Text

Proposed Tech Specs Re Moderator Temp Coefficient & Fq Surveillance
	ML20084V145
Person / Time
Site:	Comanche Peak
Issue date:	05/24/1991
From:	; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	;
Shared Package
ML20084V138	List: ML20084V140; ML20084V145; TXX-9117, Application for Amend to License NPF-87,consisting of License Amend Request 91-007,changing Tech Specs to Remove cycle-specific Parameters,Including Moderator Temp Coefficient & Fq Surveillance.Safety Evaluation Encl;
References
	NUDOCS 9106040005
	Download: ML20084V145 (47)
	v • d • e

_ - _ - - . _ - - . - . . _ - - - . - - - - _ - . . - - - . - - - _ _ . _ .

RticTivin eCNTRot sysTEw1 MODERA90R ?EwpfRATURf CofFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:

,- m 'a.

( InSe d ^> Less1ositive than 0 at/kM F for all'vN s withdF4wn.

N beginnkg of cyct(Ilfe (80L s

v. N eonditioth and N tzeroTWERMALPCK

_L

b. Less negative than .4.0 x 10'4 a WCF for the all rods withdrawn. end of cycle life (E0L), RATED THERMAL POWER conditioni aPolltABilfTY: Specification 3.1.1.3a MODES 1 AND 2' only 8 Specification 3.1.1.3b. MODES 1. 2, and 3 only8 .

aillQH:

4. With the MTC more positive than the limit of Specification 3.1.1.34, above, operation in MODES 1 and 2 may proceed provided:

1 Cont rod wit}illhtpwal liatgare est4R{Shed and A tV sufficie to resto g the MTC Q, k- y \ mainpeittive t HO^ AmtY w (taine(h 0 a k/ within z rs or ss n the no 6 heers, so withdr 1 limits 11 be in ition he sortion sits of ificatt .l.3.6:

2.

The control rods are maintained within the withdrawal iteits established above until a subsequent calculation verifies that the MTC has been restored to within its liett for the all rods withdrawn condition; and

3. A Special Report is prepared and submitted to the Commission, pursuant to $pecification 6.9.2, within 10 days, describing the value of the measured MTC.

the interia centre red withdrawal limits, and the predteted averste core burnup necessary for restoring the positive NTC to within its limit for the all rods withdrean condition.

b. With the MTC more negative than the limit of Specification 3.1.1.3b. above, be in NOT $HUTDOWI within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With K,ff greater than or equal to 1.

8 See Specia' Test Exceptions specification 3.10.3.

COMANCHE PEAK UNIT 1 3/4 1 4 su oco. ,oos 9n:m4

DR e Ti'0500g5

_ _ . _ . - _ _ _ . - - _ _ _ _ . _ __._ _ _ . . _ _ _ _ _ _ _ _ _ . _ _ _ _ . - - _ - ~ _ _

- - . . . _ . __m._.._ - . . . _ _ . . _ _ _. ._ _

INSERT A

a. Less positive than +0.5 x 10' A K/K/'F for the all rods withdrawn, beginning of cycle life (BOL) condition for power levels up to 10.percant RATED THERKAL POWER with a linear ramp to 0 A X/K/'F at 100 percent RATED THERMAL POWER.

INSERT 8

1. Control rod withdrawal limits are established and maintained sufficient to restore the NTC to within the above limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . These withdrawal limits shall be in addition to the insertion limits of specification of 3.1.3.6.

4 4

, . _ . , -,-.n - -- . w,- - - ~-- ' ' ' ' ~ ' "'" " "

i SECTION 5 REFERENCES 1.

WPT-8043, " Texas Utilities Generating Company Comanche Peak Steam Electric Station - Steamline Break Superheat Mass / Energy Releases," September 19, 1985.

. 2. WPT 13255, " Texas Utilities Generating Company Comanche Peak Steam Electric Station - Hass and Energy Release Data for Outside Containment Equipment Qualification," Harch 1991.

S l

l l

1 f 29

ENCLOSURE 3 TO TXX-91179 MARKED UP TECHNICAL SPECIFICATIONS FOR OPERATION OF COMANCHE PEAK UNIT 1 WITH THE CYCLE-SPECIFIC PARAMETERS RELOCATED, A POSITIVE tiODERATOR TEMPERATURE COEFFICIENT, AND AN FQ SURVEILLANCE

g. .n _ -- -.-. g-m.es

Enclosus e 3 to TXX-91179 Page 1 of 32 I DEt DE81N!'!CNS SECTION PAGE 1.3C SLAVE RELAY TEST. 1-6 1.33 SOURCE CHECK. . 1-6 1.34 STAGGERED TEST BASIS. 1-6 1.35 THERMAL POWER. . 1-6 1.36 TRIP ACTUATING CEVICE CPERATIONAL TE5T . 1-6 1.37 UNIDENTIFIED LEANAGE. . . 1-7 1.33 UNRESTRICTED AREA. . . . . . 1 ~/

1.39 VENTING. . . . . 1-7 1.40 WASTE GAS HOLOUP SYSTEM. . . 1-7 bklE 1.1 FREQUENCY NOTATION. . 1-B TABLE 1.2 GPERATIONAL MODES. 1-9 l~

- j,ll l C.06E 0ffRATIN& LlMITS REPCST . . . . . . . . . - - ' .

COMANCHE PEAK - UNIT 1 ii

- . . - . .- . - _ - _ .. - to TXX-91179 Page 2 of 32 INDEX

~

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 4PDLICABILITY. . . .

3/40-1 TABLE 4.0-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED OURING INSERVICE INSFECTION. 3/4 0-8 TABLE 4.0-2 STEAM GENERATOR TUBE INSPECTION. . 3/4 0-9 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL Shutdown Margin - T,yg Greater Than 200 F. . 3/4 1-1 Shutcown Margin - T, Less Than or Equal to 200'F. 3/4 1-3 Moderator Temperature Coefficient. . . . 3/4 1-4 Minimum Temperature for Criticality. .. . . . . 3/4 1-6 3/4.1.2 BORATION SYSTEMS Flow Path - Shutcown. ..,. . . . 3/4 1-7 Flow Paths - Operating. . . 3/4 1-3 Charging Pump - Shutcown.. . . . . , . 3/4 1-9 Charging Pumps - Operating. . . . 3/4 1-10 Borated Water Source - Shutdown. . 3/4 1-11 Borated Water Sources - Operating. . . .. . 3/4 1-12 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height......... . .. ... . . . . . 3/4 1-14 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE R00 .. . ... . . . , , 3/4 1-16 Position Indication Systems - Operating. . . ., .. 3/4 1-17 Position Indication System - Shutdown. . .. . . . . 3/4 1-1B Rod Drop Time... . .. ... .... . ... 3/4 1- 19 Shutdown Rod Insertion Limit.. . . . . .. . 3/4 1-20 Control Rod Insertion Limits. . ... . .. ... 3/4 1-21 FIGURE 3.1-1 ROC EANs INSERTION w;nI!; ,;;;U; Th:RMA; DOWER. 3/4 1-22

( Pft6TT P)

COMANCHE DEAK - UNIT 1 iv

Enclosure 3 to TXX-91179 Page 3 of 32 INDE(

LIMITING CCNDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE l 3/4.2 POWER DISTRIsuTION LIMITS 3/4.2.1 A41AL O.u O!FFERENCE. ... 3/4 2-1 FIGURE 3.2-1 A: Ii "Le DI"":^lNC: .. IT; A5 A ruNCTICN OP (PFLE7FD)

RAT:. ' ;R" T0t.:n .. .. , .. 3/4 2-3 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - 9F (Z). . .. . 3/4 2-4 l-

FIGURE 3.2-2 h(Z) 3/4 2-5 NOR"ALIZCOI(2)A5AruNCTIONOrCOREHEIGai) 0 (Dilf fEP 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR F g..., ... 3/4 2-8 l

1 3/4.2.4 00A0 RANT POWER TILT RATIO. . . 3/4 2-10 l 3/4.2.5 DNB PARAMETERS. .. ... , ,, . . . . . 3/4 2-12 l

! 3/4.3 INSTRUMENTATICN i

3/4.3.1 REACTOR TRIP SiSTEM INSTRUMENTATION.. . . .. . 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION. . . .... 3/4 3-2 l

TABLE 4.3-1 REACTOR TRIP Sf5 TEM INSTRUMENTATION SURVEILLANCE REQUIREMENT 5. .. . . .. . ... 3/4 3-S 3/4.3.2 ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION. .. . . . .. . . 3/4 3< 13 TABLE 3.3-2 ENGINEERED SAFETY FEATURES ACTUATION $YSTEM INSTRUMENTATION, ... ... .. ............ . 3/4 3-15 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS.. . ... ... .. 3/4 3-25 TABLE 4. 3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS., . 3/4 3-31 i

3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations. . 3/4 3-38 TABLE 3.3-4 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS.. ...... . . .. .... . .... 3/4 3-39 Remote snutc0wn Instrumentation. . ...... . ... .. .. 3/4 3-41 TABLE 3.3-5 REMO~E SHUTDOWN MONITORING INSTRUMENTATION. . . . 3/4 3-42 Accident Monitoring Instrumentation. .. . .

3/4 3-43 TABLE 3.3-6 ACCIDENT MONITORING INSTRUMENTATION. .. ... . 3/4 3-44 3,4 3-47 Explosive Gas Monitoring Instrumentation. .

COMANCHE PEA C- UNIT 1 v

Enclosure 3 to TXX-91179 Page 4 of 32 INCE(

ADMINISTRATIVE CONTROLS SECTICN DaGE 6.5.3 TECHNICAL REVIEW AND CONTROLS. 6-1; 6.6 REPORTABLE EVENT ACTION. . .

6-13 6.7 5AFETv LIMIT VIOLATION. 6-13 6.8 PROCEDUREE AND PROGRAMS. . 6-13 6.9 REPORTING REOUIREMENTS, . 5-17 6.9.1 ROUTINE REPORTS. . . . 6-17 Startup Recort. . . 6-17 Annual Reports. , . ., ... . . 6-13 Annual Radiological Environmental Operating Report. 6-19 Semiannual Radioactive Effluent Release Report. . 6-19 Monthly Operating Report. , 6-19 r '. ' - i ' 7 t ; ; r t . 5-19 Ra;iel Isaxirg Cort Opera + n3~a;d.;s Ltm Aeroth 6,9.2 SPECIAL REPORTS. , , . 6-20 6.10 RECORO RETENTION. . . . . 6-20 6.11 RADIATION DRC'ECTION DROGRAM. 6-22 6.12 H!GH RADIAT!CN AREA. , , 6-22 6.13 PROCESS CONTROL PROGRAM (PCP). . , 6-23 6.14 0FD5ITE DOSE CALCULATION MANUAL (00CM), , . 6-23 i

l i

l COMANCHE DEaK e UNIT 1 avi l

I__-_____-___

Enclosure 3 to TXX-91179 l' age 5 of 32 DEFINITIONS UNIDENTIF:E0 LEAKAGE 1.37 UNIDENTIFIED LEAKAGE snail : e all ie hage -hich is rot ICENTIF:E: Jh AGE or CCNTROLLED LE AKAGE.

UNRESTRICTED AGEA 1.3E An UNRE57RICTED AREA shall se arv area at or ueyond the 3;TE ECLN;;;;

access to onicn is not controllec tj tre licensee, for Durposes of protect ion :(

individuals from exposure to radiation and raoloactive materials, or anj area within the SITE BOUNDARY _used for resicential cuarters or for industrial, commercial, institutional, and/or recreational purposes.

VENTING 1.39 VENilNG shall be the controlled process of discharging air or gas ' rom a confinement to maintain temperature, pressure, humidity, concentr ation, or :tner operating concition, in such a manner that replacement air or gas is not tr -

viced or reovired curing VENTING, vent, usec in system names, does not 9sij a VENTING process.

WA5TE GA5 WOLDUD SYSTEM 1.A0 A WASTE GAS -'0 LOUP 5f 5 TEM shall be any system cesigned anc instal:ec to reduce radioactive gaseous effluents Oy collecting Reactor Coolant System offgasEs fecm the Desctor Coolant System and provici - # 3r celay or ro'Or for the purpose of reducing tre total raciO3ctivity p Or to release to t*e environment.

CORE OPERATING LI M T TS REPORT I

l I.4 I The CORE OPE R A T.TN& LTMITS R E PORT (COLR) is t he unit ~ Spec.)[ic. cloc um e nt tha+ p rovick es tore.

operui;~) lim +s for +he e.o r res t ope,rwhy reloc A cy cle. .

l_ These eyele. - s pe uA <. n o e e- o p e e< & ,ny li - t +.s s ka ll 6e. .

de t<r m w e d %. euk te. la u d. cy e.le. In a.< c a c h e c. m Fk Sp e; {t ca n e n 4. 4.1. 4 . .

L; + o pe c ~ n o~ wit h :~ Aase ofers.+1 liml+$ is a clck t e.s s esk \p lad;u's ek uwI Spe < ;[,% ilpH s ,

i l

00MANCHE DEAK - UNIT 1 1' et am -

w m 2 --- T-, - -J -m *- -v - '

- 7 Y T

Encionure 3 to TXX-91179 ~'

Page 6 of 32 w i t h; ,v de: lim;+3 .sp e c ; 6 e d i n t h e. C CR C OPE R A TING LIMITS R CPORT (COLR). The REACT!VIT< CONI:CL SYS' EMS m a,; m um ugge ,- lim;f Sh ll be leu +6 or e g uni + o 4 0.5 vID'" b k/k /*F for power MODERATOR TEMPERATURE COEFFICIENT le ve h up +o 70 % RATEb T H E R P! /11. /20WER w e'r k a. li ~ ec. r ca ,p t o O a k/k/*f a4 /00 %

!MITING CONDITION FOR OPERATICN R A TE D TH E # bi A L Po k/ER.

%= - _ , = . _ - .-

-pJ 3.1.1.3 Themoceratortempersturecoefficient(MTC)shallbe[

-e. L+s++o+4t4ve-tun-4-a ' '" f o r-t ne a 11 r oos-w4+ocewn , b c g i m i ng =

=cf cycle f: (SOL), xt c o 'E WAWwE4-eeec i t i c n , cnc

=t. Len nega R e than ^.0 - 10 4 n > E '" for the ol' roo: t incrw ,

-end o' c,cle fc (EOL), ATED THE4"AL ^0WEbeendM4ee--

sD;nu;dn of cycle L;te (Bot) n H APPLICABILITY: see 4es t i o - 3 ,1.1-h. - MO D E 5 I a nd 2

o n l y *

5peci ication ' 1.1. 3 b. - MODES 1, 2, and 3 only**

Ea) af Lp el Life lEOL) Irm;+

ACTION:

re " ' 7' "j ',

. jy cong Bot

a. W i t h t h e MTC mo r e p o s i t i v e t h a n t h e Al i m i t e4-Gpee444+st i o r 3.1.1. h

-eseve, operation in MODE 51 and 2 may proceed provided: *

ks 6 0 L I: ><;4 secO U',1 ta+Le COL

1. Control roc witndrawal limits are established and maintained /-

suf ficient to restore the MTC to less positive tnan -0 _., - "

within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or ce in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

These witncrawal limits shall be in acc' tion to the insertion limits of Specification 3.1.3.6;

2. The control rods are maintained within .ne withdrawal limits estaclished above until a subsecuent c3':ulation verifies tnat the MTC has been restored to within its limit for the 311 r0ds witndrawn condition; and

3. A 5pecial Report is prepared and submitted to the Commissi0n, pursuant to Specification 6.9.2, within 10 days, describing tne value of the measured MTC, the interim control rod witnorawal i limits, and the predicted average core burnuo necessary #cr restoring the positive MTC to within its limit for the all rods withdrawn condition. spedk J ,~ +M ( C'g gou *

b. With the MTC more negative thanA the limit-cf :;e:i'icsticr :.1.1.:;.

--ebeve., ce in NOT SHUTOOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , "Witn (eff greater than r equal to 1.

- See Special Test Exceptions Specification 3.10.3.

1 COMANCHE PEAK r UNIT 1 3/4 1-4

Enclosure 3 to TXX-91179 Page 7 of 32

E AC' i ~ :-:N'::L i i'EM SURVE!LLANCE REQUIREMENTS

.1.1.2 ' e MTC se-ai' ce determinec to te within its limits curi ,g esen <ael

. c ' e a s ' c ' ': w s : .g g

3. T e MTC 5 3 1' be measured and compared to tne DL limit :' -:;c: ' -

ti -: .1.1.2 , :nve, prior to initial operaticn acove E'. Of RATED inERMAL 00WER, after each fuel loading; and D. The MTC shall be measured at any THERMAL POWER and compared to -3.1 1; ' . . ^" (all recs witnarswn, RATED THERMAL POWER conciticn)

Litnin 7 EFPD af ter reacning an equilibrium boron concentration of 300 ppm. In tne event tnis comparison indicates the MTC is more negative than 1.1 ;; ' 2 ' ", the MTC Shall be ret *easurec, anc comparea to t*e A EOL MTC 11mit c' :ccci'icatic- 2.1.1.2b , at least once per la EF M during the remaincer of the fuel cycle.

spec;Oed la +Le COLR 1G 300 p p ,,, s u r se ; lle.m e. I;n;+ sped DeJ la 4ks WA

+k 300 pen .s a racill w a- hm;+ yedDcd :n a c- COLR I

l

PANCHE :EAK UNI' 1 3/4 1-5 r

_ - ____ ______________m_____

- = ~ . _ . -- - . --. . . _ = - _. . __.

Enclosure.3 to TXX-91179 Page 8 of 32 REACTIV!'i C:NTROL 5(5'E95 3/4: 1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION

=

3.1.3.1 All snutdown and control rods shall be OPERABLE and positioned .ithin

12 steps (indicated position) of their group step counter cemana position.

APPLICABILITY: MODES l' and 2*

ACTION:

a. With one or more rods incperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied witnin 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. With one rod trippable but inoperable due to causes other than addressed by ACTION 3., above, or misaligned from its group step counter demand height by more than i 12 steps (indicated position),

POWER OPERATION may continue provided that within 1 hour:

1.

' The rod is restored to OPERABLE status within the above alignment requirements, or

2. The rod is declared inoperable and the emainder of the rods in the group with the inoperable rod are igned to within t 12 steps of the inoperable rod while maintainin; the rod sequence and fYo*.gg y l,3,(, insertion limits oF ~ig m :.1 1. The NERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 curing su0 sequent operation, or

3. The rod is declared inoperable and the SnUTDOWN MARGIN repuirement of 59ecification 3.1.1.1 is satisfied, POWER OPERATION may then continue provided that:

a) A reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions; b) The SHUTDOWN MARGIN requirement of Specification 3.1,1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

CO.MANCHE PEAK - UNIT 1 3/4 1-14

.~

_w

Enclosure 3 to TXX-91179 Page 9 of 32 REA:':;; - ::'.' R: t 5 5' EMS L:M!'!NG CCNDITION FOR ODECATION A '!!N f 't nueC) i c) A 00wer Oistr'oution mad is Obtainea from the mossoie N

inc0re cetectors and Fy (Z) and F,Ha are verifiec to ce

.ithin treir limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and d) The THERMAL POWER level is r seuced to less than or ecual to 75% of RATED THERMAL F0WER ithin the next neur and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the High Neutron Flur.

Trip 5etooint is reduced to less than or ecual to B5%

of RATED 'HERMAL POWER.

c. with more than one rod trippable but inoperable due to a rod control urgent 'ailure alarm or obvious electrical problem in the rod control system, POWER OPERATION may continue provided that:

1. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the remainder of the rods in the bank (s) aith tne inoperaDie rods are aligned to within : 12 steps of the inoperaole rods wnile maintaining tne rod sequence and insertion SP uif". elita 3 Al#~~'Timits oT'*Lgure 3.1-1. The THERMAL POWER level shall te restricted pursuant to Specification 3 . 3.6 during subsecuent operation, and

2. The inopersole rods are restored to OPE 4BLE status within 4B nours.

c. Witn more than one rod misaligned from its group step counter cemand neignt by more than : 12 steps (indicated position), be in n0T STANDBY witnin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each rod shall be determined to be within tne group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals *nen the rod position deviation monitor is inoceracle, then verify tne group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each rod not fully inserted in the core shall be determined to be OPERABLE oy movement of at least 10 steps in any one direction at least once per 31 days.

C MAN;HE ;EAK UNIT 1 3/4 1-15

Enclosure 3 to TXX-91179 Page 10 of 32 REACT:/Iiv CONTROL Sv5TEMS 5HUTDOWN RCD INSERTION LIMIT LIMITING CONDITION FOR OPERATION 3 . ,A . a . 5 - ! ,. sne,..,own rods shall be lmW,,34: d ea

. -,e !L mf .h.t! L* N ;~ * '*!*a as sp* < i fi e d Lo N C GRE O pcce1HWp Lrr{r 7.5 R eFod T (c o Af) ,

APPLICASILITY: MODE 5 1 *) and 2 .

ACTION

nse n ,< J sep,~J % im eeti~ I ~; + se<<ined r~ +Le ccie, s

With 3 maximum of one shutdown rod cet ful'y !!'d ::w k except for surveillance testing pursuant to Specification 4.1.3.1.2, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either:

$es+e m +Le

- d 4 withia ,Le ;mnoa /Im;+ spec;6c J i.0 d e. C OL C, er

a. >,,1 ., ;t crs t'c rod, or

b. Declare the rod to be inoperable ano apply Specification 3.1,3.1.

SURVEILLANCE REQUIREMENTS u,+kw +k< ;~ s e r + 1 o w 4.1.3.5 Each shutdown rod shall be determined to be fJlly ithdrc r

%t sper:4:<el ;a t h e. ConR:

a. Within 15 minutes prior to withdrawal of any rods in Contrcl Bank A, B, C, or 0 during an approach to reactor criticality, anc

b. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

"ul'j ;t"cra n ; mall be the ccacitica here snutccer rads sie at a ;:. ; r withi n inc 'nterwal- cf 222 and _ 231 steps .sithdre n j

'65ee$pecialTestExceptionsSpecifications3,10.2and3.10.3.

i 4 i

with seff greater than or equal to 1.

i CCMANCHE PEM - UNIT 1 3/4 1-20 l

l i

_ __. _ __ _ _ . _ . . . - . _ . . _ _ . _ . _ . . _ _ __ ._ _. _ m . .-

Enclosure 3 to TXX-91179 Page 11 of 32 REACT!VIT CCNTROL 5tSTE45-CONTROL R00 INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The control banks shall be limited in physical insertion as 3 : -

ri;;z 3.1- 1 spe ei ne ck w + h COCC O PE R A T] ht & LI NI T.5 R EPORT (C OLR),

APPLICABILITY: MODES 1* and 2' **.

ACTION:

With the control banks inserted beyond the e4HFe> insertion limits, except for surveillance testing pursuant to Specification 4.1.3.1.2:

a. Restore the control banks to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or

b. Reduce THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the bank posi-tion using the g - g, c y- pg g 9q g

c. Be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1,3.6 The position of each control bank shall be ce'. ermined to be within the insertion limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months excep. curing time intervals when the rod insertion limit monitor is inoperable, then verify the incividual

. rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

"See Special Test Exceptions specifications 3.10.2 and 3.10.3.

- With Keff greater than or equal to 1.

COMANCHE FEAK - UNIT 1 3/4 1-21

Enclosure 3 to TXX-91179 1' age 12 of 32 e s

( del.E TED )

\ .,

l ...

,. - e; ,4-...).-- 3 f a. t. . ,. . ., .

. .f =gs< =*-

{ ...

n . .. . .

1 5

N / 0,16.k. _/ ,

T - ..w.

= : ,

= .- ,

% f (100.116')@

E

'3 BANK C

= : , ,

1 2 ,-

..'h C

+

[ , [

y

g. .,/ ..' , .-'

= f x, f . 5AV ?

a C

": {

x .: -

M i O.19 )! ,

, ,f s;

,.f' 1 fj(31.0)

: : ;0 20 40 10 60 70 30 r. .'

PERCENT OF RATED THERMAL r WER

. T*.".LY .:!H:TdW SKALL SI THI CO.VDI!!:N ' dIII C CRCL RCOS A3I A! . . . .. .

.s 2 . .... .. .. N . ...a.

. . ... . N . .nz . . . ... % . %,:a A.,. C , ..... AND s , ....e . = .,5 ...a w. 3. .. .

FIGURE 3.1-1 ROD BANK INSERTION LIMITS VERSUS THERMAL POWER COMANCHE PEAK - UNIT 1 3/4 1-22

. . + . . . ,, , __

1 to TXX-91179 Page 13 of 32 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX OIFFERENCE LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX O!FFERENCE (AFO) shall be maintained within the 4 f w11cingtargetband(fluxdifferenceunits)aboutthetargetf.l.uxdi{Jeence, x v~. ~,m

-f or ' form.Q C9 era t icr and S000 leadOperat3ry

" - ~

ru mMa wa .

cm o pann6 t y m 7,5 I R E t4 R7- cocR ,

c. 5% for core average aceemulated-burnup--of le;(. than)er equal-4e-3000 lTJ/MTU, and

-b. 3%, -12% for core asceege accumulated burnup cf-greeter thar 3000 li.JOlMTU.-

T h e-c or Nermal Operatien, the indicated AFD may deviate outside the ebeve required tdrget band at greater than or equal to 50% but less than 90% of RATED THERMAL POWER provided the indicated AFD is within the Acceptable Operation Limitgeh figure 3.0-1 and the cumulative penalty deviation time does not exceed Tliour**

during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (spec; 4nl la de col 4 T h e.

Fcr Norm:! Operati^ , the indicated AFD may deviate outside the ebeve required target band at greater than 15% but less than 50% of RATED THERMAL POWER pro-vided the cumulative penalty deviation time does not exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

For 8:00 Lead Operation, the ^F0 ch !' remain 'ithin the target band defined-

-above.

APPLICABILITY: MODE 1, above 15% of RATED THERMAL POWER.*

ACTION:

Wah

a. For Normal Operation with the indicated AFD outside of the h required target band and with THERMAL POWER greater than or equal to 90% of RATED THERMAL POWER, within 15 minutes either:

1. Restore the indicated AFD to within the target band limits, or

2. Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.

E cr Sa:c Lcad Operation with the indicated AFD cut:!de of the abcvc rcquired target band, dthin 15 minetes either;

See Special Test Exceptions Specification 3.10.2. ; fad ia

C OL k *

- Surveillance testing of the Power Range Neutron F1 Channels may be per-formedpursuanttoSpecification4.3.1.1 provide (theindicatedAFDismain-tained within the A Whilc ir NcrealOperat:cn,;jceptableOperationLimitsof,igurc3.2-1.

total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be accumulated with the AFD outside of the above required target band during testing without penalty deviation.

NO

[

Base Load Operation' requires # minimum aljoWable power level, APLy r of 75%'-

RATED'THERMALf09ER to bedaintained . band on the figd'res givenqn the, Radial Peiking Factor Limit Re% ort for BasiLoad Operatio'n' per Specfficatio(6.9.1.6 f COMANCHE PEAK - UNIT 1 3/4 2-1 Amendment No.1

s._ _..__. m. - _ -._ _ __. _ _ _ _ _ . _ _ . _ . . _ . . - . . to'TXX-91170 Page 14 of 32 POWER OfSTRIBUTION LIMITS

' LIMITING CONDITION FOR OPERATION ACTION (Continued]

- 1. D :ter: the 'ndi :ted ?FD-t: within the teget band limht-ee-

2. Dise ntinu; S :: L d Operation and djust T"EC"AL POWER as nect;;;ry for Normal Operati n

b. "Or N r: 0! Oper:ti:n%llth-the wi lk indicated AFD outside of the etme re-quired target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of cumulative penalty devi-ation time during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or outside the Acceptab_le ur 2.2-1 and with THERMAL POWER less than 90%

Operation but equal toi.imits of Fi;;dthan 50% of RATED THERMAL POWER:

or greater NgpcAed no t he ce t 't

1. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes, and

2. Reduce the Power Range Neutron Flux - High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

WiA For Normal Operatier ith- the indicated AFD outside of the ebeve-c.

required _ target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of cumulative penalty devi- l.

ation time during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and with THERMAL POWER less than 50% but greater than 15% of RATED THERMAL POWER, the THERMAL.

POWER shall not be increased equal to or greater than 50% of_ RATED THERMAL POWER until the indicated AFD is within the Ob ve required target band.

SURVEILLANCE REQUIREMENTS 4.2.1.1 -The indicated AFD shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a. Monitoring the indicated AFD for each OPERABLE excore channel:

1) At least once per 7 days when the AFD Monitor Alarm is'0PERABLE, and

2) At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after restoring the AFD Monitor Alarm to OPERABLE status,

b. Monitoring and logging the indicated AFD for each OPERABLE excore channel at least-once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once er 3 minutes thereaf ter, when the AFD Monitor Alarm is inoper-able.U The-logged values of the indicated AFD shall be assumed _to exist during the interval preceding each logging. g

During Base 4'oad Operation at less than'or-equal to-90% RATED' THERMAL, POWER,.

the AFD)Mnitor Marm shalf be copsidered inoperible unless'the AFD Monit c' ND Alarm'has prd sionp immediately alarm ove APL ith AFD ide e target band. , /

COMANCHE PEAK - UNIT 1 3/4 2-2 Amendment No. 1

-- . - -- _=- - - --- .. . - -. _-

Enelosure 3 to TXX-91179 Page 15 of 32 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.1.2 .The indicated AFD shall be considered outside of its target band when two or more OPERABLE excore channels are indicating the AFD to be outside the target band. Penalty deviation outside of the above required target band shall be accumulated on a time basis of:

a. One minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and

b. One-half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER 1evels between 15% and 50% of RATED THERMAL POWER. p 4.2.1.3 The target flux difference of each OP,ERABLE excore dete fned by'measurepe'nt at least once per 92 Ef fectivefti, channel shall be ll Power Days.

The rovi ons of pecificatioy4.0.4are4otapplicab)e. /-

Theta'etfluxdfferencespilbeupdatpd'atleast, d1 Ef f,e tive F 11 Power Da)ys by either determinir)q the targpt flux/diffpfence 4 . 1. ce per j

pursydnt to p ecificatipli 4.2.1.3 above or by li'near interpolation beJween the mos,t'recentJy measured /value and 0% at the enQ of the cycle life. Jfie provi-sions of Specificatiori 4.0.4 are not applicable. , /

t~ ey e t flux eA ; ffe ren c e. of ewek V 4. 2, I . 3 The- O PER A B L E excore c h(n ue l s h~ ll bc <d e i e+ mi n e ct in c oj o nc. tion win ekt m e w.s a re m e a + oZ Fa (Z) a .s d e foaeci ia SecsMMon p

'i . 2. 2 . 2. e . The pros;sion.s J .5p e e ; h e.~ +; e n 't . o . ') arc m+ app /; em. 6 /c .

l l

A COMANCHE PEAK - UNIT 1 3/4 2-2a Amendment No. 1

. . _- . - - _ - _- . . _ . . . . . . . _ - , - - _ - - . - to TXX-91179 Page 16 of 32 L QELETED)~

120

/

'l 100

/

(-il.so) (ii.so)

E UNACCEPTABLE / ACCEPTABLE OPERATICN / OPERATICN

/ {

C ACCEPT /SLE h 60 ' '

c N (-3 .so)

V ' / \

(si so)

$ 40

u. !

o N

20 ,

3 0

-50 40-30 10 O 10 20 30 40 50 FLUX OIFFERE E (AI) %

\

FIGURE 3.2-1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER

.- s CCMANCHE :Ek - UNIT 1 3/4 2-3

F.nclosure 3 to TXX-91179 Page 17 of 32 t ER C:5*0: E :., ' ' N .:o:*?

3/4.2.2 HE AT ~ LUX -0T CHANNEL f aCICR 'g(Z )

L!u!I!NG CCNDITION FOR CPE;ATICN 3.2.2 F,(Z) s a ' l t e ' im' tec D,

e tci'; ina eist4crs- ;s.

f, R16,.3 . f : ,- ~4- - - . a, s wb4) e.x(-)-s ,,, p p m) o -

0 s P

~})

~

.ll. O r ,

L/ [Mt),; 'e r -v s.-a

, ... ' r ,J ( t ) 4(H~p7 -

, prP ' "ERuAL P %ER / _ , anc

~~~~

-~~

[{L

/ ,5 Q

/

[';/--

/

. RATED irERMAL,f0'aER .

, /

o. S /

- / -

%2) : the function optainec,from Figure 3.2-2 'cr 3 gicen N ,/

-+ core hsignt iccaticn! / /

APPLICABILITv. MCDE 1.

ACT:C_N :

Witn F,(2) exceecina ' ts limit; -

w

a. Recuce NERMAL PCWER at least l' for each 1% Fg(Z) that exceeds the limit altnin 15 m nutes anc simila recuce the Pcaer Range Neutron Fl am--ign Trio 5etcoints -ith' *ne rest 4 nours; ;CWER OPERATION ma, or ceec 'or up to a tota ;f 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; suosecuent POWER OPERATION maj aroceec provided t- Overpower N 16 'ric Setpoints have teen recaced at ' east ; #:r eac9 l'. -(I) inat exceecs t*e limit, and *

. Ident'fy and correct t"e cause of the c *-of 1 mit ::nc' tion prior to increasing inERMAL POWER above *. e recucea 1 91t re-cuired by ACTION a., above; THERMAL P0wE; may then te 4 creaseo p r o '. .ec F (Z) is cemonstrated tnrougn score ma D i ng to te q

within its limit.

-~

m , w , -,- _

f RT P :

f \A/ h e r e : Fg 4 tu Fg 6;t at RATE 6 rocaMnt Pou) E R (RT P) spc & J la +ke CME O PE MJ /V6 LI t1 T T.5 R E Po R T (coun), f, THERMnL PowCR P =

pp,gy 7 n g g ,, p u poweg , w cl

+h mormc liz c J Fg [2] o..s a. Lu d ; o ~

R (Z) =

or esce ke;p e sen.; hed ia ne COLR, 1 77

%"+~~"~n~- -- -.~ _x .n a f CCMANCHE PEAK - UNII 1 3;a 2-A

I:nclosure 3 to TXX-91179 Page 18 of 32 I

(OGLET5 }

/

4

^

\'O.0.'.0) ,

(6.0,i.j )

O (10.e,0.94) l N !

- i d

0.5 (iz.o.o.e4) -

I ,

j z : ,

o

- n .

- s.- ,y,

- ' 1 i N O.2

\N

. l I x i 1

,m

\ l I O 4 6 8 10 12 !A CORE HEI HT (PT)

FIGURE 3.2-2 s K(Z) -

fiCRf1ALIZED Fg (Z) AS A FUNCTION OF CORE HEIGHT CCf'ANCHE PEAK - UNIT 1 3/4 2-5

Enclosure 3 to TXX-91179 Page 19 of 32 POWER DISTRIBUTION LIMITS IVlW SURVEILLANCE REQUIREMENTS ff E!

w ~

2.1 The provisions of Specification 4.0.4 are not applicable.

.2.2.2. Base Load Operation # is permitted at powers at/or above APLND jf ,

following conditions are satisfied: \

. Prior to entering Base Load Operation, maintain THERMAL POWER above N0 APL and at or below the maximum allowable power level in ated by the most recent F xy surveillance (and maintain THERMAL P0 R within 1 %) for at least the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Maintain the FO within the target band required for Base Load Operation duri this time perio Base Load Operation is the permitted prov ed that THERMAL POWER i maintained at/or above APL and F surv illance is main-tained pur uant to Specification 4.2.2.3.

b. During Base L d Operatiun, if the THERMAL P ER is decreased below ND APL then the nditions of 4.2.2,2a sha be satisfied before re-entering Base Loa Operation.

4.2.2.3 F yy shall be evaluat to determine if eq (Z) is within its limit by: I

a. Using the movable incor detectors o obtain a power distribution-map at any THERMAL POWER reater an 5% of RATED THERMAL POWER for ND Normal Operation or A)L r 8 se Load Operation, l Increasing the measured F yy c mponent of the power distribution map b.

by 3% to account for manuf tur g tolerances and further increasing j the value by 5% to accounY for me surement uncertainties,

c. Comparing the F comp ted (F ) ob ined in Specification 4.2.2.3b.,

l xy above to:

1) The F limi s for RATED THERMAL PO ER (F P) for the appropriate measured re planes given in Specifi tion 4.2.2.3e. and f.,

l below, a d t 2) The r ationship:

F =FRTP [1+0.2(1-P)],

x here F ' is the limit for fractional THERMAL PO' R operation express as a function of F R and P is the fracti of RATED THERMAL-POWER at which F was measured.

Bas Load Operation requires a minimum allowable power level, APLNO ,o 75%

R 0 THERMAL-POWER to be maintained based on the figures given in the Ra(ial

j. P aking Factor Limit Report for Base Load Operation per Specification 6.9.1\6.

( _

COMANCHE PEAK - UNIT 1 3/4 2-6 Amendment No. 1 i

F.nclosure 3 to TXX-91179 Page 20 of 32 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 FQ (Z) shall be evaluated to determine if it is within its limit by:

a. Using the movable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% of RATED THERMAL POWER.

b. Degermining the computed heat flux hot channel factor, Fg (Z), as follows:

Increase the measured F distribution map by 3%tog(Z) obtained account from the power for manufacturing tolerances and further increase the value by 5% to account for measurement uncertainties,

c. Verifying that FgC(Z), obtained is Specification 4.2.2.2b.

above, satisfies the relationship in Specification 3.2.2.

d. The Fg C (Z) obtained in 4.2.2.2b above shall satisfy the following relationship at the time of the target flux determination:

FgC (Z) $ FgRTP x K(Z) for P > 0.5 P x W(Z)

FgC (z) g rqRTP x K(Z) for P $ 0.5 0,5 x QZ)~

C where Fg (Z) is obtained in Specification 4.2.2.2b. above, RTP Fg is the Fg limit, K(Z) is the normalized Fq(Z) as a function of core height, P is the fraction of RATED THERMAL POWER, and W(Z) is the cycle dependent function that accounts for power distribution transients encountered during normal operation. FORTP, K(Z) and W(Z) are specified in the CORE OPERATING LIMITS REPORT as per Specification 6.9.1.6.

e. Measuring F Q (Z) according to the following schedule:

1. Upon achieving equilibrium condition after exceeding by 20% or more of RATED THERMAL POWER, the THERMAL POWER at which FQ (Z) was last determined *, or

2. At least once per 31 Effective Full Power Days, whichever occurs first.

Power level may be increased until the TilERMAL POWER for extended operation has been achieved.

Enclosure 3 to TXX-91179 Page 21 of 32 POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS (Continued) 4,

( Remeasuring y according to the' foHowingMe15 elk-

1) When F is greater than the Fy limit for the appropriate m sured core plane but less than the F relationship, additi al R

power distribution maps shall be take and F compared F,TP and F xy either:

a) Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of RATE THERMAL POWER or greater, the THERMAL POWER at whic was last determined, or *Y b) t least once per 31 Effective Full Pow Days (EFPD),

ichever occurs first.

P

2) When the is less than or equal to t F limit for the appropriat measured core plane, addi onal power distribution maps shall b taken and F compare to F P and F at least once per 31 E 0.

e. (FRTP) shall be provided for The F,y limits for R ED THERMAL POW x all core planes contai 'ng Bank " control rods and all unrodded core planes in a Radial eaking ctor Limit Report per Specifica-tion 6.9.1.6;

f. The F xy limits of Specifica on 4.2.2.3e., above, are not applicable l in the following core pla r ions as measured in percent of core height from the bottom the el:

1) Lower core regi from 0 to %, inclusive,

2) Upper core r ion from 85 to 1 , inclusive,

3) Grid pla regions at 17.8 t 2%, 3 1 1 2%, 46.4 1 2%, 60.6 1 2%,

j and 74. t 2%, inclusive, and

4) Cor plane reoions within i 2% of core ight [t 2.88 inches]

l

' a ut the bank demand position of the Ba "0" control rods.

g. Wit F x exceeding F , the effects of F on F q ) shall be aluated to determine if9F (Z) is within its limit .

4.2.2.4 When qF (Z) is measured for other than F xy determination an overall l meas ed F (Z) shall be obtained from a power distribution map and increased 9

i by % to account for manufacturing tolerances and further increased 5% to l M count forJeaswomant uncertminty.

COMANCHE PEAK - UNIT 1 3/4 2-7 Amendment No. 1 l

Enclosure 3 to TXX-91179 l Page 22 of 32 8N5tRT 8

f. Vich measurements indicating maximum [F (!) )

over Z ( K(Z) /

has of the increased followingsince actions theshall previous determination of Fq (!) either be taken:

1) Increase F Z) by 2% and verify that this value satisfies the relatibs(hip in Specification 4.2.2.2d, or

2) F shall be measured at least once per 7 Effective Full Pbe(!)r Days until two successive maps indicate that maximum /Fq (!) ) is not increasing, over Z ( K(Z) )

g. With the relacionships specified in Specification 4.? 2.2d above not being satisfied: -

1) Calculate the percent that Fq (Z) exceeds its limits by the following expression:

maximum Fq (Z) x V(Z) i gg 1 x 100 for P > 0.5 over Z F l

Q x K(Z)

P

. . i maximun F O III * "II) l , gg 1 x 100 for P $ 0.5, and

< over Z F l Q x K(Z)

, . 0.5 -

2) Tha following action shall be cakan:

Within 15 minutes, centrol the AFD to withia new AFD limits which are determined by reducing the AFD limits specified in the CORE OPERATINo LIMIT REPORT by it AFD for each percent Fg(E) exceedes its limits as determined in specification Withia 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , reset the AFD alarm setpoints 4.2.2.2g.1.

to these modified limits.

I 1

_ , __ _, , , . _- .-. ... . ---. . - -- - - to TXX-91179 Page 23 of 32-INSERT C

h. The limits specified in Specification 4,2.2.2c are applicable in all core plane regions, i.e. 0 1006. inclus ive .

1. The limits specified in Specifications 4,2.2.2d 4.2.2.2f. and 4.2.2.2g, above are not applicable in the following core plane regions:

1. Lower core region from 0 to 154, inclus ive .

2. Upper core region from 85 to 1006, inclus ive .

4.2.2.3 When qF (2) is seasured for reasons other than meeting the requirements of Specification 4.2.2.2 an overall measured F9 (Z) shall be obtained from a power distribution map and increased by 34 to account for manufacturing tolerances and further increastd by 5%

to account for measurement uncertaincy.

4

I:ncle sure 3 to TXX-91179 Page 24 of 32 POWER DISTRIBUTION LIMITS 3/4.2.3 NUClitR ENTHALPY RISE HOT CHANNEL FACTOR F H LIMITING CONu! TION FOR OPERATION 3.2.3 F g shallbeIfhfdby hhfpilowingrelationship:

N Fu b

I 3H 1 1. 0 g @t Al.0 - Q

, , . , ~ ^ _s Where: -

p[ : th p[g ; 7,, , ; , my Rf)7c 6 THERMAL POWER p _ RATED THERMAL PowEfl l( 7 ptRM At Po u) E R (RT P) . spec;li e J zu + L e. C o /td o PER /4 T.I tJ & L Jt-il T.5 0 '

APPLICABILITY: MODE 1.

ACTION: P I'A H

" N* fewer ( w ine aw h!p he r i f c> e Ffp .s p e e ; fi e .1 in -I k e COLR yaf' With F 3g exceeding its limit: _ j

a. Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

1. Restore F H te within the above limit, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the above limit, verify through incore flux mapping that F H has been restored to within the above limit, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

c. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit

! required by ACTION a.2, and/or b., above; subsequent POWER OPERATION may proceed provided that F g is demonstrated, through incore flux l mapping, to be within its limit prior to exceeding the following l THERMAL POWER levels:

1. A nominal 50% of RATED THERMAL POWER,

2. A nominal 75% of RATED THERMAL POWER, and l

l 3. Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMAL POWER.

1 COMANCHE PEAK - UNIT 1 3/4 2-8

REACTIVITY CONTROL SYSTEMS to TXX-91179 i Page 2gy2 C- 360 eem ww M h ""

MODERATOR TEMPERATURE COEFFICIENT (Continued) h1 s ( Ly el U St- WO

]

involvedsubtractingtheincrep[alchangeintheMDCassociatedo'tnacore cond tion of all rods inserte( (most positive MDC) to an all rods thdra.n condition and, a conversion fpr the rate of change of moderator de sity with temperatureatRATEDTHERMALpWERconditions. This value of the y0C was then transformed into the limiting MTC value,4 0 - 10 ' ak/k/24- The MTC value af 3.1 m 10

LKiv*r represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppm equilibrium boron concentration and is obtained by maxing these corrections to the limiting MTC y value.cf,-1.0 10 ' ak/k/" p ot, The Surveillance Recuirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System everage temperature less than 551 F. This limitation is required to ensure: (1) the moderator 'perature coefficient is within it analy:ed temperature range, (2) the trip ,strumentation is within its normal cperating range, (3) the pressurizer is ca: 3cle of being in an OPERABLE status witn a steam buccle, and (4) tne reac + vessel is above its minimum Ri temperature.

ND7 3/4.1.2 BORATION Sf5TEMS The Boron Injection System ensures that negative reactivity control is available during each mode of facility operation. Tne components required to perform this f unction include: (1) borated ater sources, (2) charging pumps, (3) separate flow paths, (4) boric acid transfer pumps, and (5) an emergency power supply from OPERABLE diesel generators.

With the RCS average temperature above 200 F, a minimum of two boron injection flow paths are required to ensurs single functional capability in the event an assumed failure renders one of the flow patns inoperable. The boration cacability of either flow path is sufficient to provide a SHUTOOWN MARGIN from expected operating conditions of 1.6*. Ak/k after xenon decay and cooldown to 200 F. Tne maximum espected boration capacility reauirement occurs at EOL from full power equilibrium xenon conditions and requires 15,700 gallons of 7000 ppm borated water from the boric acid storage tanks or 70,702 gallons of 2000 ppm borated water from the refueling water storage tank (Ra5T).

COMANCHE PEAK - UNIT 1 B 3/4 1-2

__ ___.-_____m.. _ _ _ _ _

En:losure 3 to TXX-91179 Pase 26 of 32 3/4.2 POWER DISTRIBUTION LIMITS

-BASES The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by: (1) maintaining the minimum ONBR in the core greater than or equal to 1.30 during normal operation and in short-term transients, and (2) limiting the fission gas release, fuel pellet temperature, and cladding mechanical properties to within assumed design criteria. In addition, limiting the peak linear power density during N ndition I events provides assurance that the initial conditions-assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200'F is not exceeded.

The definitions of certain hot channel and peaking factors as used in these specifications are as follows:

F9 (Z) Heat Flux Hot Channel Factor, is defined as the maxicaum local heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods Q a.m L N

F AN Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of

.the integral of linear power along the rod with the highest integrated power to the average rod powe @

FgZ) 5 di:1 P :k4r.g.F :ter, i; d ffned as th; rati Of peak p wer dens +ty t ever:g: p w;r den:ity h the heri:ent-1-pl:n: at 007: elevat-icn Z.

+Q Yq %;+ speded w Ac CQ22 OPERATrd& L,IfG TS Rt: 90R.T 3/4.2.1 AXIAL FLUX OIFFERENCE bN The limits AXIAL FLUX OIFFERENCE (AFD) arure that the F (Z) upper bound envelope o +:90 times the normalized axial peaking factor Eis not exceeded during either normal operation or in the event of xenon redistribution following power changes.

Target flux difference is determined at equilibrium xenon conditions.

The rods may be positioned within the core in accordance with their respective insertion limits and should be inserted near their normal position for steady-state operation at high_ power levels. The value of the target flu: 'ference obtained under these conditions divided by the fraction of RATED THn ~il POWER is the target flux difference at RATED THERMAL POWER for the asso v ted a core burnup conditions. -Target flux differences for other THERMAL POWER levels are obtained.by multiplying the RATED THERMAL POWER value by the appropriate fractional THERNAL POWER level. The periodic updating of the target flux-difference value is necessary to reflect core burnup considerations.

COMANCHE PEAK - UNIT 1 B 3/4 2-1

1:ne l mu r e 3 to u x-91I w I' o r. e 27 of 32 POWER DISTRIBUT!,0N,LlHITS

, BASES _

AX!AL FLUX O!FFERENCE (Continued)

The lintits on AX! AL FLU)L DITFERENCE ( Af D)feregiveninSpec)fication,3.2.1.

[

Twoffi edes of oper4t' ion are germissible. If the

,AFD teelimi,ti >perationresult'in res 0

/th lessFt (Z)}rictions/n n its lif ting VAlue, anotbe'r the mapfmum operatfng mode a)iowed p in powyf level has'been deffned. Tt is

' mode' whichpdoes NO is called Base t' cadnot allow Operition, w (c 5'gnific4d)t levels t,6 change)h between resp

,A[L and RATED ve.

tion /a24-hoyr'JH waitin MALPpdR,inclu Prior to eptering B[adLoad Opp power,devel aboyb APLND ( d mainta hed witpIn i 5%)/1s necess'g ary toperiod a a f After t waiting pptiod,Ba.seLoadOp6 ration's}JowcoretenonstapflizationDuring Base Load Op r'emain witnin its -taraet band. permitted.

~

/ '

Although it is intended that the plant will be operated with the AfD with-in the target Land "equired by Specification 3.2.1 about the target flux differ-ence, during rapid plant THERMAL POWER reductions,wh44e-4&HomaMperat4ehr' q/ control rod motion will cause the AFD to deviate outside of t.1e target band at a reduced THERMAL POWER levels. This deviation will not affeet the xenon redis-O tribution sufficiently to change the envelope of peaking factors which may be U reached on a subseouent return to RATED THERMAL PpWER (with the AFD within the g target band) provided the time duration of the deviation is limited. According-ly a 1-hour penalty deviation limit cumulative during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is

+

a(pro,videdforoperationoutsideofthetargetbandbutwithinthelimitso'4g-ure 3.2-1 while at THERMAL POWER levels between 50% and 90% of RATED THERMAL p

POWER. For THERMAL POWER levels between 15.% and 50% of RATED THERMAL POWER, deviations of the AFD outside of the target band are, less significant. The 5w penalty of 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months actual time reflects this reduced significance.

3 Provisions for monitoring the AFD on an automatic basis are derived from the plant process computer through the AFD Monitor Alar.a. The computer deter-y 4

mines the 1-minute average of each of the OPCRABLE excore detector outputs and provides an alarm message immediately if the AFD for two or more OPERABLE excore channels are outside the target band and the THERMAL POWER is greater than 90% of RATED THERMAL POWER. During operation at THERMAL POWER levels between 50% and 90% and between 15% and 50% P.ATED THERMAL POWER,-the computer outputs an alarm message when the penalty deviation accumulates beyond the limits of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , respectively.

/ During Base, Load OperaOon at-less than'o'r equal to 90% RATED THERNAL'

, POWER tffe AFD,Monito i unlesy the AFO Monitor' Alays has provisiops'pAlarm iV6onsidered' to immediately/ alarm abov /ADL with AFDinoper outside,the target band / '

/ / f Figure B 3/4 2-1 shows a typical monthly target band.

3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and NUCLEAR ENTHALPY R!SE HOT CHANNEL FACTOR The limits on heat flux hot channel factor and nuclear enthalpy rise hot channel factor ensure that: (1) the design limits on peak local power density COMANCHE PEAK - UNIT 1 8 3/4 2-2 Amendment No. 1

. - - - - . - - . - - - . - - - ~ -

Enclomtre 3 t o TXX-91179 Page 28 of 32 POWER DISTRIBUTION LIMITS BASES s

HEAT FLUX HOT CHANNEL FACTOR and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)

When an qF measurement is taken, an allowance for both experiment.tl error and manufacturing tolerance must be made. An allowance of 5% is approoriate for a full-core map taken with the Incore Detector Flux Mapping System, and a 3% allowance is appropriate for manufacturing tolerance.

N p When F 3g is measured, an adjustment for measurement uncertainty n.ust be

( g, included for a full-core flux map taken with the Incore Detector Flux Mapping 6 System.

IFRadial T eaking Factor', F ,isitasurgdperiodicallyto]rovide

/

ass rance tha

/ X1 thedfot Chann[1 Fact r, F t

/

(Z)f emains

/ /

within itylimit,.fe

/

f F limi r T TP)qdsprovdedint .' Radial Pf iking xy ATED JH N L P)W d (F Facto Lim) Repor Vper Spetification'6.9.1. was det c t power control manuevers 4ver the full rangeconditinns _nf_.burnup$

in tli inedfropIxpep re Fg(2) r g should be measured with the reactor core at, or near, equilibrium conditions. Therefore, the effects of transient maneuvers, such as_ power increases, should be permitted to decay to the extent possible while assuring that flux maps are taken in accordance with the specified surveillance schedules.

1/4.2.4 QUADRANT POWER TILT RATIO

' The QUADRANT POWER TILT RATIO limit assuree that the radial power distribu-tion satisfies the design values used in the power capability analysis.

Radial power distribution measurements are made during STARTUP testing and periodically during power operation.

The limit of 1,02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A limit of 1.02 was selected to provide an allowance for the uncertainly associated with the indicated power tilt.

The 2-hour time allowance for operation with a tilt condition greater than 1.02 is provided to allow identification and correction of a dropped or misaligned control rod. In the event such action does not correct the tilt, .'

-the margin for uncertainty on F q is reinuated by reducing the maximum allowed power by 3% for each percent of tilt in excess of 1.

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles.

COMANCHE PEAK - UNIT 1 8 3/4 2-5 Amendment No. 1

Encionure 3 to TXX-91179 l' age 29 of 32 INSERT E The heat flux hot channel factor FQ(Z) is measured periodically and increased by a cycle and height dependent power factor appropriate to CAOC operation, W(Z), to provide assurance that the limit on the heat flux hot channel factor, FQ(Z), is met. W(Z) accounts for the effects of normal operation transients within the AfD band and was determined from expected power control maneuvers over the range of burnup conditions in the core. The W(Z) function is provided in the CORE OPERATING LIMITS REPORT per Specification 6.9.1.6.

1:nclosure 3 to TXX-91179 Page 30 of 32 4 yy//

ADMINISTRATIVE CONTROLS I

MONTHLY OPERATING REPORTS (Continued)

Management, U.S. Nuclear Regulatory Commis ion, Washington, D.C. 20555, with a copy to the Regional Administrator of the egional Office of the NRC, no later than the 15th of each month following the alendar month covered by the report.

YADIALPEAKINGFACTORLIMITREPORT ~N-6.9.1.6 The F xy limits for RATED THERMAL POWER (F,RTP) shall stablished be foratlekeachreloadcoreforNormalOperationandBase d Operation and (

shall be mainta.ined available in the Control Room. The y ts shall be estab- )

lished and imple nted on a time scale consistent witivfiormal procedural changes. /

The analytical methods bsed to generate the F/ limits shall be reviewed and I approved by the NRC for CbES. specific u . changes to these methods are deemed necessary they will behaluatyd in accordance with 10 CFR 50.59 and submitted to the NRC for review &n 4pproval prior to their use if the change is determined to involve an unr3 e d safety question or if such a change would require amendment o viously bmitted documentation.

A report containing the xy limits for all re planes containing B&nk "D" control rods and ay unrodded core planes along ith the plot of predicted F

q P

REL axi ) core height (with the limit envelop for comparison) shall be provide o the NRC Document Control desk with copies o the Regional Admin-!

Istrato nd the Resident Inspector within 30 days of the(ir mplementation.

Th eport shall also establish the minimum allowable power leve APL ND , for e Load Operation for at least each reload core and shall be main ined in

. the Control __ Room._ j

) '

SPECIAL-REPORTS 6.9.2 In' addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, special reports shall be submitted to the Regional

-Administrator of the Regional Office of the NRC within the time period speci-fied for each report.

6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal-Regulations, the follering records'shall be retained for at least the minimum period indicated.

6.10.2 The-following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level;

b. Records and logh of principal maintenance activities, inspections, repair,'and replacement of principal items of equipment related to nuclear safety; 1

COMANCHE PEAK - UNIT 1 6-20 Amendment No. 1

_ ... . -- _ _~_ _._.___~____ _

1:nc ionure 3 t o TXX-91179 Page 31 of 32 hgh p q_QRE OPERATING LIMITS REPORT 6.9.1.6 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 followings

a. Moderator temperature coefficient DOL and EOL limits and 300 ppm surveillance limit for Specification 3/4.1.1.3,

b. Shutdown Rod Insertion Limit for Specification 3/4.1.3.5,

c. Control Rod Insertion Limits for Specification 3/4.1. 3.6,

d. AXIAL FLUX DIFFERENCE Limits and target band for Specification 3/4.2.1,

c. Heat Flux Hot Channel Factor, K(Z), W(Z), and F f for Specification 3/4.2.2,

f. Nuclear Enthalpy Rise Hot Channel Factor Limit and the Power Factor Multiplier for Specification 3/4.2.3.

The analytical methods used to determine the core operating limito shall be those previously approved by the NRC int

a. WCAP-9272-P-A, "WESTINGIIOUSE RELOAD SAFETY EVALUATION METilODOLOGY", July 1985 (H Proprietary).

(Methodology for Specifications 3.1.1.3 - Moderator Temperature coefficient, 3.1.3.5 -

Shutdown Bank Insertion Limit, 3.1.3.6 - Control Sank Insertion Limits, 3.2.1 - Axial Flux Dif ference, 3.2.2. - Heat Flux Ilot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise !!ot Channel Factor.)

b. WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES -

TOFICAL REPORT", September 1974 (W Proprietary).

(Mothodology for Specification 3.2.1 - Axial Flux

Difference (Constant Axial Offset Control).)

i

c. T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC January 31, 19 80-- Attachment : Operation and Safety Analysis Aspects of an Improved Load Follow Package.

(Methodology) for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control].)

d. NUREG-0800, Standard Review Plan, U. S. Nuclear Regulatory Commist. ion, Section 4.3, Nuclear Design, July 1981. Branch Technical Position CPD 4.3=1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981.

(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control).)

l l

l

. ._ _ _ - _ . . . _ . . - _ _ _.- _ . , , _ . . , . . _ . . _ . ~ . _ . _ _ _ . . _ _ - - , . . _ _ . . , _ - , _ . , _

_ . . _ _ . _ _ _ _ _ . . _ _ .. _ _ .. m . _ _. _ __ _ .m. _ -

Enclosure 3 to TXX-91179 Page 32 of 32

e. WCAP-10216-P-A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLARCE TECl!NICAL SPECIFICATION", June 1983 (H Proprietary).

(Mothodology for Specification 3.2.2-Iloat Flux Ilot C%nnel Factor (W (z) surveillanco requiromonts for F, Methodology).)

f. WCAP-8200, "WFLASli, A FORTRAN-IV COMPUTER PROGRAM FOR SIMULATION OF TRANSIENTS IN A MULTI-LOOP PWP," Rovision 2, July 1974 (H Proprietary).

(Mothodology for Specification 3.2.2 - lleat Flux Ilot Channel Factor).

g. WCAP-9220-P-A " Westinghouse ECCS Evaluation Hodol, February 1978 Vorsion," February 1978 (H Propriotary) .

(Mothodology for Specification 3.P.2 - lloat Flux llot Channel Factor) .

The core oporating limits shall be datorminod so that all applicablo limits (e.g., fuel thermal-machanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are mot.

The CORE OPERATlHG LIMITS REPORT, including any mid-cycle revisions or supplomonts thoroto, shall be provided upon issuanco, for each roload cycle, to the NRC Document Control Desk with copics to the Regional Administrator and Resident Inspector.

I k

I t

ENCLOSURE 4 TO TXX-91179 PRELIMINARY VERSION Of THE CORE OPERATING LIMITS REPORT USING PREllHINARY CYCLE 2 INFORMATION FOR UNIT 1 i

o i

?

7

.~+-..-..~.y.m<..,.y,m,,,,,.

y .....,,.._..~,,,_r,,,m._m~.___,-,,,_,,,,,__,,,.._ , . . , ~m.......,~.m..._..m,,

o- .

PREllMINA9Y CPSL UNIT 1 CYCLE 2 CORE OPERATI!1G LIMITS REPORT Revision - Preliminary March 5, 1991 I

. _ . . ,.-----.,-,_.._m.m._,

NIEl.lMIN AR ( l COLR for CPSES UtilT 1 CYCLE 2 1.O CQRIL_Q1'EIMT1110_ LItilTS-.13EPQRI Thin core operating Limita Report (COLR) for CPSES UNIT 1 CYCLl: 2 han boon prepared in according with the requiremonta of Technical Specification 6.9.1.6.

The Technical Specifications affected by this report are linted below:

3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Rod Insortion Limit 3/4.1.3.6 Control Rod Innortion Limits 3/4.2.1 Axial Flux Difference 3/4.2.2 Ileat Flux !!ot Channel Factor 3/4.2.3 Nuclear Enthalpy Riso llot Channel Factor REV. Preliminary PAGE 1 OF 9

, PRI.t.tMitMRY

_=

COLR For CPSES UNIT 1 CYCLE 2 2.0 OPERATING LIMITS The cyclo-specific paramotor limits for the specifications listed in Section 1.0 are prosented in the following subsections. Thono limits have boon developed using the NRC-approved methodologien specified in Technical Specifications 6.9.1.6.

2.1 Moderator Temperature coefficient (Specification 3/4.1.1.3) 2.1.1 The Moderator Temperaturo Coef ficient (MTC) limits aret The BOL/ARO/IlZP-MTC shall be less positivo than

+5 pcm/*F.

The EOL/ARO/RTP-MTC shall be loss negativo than 4 0 pcm/'F.

2.1.2 The MTC surveillanco limit ist The 300 ppm /ARO/RTP-MTC should be loss negativo than or equal to -31 pcm/*F.

whoro: BOL stands for Beginning of Cycle Life ARO stands for All Rods out HZP stands for llot Zero THERMAL POWER EOL stands for End of Cycle Lifo l

RTP stands for RATED Ti!ERMAL POWER REV. Preliminary PAGE 2 OP 9

PRf.LlhOi4ARY COLR for CPSES UNIT 1 CYCLE 2 2.2 Shutdown Rod Insertion Ldn11 (Specification 3/4.1.3.5) 2.2.1 The shutdown rods shall be withdrawn to at least 222 stops.

2.3. Control Rod Insertion Limiin (Specification 3/4.1. 3.0) 2.3.1 The control rod banks shall be limited physical insertion as shown in Figure 1.

2.4 Axial Flux Differente (Specification 3/4.2.1) 2.4.1 The AXIAL FLUX DIFFERENCE ( AFD) target band is

+5%, ~5%, for core average accumulated burnup 5 3000 MWD /MTU.

2.4.2 The AFD target band is +3%, -12%, for core average accumulated burnup > 3000 !!WD/MTU.

where: MWD /MTU stands for megawatt days /motric tonne of initial uranium metal 2.4.3 The AFD Acceptable Operation Limits are provided in Figure 2.

l REV. Preliminary PAGE 3 OF 9

PR Et.IMINARY COLR for CPSES UNIT 1 CYCLE 2 2.5 Heat Flux llot Channel Factor - F,(Z) (Specification 3/4.2.2)

F,(Z) 5

K (z) for P > 0.5 P

F,(Z) S

K(z) for P s 0.5 0.5 where P = THERMAL POWER RATED TilERMAL POWER 2.5.1 Fo * = 2.32 2.5.2 K(Z) is provided in Figuro 3 2.5.3 W(Z) values are provided in Figure 4.

l REV. Preliminary PAGE 4 0F 9

PRELIMINARY COLR for CPSES Ul1IT 1 CYCLE 2 2.6 fluclear Entilainy Rise 110t channel Factor - F"g, (Specification 3/4.2.3)

F"3, 5 F RIP e {g 4 pp ,

{ y.py )

where: P = TilERMAL PO'/ER RATED TilP:d4AL POWER 2.6.1 F RTP AN = 1.55 2.6.2 PF 3, = 0.2 l

l l

l I

l REV. Preliminary PAGE 5 OF 9

FRF. LIM Nr.rgy __.

COLR for CPSES UNIT 1 CYCLE 2 FIGURE 1 ROD BANK INSERTION LIMITS VERSUS TIIERMAL POWER l'0

.t.

e ,- _

_: (27.3.222) _ !(81.6,;;; E r

f 3ANK B f'

'^

.,, .- i -

..- ~;

2 4' -,-

s r*EE (0,164) -

2:60 f e .-

O (100,146) 7 x

's / ,.-

c. 9ANK C ,f so .-

5 s

@ ./ j C

x 0c :

f -

a .

r .-_

y ,. -

/ /

4 ' '

= .- ,- EANK 0

$ ,/

w 4. .- ,

M (0,49) ,f'

~

so : _

_= .

l l0 .-

(31.0) 0 3 10 20 30 40 SO 60 70 - 40 10 *;

PERCENT OF RATED THERMAL POWER

FULLY VITHDRAVN SRALL BE THE CONDI!!ON VHIRE CONTRCL RCCS ARE A!

A POSITION VITHIN THE INTERVAL CF 2 222 AND 1231 STI?S VITER.WN.

REV. Preliminary PAGE 6 OF 9

l FRELIMit4ARY \

COLR for CPSES UNIT 1 CYCLE 2 FIGURE 2 GXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED TilERMAL POWER '

120

- 100

(-11.90) (11 90)

O c, UNACCEPTABLE UNACCEPTABLE ;

CPERATION CPERATION

.J ,,0 t:: :

b C

y ACCEPTABLE

. CPERA TICtf oO e

O W ,

(-31.50) r (31.50)

~- l- I

. 40 u

C at 20 I

0 '

40 20 -lO O IO 20 30-40 50 FLUX OIFFE:ENCE (.^.,I) %

P.EV . Preliminary PAGE 7 OF 9

, . - , - - , , - - - , . , - ,v,,, -- ,,.,,nv r-,a,.n a,- g.. ,.,._-,,_,.m-,m_,,v.&.n.n,.._,,.,n,, ,,_,_unemm.---~,,e.,-.,g,r-._,-7,-,-n,.-, ,.-.,v,..,nmwmqw. ,--g e v -. me

PRELIMitJARY "

COLR FOR CPSES UNIT 1 CYCLE 2 FIGURE 3 K(Z) -

NORMALIZED F,(Z) AS A FUNCTION OF CORE llEIGitT l.2

~

l (0.0.1.0) (6,0.1.0)

UC; l.0 I10.8.0.341 L ,

C 0.E .

4g U l g 0.6 . (it.:.0.s') -

I Q ,

i I

- O.4 -

8 l

- t i N C.2 O.O O 2 4 6 9 10 i2 la CORE HE!3HT !PT; 1

i l

l i

l-REV. Preliminary _

PAGE 8 OF 9

f PHCLIMINArgy ~

COLR for CPSES UllIT 1 CYCLE 2 FIGURE 4 W(Z) AS A FUliCTIOli OF CORE 11E1011T 1M ..I, .i.. . i ii i_l, i. . . . .. I,i . .. iii. iii.

ill teli till iall til. I..' .i till 41. lill Ill. 166.

.tel e.l. . Ili alii

.i iil tit i.l list I it

. .i ..

, ,1l 11;. tili i t. 1 1 (_ . .l. til liti l{ll

.ill ll1 .til til lll1,1e11 ll lill til* liii Ille flil

.lil 194 .iil .tif' t il l '8 4_ e it ; ,

s ..l. f(qq i,q. g, il aj ~ elli ..!I iill (i i ! e 1.1 ..' I all alli lij. I II eli l'l. l .1 - *lli ll11 ...l i.i' Ilia 14.8 - ill ill i' il

,tli ..l. ;..! ilt til! I,.i . . I't. ;. ..le eil, titi isit e . 8: l t esi illi sill illi i li eie . set .il lei.

1.25 , , ., ii. ... .... .... . , .

1,, ..l. iil

. , i. i.

.i =. .. .. . . .a :. . ,.

i . , ... ,

ie o . . ... .... . . . ...

1.20 si i o ,, i. . ., ,, ,ii, .. .. ... .ii, n

.. .. .. o ,

il 3 ,, i, ,

.n....e i,. .. . .

si in- .i

.;. is .i .... ..i in. . iu .,

i ii. .n .* o iiii o. ..., ieo .. o. . .i. ii ,

1.1'* o ,ii; s

.. . ..i .ti .i.il ..i ,iis ii.- i- .ii iiii a11 It1. 't ' let ilI. 'is" <

'll ille it; d'.'l. ill' lill t 't* to til . l : l' a'

il iiis is. '!! 'il ;.i

. i! - i .', i lll ilil

Iiji .

ll1 li, l8i

isl. l}e4 si ..!. ..i . iti liti i .i'l i .14 ilia .

s. til 4ll. -

1.10 oo .. ois oii

i. iii, ii! n i i nii io, iii. ..ii i i .si 6 ett lill .Ie . .ill liis l lit 'lli ill' ist' I til i;i. ii elii tali .

i. init lili iti. ilt! ist. ilii i+i *4t. . iis iitl' .: - e l' ifli la sili ell 1111 i.I 1. 1 . 4ij lill i. I als lil, ele .fli illi lill 1.e5 ... . ,n .n. o,

... .. o3 iiii 1 .I i. . .i-.

ilil ll'i .llI li ll lia l 4 8ll ll1 (i ill! tlli Ill I ll i * . cs.. i s). "l e t fl< 1 it. 'ill li i siti ill: ll i li

_lii ill: .111 .I .I l< ! 1 .* t ..i' 1 14 1 ill' illl ilta l' il lij . 41 ...l L' if 1 i i.it ..! Il I ill till ll11 i' ll s.m 6 1 2 3 4 6 6 7 8 9 10 11 12 COREHEIGH1-(Teet) l REV. Preliminary PAGE 9 OF 9 l

- . _ _ .-- , _ _.._ _ _ _ - - - . _ . , _ ,

ML20084V145

Text

Navigation menu

Search