Text

Proposed Tech Specs 3.1.1.3 & 4.1.1.3 & Associated Bases Re Moderator Temp Coefficient
	ML18094B319
Person / Time
Site:	Salem
Issue date:	02/22/1990
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18094B318	List: ML18094B317; ML18094B319; ML20011F749;
References
	NUDOCS 9003070379
	Download: ML18094B319 (9)
	v • d • e

REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:

a.

b.

Less positive than 0 delta k/k/°F for the all rods withdrawn, beginning of cycle life (BOL), hot zero THERMAL POWER condition.

-L/,'/~

4 Less negative than(~8 Jx 10-delta k/k/°F for the all rods withdrawn, end of cycle life (EOL}, RATED THERMAL POWER condition.

APPLICABILITY:

Specification 3. 1.1.4.a - MODES 1 and 2* only#

Specification 3. 1. 1.4.b - MODES l, 2 and 3 only#

ACTION:

a.

With the MTC more positive than th* limit of 3.1.1.4.a, above, operations in MODES 1 and 2 may proceed provided:

1.

Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than O delta k/k/°F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY 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 3. 1. 3.6.

2.

The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition.

3.

A Special Report is prepared and submitted to the Corrmission pursuant to Specification 6.9.2 within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.

b.

With the MTC more negative than the limit of 3. l. 1.4.b, above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With Keff greater than or equal to l~O See Special Test Exception 3. 10.3 SALEM - UNIT 1 3/4 1-5

.Amendment No. 16 900307037~ 900222 PDR ADOCK b§600272 p

PDC I I I

I I

I

REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS 4.1. l.4 The MTC shall be determined to be within its limits during each fuel cycle as follows~

a.. The MTC shall be measured and compared to the BOL limit of Specification 3. 1.1.4.a, above, prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.

b.

The MTC shall be measured at any THERMAL POWER and compared to

-2. x 10-delta k/k/°F (all rods withdrawn, RATED THERMAL POWER condition) within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm.

In the event thi~4 comparison indicates the HTC is more negative than -

x 10 delta k/k/°F, the HTC shall be remeasured, and compared to the EOL MTC limit of specification 3. 1. 1.4.b, at least once pe 14 EFPO during the remainder of the fuel cycle.

-3./

SALEM - UNIT 1 3/4 1-Sa Amendment No.

i6

e.

3/4.1 REACTIVITY CONTROL SYSiE~S BASES The MTC values of this specification are applicable to a specifi c set of plant conditions; accordingly, veri fication of MTC values at condi tions other than those ex? li cit 1y stated ~ i1 1

r:qu ~,. : e x tr!: ~'. a: i:~

to those conditions in order to pern:it an acc~rat: cc~~ariscn.

The rncst neg!tive MTC va1ue equiva~ent t: t he mcst posit ive density ;.c_ fficient (MOC), was obtained by incrementally cor,.:ct * ~ :::e MDC used in

~

SAR analyses to nominal operating conditi corrections involve *ubtrac:ing the incremental cha __

in tr.e ~G:

associated '"'ith a core c

t i an of all recs i

... ed (ri'.ost ::ics ::i *1e

~DC ) to an all rods withdrawn -- * ~ ~ t i cn ar~, a canv!rs i:n for : n!

~!':!

of change of mo~:rator density ~ i th ccndi:ions.

Th is val:!e of t :1=

... 1...,.,?s tne...... a:;sfo~ed irt:.: !':e

'. - ~: ; r:;

~*17C val:Je - 3.3 x 10

,

F.

7he "47C value o*.

.9 x :o*.. :..<! '< / =.=

I r ='"'r=S"'"'t-2 C"'"S='"'

11= *1a' " e (*_,;.... -o,.ra.-.. ; '"'r.-.:or

.,..,.,,.. *r."' *... * *... * *

-~ -

c;. I wi l w

. ~

I

l... W

~

.J-1 boron) at a c~n *:ition of 3CC ;:;::: ac;ui~::

... "':1 bor::r..:on... _. *:-a: ~ ~~

and is

1ned by making these correc:~ons co the limiting MTC x 10-.,. k/ krF.

The surveil lance requ ~ re~en:s for m easu r e~en: of t he ~ T C a: : ~ e

eg in ~~ ~ ; an~ near :~e ena of :~ e f ~ e l cycla are a~e~ ~ !:e : J ::~: i

-~

--!:)

' 1 ~ *- r--* ir.s *u... * 'n,.* _,~ - ~ -.. s:,..,.. =..,.,,.5 coe.:: ; ~

,* ~ r. -._-*_-__

_-_ ~:;---s I

I ;,... c...

-~ *.. :... ~

1 !' --

- 1

1. * -

}

1

....,.3

-ir;~c

-t -~ ":~j

.411fi

r.*:i raf"! 11c-.;""'n ;,.,

= r ~

~"""r"' r.,..,..,..,.. ::ll"'l_,..,_.. Ail,..

~--~------*'.

a.-. ~-

J..,,.

1 I tr..

+.., I J

I

.._..., 1, __ :1 *... -* ' ""' ' '

'"' ; ~;., :,,.:i ;.," r"'" "'

I t

~-

~~,,.,.:J

3/ 4.1.1.5 MINI~U:-1 T!?~?:'.~A7 '.J R£ !='CR CRI"7":C..l.LI '7"Y This specification ensures that the reactor will not be made criti ca1 with the Reactor Coolant System average temperature less than 541°F.

This limitation is required to ensure 1) the moderator temperature Coer-~,*ci* e,.~ i*s w1't1o1*n i*rs 2.. 2 1J":i"

~""'"'"'er 2.. " r.:1 r.:"":i 2)

i, a

..... ~-.:i.-.. ; *1.:i

~

--~.. c;;;; * ** ~

.I

~

instrumentation is within its normal operating ran;e, 3; t r.c ?- ~ Z interlock is above its setpoint, 4) the pressurizer is capao1e of ~e in ; in an OPERABLE status with a steam bubble, and 5) the reactor pressure vessel is above its minimum RTNDT tem9erature.

SALEM - UNIT 1 B 3/4 1-2

.Amendment Na. 16 i.

I

INSERT A The most negative MTC value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analysis to nominal operating conditions.

These corrections involved: (1) a conversion of the MDC used in the FSAR analysis to its equivalent MTC, based on the ra~e of change of moderator density with temperature at RATED THERMAL POWER conditions, and (2) subtracting from this value the largest differences in MTC observed between EOL, all rods withdrawn, RATED THERMAL POWER conditions, and those most adverse conditions of moderator

~emperature and pressure, rod insertion, axial power skewing, and xenon concentration that can occur in normal operation and lead to a significantly more negative EOL MTC at RATED THERMAL POWER.

These corrections transformed the MDC value used in the FSAR analysis into the limiting MTC value of -4.4 x 10- 4 6k/k/cF.

The MTC value of -3.7 x 10- 4 Ak/k/°F 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 making these corrections to the limiting MTC value

-4.4 x 10-4

~k/k/°F.

- e-REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:

a.

Less positive than 0 delta k/k/°F for the all rods withdrawn, beginning of cycle life (BOL), hot zero THERMAL POWER condition.

- '-/Av

b.

Less negative than 4.0 x 10-4 delta k/k/°F for the all rods withdrawn, end of eye e life (EOL), RATED THERMAL POWER condition.

APPLICABILITY:

Specification 3.1.1.3.a - MODES land 2~ only#

Specification 3.1.1.3.b - MODES 1, 2 and 3 only#

ACTION:

a.

With the HTC mare positive than the limit of 3.1.1.3.a, above, operat_ions in MODES 1 and 2 may proceed provided:

1.

Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than O delta k/k/°F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY 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 3.1.3.6.*

2.

The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the HTC has been restored to within its limit for the all rods withdrawn condition.

3.

In 1 ieu of any other report required by Specification 6*. 9.1, a Special Report is prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days, describing the value of the measured HTC, the interim control rod withdrawal limits and the predicted average core burnup necessary for restoring the positive HTC to within its limit for the all rods withdrawn condition.

b.

With the MTC more negative than the limit of 3.1.1.3.b, above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With Keff greater than or equal to 1.0

See Special Test Exception 3.10.3 SALEM - UNIT 2 3/4 1-4

REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT SURVEILLANCE REQUIREMENTS 4.1.1.3 The MTC shall be determined to be within its limits during each fuel cycle as follows:

a.

The MTC shall be measured and compared to -the BOL limit of Specifi-cation 3.1.1.3.a, above, prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.

b.

The MTC shall be measured at any THERMAL POWER and compared to

-3.7 7> -3.

x 10-4 delta k/k/°F (all rods withdrawn, RATED THERMAL POWER condition) within 7 EFPD after reaching an equilibrium boron concen-tration of 300 ppm.

In the event this comparison indicates the MTC

-3.7 is more negative than 3.

x 10-4 delta k/k/°F, the MTC shall be remeasured, and compared to the EOL MTC limit of specification 3.1.1.3.b, at least once per 14 EFPO during the remainder of the fuel cycle.

SALEM - UNIT 2 3/4 1-5

REACTIVITY CONTROL SYSTEMS BASES 3/4. 1. 1.3 MODERATOR TEMPERATURE COEFFICIENT (MTC) (Continued)

The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.

The most negative MTC value equivalent to the most positive moderator density ficient (MDC), was obtained by incrementally correcting C

used in the F alyses to nominal operating conditions.

T corrections involved subtracting

ncremental change in the MDC c1ated with a core __,

t condition of all rods inser ost positive MD an all rods withdrawn

_l/\\JS6(2.T condition and, a conversion for the o

ange of moderator density with temperature at RATED THERM~LP~~~nd 1 in This value of the MOC was then transformed into the limit~ -~~!ue -4.0 x l k/°F.

The MTC value of

-3. 1 x 10-4 Ak/k/°F re esents a conservative value (wi rections for burn up and sol u J.e-15oron) at a core condition of 300 ppm equi 11 boron concentr and is obtained by making these corrections to the limi v

-4.0 x 10-4 k/k/°F.

The surveillance requirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains with its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associateg with fuel burnup.

3/4. l. 1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 541°F.

This limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) the protective instrumentation is within its normal operating range, 3) the P-12 interlock is above its setpoint,

4) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and 5) the reactor pressure vessel is above its minimum RTNDT temperature.

SALEM - UNIT 2 B 3/4 1-2

j

'71' INSERT A The most negative MTC value equivalent to the most positive moderator density coefficient (MDC), was obtained by incrementally correcting the MDC used in the FSAR analysis to nominal operating conditions.

These corractions involved: (1) a conversion of the MDC used in the FSAR analysis to its equivalent MTC, based on the rate of change of moderator density with temperature at RATED THERMAL POWER conditions, and (2) subtracting from this value the largest differences in MTC observed between EOL, all rods withdrawn, RATED THERMAL POWER conditions, and those most adverse conditions of moderator

~emperature and pressure, rod insertion, axial power skewing, and xenon concentration that can occur in normal operation and lead to a significantly more negative EOL MTC at RATED THERMAL POWER.

These corrections transformed the MDC value used in the FSAR analysis into the limiting MTC value of -4.4 x 10- 4 6k/k/°F.

The MTC value of -3.7 x 10- 4 Ak/k/°F 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 making these corrections to the limiting MTC value

-4.4 x 10- 4

~k/k/°F.

EC>L MC>DER..A.TC>R.

CC>EFFIC IENT BASIS.A.ND TEMPERATURE TECH SPEC LIMITS CURRENT STANDARD TECH SPEC DELTA MTC ARO, EOL, 0 PPM to ARO.r.. Near EOL,

,jOO PPM SR LIMIT LCO LIMIT NEW TECH SPEC BASIS DELTA MTC ARI, EOL to ARO, EOL SAFETY LIMIT MARGIN INCREASE DELTA HTC ARO, EOL, 0 PPM to ARO, Near EOL, 300 PPM DELTA MTC Most Negative to ARO, EOL LCO LIMIT SAFETY LIMIT

+

I

+---+---+---+---+---+---+---+---+---+---+---+---+---+---+---+ 26 30 34 38 42 46 50 -52 EOL MODERATOR TEMPERATURE COEFFICIENT (PCM/DEG F)

+

Unit 1 Cycle 9 Predicted SR Unit 1 Cycle 9 Predicted LCO l

'

ML18094B319

Text

Navigation menu

Search