5.5-14 The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.
(continued) CPSES Markup ofNUREG-H31 -ITS S.O S.043 8/28M8 _~
l ADDITIONAL INFORMATION COVER SHEET 1 ADDITIONAL INFORMATION NO: O 5.6-1 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 5.6.5 a.7&8, Changes 03-14&15 M Comment: It is true that the additions would make the COLR more restrictive however, the removal of the specific values from the TS is a less restrictive change that needs to be justified. Provide justification. FLOG RESPONSE: DOC-03-14-M describes the addition of the SHUTDOWN MARGIN (SDM) limits and the Moderator Temperature Coefficient (MTC) limits to the Administrative Program description of the CORE OPERATING LIMITS REPORT (COLR). As stated, this change is more restrictive to the COLR. The change for moving the actual limits from the technical specifications to the licensee controlled COLR are addressed and justified by DOC 01-01-LG (SDM) found in Section 3.1 (not applicable to CPSES) and DOC 03-07-LG (MTC) found in Section 3.1 (applicable to DCPP only). DOC-03-15-M, in a similar way, adds the Refueling Boron Concentration limits to the Administrative Program description of the COLR. The change moving these limits to the licensee controlled COLR is addressed and justified by DOC 01-02-LG found in Section 3.9. ATTACHED PAGES: None l I i
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: O 5.7-1 APPLICABILITY: CA, CP, DC, WC REQUEST: ITS 5.7.2 and Difference 5.7-2 Comment: TSTF-167 has been rejected by the NRC. Use current ITS. FLOG RESPONSE: Traveler TSTF-258 has been submitted to the NRC for review. This traveler superseded travelers, TSTF-86, TSTF-121, and TSTF-167. TSTF-258 is based on the recommendations in the April 9,1997 letter from C. Grimes (NRC) to J. Davis (NEI), with some exceptions. The FLOG submittals have been revised to incorporate TSTF-258 and encompass the NRC comments of 6/11/98. Additional technical changes made to Section 5.7 are identified and justified. (See JFD 5.7-2 which revises ITS 5.7.2e consistent with CTS 6.12, and JFD 5.7-4 which revises ITS 5.7.2f consistent with CTS 6.12) The latest industry status on TSTF-258 is that the NRC has requested changes to Section 5.7, High Radiation Area. ATTACHED PAGES: See markups associated with Comment Number O 5.2-1. I l l l
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: TR 5.0-003 APPLICABILITY: CA, CP, DC, WC REQUEST: TS 5.6.6," Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)", was revised to incorporate changes based upon WOG-67. WOG-67 has been approved by the TSTF and is designated as TSTF-233. This traveler has been submitted to the NRC and the latest traveler reports indicate that TSTF-233 has been approved by the NRC. The attached pages reflect changes associated with WOG-67 being designated as TSTF-233. ATTACHED PAGES: Enci5A Traveler Status sheet Enci 6A 4 Encl 68 5 I i l
~
Industry Travelers Applicable to CTS Section 6.0/ITS 5.0 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF-9, Rev.1 Incorporated B-PS NRC Approved. TSTF-37, Rev.1 Incorporated 5.6-2 DCPP only TSTF-52, Rev.1 Incorporated 5.5-4 Incorporated _ draft _Rev4 C 3.6.1 6 1 per Q3.6.1-6z TSTF-65, Rev.1 Not Incorporated NAS.2.-9 Not NRC approved atef tr;vdcr ;;:-eff d;;;. 1R 5.0 005 i TSTF-106, Rev.1 Not Incorporated NA Retain CTS TSTF-115 Not Incorporated NA Not NRC approved as of traveler cut-off date. TSTF-118 Incorporated 5.5-8 NRC Approved 1R 5.0 006 TSTF-119 NotIaccep;ra:cd NA Ile:;ia CTS 1R 5.0 006 TSTF-120, Rev.1 Not Incorporated NA Retain CTS 1R 5.0 006 TSTF-121 I;cerpor;;cd 5 72- 3 0 5.2 1 TSTF-152 Incorporated 5.6-4 P(RC,Approyed 1R 5.0 006 TSTF 167 !acarpora:cd Sr7-3 0 5.2 1 _ ^ WOC-67, !!cv.1 Incorporated 5.6-5 1R 5.0 003 Ef2E WOG-72 Incorporated 5.5-13 WOC-05TSTF-237 Incorporated 5.5-14 0 5.5 2 Frap;;;d Travdcr Incorporated 5.2JiS_.2-3,12-6f. 0 5.2 1 TSR-258,, 5}]i;5.5-1,5_.5-16; j 5.6-6,15.7-1
CHANGE NUMBER JUSTfF1 CATION 5.6 3 This change revises the report date in Section 5.6.2 " Annual Radiological Environmental Operating Report" to be consistent with current TS. 5.6 4 This change revises Sections 5.6.1 and 5.6.3, " Occupational Radiation Exposure Report" and " Radioactive Effluent Release Report", respectively, per NRC letter dated July 28,1995, " Changes to Technical Specifications Resulting from 10CFR20 and 50.36a Changes" (From Christopher I. Grimes to Owners Group Chairs). This change is consitent with TSTF 152. 5.6 5 [ ] PORV lift settings are referenced in PTLR section pe d $ .5.0 003 233
- ocv. 1 TSTF M.
5.6.i6 The ITS; requirement;to_provideEdocumentation;ofjallsc hallenges'to . 0 5'2 1 the , pressurj zetjowertoperated_ relief;v.al_veslorj pressutizer; safety valves l1s: deleted.5The; reporting ofjpressurizer safetyjandf relief valve failuresjand chall.enges:isf based' on the?guidanceJjniNUREG-0694, L"THI-Re1ated RequirementsJoriNew;0perating Licensees /*SThe; guidance of NUREGf 0694,. states::"Assureithatiany failure:of a,PORV ot;safetyivalve toLglose.will be, reported toithe.NRCipromptly.?AlllchallengesLtolthe PORVs orlsafety valves ~should beidocumented;in the Lannual report.";NRC Generic Letter 197 02,
" Revised. Contents ~of,the Monthly Operating Report"f requests ,the submittal;of less information;in thejmonthly operating r.eportCTheigeneric11etter identifies _ whatuneedsito.;be; reported,toisupportithe NRC; Performance l Indicator Program,Yand.availabilityiandipapacity.statisticsGThe generic 11.etter;does not specificallyljdentify;the;need to . report challengesito the; pressurizer safety and relief; valves; ;This3hangefis consistentyith TSTF-258.
5.7 1 This change revises !!igh Radiation Arc; to incorporate changes consist i "$5.21 with [the current TS). Specificolly, distences from the rcdiction source; Section15:7 jsdevjsed;jnlaccordancefwith]10;CFR 20;1601(cLandlupd.a.tesjthe^ acceptable alternate:conttolsit.githose.,givenJin;10 CFR;20.;1601.E]heselchangesiarelcon_sj stentyithitheldtaft ~ Genetic 1LettetM933 XXLonfptoposed;changesltCSTSiNUREGsbased;on;theineW:10iCFR201andithe letterifromiCEGrime.sENRCUtoEDavjsINElidatediAptiL9399EThis changens;consistentiwith3STFi2581andiencompassesithe;NRC! comments;on 6/11/9_8Edditjona]itechnicalZchange.s;madeltolSectionl52] ate:1dentifiedland justifjed; 5.7 2 This change revises "uncuthorized" to " inadvertent" in the "igh 0 5'2 1
- R; diction Arc; scetion to reflect NRC's position s stated in R0 S.38, Section 1.S rcserding physical barricrs for liigh Radiation Arcas. This is censistent with traveler TSTF-157. ITSiSj7.2ielis revised gonsistentiwithlCT_S16;12 x that'allowslanylindlyidual;origroup of individu.al.s talenteria31ghihighf adiation'atea3 dose _tates;greaterithanjll.0_ rem /houtiat .
3.0_cataccompanjed_by;anlindiyvidua]Iqua]jfiedlin radiation'ptptection pro.ceduresIWithla' radiation'do.seJrate'monitoting;deyice" S he qualified indiyjduR1 s7responsj ble2foriptoyldinglpositive~contro];andjshaRiperf,ota petiodicItadiatjog'sutvejll ancesIatithelf teguencyispecified;in;the JWPAThe CTSjeg'ulteme_nts31]owlthelqua]ifj.edZindividuantolenteriallocked..hjgt) tad tatio[ area'with ~ plant 1Worketsiwj thout if,1tstihaviggito ~enterithef.ateaito 4 8/28/98 CPSES Differencesfrom NUREG-1431 -ITS 5.0
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 5.0 Page 5 cf 6 TECH SPEC CHANGE APPLICABILITY DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY NUMBER DESCRIPTION Yes Yes Yes Yes 5.6-3 Revises report date in Section 5.6.2. " Annual Radiological Environmental Operating Report" to be consistent with Consistent with See LA 42/28 current TS. original TS and LA 78/77. Yes Yes Yes 5.6-4 Revises Sections 5.6.1 and 5.6.3. " Occupational Radiation Yes Exposure Report" and " Radioactive Effluent Release Report." respectively, per NRC letter dated July 28.1995. " Changes to Technical Specifications Resulting from 10 CFR 20 and 50.36a Changes" (From Christopher I. Grimes to Owners Groups Chairs). This change is consistent with TSTF-152.
""n Yes Yes Yes Yes 5.6-5 wttinm are referenced in PTLR section per
[] TR-5.0 -003 l' F2 233 '.00 57. Rc; 1.' _ C Yes Yes Yes Yes 5.6-6 The!ITS;_requjrementito provide; documentation,0f;all challengesgo;;the. pressurizer; power 20peratedfeliefivalves 0-5.2-1 l or:pressurjzerisafety;v41 vests; i deleted; Yes Yes Yes 5.7-1 Revisc; "igh R;distion ".rc; to iracrperst; can;i;ttnt Yes. chc.ngc; wi .. .. .. ., .... .. .Section;5,7 Ais,revjsed ,in l 0-5.2-1 l accordance with:10 iCFR12016011c)landiupdatesithe; 6 acceptable alternate controls 3 to;those giveniin;10,CFR;20,1601. Yes Yes Yes Yes 5.7-2 Cheng; unauthcciccd to inedwcctant" i- thc l'igh n;distion A c; acction to rcficct the TC'; pc;ition ;; stetcd i- RC 0-5.2-1 l 0.30. Scction 1.0 cc;;rding phj;ical barricr; for 'ligh Radiction ".rc;;. 'his chen;c i; ca.;i;tcrt with TSTI 157 ITS;5.7.2,e;is; revised consistent [with; CTS 16,125 that; allows anyl.individualaor. group ofjindiv_iduals toienterja high-high radiatiortareai{doselates;. greater than a 1;0mren/ hour _at,30 cm)iaccompanied;by an11ndividualiquay10ed 2 in_ radiation protection; procedures;with:afadiation;dosefate, monitoring device) CPSES Conversion Comparison Table -ITS 5.0 8/2&98
ADDITIONAL INFORMATION COVER SHEET , ADDITIONAL INFORMATION NO: TR 5.0-005 APPLICABILITY:, CP REQUEST: This change incorporates NRC approved traveler TSTF-65 Rev.1 which provides for the optional use of generic titles for certain utility positions. ATTACHED PAGES: Enci2 6-1 Enc! 3A 1a Enct 38 2a EnctSA Traveler Status sheet,5.0-1 and 5.0-2 Encl 6A 1a Encl 68 2 4
ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Vice President of Nuclear Operations
- shall be responsible for overall operation of the units and shall delegate in writing the succession to this responsibility during his absence.
The Vice President of Nuclear Operations *, or his designee, in accordance with approved ! administrative procedures, 5 # ' approve prior to implementation, each proposed test or j experiment and proposed changes and modifications to unit systems or equipment that i affect nuclear safety. 6.1.2 The Shift Manager shall be responsible for the control room command function. A =cnage: cat directive to this effect. signed by the Croup " ice Prcoident. Nucicar 101-A : Production shall be reissued annually to all ;tation personncl. During any absence of the Shift Manager from the control room while the unit is in MODE 1, 2, 3 or 4, an individual with an active Senior Reactor Operator (SR0) license shall be designated to assume the control room command function. During any absence of the 3hift Manager from I the Control Room while the unit is in MODE 5 or 6, an individual with an active SR0 '/ license or Reactor Operator license shall be designated to assume the control room command function. 6.2 ORGANIZATION 6.2.1 ONSITE AND OFFSITE ORGANIZATION An onsite and an offsite organization shall be established for unit operation and corporate management, respectively. The onsite and offsite organization shall include the positions for activities affecting the safety of the nuclear power plant.
- a. Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating organization positions. Those relationships shall be documented and updated, as appropriate, in the form of organizational charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation. These requirements shall be documented in the FSAR.
- b. The Vice President of Nuclear Operations
- shall be responsible for overall site safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
- c. ,,,c Croup " ice President of Nucicar Production A'corporateh 1-16 LG fficer* a 1 have corporate responsibility ror overala plant TR 5,0 005 nu safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining.
! and providing technical support to the plant to ensure nuclear safety. l l
- Duties may be performed by the Plant Manager if that organizational position is assigned CPSES Markup of CTS 6.0 6-1 8/28/98
i s CHANGE j NUMBER JUSTIFICATION , l 5.2 4 Not applicable to CPSES. See conversion comparison table (enclosure 68). l 5.2 5 Not used. ) , 5.2-6 Thi: chcagt rcvi::: Scctica 5.2.2f to i;;ribc thc current l {-1-icen ing bc;i;] fcr the Shift Tcchnicc' A&iscr (STA). This, change 0 5.2 1 l revises;ITS_Section;5;2J2ifjISTSlSection5;.2.2g);toldescribelthe i current 1[TS]Jnd3oie]1sjDateltheltitle otdShift;TechnicallAdvisot l (STA);"51 STAS; ate;gotAsediatial]2plantsl(thelfunctionimayibe;ful f111 ed l by onefofithelptherion-shjftjindiyjduals)DThis;Section11s; revised _so ) that ;itidoes;notJjap]y;thatithe:STA and thelShjft;S.upervjsor2must]be I differentI1ndividuals20ptionJ qfithe;Commissjon. P_o11cyiStatemention Engineering Expertise 3niShiftlisjsatisfied;byla.ssigningfan;.individu_al. ( with;specffied;educationallqualificationsitoleach; operating;; crew as1one l of,the;SR0sff prefetably;thelShiftiSupervi sor);requi red _ by;10 .CFR 50.54(m)f2)(1)1tofproy1deltheitechnicalfexpertise;on shiftCHoweverLthe l ISTS 5;2.2.g wording;of,Sthe;STAishal.liptovjdez.",:Zsupport.totheShift l Supervisor lJ;.%is consi.deredito be;ea.sily;mi.sinterpreted. to. require separatejindiyiduals3Thereforeijthe1wordjngl1s revised,so that the STA function;may belproytdedibyieitheria separate; individual,or_the - l individuallwho;also fulfjllslanotherirolelin'thoshift command structure.' l This~ change _.is:consis. tent withiTSTF;258] I l 5.2 7 This change revises 5.2.2c to add a note that a single Radiation Protection Technician and a single Chemistry Technician may fulfill the l requirements for both units. This statement was added to clarify operational practices consistent with current licensing basis. , n 5.0 005 l 512iB AfgenericJtitle hasjteplacedithelplantispecificiutjlity title for the corporate.LofffjcerJhaving;tespgg,sjbility;forloyera)); plant safety? 61reviewerisinoteJasladded;descrjbjpgJithenJhe;us.eiof2 ge0erjc titles 11s;allowedgA3tatenegtJ!asialsgladdeditndicating thatlthe; plant speciff cItitlesiforlanEgenetic;titlesjused;willibelptoyj ded_j nithel , ThWehance ii s "consistegt1MthlTSTEI65; 5.3 1 This change revises Section 5.3.1 to be consistent with the current TS regarding plant staff qualifications and training. 522 New;patagtaph151312Jj g'a~ddedito~ensore ithatithereJ sinot 0 5.2 1 l
- misunders_tandip~g;when: comp]yjpg-]lth ;10;CFRl55]4;tequi rements .iSThe DefinitionsJin30iCFR;5514;stateEMtive]fpetforming;the; functions l
ofian opetatorlorZseniqrlopeta_torlpeansithatlanlindlyiduallhas;a
- posjtjonlon
- .thelshjftigt.ew2thatir_equjres mthelindiyid_ualj,tolbe31 censed a sidefine_dji n itheifacjlttyis3echgicallspecifj cations Eand ;that X;lJ. " '
Placing;this:paragtephiinit!!clITSleeetsithe]10JFRf.55;43. equirement;.for defining;1n thelfac11jty's3echnica]lepecjffjgationsithelfunction ! perfotmed;by Atgensed;jpdivjdualCper 10CFE50154Jm)U6ddingJhis i patagraphlis; consistent,11thlthelecommendationsjin;the3pr11E1997 l l etter;from:C " Grimes ;tg 'J EDaylislandjT.STFi2581 CPSESDifferencesfrom NUREG-131 -ITSS.0 la 8/28/98
~ n w-m -
p e--
CONVERSION COMPARISON TABLE - CURRENT TS 6.0 Page 2a of 8 TECH SPEC CHANGE APPLICABILITY iNUMBER DESCRIPTION DIABLO CANYON COMANCHE PEAK WOLF CREEK CALLAWAY l 01:15 This; change; revises;thes CTS.;to_ eliminate the title of Yes Yes Yes Yes A
- Shift;Jechnical;Mvisor;(STA)J B0-5.2-1 l
$16 A generic, title,hasfeplaced the_ plant: specific util_ity No ' Retained CTS Yes No Retained CTS Noi LG title for the;s corporate mofficer 2 having gesponsibility for Retained l TR-5.0 1 05 [.
overallplant;safetytandithe plantispecific titleijs,moyed CTS
\__to;the1FSAR; /
j l CPSES Conversion Comparison Table - CTS 6.0 8/2888 i
Industry Travelers Applicable to CTS Section 6.0/ITS 5.0 TRAVELER # STATUS DIFFERENCE # COMMENTS TSTF-9, Rev.1 Incorporated B-PS NRC Approved. TSTF-37, Rev.1 Incorporated 5.6-2 DCPP only TSTF-52, Rey.1 Incorporated 5.5-4 Incorporat_ed draft Rev' ( 3.6.1 6 1 per Q3.6.1-6z
.7 iSTF-65, Rey.1 Not Incorporated NAS.2-9 Not NRC approved 2, ,1 R-5.0 005 travc:cr cut-off da:c.
w TSTF-106, Rev.1 Not Incorporated NA Retain CTS TSTF-115 Not Incorporated NA Not NRC approved as of traveler cut-off date. TSTF-118 Incorporated 5.5-8 NRC Approved 1R 5.0 006 TSTI'-119 Nc: Inccrpora:ed NA Rctain CTS 1R 5.0 006 TSTF-120, Rev.1 Not Incorporated NA Retain CTS 1R 5.0 006 TSTF42+ Incorpora:cd 5d-2 0 5.2 1 TSTF-152 Incorporated 5.6-4 IMC Approved 1R 5.0-006 l TSTF-My Inccrpcrated Sr7-2 g.5.2-1l
"/ O C -57,Itcv. Ineorporated 5.6-5 1a.5.0 003 TSTF,i233j WOG-72 Incorporated 5.5-13 "/OG-85TSTF-237 Incorporated 5.5-14 c.5.5 2
l Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility - X x r e i..__*_ u_A_. Tass __ s_ -_ '___ _ c- su _ s . a s _ a. . s _u 11 6 - ___. ass.2 um
.myxe -ww - m. ., x-em,-
. . _ _w.. _un, __ .. ...___,,
- -~tr_ .u ev u_ _ m.a, t av . c. e.u-w u,- ge-nuwy une as 5.2 9 e.__2._# _____
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m..sm._eu s.s.s._ .a1. . emu. . m.. ____a.s.e.m_u erx.v . ~ . c. a... _.u1 e u . s ,. .j Analysis 'icport cr Ouality Assurance "lan.L'Jait staff titles :;hallic maintained a u l g'ised.using thosc procedure . approved 'cr modifying / revising thc "inal Safet" Am " sis "cport or Ouality Assurance "lan ' f 5.1.1 The [ Plant Superintendent} Plant Manager
- shall be responsible for B-PS overall unit operation and shall delegate in writing the succession to this responsibility during his absence.
l The [ Plant Superintendent] Plant Manager
- or his designee shall B-PS approve, prior to implementation each proposed test, experiment or modification to systems or equipment that affect nuclear safety. '
5.1.2 The [ Shift Supervisor (55)] Shift. Manager shall be responsible for the 'B-PS# control room command function. During any absence of the [SS3 Shift Manager from the control room while the unit is in MODE 1. 2. 3. or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the ESS3 Shift l. Manager from the control room while the unit is in MODE 5 or 6, an individual with an active SR0 license or Reactor Operator license shall be designated to assume the control room command function.
*2 Duties'may.be perf.ormed.by the;Vice_ President of Nuclear 0perations if that 'B-PS
~"'
N, or_ganizational positionJis assigned.' l l i { CPSES Markup ofNUREG-1131 -ITS 5.0 S.0-1 8/28/98
Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Oraanizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.
- a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions.
These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requiremen M nituaing. 005 ant-specific ztitles _of those. personnel fulfilling _the re_sponsibilities;ofjhejpo_sitions: delineated in these Technical;.Specifica iaii ce documented in FSAR ,8.,~j
- b. T e L1.. 4. ...wnm.nt] PlantLManager* shall be responsible m, for overall safe operation of the plant and shall have control : B-PSA over those onsite activities necessary for safe operation and maintenance of the plant
- c. to specifisc csri,crat; cxacutive position] CrouM
'rasidcgt;;NucicerTroduction~A'specified corocrate~offh snan nove corporate respons10111ty for overall plant nuclear
[ 5] safety and shall take any measures needed to ensure deceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and
- d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager: however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.
*2. Duties _may;.be, performed byltheJjce'P_residentiof1Nuclear _0perations21f_that jB-PSj organizationalipositio[i s ~as signedj (continued)
CPSESMarkup ofNUREG-1131 -ITS S.0 S.0-2 8/28/98
I CHANGE , I NUMBER JUSTIFTCATION 5.2 4 Not applicable to CPSES. See conversion comparison table (enclosure 6B). 5.2 5 Not used. 5.2 6 Thi; change reviscs Sectica 5.2.2f to describe the currcat [ licensing basi:] for the Shift Technical Advi:cr (STA). Thisichange o.s.2-1 revises ITS Sectjonl51212.;[fl(ISTS1Section;5. 2;2]g)ito describe;the gurrent3TS] and!to_.e]iminateitheititlelof,2Shiftlechnical Advisor (STA) . "2 STAS ~areinotlused At:al,1;pl ant s;(thelfunctionJay'be;ful filled by;.oneiofjthelotherlon shift $jndivjduals);IThis;S.ection._jsirevised so that it,.does not;implyLthatlthe STA andLthe; Shift';Supervisorimust. be differ.ent;individualsR0ption 1,ofJthe.. Commission 1 Policy Statement "on EngineeringLExpertis.eion1Shiftjislsatisfied.by f assigning an; individual with specified educationaEqualif,1cationsltoleach' operating crew as_one of the1SR0s (preferably;the;Shiftjupervisor); required by 10iCFR 50 54(m)(2)(1)Jtoiprovide~theitechnicaliexpertise onishift71However,;the ISTS 5.2.2.g wording of,("the:STA:shallipr_ ovide . .J(support to. the S.hift Supervjsor.c..".js_conside. red;.to..be easily misinterpreted to require separate 11ndividuals;7Therefore, the wording'.is; revised _so' that the STA function;may be.provided bydeither ~a ~ separate individual or_ the individualawhof al sojful fill s;another1 role 'in the '. shift; command structure. This; change.1s; consistent with.TSTF 258; 5.2 7 This change revises 5.2.2c to add a note that a single Radiation Protection Technician and a single Chemistry Technician may fulfill the requirements for both units. This statement was added to clarify operational practices consistent with current licensing basis. 5;.2-8 Not applicableito CPSESRSeelcogversion comparjsogitable;(enclosureJB). s.o. 02
.2 9 A generic; title hasJr_eplagedithe;plantispecific; utility;ti_ _
the corporate lofficerdhavinglesponsibi)ity;forLoveral); plant - , m.s.0 005 saf.e_ty; A reviewerisinoteyaslajid_edide.scrjbing when;the;use_of genericitit)es;jfallowedE3~ statement wa_s;Ialsoladdedjndjcating that!the plantispecifjcitttles;forZa~ny;generJcitjtlesiusedy111jb rovidedlindthe1F_SAR?, ThisJghangelis1consis.tentJithlTSTF.J65? 5.3-1 This change revises Section 5.3.1 to be consistent with the current TS regarding plant staff qualifications and training. New paragraph 1513.251sladdedito"egsure that;thereiis;not 0 5.2 1 5.[3 2 . mj sunderstandi ng ) hen; comp]Mnglith110;CF8 55lLtequirements.1The Definitions;ig 10;CFRj55:4TstateE" Actively;performingithe~fuggtions of. an;operatorlorisenjoCJp#ratorimeanslithat.anjindividua]ihasia posi tioCon;thelshjft;crgthatiteguj resithfindividuallto~ bellj cens_ed as2defin.ed inith[ facility'sitechnigaEspecifjcationsland;thaty.W.; l PJacing;this paragr,aphiin:the3_Simeet.sithe30iCFR155.Eteguirement;fot s T d.efi ning;f n ;the;fagjlityls2t_echnical[specj fipatjo.ns;thelfunction Per formed, by;licensedlindividuals]perJ102C_FRl50j 51(m)EAdding;thi.s pa ragraph;i siconsi s. tent 31thithelrelgommendatjon.sli n;t_helptil.9, ;1997 letter:fCom CgGrimesjtoEDaVis"and TSTFR58; CPSESDifferencesfrom NUREG-1D1 -ITS5.0 la 8/28/98
CONVERSION COMPARISON TABLE FOR DIFFERENCES FROM NUREG-1431, SECTION 5.0 Page 2 cf 6 TECH SPEC CHANGE APPLICABILITY DIABLO CANYON CONANCHE PEAK WOLF CREEK CALLAWAY NUMBER DESCRIPTION Yes LA 50/36 moved Yes Yes 5.2-6 Revises Section 5.2.2f to describe the current [ licensing Yes basis] fra SA - and eliminate,the.titlejf, Shift; Technical text to FSAR lQ.5.2-1 l advisor (STA); Section 13.1 which permits on shift SR0 te fill STA position Yes No No 5.2-7 Revises 5.2.2c to add note that a single Radiation No Not current Wolf Creek is a Callaway is a Protection Technician and a single Chemistry Technician may fulfill the requirments for both units. procedure or single unit site single unit site operational requirement Yes No No No 5.2.-8 Revises: Sections 5;2,2;and;5.-3;1 3 to;re{lectJicense Amendment;128/126Ldated_6/11/.8 9 phich; changed gequirements LA128/126 l DC-5.0-002 l for2t_he,_DCPP Operations Director) No Yes No No 5:2-9 A,gener,ic; title hasireplacedithe;plantispecif,ic utility m title;for;the, corporate! officerthavingyesponsibility;for TR-5.0 005 $ overall, plant- safety;' '
)
Yes Yes Yes Yes 5.b1 Revises Section 5.3.1 to be consistent with current TS regarding plant staff qualifications and training. LA 43/42 Yes Yes Yes Yes 5.3-2 New paragraph 1 5.31 2ii sladded i to ensure 3that;therejs not l 0-5.2-1 misunderstanding when; complying withJ0 CFR 55.4 requirements. Yes Yes Yes Yes 5.5-1 Revises Section 5.5.4. '11adioactive Effluent Controls l 0-5.2-1 Program." to reflect new 10 CFR Part 20 requirements. end mC icttcr d;ted '/20/ % ;;mi;tcr.t with repo;cd travcicr Yes Yes Yes 5.5-2 Revises Section 5.5.3. " Post Accident Sampling " to ensure Yes the capability to obtain and analyze radioactive " iodines" in lieu of " gases.* This change is consistent with the current TS and plant practices. Revises Section 5.5.8.
- Inservice Testing Program." to Yes Yes Yes Yes 5.5-3 delete
- including applicable supports." This change is consistent with tise current TS.
CPSES Conversion Comparison Table -ITS 5.0 8/2&98 E- _ _ - _ - - _ - . _--_ _ - - ___ _ _ _ _ _ _ _
ADDITIONAL INFORMATION COVER SHEET ADDITIONAL INFORMATION NO: TR 5.0-006 APPLICABILITY: CA, CP, DC, WC REQUEST: Revise the Traveler Status Sheet to reflect the latest status and revisions of the following travelers:
- TSTF-118 - NRC Approved
- TSTF-119 - NRC Rejected
- TSTF-120, Rev.1 TSTF-152 - NRC Approved ATTACHED PAGES:
Encl.5A Traveler Status Page I
Industry Travelers Applicable to CTS Section 6.0/ITS 5.0 TR#WELER # STATUS DIFFERENCE # COMMENTS TSTF-9, Rev.1 Incorporated B-PS NRC Approved. TSTF-37, Rev.1 Incorporated 5.6-2 DCPP only TSTF-52, Rey;1. Incorporated 5.5-4 Incorporated draft _Rev. C 3.6.1 6 1.perp3_:6J-63 TSTF-65, Rev.- 1 Not Incorporated NAS.2-9 Not NRC approved as-of 1R 5.0 005 treve:cr :::-;ff d;;;. TSTF-106, Rev.1 Not Incorporated NA Retain CTS TSTF-115 Not Incorporated NA Not NRC approved as of traveler cut-off date. TSTF-118 Incorporated 5.5-8 NRC Appro in 5.0 006
. Sn -11') N;; interparated NA l1 tain CTS 1R 5.0 006 TSTF-1 ,Rev.1 Not Incorporated NA Retain CTS 1R 5.0 006 TSTF-121 Incorper;;;d 5r3-2 0 5.2 1 TSTF-152 Incorporated 5.6-4 (hCApprovd 1R 5.0-006 4
V TSTF-157 !accrporated W 0 5.2 1
,, u m ,, m ,.. Incorporated 5.6-5 1R 5.0 003 j T,STEj233]
^ WOG-72 Incorporated 5.5-13
"/OC-05TSTF-237 Incorporated 5.5-14 ( 5.5 2 i
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