ML18102A253

Proposed Tech Specs 3.3.2.1 Re ESFs Interlock P-12

ML18102A253
Person / Time
Site:	Salem
Issue date:	07/12/1996
From:	Public Service Enterprise Group
To:
Shared Package
ML18102A252	List: ML18102A251 ML18102A253
References
LCR-S96-09, LCR-S96-9, LR-N96188, NUDOCS 9607220286
Download: ML18102A253 (6)

Text

e Document Control Desk LR-N96188 LCR S96-09 SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGE TO TECHNICAL SPECIFICATIONS ENGINEERED SAFETY FEATURES INTERLOCK P-12 TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License No. DPR-70 are affected by this change request:

Technical Specification Table 3.3-3 Bases 3/4.1.1.5 3/4 3-22a B 3/4 1-2 The following Technical Specifications for Facility Operating License No. DPR-75 are affected by this change request:

Technical Specification Table 3. 3-3 Bases 3 / 4

• 1

• i. 4 3/4 3-23a B 3/4 1-2 Page 1 of 5

(

9607220286-960712 _____

' -\\

I PDR ADOCK 05000272 p

PDR I

I

DES +GNAT!ON P-ll P-12 e

e ENGINEEp.EO SbFE7Y FtATUp.:;s IN7ER.;_-;xs CONDITION,a.NO st;poIN; With 2 of 3 pre**urizer pre**ure channel*

~ 1925 p*i9.

With 3 of 4 T channel*

iii! SU'F.

av;

'*j\\c.re.ctsi "'J ~cN--\\ s: "3 "'F

( 1.i"1'l~ Oi.I'\\ ci,\\\\ou~e. se:-.\\-ro11-J\\tlle

~sq.s~)

With 2 of 4 T channel*

-'II 54l91'.

av; cleuetLS ~

-Q-<-~ Sat3 °f l "' 1th ""'.,f

...i able se--l-r,;. t v{\\,lkt. ~ 511-l ~f)

FtJNC7ION P-ll prevent* or defeat*

manual block of *af ety injection actuation on low pr***urizer pre**ure.

P-12 prevent* or defeat*

manual block of *afety injection actuation hi9h

• team line flow and low

• team line pre**ure.

Allow* m.anual block of

• &fety injection actuation on hi9h *team line flow and low *team line pre**ure.

Cau*e* *team line i*olation on hi9h *team flow. Affect*

• t*am dump blocit..

SAL&X -

OlllT l 31' 3-22a Amimndment Ro. 138

e 3/4.l RF.ACIIVITY CONIROL SYSIEKS MSES 3/4.1,l.4 HQD£RATOR TEMPERATURE COEFFICIENT C!1ICl (Continued)

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

'nte 110st negative KTC 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.

'nlese corrections 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 TiiERMAL PO\\lE.R conditions, and (2) subtracting from this value the largest differences in MTC observed between EOL, all rods withdrawn, RATED TiiE.RMAL POWER conditions, and those most adverse conditions of moderator temperature 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 PO\\lE.R.

'nlese corrections transformed the MDC v~lue used in the FSAR analysis into the 11.lli~!ng MTC value of

-4.4 x 10 delta k/k/*F.

'nle MTC value of 0 3.7 x 10 delta k/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 ~X making these corrections to the limiting KTC value

-4.4 x 10 delta k/k/*r.

The surveillance requirements for measurement of the KTC at the beginnin&

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 associated with fuel burnup.

3/4.l.l.S MINIMUM TEMPERATURE FOR CRITICALITY

'nlis specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 54l~F. 'nlis limitation is required to ensure 1) the moderator temperature coefficient is within its analyzed temperature range, 2) t~e 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 1 B 3/4 1*2 Amendment No.

113

DESIGNATION P-11 P-12 TABLE 3.3-3 (Continued)~

ENGINEERED SAFETY FEATURES INTERLOCKS CONDITION AND SETPOINT With 2 of 3 pressurizer pressure channels ~ 1925 psig.

With 3 of 4 T channels

~ Ei 4 S ° F.

avg

\\nerev._5;"(} -C.~ 6f~ °F

(..s ;4-h ~Ii\\- c,.,hc,JA.b \\e ~e'tro:,;\\

f 6'f5' 0~)

With 2 of 4 T channels

-< 54l°F.

avg deel'eLtS~ J -Cr(JM _sit~ *r- *

( t.J; th °'"' o,l\\°'-"'~~~ \\e.s~r"t" 1-V1t \\v.e. 1. Stfl ~)

FUNCTION P-11 prevents or defeats manual block of safety injection actuation on low pressurizer pressure.

P-12 prevents or defeats manual block of safety injection actuation high steam line flow and low steam line pressure.

Allows manual block of

• afety injection actuation on high steam line flow and low steam line pressure.

Causes steam line isolation on high steam flow. Affects steam dump blocks.

SALEM - UNIT 2 3/4 3-23&

Amendment No.

116

3/4.l RF.ACTIVITY CQNIROL SYSID(S RAS ES 3/4.1.1.3 MODERATOR TEMPERA11.JRE COEFFICIENT CHIC> (Continued)

The HTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of HTC 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 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 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 temperature 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 PO'JER..

These corrections transformed the MDC v~!ue used in the FSAR analysis into the limi~!ng HTC value of

-4.4 x 10 delta k/k/*F.

The MTC value of -3.7 x 10 delta k/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 ~4 making these corrections to the limiting MTC value

-4.4 x 10 delta k/k/*F.

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

3/4I1.1. 4 MINIMUM TEMPERATIJR.E FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 541*r. 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 Amendment No.

94 l

I

' I 4

1.0PS~G Number of Pages (Including cover sheet)

TO:

• ~a;U ~i!J11J){m &N LOCATION:

/lJRC Licensing & Regulation Fax# (609) 339-1448 Phone/Fax# ________________ _

FROM:___:S~Tt~6~VL~~L-.t/fl~&~N~!U~~~iLI_* ______ _

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Phone: _________________ _

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Transmit Operator: ____________ ~';L-

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