ML19351A570

Proposed Tech Specs Re Core Operating Limits Rept,Core Alteration,Moderator Temp Coefficient,Movable Control Assemblies & Shutdown Rod Insertion Limit

ML19351A570
Person / Time
Site:	Summer
Issue date:	12/11/1989
From:	SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML19351A566	List: ML19351A565 ML19351A570 ML19351A674
References
NUDOCS 8912190343
Download: ML19351A570 (35)

Text

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y 1.1 ACT!0N........................................

1.2 ACTWT!0ll LOGIC TE8T..........................

.......... 11

1.3 A MLOS CM181EL OPERATIONALTE5T................

.......... 11

......... 1-1

1.4 AXIAL FLN 0!FFEREllCE..........................

~( .

1. 5 CMisEL CALISRAT!0ll. . . . . .

......... 1-1

! 1-1

• 1.6 CNA191EL CNECE............................................

................................ 1-1

)

1.7 C00ffA!IO W ff IlffE8t!TY......... .......................... 1-2 1.8 CelffRDLLED LEA M8E............ .

1-2 i

' 1. 9 CORE ALTEMT!0N. . . . . . . . . . . . . . . . .........

I u .10 00$E EQUIVALENT I-131..................... .......... 1-2 1-2 lt l g 1.11 E AVERAGE DI518tTEGRATI0ff ENERBY. . . . . . . . . . . . . . . . . . . . . . . . . 1-3 .

h

'1.12 EN8311EERED SAFETY FEATURES RESPONSE 1.13 F T1M................. 1-3 g WTAT!0N....................................... 1-3

t 1.14 e E RA0 m sTE TREATnENT sYsi m..................... .... 1-3 Q4 l

1.15 IDENTIFIED LEA M 4E............ .......................... 13 i 1.16 28tER RELAY TE57.............

.......................... 13 ig.- 1.17 0FF8ITE 00$E CALCULATION IIANUAL 00CM ...... 1-4 l

b 1.14 OPERABLE - OPERA 81 LITY. . . ............. . . . . . . (. . . . . .).1-4.......

I % 1.19 OPERATICIIAL MODE - MD0E. . . . . . . 14 1.20 Piff$tCS TE578............................................

................. ......... 1-4

' 1.21 PRE $$URE SOUNDARY LEARA0E...................... ......... 14 1.22 PROCES$ CONTROL PROGilAll PCP ..

[Q',

1. 23 PURBE-PURBI818. .. ...........................

1.24 QUA0lWif POWER TILT RAT!0.............

. . . . . . . . (. . . . ). . . . . . . . . 1-4

.14. -. . . . . .

1-5 1.25 RATB T m P0WER................... .................. 1-5 l >

1.26 REACTOR TRIP WSTEN RESP 0ll5E T1M....... 1-5 l t 1.27 REPORTABLE EVEkT......................................... ................. 1-S-dj 1. 28 SIRff00W MABIN. . . . . . . . . . . . . . . . . . ....................... 1-5 l

i y 1.29 SLAVE RELAY 7E87................. ....................... 1-$

1.30 $0L10!FICATI0ll................. ......................... 15 l

1.31 SOURCE CMcK................... ......................... 1-5 1.32 STA00ERED TEST 848!0............. 1-6

1. 33 TEMAL P0ER. . . . . . . . . . . . . . . . . . . . ........................

...................... 1-6

1. M TRIP ACTunTINB DEY!CE OPERATI0llAL TE57.... 1-6

1. 35 ist!OElfTIFIS LEAEA0E. . . . . . . . . . . . . . . . . . . ...............

.................. 1-6

1. 34 VElfTILATION EMAUST TREATMiff $YSTM. . . . . . . . . . . . . . . . . . . . . 1-6 1.37 VElfTINS.................................................. 1-6

^

TABLE 1.1 OPERATIONAL 2 0ES................................... 17 -;

TABLE 1.2 FREQUEEY NOTAT!0N.................................. 18 I.

SLMER - UNIT 1  ! Amendment No.

4 e

8912190343 891211 PDR ADOCK 0500039S g PNV

s

.c. ,

,, ADMINISTRAT!Vf CONTROLS Ed Re,se ........................................ ............ ..,

Audits......................................... ............

Authority...................................... ............

4 10 4 10 Records........................................ ............ 6-11 4.5.3 TEOst! CAL REVIEW Af8 CONTROL Activities..................................................

. 6-11

6. 6 *. REPORT @_t EVENT ACT!0N. . . . . . . . . . . . . . . .6 .12. . . .

6.7 SAFffY LIMIT

. V10LAT!0N........................................ 4-12 L

6.8 PROC 8"!! Als PR00RAMB. . . . . . . . . . . . . . . . . . . . . . . . 4-13 .......

( 6. 9 REPORTING ar m Ingw._NTS

6. 9.1 R0llf!NE REPORTS .

5tartup Report........................................... ..

4 14a Annual Report............................................ ..

4-15 Annual Radielegical Environmental Operating Report..........

L 6 16 5est annual Radioacti ve Effluent Release Report. . . . . . . . . . . . . .

( 6-16 j Month) Operating ope mi .................................... 4 14 i Repo rt . . . . . . . . . . . . . . . . . . . . . . . . . . \

l 4 14 i 6.9.2 'SPECIAL REP 0Rf$............................................. 6 14  !

6.10 RECOM RETEN10N. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4. 1s ....... .

6.11 RADIATION M inifiON P * * "................................. 6 20 6.12 NION RADIAff M .......................................... 6 20 4

_, y_mev , ,,,,.w....mw,--'w" ' ,,,._y,,c,e--,-*----"*"^"

1 otFINIT10NS CONTAINMENT INTEGRITY l

1.7 CONTAIMENT INTEGt!TY shall exist when:

a.

All penetrations are either: required to be closed during accident conditions 1)

Capable isolation of valvebeing closedorby an 0PERABLE containment automatic system, 1

2)

Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.4.

b.

All equipment hatches are closed and sealed, c.

Each

3. 6.1. 3, air lock is in esapliance with the requirements of Specification d.

The containment 3.6.1.2, and leakage rates are within the limits of Specification e.

The sealing bellows or 0-rings) mechanise is OPERA associated 8LE. with each penetration (e.g., welds, CONTROLLED LEAKAGE

1. 8 coolant CONTROLLE0 pump seals. LEAEAGE shall be that seal water flow suppiled to the reactor CORE ALTERATION 1.9 l C0RE ALTERATION shall be the movement or manipulation of any component within the vessel. the reactor pressure vessel with the vessel head removed and fuel in Suspension of CORE ALTERATION shall not preclude completion of

. movement of a component to a safe conservative position. i

@ DOSE EQUIVALENT I-131 I i

1.10 DOSE EQU! VALENT I-131 shall be that concentration of I-131 (sicrocurie/ gram which alone would produce the same thyroid dose as the quantity and isotopic mixture of I 131,1-132, I-133,1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14444, " Calculation of Distance Factors for Power and Test Reactor Sites." 1 l

.hter @

i SUMMER - UNIT 1 12 i I

)

l 1

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

e ,

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russat A ( Ao# TO PAos 1 3)

........................,,,,,, i f

CORE OpBRATIas Ltu!pg asygag }

1.9a The C00LB OpsakTING LIMITS REPORT (COLA) provideo core operettag liette ter the everent operatine reload e} ele.le The the unit specifi cFele in seeerdance speelfic core operattag liette with Speettisation shall be determined for each reload eyele 6.t.1.11.

operating 11alte is addressed la individual specitisettene. Plant operation within these ,

(.

f 6

6 h

9 l

t k t

L

+

h I

e k

1

\

i. - l REACT 1v!TY CONTROL $YSTEMS l

M00t4ATot TEMPERATUtf COEFFICitNT J.

oA, 2 r0  :

LIMITING CON 0!T!0N FOR OP[tAf!0N ,

i 3.1.1.3 The 3

orator temperature coefficient (NTC) shall ed IM the M6 M6 ten # kMirs UM (Col.8), The.

dd d messman m,lef SA'A e

APPLICASILITY:

. -- ;;. g

= 100t$ 1 and la onlyf '

i ACTION: ^ ^ ^

[>

dp6

a. _- -

i With the MTC sore positive than the91mit - above, operation in M00E51 and 2 may proceed preyfdod:

^"~ 1. 40L sControl rodtowithdrawa) Itaits are estabitshed and main "

• efficient re w the MTC te less positive than the I ,

k k Col.f. ~

__ . f_ Swithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in NOT STAN00Yatg  ;

' w sntn the next b hours. These withdrawal Ifeits shall be in addition to the insertion limits of Specification 3.1.3.6. .

2.

' The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that  :

[ the NTC has withdrawn condition.been restored to within its Itait for the all rods o

3.

In lieu of any other report required by Specification 6.9.1, a Special Report is prepared end submitted to the Commit, ten  ?

pursuant to Specification 6.9.2 within 10 day , describing the ,

i. value of the measured NTC, rodcontre withdrawal l units and the ,redict.d av.ra.e cor.theuroup interie.

n.c.ss.r, f.r restoring the positive NTC to within its limit for the all rods withdrawn condition. '

b.

mit lhein With the NTC eore HOT $NIJTDOWI withi hours,btive than the

,gg "With K,,, greater than or equal to 1.0

1. $ee Special Test Exception 3.10.3 0

4

+

w-w-e-y-,-+,-t,w-v=ce,w,---,-e - - = - - - .ve --4,v ,.+-e --w-e---es,e-e--- - - - , - - - - - - , ,e- - - . - - - - - - - - - - - - --

l l

.w l REACTIVITY CONTROL $YSTEMS I

$URYt!LLANCE Rt0V!AEMENT$

z l 4.1.1.3 cycle as fallows:The NTC shall be determined to be within its limits during eac;

s. The M C s

.yu.g ,

seasured and compared to the SOL limit ll prior to initial operation above e r each fuel leading. I b.

The NfC__._ shell red ta J- -~be J(allseasured rods withdrawnat any THEDEL POW C " ; __ x censmen; witnfa 7 trry after reaching an eq,uilibrius beren concen-RATED l.  ;

l a

tat C0LAg

/tration of 300 ppe.

1s more negative than ' T -In the event this e . and c to the EOL Mt 1st e

maarisen-indicates the MTC shall ,be,,, %j

> at le ,

cyc e. ace per 14 EFPD during the ress' re

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. r l t 3

E00 ffA Alsts $ . & Aft n L

( _

4044 _ _

e ___

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1 SUMER - UNIT 1 3/4 1-5 Amendment No.

d

...,,.,,.......,,m_, , , _ _ , , , _ _ , , , . . _ _ , . . . , . . _ , . . . _ , . , . ._m,..,n.-_,,_mm_..,,_,,,

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1/4.L3 luMME OWfRDL ggagtigg  ;

i

' LDt! TIS Com! TIN POR OpttfleN  ;

t 3.1.3.1 All full 1 ,

core shall be (shutdeun and control) reds'uhich are inserted in the I of their g oup step counter demand positten.and posittened within t it steps (

t

' i APPLICABILITY: 20t8 la and 28 g .

..v i j

, . vt < .

a. W )

- , ith one or more full length rods insperable due to being immovable '  !

es a tesult of ancessive fricties or eschemical interference se  !

kasun ment

.NOT.57 of to ification be untrippable,1.1.1

3. determine that the SIRIT90ldi is satisfied NhABIN within require-and be in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> i l

Y within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. -

i b.

With sets then one full length red sisa11gned free the stip b counter deoend positten by more than i 12 steps (indica position)-, i be in NOT STAWBY within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

j c.

With more than one fu11' length red inoperable due to a red control I

j, g i urgent failure alare er ebylous electrical problem in the red control system6for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, be in.NOT STA MBY within the fel-

{ lowing hours.

I gQ d.

With one full length red inesorable'due to causes other than addressed

( y by ACTION a., above or eisaligned free its grew ste l

I{g height by more then,i 12 stape (indicated position), p POWER counter deoend OpfRATION y g may continue provided that withis one hour either:

Ig 1. The red is restored to OptRABLE status within'the above alignment requirements, or ,

.{

t 2.

P p' The remainder of the rods in the gree with the inoperable red are s

f g'6 % esso 444menMete; while enintaining the red sequence and insertion tQ the THEmhL POWER level shall be restricted ,

pursuant to Specification 3.1.3.5 during subsequent oper,ation, or l

3. The red is declared inoperable and the $NUTDOWN MhtGIN requirement of $pecification 3.1.1.1 is satisfied. POWER OPERATION may then continue.provided that:

"See Specisi Test Exceptions 3.10.2 and 3.10.3. *

$UMER - UNIT 1 3/4 1-14 I 4

AmendmentNo.h l

l' .

.. GIAff!VffY CniffMLvs iin.

E I"T!olf Lfatt7 _

LIlttTINS COISIT1oM POR 4 eM* Tim -_

t 3.1.3.5 All shutasun roes shall be Maast a Znd m,i coM j

APPLICAtiL17Y: Meets 1. and **f.

ML' O f hate 4.smsfs  !

R8AFAT(CeM).

with a sentous testing pure of one samtasun roe to Specificetten 4. . . . , essept for survettlance a one hour either ,

e.

b. the re @ b M k M s/bnel M M 08kIs I Desiste the red to to inspareale and apply spesificatten 8.1.3.1.

a . ,

hteJ,

- L J '

Iw%tk& M[ew M '

r- p - 1&4, c,o L,f) . .

gewrn am -- temerts ,

L-i 4.1.3.3 tash red shalt

' 1As,'mth M I eget a.

Sa Sekt.he esterstase to be  ;

itith n Il sinutes prior to witheren) of any rees in senteel banks .

A, 8 C er 9 eurtag an appresen to reester criticality, and b.

At least enee per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> therecfter. ,

6 4 taseptfene 3.10.8 and 8.14.8. .

stfith K,pp greater them er aquel to 1.0 I

sueltR

• UNIT 1 3/4 late a P

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f.* t

• [

' REACTIVITY CONTROL SYSTEMS CONTROL R00 INSERTION LIMITS LtMITING CONDITION FOR OPERATION t ._

7 '

4-3.1.3.6 The control banks shall be liailed in physical insertion asMG

~

h tE4. C RE APPLICABILITY: 6Ps* has L.imifs REPeRT (Cot 8%fideJ. R)-

M00E3 18 and 2*W.

ILL % h 'n. Umih "LTauw

' MTION: Jpph M Pedt4, Jet, jam.l.o*p L

u. With the control banks inserted beyond the above insertion limits, except for i

surveillance testing pursuant to Specification 4,1.3.1.2, either:

a.

Restore the control banks to within the limits within two hours, or c.

L Reduce THERNAL POWER within two hours to less than or equal to that fraction using the of "RATED "; THERNAL

. POWER which is allowed by the bank pos c.

Wien, Ediu ~4M0 A m.h doLR;ot Be in at least NOT STAN08Y within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

f'JRVEILLANC,EREQUIREMENTS 4.1.3.6 The position of each control bank shall be determined to be within 1

the insertion limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals when rod positionsthe RodatInsertion least once Limitper Monitor 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. is inoperable, then verify the individual '

l 1

"See Special Test Exceptions 3.10.2 and 3.10.3 fWith K,ff greater than or equal to 1.0.

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0 0.3 03 0 02 0A 0.1 02 02 1.0 FULLY PRACTION OF TED THERMAL POWER -

l; INSERTED FlO E 3.1 1 R 0 0 OUP INSERTION LI 8 VERSUS THERMAL POW THREE LOOP OPERA ON

$l#9CR - UNIT 1 3/4 1-22 d

. ., . , - , _ - , , , , , . . ~ , . . r.,-..,,,. -_-e.,. . - . , , . . - , . , , . - . . ~ . . , . - . . -

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i DELETE BLANK FWU.RG FR.orr) Tec.H S PGCp AND ADD To d.o L R IF A9PP.40AL Foe Two Loo 9 c9644 Time is eBTAscEp In Tl4E Fu.Tu.RE .  ?

1 SUMMER - UNIT 1 3/4 1-23

,,r ' . "

('(@wspAId$&C 3/4.2 POWER O!$TRI8UTION LINITS E44Il (r s.imlT S RINSI e

3/4.2.1 AXIAL FLUX O!FFERENCE (AFO)- cola) 3 LIMITING CON 0! TION FOR OPERATION 3.2.1 The indicated AXIAL FLUX O!FFERENCE (AFO) shall be a.

_the allowed coerational. space j M

~

' '- 1 J for Relaxed Axia nt operat'on, or

b. COL within the target hand specified in the difference during base load operation. @ about the target flux L APPLICABILITY: M00E I above 50K of RATED THERMAL POWER *.

ACTION:

a. For RAOC operation with liefts specified in the ndicated AFD outside of the a'ppitcable 1.

c A-Elther restore the indicated AFD to within the specified limits within 15 minutes, or ~

L 1: 2.

Reduce THERMAL POWER to les than 50K of RATED THE within 30 minutes and reduce the Power Range Neutron Flux - High E Trio setpoints to less than or equal SSE of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, b.

[

t For lese Load of the appitcab ration above APLE target band about the with the indicated'AFD outside target flux rences:'

1.

i Either restem the indicated AFD to within the specified target band within 15 minutes, or 1

2.

i Reduce THERMAL POWER to less than APLE of RATED THERMAL POWER and discontinue lase Load operation within 30 minutes, c.-

THERMAL unless POWER the indicated AFDshall notthe is within beapplicable increased RAOC above limits.50K of RAT "See Special Test Exception 3.10.2

• • APL E

is'the einfeum al'owable be pow 44eg in thel _ '::^ power1'_. -

level for base load operation and will

... . Oper Specification 6.9.1.11.

Y -

z-- -

Cod.E O Md6Tl4 u m:75 AEh4T) _

SUMMER - UNIT 1 3/4 2-1 Amendment No I

1 POWER DISTRIBUTION LIMITS

~

3/4.2.2 NEATFLUXHOTCHANNEL' FACTOR-F%

LIMITING CONDITION FOR OPERATION R

i 3.2.2 F k(z) shall be limited by the following relationshi s:

arP F9 (z) f ( (K(a)) for P > 0.5

-l

• Fg (z (K(2)] for P 1 0.5 -

m p ,MA TH M . POWER amd, ED iMERPIRL PUutR I W K(z) ItM ' M ^ 9( _. _ :.: ; for a '

givencoreheightaseennemafu n ch.-colt. i L APPLICABILITY: N00E 1. .

! gJTig.

With Fg (Z) exceeding its liett:

I a.

Naduce THEWEL POWER at least 15 for each g 15 F (z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip 5etpoints within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; POWER OPERATION any proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION any proceed provided the Overpower delta T Trip -

Setpoints have been reduced at least 15 for each 1X F (t) .

exceeds the limit. O b.

Identify and correct the cause of the out of limit condition prior to increas yi THEN EL POWER above the reduced limit required by a, l above; THEmuu,. POWR esy then be increased provided F (x) is demon-strated through incere aspping to be within its limitg

[_ - - - -

=

[A F."= tAs, % 1146 t Raven weemat %EA (RTP)

• p*T-d s i cofE OPEA AT 4 Limits >

REPoQ.Y (COLQ) }

SumER - UNIT 1 3/4 2-4 .

Amendment No. 86 e

~

4 j .

s e' - POWER O!$7AllWT!0N l!N!T$-

. . I SURVEILt.AkCE REQUIRDIENTS 4.2.2.1 z The provisions of Specification 4.0.4 are not applicable. I 4.2.2.2 is within its ' For Itait by- RAOC operation, 0 F (a) shall be evaluated to 0

4. 1 map at any THERMAL POWEA greater than b.

Increasing the esasured g F (3) component of the power distribu ese tr/ 5 to account for manufacturing toleranc Verify the requirements of Specification 3.2.2 are satisfied. . I j

c. . Satisfying the followi relationship F0 (a) ~<# Ma * * (II K (a) for P > 0.5 - - VJJ k Myj:J $(s)

[" E I*I ' as a. 6 4 'r ceu, IQ(a) < "v (3) a c.3 for P < 0.5 er t

whereg E(a) is the esasured g Fased (a)byi the allowances Et fe,K l

1. (r)' for Fannufacturing) the limit is '; rtolerances and Cse__.uncertainty

-((p is .

~-

g g(g)g .POWEk,E(t - and W(3, 3 P is the relat we distris the cycle cependent function that ace ha*4aa trans'ents r 4d* iUnliium,er %mcau.n .. d '

d.

Measuring eMR &

ge, (I) escording'to the following schedule:

,angggg7J

1. -

Upon achievins aguilibrius conditions after exceeding by 105 or more of RATB THENIAL POWER, the TitENIAL POWER at which e Pg (a) was last determined.

• er o- 2.

At occurs least ffrst. once per 31 Effective Full Power Days, whichever "During power escalation at the beginning of each cycle, po increased power distribution until sap a power obtained. level for extended operation has been achieved a l

$1MIER - UNIT 1 3/4 2-5 Amendment No '

4-e w* * , , , - t#'Vf*- -

• e-M--*+--t-N'*v W a + -w *s + w v v' *tave--,-e**m--*=-==-*'=ww'-e------'=='+'wr

• [' 4,

.[,

.A: ,

POWER 0!$TRituTION LIMITS l .-

L.

$URVEILLANCE REQUIREMENTS (Continued)

[ ,

2 e.

With the maximum value of

((a) 1 K(1) of g(2) either of the following actions shall be taken:-ovl t i;

-(1) (z) shall be increased by 25 over that specified in Specification 4.2.2.2c. or (2) Ff(z) shall be measured at least once per 7 Effective Full Powe Days until two successive maps indicate that the maximum value of  !

((t)

K(s) -

over the core height (a) is not increasing. i h . f.

i With beingthe relattenships specified in Specification 4.2.2.2c..above not satisfied: ,

(1) Calculate the sentem percent ever the care height (t) that Fq (s) esteeds its limit by the fo11 ming empression:

(8) " N 8) - 1 t

a 100 for P 1 0.5 a1(a) l ave E4 ' '

- @ s) W )q. 3 , gag ,,, , , ,, ,

""(8)J

__ _ __.~ -- -

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

• l s ,

eg.<

,,  : p0WER 01_$D18, W tJN!JJ SURVE!LLANCE 3!

3 NT$ (Continued)

(2) One of the fo11owing actions shall be taken:

(a) Within 15 minutes, centrol the MO to within new M0 limits  ;

which are detemined by reducing the applicable M0 lleits by 15 M0 for each percent F q (a) exceeds its limits as

. detemined in Specification 4.2.2.tf.1). Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> . >

reset the MD alam setpoints to these modified limits, er (b)' Comply with the requirements of Specification 3.2.2 for Fg (s) exceeding its limit by the percent calculated above, er (c) Verify that the requirements of Specification 4.2.2.3 for Base Lead operation are satisfied and entar Base Lead  !

operation. i

g. The Ifeits specified in Specifications 4.2.2.tc. 4.2.2.te.,'and 4.2.2.tf.abovearenotappitcableinthefellowInBcoreplane regions:- ~

1. Lower com region free 0 to 155 inclusive. '

2. Upper core reglen free 85 to 1065, inclusive.

4.2.2.3. Base Lead operetten is' permitted at powers above APL E ff the fe11 swing conditions are satisfied:

a.

o Prior to entering Base Lead operation, enintain THERMAL POWER above APL L E ~and less than er equel to that allowed by Specificatten

.for at least the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Maintain Base Load operetten-surveillance flum differenc(APD within applicable t band about the target e) during this time peri Base Lead operation is then itted providi and er between POWER is enintained between APLE +

and F and 108 (whichever is meet liettine e L Apt"gis surveillance deft is asistained pursuant to Specification as the sintaa value of:

Fe" apth. 10as q s) x W )g I

everthecoreheight(a)where: ((s)istheseasuredF(s) q increased by the allemences for sanu esasurement uncertainty. TheqF limit 1 tolerances and P

-' : _~ _-- J M"_- _ ^ ^ O Ws)g s the cycle i dependent function that accounts

)g(g) t i e W(a)g aAs. , per Specmcauen s.v.1.

• guest o e unurs SLMER - UNIT 1 1/4 2 la Amendment No

-j .ggg -'w4-rm--e we y-w m ym g --g-+ w9w-- r- w-e -yg g -w wsy-p,ig-g-,,eg,-eaw,y --g- me *-w-is-- +-w ,,e----or -sw

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

. , L .. 1 t

3; MOL5TRIBUT!0N ~ LIMIT $-  !

1

$URyt!LLANCE REQUIREMENT $ (Continued) .

i

b.  ; f i

During Base Lead operation, if the THERMAL P APLE then the conditions of 4.2.2.3.a s ed beforeshall jb l- re-entering 8ase Load operation. -

4,2.2 Fg (x).4 Duri its is withi Base limit Load by: Operation g F (t) shall be evaluated  ;

. 4. etermine if Using the novable intore detectors to obtain a map at afty THERMAL POWER above APLE. power ~ distribution-6.

,~ Increasing the asasured q F (a) component of th esp by.35 to stribution-increasing theaccount value byfor$5annufacturing to account fortolerances n further measu a

c. Verify the requirements of Specification 3 2 2 arreme

$atisfyin0 the fo11 swine relationship:-e satisfied -

E

$(s) shtl for Pi APL"' [_ '

where:

- (1) is tN asasured q F The (s).'qF limit is  ;

ERTP is the P is the relative THElpi4L POWER.

m ;K(dM dist g(g) g- '

M cat <en 1ents n the function that accounts fee limited ration.

d. Measuring we, a,eme per gamay determinatt(enaccordingtothefollow

~

M8M "I

1. e:-

Prior to entering 8ASE LDAS eparation after sat tien 4.2.2.3 unless a fe11 core flun y ngmapSec-- has bee previous 31AptEITO witgths relative thermal a en in the- power esintained above ge

2. for the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prise to anpping, and en At least once per 31 Effective Fv11 power Days

e. .

With the maniaus value of

. d(a)

. R(a) -

of over the core height (t) increasing since the previou (t) either of the fe11 swing actions shall  :

be taken rmination SUPMER - UNIT 1 3/4 2-84 Amendment No.

o e

b a iww-m- w- , *--m--re e w sm,- sm----,o,.,--_,na,.-- . - - +

Y i; ?' ' -

M 015 fats'JT10w LintTs g

L a'-

SURVEILLANCE REQUIREMENTS (Continued) i i

1.

l_ (1) shall be increased by 2 percent over that specified in

'y.2.2.4.c, or 2.[- /g(x)s ' hall be measured at least once per 7 Effectiv Power of Oeys until 2 sun.csssive seps indicate that the maximum yalus  !

((z) i K(z)

I s

over the core height (1) is not increasing. '

f.

1 With the relationship specified in 4.2.2.4.c above not being satisfied, either of the following actions shall be taken: .,

1.

L Place core in an equilibria condition where the Itait in 4.2.2.2.c is satisfied, and renessure ((z). or

2. Coo F (p1y with the requirements of Specification 3.  ;

j ever the core height (z) with the fellowing expression:

y P

,a 100 for P 1 APLE

==

• 1 g.

, The limits specified in 4.2.2.4.c. 4.2.2.4.e are not applicable in the following core plan. e and 4.2.2.4,f above regions:

1.

Laser core region 0 to 15 percent, inclusive.

2.

W core region 95 to 100 percent, inclusive.

4.2.2.5 : When q F (s) is measured for reasons other then meeting the requirem

[.

of Specification 4.2.2.2 an everall asesuredqF (s) shall be obtained free a .

power distributten ese and increased by 5 to accout for annufacturing i tolerances and further increased by W to account for esasurement uncertain e *

\

g - --~ - ~ ~~ ' ~ ~ ~ ~ ~ ~ ' ' ~ ' ~

DELETE F%2E h TECH sPEcp l  ;, ,

R& LOCATE . k'(g) y, gay, 1.2 - \ \ \ -~i g 1..

Nl i \

, L Al i K ix m

... '\ 'N I ixl iN

.. \ X \

,, \ \ \

\ \- '

u

,, \-l \ \ \

L

,, N N X '

3

'"?f""" M \ \ '

2X 1

:h . N N O

,L \ ,

\ \ ,

0 1 2 3 4 5 7 8 9 10 11 12 TTOM COM HSGNT.Pt. TOP

t. Op E3.21 NQRMAUZIO Pg(a) . AFUNCTION OFCOA IIGHT Q

• L M

l\

sun - w 1 3/4 2-7 mns %

l

.<<v - 6 >-y,v - - ., r.. , .--,r.,--,.-4--- , . . - - . - ,,-.,.--#.r,-.., ---..------or. - . - + . . . - -

W W 002G OPGLAftAnr Limits RGPolT(coa as w u.ca w ea ru,,,, g) .y  !

POWER DISTRIBUTION LIMITS 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE NO _-

(IMITING CONDITION FOR OPERATION \

3.2.3 The combination of indicated Reactor Coolant Systee (RCS total flow rate and R shall be maintained within the region of allowable op g

Where:

h F[

• p ,

% ha I RAltD THtRMAL PUWER c.

L FhaMeasuredvaluesofFhobtainedbyusingthemovableinco oetectors to obtain a power distribution map.

_ _ The measured

~~'] values of Fh shall be used to calculate R since(Ai l-

/ _ includes measurement uncertainties of 2.1% for flow a incoremeasurementofFh,and APPLICABILITY: M00E-1.

t;At Ad5 Te:tallled 84Is Y848"*'

ACTION:

With the combination of RC5 total fl

.able operation 6ow rate and Rroutsjde the region of accept-a.

Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either: Mt' Id k i cot.& l 1.

Restore the acove limits, the or combination of RCS total flow rate and R to 2.

Reduce THERMAL POWER to less than 50% of RATED and less reduce than or ethe Power Ran_ge Neutron Flux - High trip setpoint to next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. qual to 553 of RATED THERMAL POWER within the '

l b.

Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of initially being outside the above limits , verify the combination of R and RCS total flow rate are the above limits, or reduce THERMAL POWER to less than 5% of RATE c.

THERMAL POWER within the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

to increasing THERMAL POWER above the redu recuired by ACTION items 4.2. and/or b. above; subsequent POWER n

OPERATION indicat ed RCS t may proceed provided that the combination of R and otal flow rate are demonstrated, through incere flux ofacceptableoperationqeenmapping and RCS total flow rate co following THERMAL POWER ~

eve" :: prior to exceeding the l

SUMER - UNIT 1 3/4 2-8 Amendment No. # , $$,

r m e-w e Y, w-gy.*1 -g 't m- w y--p-v- e- e s'~ eN m'- -mi --'___ a *- - - - - - - - - - -

r: r ._ ;

F t.. .*c

!5 ...9

, .y , .. .

j. e n  ; cssse a:.(Ase to Pact 3/4 3-s)

-r; ' 4 RT9 .

'd. Pg l-* The F limit at RA m m pg,g, ,,,,ggg,4 g, the COLA

~' ~

- e.- P4g. - the me.ec ye.g., i3ti 1188P specified Lie the CDsR.

+  %

4 1

. l 1

s

.i

.. 4

,- I ls 3 c  !

l l-v

f 1;ilQ'lL j

POWER 0!$7RIBUTION LIMITS LINITING CONDITION FOR OPERATION- __

A[Tjg. i x (Continued)

I-1.

.A nominal 50E of RATED THERMAL POWER, 2.

A nominal 7s of RATED THERMAL POWER, and 3.

RATED THERMAL POWERWithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining g

$Utv51LLANCE REQUIREMENTS

! 4.2.3.1 The provisions of Specification 4.0.4 are not appIfcable .

(-

' determined to be within the region of acceptable o "3:

'l

~

a; .

\ Prior toand loading, operation above 755 of RATED THERMAL. POWER aft '

=~ ~

{ b.-

f $ h* TY^ .

At least once per 31 Effective Full Power Days. r 4.2.3.3 The indicated RCS total fl region of acceptable operationc ow rate sham verified to be within the- -

i the most assumed recently to exist. obtafaed value of a entainee per . . . Specification 4

[

-4.2.3.4 CALIBRATION at least once per 18 months.The RCS total flow ra 4.2.3.5 once per 18The months. RCS total flow rate shall be determined by esasurement a

/

\

l -)

e ,

', l l

l l \

l I i

s a c - uNrT 1 m 2.,

I AmenentNo.n.@

--y '.- y w- w -m- r=-p. ., , w*e-,6- -w=, ,,e -----.4- - - , - -e*-. w..-., -, . - -- -

, wtstie; rmuxt f20m TECH SPEcp 4

W Tb col 2, l

MEAluntMENT UNC8RTAI El 0F 2.1% POR P Ano 4.os sonincome u unau Nrorpas Low Ana t-i' 34 - INCLUDED TMisReunt i O

d I' _

' "l OPRefl0m Opm\

34 - ces I i

n A

I n ,, i ~

E ,

3 4

'2 '" l l (1.80,E981 %

_, (t.se,E m 28 l (1.80, E3M

,(l.se,as.m ' -

m -(1.80.N.79)

(t.se,p. set /

.a a J -

L l -

.s .a

/ / ,

i.m i.i a

. set 4 . eJti a pp

1. 8tt: tauneouseastierJu denetteato menemmassemarasentenes suessWumetseusertATP)for 1 FIGURE 3.2-2 TOTAL FLOW RATE V5. R 00P OPERATION j

J sumER - UNIT 1 3/4 2-10 Amendment No. M , 30 1'

l 1

h l'm &,

'.. s F

9 L,y&

E.nI REACTIVITY CONTROL SYSTEMS BASES 1

MODERATOR TEMPERATURE COEFFICIE -

(Continued) involved subtracting the incre condition of all rods inserted ntal change in the MC associated with a core condition and. a conversion f most positive M C) to an all rods withdrawn -

temperature at RATED THERMAL the rate of change of moderator density with transformed into the lietting CR ccaditions.'

v,alue ~ ^_ ^^ This value of the @C was t value f --[The'MTC tions or urn a s represents a conservative value e cron) at a core condition of 300 ppe(with correc-equilibrium

boron Eo,L NTC valuef"concentration

: ' - and is obtained by making these correc t Pt-The surveillance reevirements for seasurement of the NTC a and near the end of the fuel cycle are adequate to confire that the N within its-limits since this coefficient changes slowly due principally reduction in RC5' boron concentration associated with fuel burnup.

-3/4.1.1.4 MINIMLM TEMPERATURE FOR CRITICALITY '

This specification ensures that the reactor will not be made critica with the Reactor Coolant System average temperature lessThis than 551*F.

limitation within is required its analyzed temperature to ensure range 1) the moderator temperature coeffi

2) the protective instr aentation is l within its nomal operating range 3),the pressuriter is capable of b an OPERABLE above its einis m RTg status with a staae bubble, and 4) the reactor pressu g emperature.

t 3/4.1.2 BORATION SY$TEMS _

• available during each mode of facility operation.The boron i perform this function include.1) borated water sourcesThe components required to

2) charging pumps

3) separate supply free OPERABLE flow paths, 4) boric acid transfer pumps, a,nd 5) an em diesel generators.

With tho' RCS average temperature above 200*F, a sintom of two boro jaction flow paths are required to ensure single functional capabtlity in event an assumed failure renders om of tu flow paths inoperable.

capability of either flow path is sufficient to provide the reevired The boration SHUTDOW l'

l l

St#9tER - UNIT 1 8 3/4 1-2 Amendment No. f),75 g

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

7 L  :..

I' -

3/4.2 POWER DISTRIBUTION LIMITS

• ' BASES The specifications of this section provide assurance of fuel inte during by:Condition I (Normal Operation) and II (Incidents of Mod t

events desi (1) enintaining the calculated DNBA in the core et or above the

' (2) gn limit during normal operation and in short tare transients, and sechanical properties te within assum,ed design critaria. lim u ~

In addition lietting g i the initial condittens assmed for the LOCA analyse acceptance criteria limit of 2200*F is not exceeded.

a l

9$ l these specifications are as fellows:The definitions of certain het chann L bi 4.v FS (z)

• Heat Flux Net Channel Factor, is defined as the maximum loca) r A(' heat flux en the surface of a fuel red at core elevation I divided tolerances en fuel pe11sts and reds;by the average fuel r F"

g q Nuclear Enthalpy Rise Het Channel Factor is defined as the ratie of

@w,  ; the integral of itnear power along the re,d with the highest integrated power to the average red power.

j 3/4.2.1 -AXIAL FLUX O!FFER N !

The .j sits on AXIAL FLUX 0!FFERDICE (APD) assure that the F (a) upper bou envelope e q  ;

during eithe tiens the normalized amiel peaking factor is not exceeded power changes.neraal operation er in the event of xenon redistribution fellowing GoL,ft t488004per Technical Spectfication 4.9.1.11."he limits en AFD will b '

i i

Target flux difference is determined at equilibrim menen conditions. The l full-length rods any be posittened within the core in accordance with their respective insertien limits and should he inserted near their neraal position for staety state operettee at high power levels. The value of the target flux difference obtained under these conditions divided by the fraction of RATED THENt4L PERER is the target flut difference at RATED THEWinL P0 DER for the associated core burne conditions.

POWER tevels are obtained by cultipi iTarget f1m differences for other THERNAL the appropriata fractional HEN 14L the GATED THEN14L POWER value by level. The periodic e dating of the target flum difference value is necessary to reflect care burng considerations.

4 SuleqER - UNIT 1 8 3/4 2-1 Amendeont No. 88 I

l i

^ ^ ~ ~ ~ ^ " ^ ~ ~

• *} }~

.~

n,

POWER DISTR!guTION LIMIT' '

, x 8ASES AXIAL' FLUX OIFFERENCE (Continued)-

At power levels below APLO g

o' consistent and limits. with the limits on AFD are defined in the the Relaxed Axial Offset Control (RA0C) operating proce l These limits were calculated in a osaner such that expected operational transients, o.a.

AFD deviating outside of tfes.-load follow operations, would not result in the occurs e limits.

the short period of time However.

allowed outsideInofthe theevent 11eitssuch a deviation at reesced power Ievels will not result in significant xenon redistribution such that the ~

envelope of peaking factors would change sufficiently to prevent operation in the vicinity of the ApLE power level, g,gg At power levels rester than APL . two modes ration are pemissible:

(1) RAOC. the AFO lieft of which are definedand

-operation, which.is defined as the saintenance of in (2) theBase Load g

+ within PFLA specifica-tions band about a target'value. The RA0C operating precedure above _APL ND g, the sase'as that defined for operation below O However it is possible L

when following extended load following seneuv$PL .

ersthattheAF6limitsmayresult i in restrictions in the maxima allowed power or AFD in order to guarantee

[

' operation with qF (a) less than its lietting value. To allow operation at the anziam permissible power level the Base Lead operating precedure iets.the indicated AFD to relatively small target band (as specified in the and powerswings(APLE < power < APLIL or 103 Rated Theres1 Power, whichever is 0

lower).the within Fortarget Baseband.

Load operation. It is expected that the plant will operate L Operation outside of the target band for the short time period allowed will not result in significant menen redistribution such L that the envelope of peaking. factors would change sufficiently to prohibit continued operation in the power region defined above. To assure there is no

- residual menen redistribution impact free past operation on the Base Load operation, a 24-hour w O and allowed by RAOC is necessasy. aiting period at a power level above APL During this time period Ioed changes and red motion are restricted to that allseed by the Base Lead precedure. After the wetting period extended Base Lead operation is permissible.

The computer determines the one sinuta average of each of the OPERABLE excere detector evtputs and provides an alare message immediatel for at least 1 of 4 er 2 of 3 OPERABLE encore channels are:

allowed delta-I power operating space (for RAOC operat outside the (2) outside the allowed delta-I target band (for lase Lead operation). These alares are active when power is greater than: (1) SS of RATED TMWL POWR (for RA0C operation), or (2) APLE (for Base Load operation). Peneity deviation sinutes for Base Lead operation are not accueulated based on the shert period of time during which operation outsi e of the target band is allowed. ,

SWglER - UNIT 1 8 3/4 2-2 Asenesent No l.

I a

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

Q. ,

' 4 1 3 .

g POWER 0!$TRIBUTION LIMIT b '

p SASES kl

%)

3/4.2.2 and 3/4.2.3

^

p [t/ CLEAR tNTHALPY RISE HUT CM'?%L FAG TORHE -

./ #

)9{, The limits on heat flux hot channel factor 9 enthalpy local power rise hot channel density and einimum factor ensure DNBR arethat not exceeded1),theeak designand 2l 3

LOCAlimit.

criteria the peak fuel clad temperature will not n theexceed event of a the 220 acceptance R

l$ '

as specified in Specifications 4.2.2 and 4.2.3.Each of the sufficient to insure that the limits are maintained provided:This period i

.[ a.

> %g t

iI Control rods in a single group move together with no indiv o

gG insertion group demanddiffering position, by more than 113 steps,, indicated from the rod

( $

b.

l L

g Control in Specificationrod3.1.3.6.

groups are sequenced with overlapping gro l

W *g c.

r ed q 4

3.1.3.6 are maintained.The control' rod ...

insertion limits *g of S*

d.

O!FFERENCE, is maintained within the limits,The

( p,wa4,, \Q -

will be maintained within its limits provided conditions

d. above are maintained. . "hrough a

As noted on g be " traded off" RCS flow rate ends g acceptable i inst one nother (i.e. , a low asasured RCS flow rate may )

l s -

g I 3 will not be below the design DN8R value.isalsolow)toensuret 1g Tho' relaxation of Fh as a function f -

of THERMAL p0WER rod insertion lietts.

N allows changes in the radi s e R, as calculated less than or equal to

.2.3andusedin@tguasutuesA)accountsforFh

([ '

This value is usec in sne various accident analyses where Fh influencois parameters . , peak other clad than DNSR, e temperature and thus is the maximum "as asasured" value all

[]g'g' k

design limit DN8R.- This margin isoffset owed.

more n e than sufficie i

penalty and' transition core penalty. any rod bow plant design flexibility. The remaining margin is available for q

When an F seasurement is taken, an allowance forerror both experimen y

(T and manufacturing tolerance must be made.

3% allowance is appropriate for manufacturing s and a toleran SUMMER - UNIT 1 .

8 3/4 2-3 Amendment No.

1. .

L 1

V._ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ ____ . _ . - -_ . _ . - ..- . , - .- -

w. ,

. POWER DISTRIBUTION LIMIT BASES HEAT HDT CHANNEL FLUXFACTOR HOT CHANNEL (Continuto) FACTOR and RCS FLOWRATE an The hot channel factor F (z) is measured periodically and increased by cycle and height dependent power factor appropriate j ..

channel factor, Fq (z) is met.

T v W(z) accounts for the effects of normal opera-tion transients and was determined from expected power control maneuvers o the full range of burnup conditions in the core.

W(z)gt accounts for the more

, restrictive operating limits allowed by Base load operation which result in less severe transient val,ues. The WO) and W(z) functions described above for normal operation are " ^ ^ ^ 1n the C _gg Specif1 cation 6.9.1.11. ' 1. _._.. i j per

_ When RCS flow rate an CoM o!GRR7tn uman REMT(wR) q are measured, no additional allowances are necessary prior to comparison With the limits oP'

]%4 o l i

_ __ ? : p Measurement errors in determining of 2.2% for theRCSlimits total' c hflow rate and 4% for Th have been a l

detect only flow degradation which could lethe 12-hour periodic surv acceptable region of operationdioiR)on ;ad to-2 operation outside _the_ l 9 3/4.2.4 OUADRANT POWER TILT RATIO {g.]

l

(

A M. tion. satisfies the design values used in the power Radial capa during power operation, power distribution measurements are made during y The limit of 1.02, at which corrective action is required and linear heat generation rate protection with x y plane power,tilts. provides A-DN8 FIlmiting i tilt of 1.025 can be tolerated before the margin for uncertainty in q s depleted. The limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.

The two hour time allowance for operation with a tilt condition greater

-than 1.02 but less than 1.09 is provided to allow identification and correction of theatilt,dropped the margin or misaligned control for uncertainty on Frod. In the event such action does not corre q si reinstated by reducing the maximum allowed power by 3 percent for each percent of tilt in excess of 1.0.

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore the normalized symmetric power distribution is consisten POWER TILT RATIO.

flux map.or two sets of 4 sThe incore detector monitoring is done with a full incore E-11, H-3, H-13, L-5, ~L-11,ymmetric N-8. thimbles. These locations are C-8, E-5, SUPNER - UNIT 1 B 3/4 2-4 Amendment No. 4 ,

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

POWR DISTRIONTION LIMIT 8ASE5 i

- j MUT GWWwmL FAMUN (Gontingeg) HEAT FLUX HOT CH 3/4.2.5 DPG PARMETERS at asintained within the nomel steady state env the transient and accident analyses.

FSAR assumptions a sinimum DNB have been analytically demonstrated adequate t throughout each analyzed transient.

readout is sufficient to ensure that the parameters limits following load changes and other expected transient operation.

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g,E 1 g (- 187 -4 n M *STRIBUTION LIMff 3 A

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, H TF X T FA T A F AR NTHA py R

__ .ont n with the initial FSAR tions and have been adequate to maint ically demonstrated einimum DN8R of 1.30 througho analyzed transient.

The reado e periodic surveillance of these parameters thro rument i

t.dinetran.s.ns f.no toad chan es.p.r.si.n.e and other . sufficient to ensure that th >

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-3/4.4 REACTOR COOLANT SYSTEM ' '

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BASES s

3/4.4.1 REACTOR COOLANT LOOPSBud0 COOLANT CIRCULATION The plant is designed to herate with all reactor coolant loops in operation, and maintain DN8R _'- __ . "'during all normal operations and  ;

anticipated transients. In MODES I and 2 with one reactor coolant loop not-in. ,

7 operation within this specification requires that the plant be in at least H0T STAND 8Y 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

In M00E 3, a single reactor coolant loop provides sufficient heat removal capability for removing decay heat; however, single failure considerations 'c require that two loops be OPERA 8LE.

In M00E 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or RNA loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at

least two loops (either RNR or RCS) be OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of tha steam generators as a heat L removing component, require that at least two RNR loops be OPERABLE.

The operation of one Reactor Coolant Pump or one RNR pump provides adequate. >

u flow to ensure mixing, prevent stratification and produce gradual reactivity L changes during boron concentration reductions in the Reactor Coolant System.

The reactivity change rate associated with boron reduction will,- therefore, be L within the capability of operator recognition and control.

The restrictions on starting a Reactor Coolant Pump with one or more RCS cold legs less than or equal to 300*F.are provided to prevent RCS pressure transients, caused by energy additions free the secondary system, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of-Appendix G by either (1) restricting the water volume in the pressurizer and thereby providing a volume for the primary coolant to expand into, or (2) by restricting starting of the RCPs to when the secondary water temperature of ,

each steam generator is less than 50*F above each of the RCS cold leg temperatures. ,

1 Supt 4ER - UNIT 1 B 3/4.4-1 a

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' ADMINISTRATIVE CONTROLS l'

e. Type of container

f. Solidification agen(e.g., LSA Type A, Type 8, Large Quantity), and t (e.g. , cement, urea formaldenyde).

site toonunrestricted a quarterly basis . areas of radioactive materials in effluents

~The radioactive effluent release reports shall include any changes to the Process control Program (PCP) made during the reporting period. 1 MONTHLY OPERATING REPORT 6.9.1.10 ciuding documentation of all challenges to-the PORV's '

U.S. Nuclear Regulatory Commission, Washington, D.C.be su Regional Office of Inspection and Enforcement, no later than the 15th of each month following the calendar month covered by the report.

Any changes to the 0FFSITE D0SE CALCULATION MANUAL shall be submitted Monthly Operating Repert within 90 days in which the change (s) was made effe In addition, a report of any major changes to the radioactive waste treatment .

L systems shall be submitted with the Monthly Operating Re RADIAL PEAKING FACTD# LIMIT REPORT .

6.g.1.11 The limits, thew (2)Functi L for RA0C and 8a Load operation and the val or'APLE (as required) s 1-be established core and i esented prior to use. r each reload REhue The met ology used to generate W(z)functionsfo UTN! Oper on and the value for APLN shall be those p and Base Load ,

app ed by the NRC.a If che ously reviewed and MM w' be evaluated in acco s to these methods re deemed necessary y O view and approval prier ' tt.e air with 10 CFR 50.59 use if the c submitted to the for n unreviewed safety que on or if such is determined to volve l.

previously submitted d a che would require amen at of 1: ntation.-

A report containi AFD limits, the W functions fcr RA0C Base Load operation and t alue for APLE (as ired) shall be provi to the NRC decisment coat desk with copies to t regional administrat and the resident inspector wi n 30 days of their i ntation.

Any info ion needed to support MD from t 2).W(2)!g and APL 1 be by request RC and need not be in in thi report.

-10216 P-A "Relaxati

1. echnicalSpecificatio of Constant Axial Offse entrol-Fg urveillance S

SUP9tER - UNIT 1 6 18 Amendment No. 35. 4,(

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CORE OPERAT8NguMITS REPORT -!

i"- 6.9.1.11 Core coaratina limits shall be established and documented

. portion of a reload cycle, for the following: OPERATING UMiTS RE a.

Moderator Temperature Coefficient SOL and EOL limits and 300 ppm wrveillance limit for Specification 3/4.1.1.3, b.

Shutdown Bank Insertion Umit for Specification 3/4.1.3.5, '

c.  !

Control Bank Insertion Limits for Specification 3/4.1.3.6, d.

Axial Flus Difference Limits, target band, and APLNO for Specification 3/4.2.1, e.

Heat Flux Hot Channel Factor,OF RTP, K(Z),W(2), API,Noand W(2)el, for Specification 3/4.2.2, s

f.

!- Nuclear Enthalpy Rise Hot Channel Factor, FaHRTP, and Power Factor l Multiplier, PFAH, limits for Specification 3/4.2.3.

l-The analytical methods used to determine the core operating limits shall be those previouslydocuments:

following reviewed and approved by the NRC, specifically those described in the a.

WCAP 9272 P A,

• WESTINGHOUSE RELOAD SAFETY EVALUATION

9 METHODOLOGY", July 1985 (W Proprietary).

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient 3.1.3.5 - Shutdown Bank insertion Limit,3.1.3.6 - Control Bank Insertion Limit, 3.2.1 Axial Flus Difference,3.2.2 Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor),

b.

WCAP 10216 P A, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL FQ SURVEILLANCE TECHNICAL SPECIFICATION *, June 1983 (W Proprietary).

l L

(Methodology for Specifications 3.2.1 - Aziel Flux Difference (Relaxed Asial Offset Control) and 3.2.2 Heat Flum Hot Channel Factor (FQ Methodology for W(2) surveillance requirements).)

c.

WCAP 10266 P A, REV. 2. "THE 1981 VER510N OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE", March 1987 (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).

The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal mechanical limits, core thermal. hydraulic limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met.

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, l' l A ho-y; b The CORE OPERATING LIMITS REPORT, includ _

supplementRhall be providedrupon issuance for each reload cyc )

Document Mspector. Control Desk with c'6 pies to the Refional Adminis )

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