ML20101E646

Proposed Tech Specs,Consisting of Change Request 95-03, Enhancing LCO & SRs & Revises Bases for QPTR

ML20101E646
Person / Time
Site:	Summer
Issue date:	03/19/1996
From:	SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20101E636	List: ML20101E646 RC-96-0076, Application for Amend to License NPF-12,consisting of Change Request 95-03,enhancing LCO & SRs & Revises Bases for QPTR
References
NUDOCS 9603250153
Download: ML20101E646 (33)

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OEFINITIONS SECTION PAGE 1.0 DEFINITIONS .

1.1 ACTION ........................',......................... 1-1 1.2 ACTUATION LOGIC TEST .................................... 1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST ....../.................. 1-1 1.4 AXIAL FLUX DIFFERENCE .........r......................... 1-1

1. 5 CHANNEL CALIBRATION ..................................... 1-1 1.6 CHANNEL CHECK ....................... ................... 1-1

1. 7 CONTAINMENT INTEGRITY ......................... 1-2 1.8 CONTROLLED LEAKAGE ...................................... 1-2

1. 9 CORE ALTERATION ........................................ ......... 1-2 1.9a CORE OPERATING LIMITS REPORT ............................ 1-2 1.10 DOSE EQUIVALENT I-131 ................................... 1-2 1.11 E-AVERAGE DISINTEGRATION ENERGY ......................... 1-3 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME ................ 1-3 1.13 FREQUENCY NOTATION ...................................... 1-3 1.14 GASEOUS RADWASTE TREATMENT SYSTEM ...................... 1-3 1.15 IDENTIFIED LEAKAGE ...................................... . 1-3 1.16 MASTER RELAY TEST ....................................... 1-3 1.17 0FFSITE DOSE CALCULATION MANUAL (0DCM) . . . . . . . . . . . . . . . . . . 1-4 1.18 0PERABLE - OPERABILITY .................................. 1-4 1.19 OPERATIONAL MODE - MODE ................................. 1-4

' 1.20 PHYSICS TESTS ........................................... 1-4 1.21 PRESSURE BOUNDARY LEAKAGE ............................... 1-4 1.22 PROCESS r TROLPROGRAM(PCP)........................... 1-4 1.23 PURGE-PU: iG ............. ... .................... 1-4 1.24 QUADRANT JER TILT RATIO 9.P.T8)..................... . 1-5 l 1.25 RATED THERMAL POWER ..................................... 1-5 1.26 REACTOR TRIP SYSTEM RESPONSE TIME ....................... 1-5 1.27 REPORTABLE EVENT ........................................ 1-5 1.28 SHUTDOWN MARGIN ......................................... 1-5 1.29 SLAVE RELAY TEST ........................................ 1-5 1.30 DELETE...................................................

1.31 SOURCE CHECK ............................................ 1-5 i 1.32 STAGGERED TEST BASIS .................................... 1-6 1.33 THERMAL POWER ........................................... 1-6 1.34 TRIP ACTUATING DEVICE OPERATIONAL TEST .................. 1-6 1.35 UNIDENTIFIED LEAKAGE .................................... 1-6 1.36 VENTILATION EXHAUST TREATMENT SYSTEM .................... 1-6 1.37 VENTING ................................................. 1-6 l TABLE 1.1 OPERATIONAL MODES .................................. 1-7 TABLE 1.2 FREQUENCY NOTATION ................................. 1-8 9603250153 960319 ~ )

PDR ADOCK 05000395 l P PDR l l

SUMMER - UNIT 1 I Amendment No. 35, 88, l 104 i i

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INDEX i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS I SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 4

3/4.2.1 AXIAL FLUX DIFFERENCE

................... 3/4 2-1

3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR

............... 3/4 2-4 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR  :

............. 3/4 2-8 '

3/4.2.4 QUADRANT POWER TILT RATIO (OfIR) . . . . . . . . . . . . 3/4 2-12 l

3/4.2.5 DNB PARAMETERS

....................... 3/4 2-15 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION ............ 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

..................... 3/4 3-15 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring

.................... 3/4 3-41 Movable Incore Detectors .................. 3/4 3-46 DELETED

.......................... 3/4 3-47 ,}'  !

Meteorological Instrumentation

............... 3/4 3-50 Remote Shutdown Instrumentation .............. 3/4 3-53 Accident Monitoring Instrumentation ............

3/4 3-56 Explosive Gas Monitoring Instrumentation .......... 3/4 3-67 Loose-Part Detection Instrumentation ............ 3/4 3-72 l

I SUMMER - UNIT 1 IV Amendment No. /[, [p/,122

, INDEX

[- BASES i-i SECTION PAGE 3/4.0 APPLICABILITY............................................... B 3/4 0-1

} 3/4.1 REACTIVITY CONTROL SYSTEMS 1

3/4.1.1- BORATION CONTR0L................r........................ B 3/4 1-1 l 3/4.1.2 BORATION SYSTEMS......................................... B 3/4 1-2 3/4.1.3 HOVABLE CONTROL ASSEMBLIES............................... B 3/4 1-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE................... ............... B 3/4 2-1  !

-- -- AA 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR RCS FLOWRATE and 3 l NUCLEARENTHALPYHOTCHANNELFACT0Rg..f 3 ................... B3/42-g RISE 4 3/4.2.4 QUADRANTPOWERTILTRATIO...l.4f.U.)...................... B3/42-/ l A

3/4.2.5 DNB PARAMETERS............................. A .............. B3 2-5 ,

l 3/4.3 INSTRUMENTATION  :

3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION....................... B 3/4 3-1 3/4.3.3 MONITORING INSTRUMENTATION............................... B 3/4 3-2 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION. . . . . . . . . . . . B 3/4 4-1 3/4.4.2 SAFETY VALVES............................................ B 3/4 4-2 3/4.4.3 PRESSURIZER....... .................................. B 3/4 4-2 3/4.4.4 RELIEFVALVES..h.@.V.5.).................................. B 3/4 4-2 SUW4ER-UNIT 1 XII

. DEFINITIONS 1

PURGE - PURGING 1.23 PURGE or PURGING is the controlled process ofdischarging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is

, required to purify the confinement.

. QUADRANT POWER TILT RATI (OPTQ i

1.24 QUADRANT POWER TILT RATIO shall be the ratio of the maximum upper .

i excore detector calibrated output to the average of the upper excore detector cali- '

brated outputs, or the ratio of the maximum lower excore detector calibrated output to tae average of the lower excore detector calibrated outputs, whichever 3 is greater. With one excore detector inoperable, the remaining three detectors )

i shall be used for computing the average.  !

RATED THERMAL POWER i

1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to i

the reactor coolant of 2900 MWt. g' REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shallbe the timeintervalfrom when the monitored parameter exceeds its trip setpoint at the channel sensor  !

until loss of stationary gripper coil voltage. l i

REPORTABLE EVENT

! 1.27 A REPORTABLE EVENT shall be any of those conditions specified in  !

Section 50.73 to 10 CFR Part 50. 1 1

SHUTDOWN MARGIN '

i 1.28 SHUTDOWN MARGIN shallbe the instantaneous amount ofreactivity by

, which the reactor is subcritical or would be suberitical from its present condition j assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be fully withdrawn.

1 i SLAVE RELAY TEST 1.29 A SLAVE RELAY TEST shallbethe energizationofeachslaverelayand verification of OPERABILITY ofeach relay. The SLAVE RELAY TEST shallinclude a continuity check, as a minimum, of associated testable actuation devices.

1.30 NotUsed SOURCE CHECK 1.31 A SOURCE CHECK shallbe the qualitative assessmentofchannelresponse when the channel sensor is exposed to a radioactive source.

SUMMER -UNIT 1 1-5 Amendment No. 35,104,117,

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POWER DISTRIBUTION LIMITS 3/4.2.4 00ADRANT POWER TILT RATIO, ,

l LINITING CONDITION FOR OPERATION 2

l l 3.2.4 The QUADRANT POWER TILT RATIO shall not exceed 1.02. ( l APPLICABILITY: MODE 1 above 505 of RATED THERMAL POWER

• l ACTION: I With less the thanQUADRANT or equal to POWER 1.09: TILT RATIO determined to exceed 1.02 b 1.

Calculate the QUADRANT POWER TILT RATIO at least one per hour until either

psN e a) The QUADRANT POWER TILT RATIO is reduced within its limit, b

b) THE L POWER is reduced to less tha POWER.

0% of RATED THERMAL.

J 4 -

2. Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ither:

1 a) Reduce the QU T POWER TI RATIO to within its limit, or i

b)

Reduce THERMAL P at 1 ast 3% from RATED THERMAL POWER for each 1% of indic e QUADRANT POWER TILT RATIO in excess of 1.0 and sim rly reduce the Power Range Neutron Flux-High Trip Setp nts ithin the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3. Verify that the QUAD T POWER TI RATIO is within its limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af exceeding the imit or reduce THERMAL POWER to less tha 505 of RATED THER 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 /> and redue the Power Range Neutron lux-High Trip setpoints to less than o equal to 55% of RATED THE L POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />

4. Identify nd correct the cause of the out of lim condition prior t increasing THERMAL POWER; subsequent POW OPERATION

• above 0% of RATED THERMAL power may proceed provide that the QUAD on NT POWER TILT RATIO is verified within its limit t least per hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or' un'til verified acceptable 95%

greater RATED THERMAL POWER.

i "See Special Test Exception 3.10.2.

(

SUMER - UNIT 1 -

3/4 2-12

Docum:nt Centrol D:sk

.. Attachm:ntI TSP 950003 RC-96-0076

. Page 1 of1 INSERT A

a. With QUADRANT POWER TILT RATIO (QPTR) not withinlimit:

1. Reduce THERMAL POWER 2 3% from RATED THERMAL POWER for each 1% of QPTR > 1.00 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and

2. Perform a QPTR calculation and reduce THERMAL POWER 2 3%

from RATED THERMAL POWER for each 1% of QPTR > 1.00 once per j 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and

3. Perform Surveillance Requirement 4.2.3.2 and either Surveillance Requirement 4.2.2.2 or Surveillance Requirement 4.2.2.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and once per 7 days thereafter, and

~4. Perform the following:

a) Reevaluate safety analyses and confirm results remain valid for  ;

duration of operation under this condition prior to increasing  !

THERMAL POWER above the limit required by Specification 3.2.4.a.1., and '

b) After completing Specification 3.2.4.a.4.a), calibrate excore  !

detectors to reset quadrant power tilt to within acceptable limits ,

arior to increasing THERM AL POWER above the limit required l Sy Specification 3.2.4.a.1., and c) After completing Specification 3.2.4.a.4.b), perform Surveillance Requirement 4.2.3.2 and either Surveillance Requirement 4.2.2.2 or Surveillance Requirement 4.2.2.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reachin,g RATED THERMAL POWER or within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after 4 increasmg THERMAL POWER above the limit required by Specification 3.2.4.a.1.; i otherwise, reduce THERMAL POWER to s 50% ofRATED THERMAL i POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b. The provisions of Specification 3.0.4 are not applicable.

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POWER DISTRIBUTION LIMITS '

A ON: (Continued) ,

i

b. '

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 d to isalignment of either a shutdown or control rod:

1.

Calculate the QL/ADRANT POWER TILT RATIO at least once er hour l

until either: I a The QUADRANT POWER TILT RATIO is reduced to ithin its limit, or gc b) RMAL POWER is reduced to less than 5 of RATED THERMAL b

2.

Reduce THE AL POWER at least 3% from RA D THERMAL POWER for each 1% of dicated QUADRANT POWER TI RATIO in excess of 1.0, within 3 minutes.

3. Verify that the ADRANT POWER TIL RATIO is within its limit

j. within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> af r exceeding t

limit or reduce THERMAL POWER to less than of RATED HERMAL POWER within the next 2 l hours and reduce the ower Ran e Neutron Flux-High trip Setpoints I to less than or equal 55% f 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 />, j

j 4. Identify and correct the se of the out of limit condition prior to increasing TH MAL OWER; subsequent POWER OPERATION  :

above 50% of RATED TH L P0 R may proceed provided that the  ;

QUADRANT POWER TILT ATIO is ve ified within its limit at least' '

once per hour for hours or un 1 verified acceptable at 95%

or greater RATED ERMAL POWER.

c. With the QUADRANT P ER TILT RATIO determi ed to exceed 1.09 due to causes other than he misalignment of eithe a shutdown or control rod:

1. Calculat the QUADRANT POWER TILT RATIO at east once per hour until e'ther:

a) he QUADRANT POWER TILT RATIO is reduced t within its limit, or

) THERMAL POWER is reduced to less than 50% of R ED THERMAL POWER.

4 SUMMER - UNIT 1 3/4 2-13

. POWER DISTRIBUTION LIMITS (Continued)

2. Re e THERMAL POWER to less than 50% of D THERMAL POWER within ours and reduce the Power e Neutron Flux-High t Trip Setpo to less than or e to 55% of RATED THERMAL

$@# POWER within t ext 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> b

3. Identify and correct cause of the out of limit condition prior to increas THERMA WER; subsequent POWER OPERATION above 50% of ED THERMAL P0 ay proceed provided that the QUADRANT once ER TILT RATIO is verif1 within its limit at least r hour for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or until ve

• ied at 95% or greater D THERMAL POWER.

d. he provisions of Specification 3.0.4 are not applicable. 1 I

i SURVEILLANCE REQUIREMENTS l

nnino nnuro vu v o vva ,

shall be determined to be within the imitaboe5 by:

a. Calculat.in OPERABLE.*g the ratio at least once per 7 days when the alarm is l

b. Calculating the ratio at least once p hours during steady state operatio )

thealarmisinoperablhj l 4 4.2.4.2 The 3 "^0""NT ."0We" TILT "JJM shall be determined to be wit: '7 the limit when 75 pc at of T THERMAL POWER with one Power Range Channel l inoperable bYuTfn'g th m able incore detectors to confirm that the normalized '

symmetric power distribution, obtained from 2 sets of 4 symmetric.thi b p"DsJ ull-core flux map, is consistent with the indicated Q"AD" ANT T "ATIO at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

QPTR . 3 f

• With input from one Power Range Channelinoperable and THERMAL POWER

< 75% of RATED THERMAL POWER, the remaining three power range channels can be used for calculating QPTR.

t / '

SUMER - UNIT 1 3/4 2-14 I

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TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

The provisions of Specification 3.0.4 are not applicable.

1. elow B the P-6 (Intermediate Range Neutron Flux Interlock) setpoint.

"Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

Values left blank pending NRC approval of 2 loop operation.

ACTION STATEMENTS ACTION 1 -

With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 2 -

With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. [

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per

[

Specification 4.3.1.1.

m

c. THERMAL POWER is restricted to less than ual to 75% of ERMAL POWER and the P nge Neutron

. Flux trip setpoint ed than or equal to l l 85% of RATED THERMAL P hours; or, the I QUADRANT POWE TIO is monitore t once per p r specification 4.2.4.2. f Either, THERMAL POWER is restricted to less than 75% of I RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and refer to Specification 4.2.4.1; or, the QPTR is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.

)

3/4 3-6 Amendment No. 101 SUM 9ER - UNIT 1 l

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. POWER DISTRIBUTION LIMIT BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE and NUCLEAR ENTHALPY

RISE HOT CHANNEL FACTOR (Continued)

M The hot channel factor F q(z) is measured periodically and increased by a cycle and height dependent power factor appropriate to either RAOC or Base Load operation, W(z) or W(z)BL, to provide assurance that the limit on the hot channel factor, Fq(z) is met. W(z) accounts for the effects ofnormal opera-tion transients and was determined from expected power control maneuvers over the full range ofburnup conditions in the core. W(z)BL accounts for the more i

restrictive operating limits allowed by Base Load operation which result in less severe transient values. The W(z) and W(z)BL functions described above for normaloperation are specified in the CORE OPERATING LIMITS REPORT (COLP.) per Specification 6.9.1.11.

When RCS flow rate and F$n are measured, no additional allowances are necessary prior to comparison with the limits of the RCS Total Flow Rate i

Versus R figure in the COLR. Measurement errors of 2.1% for RCS total flow rate including 0.1% for feedwater venturi fouling and 4% for i F!n have been allowed for in determining the limits of the RCS Total Flow

[

j Rate Versus R figure in the COLR.

The 12-hour periodic surveillance ofindicated RCS flow is sufficient to i

detect only flow degradation which could lead to operation outside the acceptable region of operation specified on the RCS Total Flow Rate Versus R figure in the COLR.

3/4.2.4 QUADRANT POWER TILT RATIO uadrant power tilt ratio limit assures that the radial sa Thehe es t design values used in the aower capability Radialanalysis.

pow power distribu l

, distri 'on measurements are made Euring startup testing and periodic y

', duringpo operation. )

& Thelimit o 2, at which corrective action is required, ' des DNB l

4 1#g andlinear heat gene ion rate protection with x-y plane p er tilts. A limiting tilt of1.025 can tolerated before the margin uncertaintyin Fq is depleted. The limit o . 2 was selected to pro e an allowance for I e uncertainty associated with e indicated po r tilt.

The two hour time allowance for o ion with a tilt condition greater than 1.02 butless than 1.09 is provid o. w identification and correction of a dropped or misaligned control . In the nt such action does not correct the tilt, the margin for unce y on FQ is reins ed by reducing the maximum allowed powerby 3 percen r cac percent of tiltin ess of 1.0. l For purposes o onitorin ? QUADRANT POWER TIL TIO when one excore detectoris mope le the movable incore detectors are used to e irm that f  ;

i the normaliz symmetric power distribution is consistent with the ADRANT POWER T RATIO. The incore detector monitoring is done with a fu ' core I flux or two sets of 4 symmetric thimbles. These locations are C-8, E.5, '

E- , H-3, H-13, L-5, L-11, N-8.

SUMMER - UNIT 1 B 3/4 2-4 Amendment No. Kh 119

Document Centrol D:sk

, AttachmentI-Insert B TSP 950003 RC-96-0076

. Page 1 of 4 INSERT B BACKGROUND: The QUADRANT POWER TILT RATIO (QPTR) limit ensures j that the gross radial power distribution remains consistent with the design values used  !

in the safety analyses. Precise radial power distribution measurements are made during I startup testing, after refueling, and periodically during power operation. '

The power density at any point in the core must be limited so that the fuel desi criteria are maintained. Together LCO 3.2.1," AXIAL FLUX DIFFERENCE (AFD),gn LCO 3.2.4 " QUADRANT POWER TILT RATIO (QPTR)," and LCO 3.1.3.6," CONTROL l ROD INSERTION LIMITS," provide limits on process variables that characterize and control the three dimensional power distribution of the reactor core. Control of these variables ensures that the core operates within the fuel design criteria and that the -

power distribution remains withm the bounds used in the safety analyses. ,

APPLICABLE SAFETY ANALYSES: This LCO precludes core power distributions that may lead to violation of the following fuel design criteria:

a. During a large break loss of coolant accident, the peak cladding temperature l must not exceed 2200*F; i l

b. During a loss of forced reactor coolant flow accident, there must be at least 95% probability at the 95% confidence level (the 95/95 departure from l nucleate boiling (DNB) criterion) that the hot fuel rod in the core does not i experience a DNB condition;

c. Durin g an ejected rod accident, the energy deposition to the fuel must not I exceec 280 cal /gm;and

d. The control rods must be capable of shutting down the reactor with a 4 minimum required shutdown margin with the highest worth control rod  ;

stuck fully withdrawn.

The LCO limits on the AFD, the QPTR, the Heat Flux Hot Channel Factor (F z)),

the Nuclear Enthalpy Rise Hot Channel Factor (F"an), and control bank insertion"(are established to preclude core power distributions that exceed the safety analyses limits.

The QPTRlimits ensure that FN preventing an undetected change in the gross @(adial power distribution.AH and In MODE 1, the F"an and Fq(z) limits must be maintained to preclude core power distributions from exceeding design limits assumed in the safety analyses.

The QPTR satisfies Criterion 2 of the NRC Policy Statement.

LCO: The QPTR limit of 1.02, at which corrective action is required, provides a margin of protection for both the DNB ratio and linear heat generation rate contributing to excessive power peaks resulting from X-Y plans power tilts. A limiting QPTR of1.02 can be tolerated betore the margin for uncertainty in F q(z) and (F"an) is possibly challenged.

Document ControlD:sk

, AttachmtntI-Insert B TSP 950003 RC-96-0076 1 a Page 2 of 4 4.

~ APPLICABILITY: The QPTR limit must be maintained in MODE 1 with THERM AL

POWER > 50% ofRATED THERMAL POWER to prevent core power distributions from i exceeding the design limits, i

! Applicabilityin MODE 1 s 50% ofRATED THERMAL POWER and in other i MODES is not required because there is either insufficient stored energy in the fuel or 1

insufficient energy being transferred to the reactor coolant to require the implementation of a QPTR limit on the distribution of core power. The QPTR limit in i

these conditions is, therefore, not considered a required protection factor. Note that the F"as and F o(z) LCOs still apply, but allow progressively higher peaking factors at 50% of

. RATED THERMAL POWERorlower.

i ACTIONS:

i a.1. With the QPTR exceeding its limit, a power level reduction of 3% from RATED THERMAL POWER for each 1% by which the QPTR exceeds 1.00 is a conservative tradeoff of total core power with peak linear power. The completion time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> allows sufficient time to identity the cause and correct the tilt. Note that the power reduction itselfmay cause a change in the tilted condition.

a.2. After completion of Specification 3.2.4.a.1, the QPTR alarm may still be in its alarmed state. As such, any additional changes in the QPTR are detected by requiring a check of the QPTR once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. If the QPTR contmues to increase, THERMAL POWER has to be reduced accordingly. A 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> completion time is sufficient because any additional change m QPTR would be relatively slow, a.3. The peaking factors F"aH and F (z) are of primary im >ortance in ensuring that the )ower distribution remlins consistent with the initial conditions used in t ie safety analyses. Performing Surveillance Requirements on F"an and F (z) within the completion time or 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ensures that these primary indicaiors of power distri bution are within their respective limits. A i completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> takes into consideration the rate at which peaking factors are likely to change and the time required to stabilize the 11 ant and perform a flux map. If these peaking factors are not within their Limits, the Actions of these Surveillances provide an appropriate res ponse for the abnormal condition. If the QPTR remains above its specified limit, the peaking factor surveillances are required each 7 days thereafter to evaluate F"an and Fo(z) with changes in power distribution. Relatively small changes are expected due to either burnup and xenon redistribution or correction of the cause for exceeding the QPTR limit.

a.4. Although F"ag and F a(z) are of primary importance as initial conditions in the safety analyses, ot'her changes in the power distribution may occur as the QPTR limit is exceeded and may have an impact on the validity of the safety analysis. A change in the power distribution can affect such reactor parameters as bank worths and peaking factors for rod malfunction accidents.- When the QPTR exceeds its hmit, it does not necessarily mean a safety concern exists. It does mean that there is an indication of a change in the gross radial power distr'bution that requires an investigation and evaluation that is accomplished by examining the incore power distribution.

Specifically, the core peaking factors and the quadrant tilt must be evaluated because they are the factors that best characterize the core power distribution.

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RC-96-0076 I l -

Page 3 of 4 a.4.a) This reevaluation is required to ensure that, before increasing i

THERMAL POWER to above the limit of Specification 3.2.4.a.1, the reactor core conditions are consistent with the assumptions in the

! safety analyses.

a.4.b) If the QPTR has exceeded the 1.02 limit and a reevaluation of the safety analysis is completed and shows that safety requirements are met, the excore detectors are recalibrated to reset quadrant power tilt j ,

to within acceptable limits prior to increasing THERMAL POWER to  :

above the limit of Specification 3.2.4.a.1. This is done to detect any i' L subsequent significant changes in QPTR.

4 i Specification 3.2.4.a.4.b) states that the quadrant power tilt is not i reset until after the reevaluation of the safety analysis has determined that core conditions at RATED THERMAL POWER are I within the safety analysis assumptions (i.e., Specification j i

3.2.4.a.4.a)). This format is intended to prevent any ambiguity about

, the required sequence of actions. -

, a.4.c) Once the quadrant power tilt is reset (i.e., Specification 3.2.4.a.4.b) is

' performed), it is acceptable to return to full power operation. ,'

However, as an added check that the core power distribution at 4

RATED THERMAL POWER is consistent with the safety analysis

' assumptions, Specification 3.2.4.a.4.c) requires verification that Fq(z) and F"an are within their specified limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of'reachmg

RATED THERMAL POWER. As an added prehution,if the core  ;

i 4

power does not reach RATED THERMAL POWER within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> but is increased slowly, then the peaking factor surveillances must be I

)erformed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the time when the ascent to power was

! >egun. These completion times are intended to allow adequate time

' to increase THERMAL POWER to above the limit of Specification 3.2.4.a.1, while not permitting the core to remain with unconfirmed  !

power distributions for extended periods of time.  !

Specification 3.2.4.a.4.c) states that the peaking factor surveillances

' may only be done after quadrant power tilt has >een reset to within 1 acceptable limits (i.e., Specification 3.2.4.a.4.b)). The intent of this i format is to have the >eaking factor surveillances performed at

, operating power levels, which can only be accomplished after j quadrant power tilt has been reset and the core returned to power.

, If Specifications 3.2.4.a.1. through 3.2.4.a.4.c) are not completed within their e.ssociated completion times, the unit must be brou

+

condition in which the requirements do not apply. pht to a MODE orJo a THERMAL POWER must be reduced to s 50% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The allowed completion time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is reasonable, based on operating experience regardin g the amount of time required to reach the

<- reduced power level without chal: enging plant systems.

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- Page 4 of 4 SURVEILLANCE REQUIREMENTS:

Surveillance Requirement 4.2.4.1 is modified by a footnote which allows QPTR to be calculated with three power range channels if THERM AL POWER is < 75% of RATED THERMAL POWER and the input from one Power Range Channel is inoperable.

This Surveillance verifies that the QPTR, as indicated by the Nuclear Instrumentation System (NIS) excore channels, is within its limits. The frequency of 7 days when the QPTR alarm is OPERABLE is acceptable because of the low probability that this alarm can remain inoperable without detection.

When the QPTR alarm is inoperable, the frequency is increased to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This frequency is adequate to detect any relatively slow changes in QPTR, because for those causes ofQUADRANT POWER TILT that occur quickly (e.g., a dropped rod), there ically are other indications of abnormality that prompt a verifi tion ofcore power Surveillance Requirement 4.2.4.2 state s that it is required only when the input from one Power Range Channel is inoperable and the THERMAL POWER is 2 75% of RATEDTHERMAL POWER.

With an NIS power range channel inoperable, tilt monitoring for a portion of the reactor core becomes degraded. Large tilts are likely to be detected with the remaining channels, but the capability for detection of small power tilts in some quadrants is decreased. Performing Surveillance Requirement 4.2.4.2 at a Frequency of12 hours '

arovides an accurate alternative means for ensuring that any tilt remains within its

.imits.

For purposes of monitoring the QPTR when one power range channel is inoperable, the moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the indicated QPTR and any previous data indicating a tilt. The incore detector monitoring is performed with a ful -core flux map or two sets of four thimble locations with quarter core symmetry. The two sets of four symmetric thimbles is a set of eight unique detector locations. These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, and N-8.

The symmetric thimble flux map can be used to generate symmetric thimble " tilt."

This can be compared to a reference symmetric thimble tilt, from the most recent full-core flux map used for peaking factor surveillance, to generate an incore tilt which is equivalent to the QPTR. Therefore, incore tilt can be used to confirm that QPTR is within limits.

With one NIS channel inoperable, the indicated tilt may be changed from the value indicated with all four channels OPERABLE. To confirm that no change in tilt has actually occurred, which might cause the QPTR limit to be exceeded, t ne incore result i may be compared against previous flux maps either using the symmetric thimbles as described above or a full-core flux map. When power is between 50% and 75% of RATED THERMAL POWER, the remaining three channels may be compared a gainst the previous QPTR recalculated using the same three channels. Nominal: y, quadrant tilt from the Surveillance should be within 2% of the tilt shown by the most recent flux map data.

POWER DISTRIBUTION LIMIT BASES "IIEAT FLUX IIGT CHAI?IJEL FACTOR oud"O '

• RISE FIOT CIIAr???EL FACTOR (Centhued) 3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial ,

FSAR assumptions and have been analytically demonstrated adequate to maintain i a mmimum DNBR in the core at or above the design limit throughout each analyzed transient. The maximum indicated Tavg limit of 589.2'F and the minimum /,!

indicated pressure limit of 2206 psi correspond to analytical limits of 591.4*F and 2185 psig respectively, read from control oard indications.

[i The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

SUMMER - UNIT 1 B 3/4 2-5 Amendment No. E

l 1

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• n.

}

, INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS 1.1 1.2 ACTION...................................................... 1-1 ACTUATION LOGIC TEST . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST . . . . . . . . . . . . . . . . . . . . . 1-1 1.4 AXIAL FLUX DIFFERENCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.5 CHANNE L CALIBRATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.6 C HANNE L C HE C K . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-1 1.7 CONTAINMENT INTEGRITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.8 CONTROLLED LEAKAGE ..................................... 1-2 1.9 CORE ALTERATION .......................................... 1-2 1.9a CORE OPERATING LIMITS REPORT . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.10 DOSE EQUIVALENT I-131 .................................... 1-2  !

1.11 E-AVERAGE DISINTEGRATION ENERGY ...................... 1-3  !

1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME . . . . . . . . . . . 1-3 1.13 FREQUENC Y NOTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 ,

1.14 GASEOUS RADWASTE TREATMENT SYSTEM . . . . . . . . . . . . . . . . . . 1-3  :

1.15 IDENTIFIED LEAKAGE ....................................... 1-3 1.16 M ASTE R RE LAY TEST . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-3 1.17 OFFSITE DOSE CALCULATION MANUAL (ODCM) ............. 1-4 1.18 OPERAB LE - OPERABILITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4  ;

1.19 OPERATIONAL MODE - MODE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 l 1.20 PHY SIC S TE ST . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.21 PRESSURE BOUNDARY LEAKAGE ............................ 1-4 1.22 PROCESS CONTROL PROGRAM (PCP) . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.23 P URG E - P UR GING . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4 1.24 QUADRANT POWER TILT RATIO (QPTR) . . . . . . . . . . . . . . . . . . . . . . 1-5 l 1.25 RATE D THERMAL POWER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 1.26 REACTOR TRIP SYSTEM RESPONSE TIME .................... 1-5 1.27 REPORTABLE EVENT ........................................ 1-5  ;

1.28 SHUTDOWN M ARGIN . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-5 I 1.29 SLAVE RELAY TEST ......................................... 1-5 1.30 DELETED ...................................................

1.31 SOURCE CHECK ............................................. 1-5 1.32 STAG G E RE D TE ST B ASIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 1.33 THE RM AL PO WE R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-6 1.34 TRIP ACTUATING DEVICE OPERATIONAL TEST . . . . . . . . . . . . . . . 1-6 1.35 UNIDENTIFIED LEAKAGE .................................... 1-6 1.36 VENTILATION EXHAUST TREATMENT SYSTEM . . . . . . . . . . . . . . . 1-6 1.37 VENTING .................................................... 1-6 TAB LE 1.1 OPERATIONAL MO DES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-7 TABLE 1.2 FREQUENCY NOTATION ................................ 1-8

\

SUMMER - UNITI I Amendment No. 35,88,104,

I l I

. 1 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS j SECTION PAGE l 3/4.2 POWER DISTRIBUTION LIMITS l

3/4.2.1 AXIAL FLUX DIFFERENCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/42-1 3/4.2.2 HE AT FLUX HOT CHANNEL FACTOR . . . . . . . . . . . . . . . . . . . . . . . . . 3/42-4 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT.

CHANNEL FACTOR ..................................... 3/42-8 3/4.2.4 QUADRANT POWER TILT RATIO (QPTR) . . . . . . . . . . . . . . . . . . . . . . 3/4 2-12 l 3/4.2.5 DNB PARAMETERS ......................................... 3/4 2-15 i l

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION . . . . . . . . . . . . . . . . . 3/43-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRU MENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-15 3/4.3-3 MONITORINGINSTRUMENTATION Radiation M onitoring . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-41 Movable Incore Detectors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-46 Deleted .................................................... 3/4 3-47 Meteorological Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-50 Remote Shutdown Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-53 Accident Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-56 Explosive Gas Monitoring Instrumentation . . . . . . . . . . . . . . . . . . . . 3/4 3-67 Loose-Part Detection Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-72 SUMMER - UNIT 1 IV Amendment No. 79,104,122, l

INDEX

' B ASES SECTION PAGE 3/4.0 APPLIC ABILITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS' 3/4.1.1~

B ORATION CONTROL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/41-1 3/41.2 B ORA TION SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/41-2 3/41.3 MOVABLE CONTROL ASSEMBLIES . . . . . . . . . . . . . . . . . . . . . . . . . B 3/41-3 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE ................................ B 3/4 2-1 3/4 2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE andNUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR ... B 3/4 2-3 3/42.4 QUADRANT POWER TILT RATIO (QPTR) ................... B 3/4 2-4 3/42.5 DNB PARAMETERS ....................................... B 3/4 2-5  !

3/4.3 IN3TRUMENTATION 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION . . . . . . . . . . . . . . . . . . . B 3/4 3-1 3/43.3 MONITORINGINSTRUMENTATION ......................... B 3/4 3-2 3/4.3 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION .. B 3/4 4-1 3/4.4.2 S A FETY VA LVE S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-2 3/4.4.3 PRE SS UR IZE R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-2 3/44.4 RELIEF VALVES (PORVs) B 3/4 4-2

.................................. l SUMMER -UNIT 1 XII Amendment No.

. DEFINITIONS PURGE - PURGING i 1.23 PURGE or PURGING is the controlled process ofdischarging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is 7

required to purify the confinement.

QUADRANT POWER TILT RATIO (QPTR) 1.24 QUADRANT POWER TILT RATIO (QPTR) shallbe the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector 1

calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. With one excore detector inoperable, the remaining three detectors shall be used for computing the average.

MTED THERMAL POWER l

1.25 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 2900 MWt.  !

/ 1

REACTOR TRIP SYSTEM RESPONSE TIME l i

1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shallbe the timeintervalfrom I a

when the monitored parameter exceeds its trip setpoint at the channel sensor l l until loss of stationary gripper coil voltage. '

1 )

j- REPORTABLE EVENT l l

1.27 A REPORTABLE EVENT shallbeanyofthoseconditionsspecifiedin ]

Section 50.73 to 10 CFR Part 50.

) SHUTDOWN MARGIN i

1.28 SHUTDOWN MARGIN shall be the instantaneous amount ofreactivity by which the reactor is suberitical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity l

worth which is assumed to be fully withdrawn.

SLAVE RELAY TEST 4

1.29 A SLAVE RELAY TEST shall be the energization of each slave relay and i verification of OPERABILITY of each relay. The SLAVE RELAY TEST shallinclude i a continuity check, as a minimum, of associated testable actuation devices.

1 1.30 NotUsed j SOURCE CHECK

1.31 A SOURCE CHECK shallbe thequalitative assessmentofchannelresponse when the channel sensor is exposed to a radioactive source.

SUMMER - UNIT 1 1-5 Amendment No. 35,104,117,

POWER DISTRIBUTION LIMITS 3/4.2.4 QUADRANT POWER TILT RATIO LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall not exceed 1.02.

APPLICABILITY: MODE 1 above 50% ofRATED THERMAL POWER

• ACTION:

a. With QUADRANT POWER TILT RATIO (QPTR) not within limit:

1. Reduce THERMAL POWER 2 3% from RATED THERMAL POWER for each 1% of QPTR > 1.00 within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, and

2. Perform a QPTR calculation and reduce THERMAL POWER 2 3%

from RATED THERMAL POWER for each 1% of QPTR > 1.00 once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and

3. Perform Surveillance Requirement 4.2.3.2 and either Surveillance Requirement 4.2.2.2 or Surveillance Requirement 4.2.2.4 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and once per 7 days thereafter, and

4. Perform the following:

a) Reevaluate safety analyses and confirm results remain valid for duration of operation under this condition prior to l increasing THERMAL POWER above the limit required by '

Specification 3.2.4.a.1., and b) After completing Specification 3.2.4.a.4.a), calibrate excore detectors to reset quadrant power tilt to within acceptable limits prior to increasing THERMAL POWER above the limit required by Specification 3.2.4.a.1., and c) After completing Specification 3.2.4.a.4.b), perform Surveillance Requirement 4.2.3.2 and either Surveillance l Rec uirement 4.2.2.2 or Surveillance Requirement 4.2.2.4  !

wit lin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching RATED THERMAL POWER l or within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after increasing THERMAL POWER above the limit required by Specification 3.2.4.a.1.;

otherwise, reduce THERMAL POWER to s 50% ofRATED THERMAL 1 POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />,

b. The provisions of Specification 3.0.4 are not applicable.

• See Special Test Exception 3.10.2.

1 SUMMER- UNIT 1 3/4 2-12 Amendment No.

]

THIS PAGE DELETED DUE TO PAGINATION i

SUMMER -UNIT 1 3/4 2-13 Amendment No.

l l

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. POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.4.1 The QPTR shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

)' a. Calculating the ratio at least once per 7 days when the alarm is

.; OPERABLE *.

l )

b. Calculating the ratio at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during steady state operation when the alarm is inoperable *. l 4.2.4.2 The QPTR shall be determined to be within the limit when 2 75 % of

. RATED THERMAL POWER with one Power Range Channelinoperable by using l 3 the movable incore detectors to confirm that the normalized symmetric power  ;

distribution, obtained from 2 sets of 4 symmetric thimble locations or a full-core i flux map, is consistent with the indicated QPTR at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.  !

I i

4 4

i j l

l

• With input from one Power Range Channelinoperable and THERMAL POWER

< 75% of RATED THERMAL POWER, the remaining three power range channels can be used for calculating QPTR.

SUMMER-UNIT 1 3/4 2-14 Amendment No.

TABLE 3.3-1 (Continued)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable ofrod withdrawal.

The provisions of Specification 3.0.4 are not applicable.

Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint. 1 Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

Values left blank pending NRC approval of 2 loop operation.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

}

ACTION 2 - With the number ofOPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

c. Either, THERMAL POWER is restricted to less than 75% of i RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and refer to Specification 4.2.4.1; or, the QPTR is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> per Specification 4.2.4.2.

i SUMMER - UNIT 1 3/43-6 Amendment No.101,

i)OWER DISTRIBUTION LIMIT BASES HEAT FLUX HOT CHANNEL FACTOR and RCS FLOWRATE and NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR (Continued)

The hot channel factor F"q(z) is measured periodically and increased by a cycle and height dependent power factor appropriate to either RAOC or Base  !

Load operation, W(z) or W(z) to provide assurance that the limit on the hot channel factor, F (z) is met. %,(z) accounts for the effects of normal opera-  ;

tion transients arid was determined from expected power control maneuvers over ,

the full range ofburnup conditions in the core. W(z)g accounts for the more  !

restrictive operating limits allowed by Base Load operation which result in less ,

severe transient values. The W(z) and W(z)3 functions described above for l normal operation are specified in the CORE bPERATING LIMITS REPORT 1 (COLR) per Specification 6.9.1.11.

When RCS flow rate and F"an are measured, no additional allowances are l necessary prior to comparison with the limits of the RCS Total Flow Rate  :

Versus R figure in the COLR. Measurement errors of 2.1% for RCS total l flow rate including 0.1% for feedwater venturi fouling and 4% for 1

F"An have been allowed for in determining the limits of the RCS Total Flow Rate Versus R figure in the COLR.

The 12-hour periodic surveillance ofindicated RCS flow is sufficient to  ;

, detect only flow degradation which could lead to operation outside the acceptable I re ion of operation specified on the RCS Total Flow Rate Versus R figure in the C LR.

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3/4.2.4 QUADRANT POWER TILT RATIO (QPTR) s l

l BACKGROUND: The QUADRANT POWER TILT RATIO (QPTR) limit ensures 4

that the p oss radial power distribution remains consistent with the design values used in the safety analyses. Precise radial power distribution measurements are made turing startup testing, after refueling, and periodically during power operation.

The power density at any point in the core must be limited so that the fuel desirn criteria are maintained. Together LCO 3.2.1," AXIAL FLUX DIFFERENCE (AF b)," LCO 3.2.4 " QUADRANT POWER TILT RATIO (QPTR)," and LCO 3.1.3.6,

" CONTROL ROD INSERTION LIMITS," provide limits on process variables that characterize and control the three dimensional power distribution of the reactor core. Control of these variables ensures that the core operates within the fuel l 4 design criteria and that the power distribution remains within the bounds used in '

l the safety analyses.

APPLICABLE SAFETY ANALYSES: This LCO precludes core power distributions that may lead to violation of the following fuel design criteria: l

a. During a large break loss of coolant accident, the peak cladding temperature must not exceed 2200*F;

b. During a loss of forced reactor coolant flow accident, there must be at i least 95% probability at the 95% confidence level (the 95/95 departure from nucleate boiling (DNB) criterion) that the hot fuel rod in the core does not experience a DNB condition; SUMMER - UNIT 1 B 3/4 2 4 Amendment No. 35,45,75, 88,119,

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Q_UADRANT POWER TILT RATIO (QPTR) (Continued)

c. During an ejected rod accident, the energy deposition to the fuel must  ;

not exceed 280 cal /gm; and  ;

d. The control rods must be capable of shutting down the reactor with a minimum required shutdown margin with the highest worth control rod stuck fully withdrawn.

The LCO limits on the AFD, the QPTR, the Heat Flux Hot Channel Factor (Fq(z)), the Nuclear Enthalpy Rise Hot Channel Factor (FNaH), and controlbank insertion are established to preclude core power distributions that exceed the l safety analyses limits.

The QPTR limits ensure that F"an and F z) remain below their limiting values by preventing an undetected change in$(he gross radial power distributio In MODE 1, the F"an and F power distributions from exceedm,q(z) limitsassumed g design limits must bein maintained to preclude core the safety analyses. l The QPTR satisfies Criterion 2 of the NRC Policy Statement.

LCO: The QPTR limit of1.02, at which corrective action is required, provides a margin of protection for both the DNB ratio and linear heat generation rate' contributing to excessive power peaks resulting from X.Y plane power tilts. A  !

limiting QPTR of1.02 can be tolerated before the margin for uncertainty in F q(z) and (F"an)is possibly challenged.

APPLICABILITY: The QPTR limit must be maintained in MODE 1 with THERMAL POWER > 50% ofRATED THERMAL POWER to prevent core power distributions from exceeding the design limits.

Applicabilityin MODE 1 s 50% of RATED THERMAL POWER and in other MODES is not required because there is either insufficient stored energy in the fuel or insufficient energy being transferred to the reactor coolant to require the implementation of a QPTR limit on the distribution of core power. The QPTR limit in these conditions is, therefore, not considered a required protection factor. Note that the F"an and F o(z) LCOs still apply, but allow pro factors at 50% of RATED THERMAL POWER or lower.gressively higher peaking ACTIONS:

a.1. With the QPTR exceeding its limit, a power level reduction of 3% from RATED THERMAL POWER for each 1% by which the QPTR exceeds 1.00 is a conservative tradeoff of total core power with peak linear power. The completion time of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> allows sufficient time to identify the cause and correct the tilt. Note that the power reduction itself may cause a change in the tilted condition.

a.2. After completion of Specification 3.2.4.a.1, the QPTR alarm may still be in its alarmed state. As such, any additional changes in the QPTR are detected by requiring a check of the QPTR once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

If the QPTR continues to increase, THERMAL POWER has to be reduced accordingly. A 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> completion time is sufficient because any additional change in QPTR would be relatively slow.

SUMMER - UNIT 1 B 3/4 2-4a Amendment No.

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S I OWER DISTRIBUTION LIMIT BASES QUADRANT POWER TILT RATIO (Continued) 1 a.3. The peaking factors F"an and F9(z) are of primary importance in ensuring that the power distribution remains consistent with the I initial conditions used in the safety analyses. Performing Surveillance Requirements on F"an and Fq(z) within the completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ensures that these primary indicators of power distribution are within their respective limits. A completion time of24 hours takes into consideration the rate at which peaking factors are likely to change and the time required to stabilize the plant and perform a flux map. If these peaking factors are not within their limits, the Actions of these Surveillances provide an appropriate response for the abnormal condition. If the QPTR remains above its specified limit, the peakmg l factor surveillances are required each 7 days thereafter to evaluate l F"an and Fq(z) with changes in power distribution. Relatively small l changes are expected due to either burnup and xenon redistribution or  ;

correction of the cause for exceeding the QPTR limit.

j a.4. Although F"an and Fo(z) are of primary importance as initial conditions in the safefy analyses, other changes in the power distribution may occur as the QPTR limit is exceeded and may have an 1 impact on the validity of the safety analysis. A change in the power I distribution can affect such reactor parameters as bank worths and  ;

peaking factors for rod malfunction accidents. When the QPTR exceeds j its limit, it does not necessarily mean a safety concern exists. It does t mean that there is an indication of a change m the gross radial power distribution that requires an investigation and evaluation that is accomplished by examining the incore power distribution. Specifically, i the core peaking factors and the c uadrant tilt must be evaluated because they are the factors that best characterize the core power distribution.

a.4.a) This reevaluation is required to ensure that, before increasing THERMAL POWER to above the limit of Specification 3.2.4.a.1, the reactor core conditions are consistent with the assumptions in the safety analyses.

a.4.b) If the QPTR has exceeded the 1.02 limit and a reevaluation of the safety analysis is completed and shows that safety requirements are met, the excore detectors are recalibrated to reset quadrant power tilt to within acceptable limits prior to increasing THERMAL POWER to above the limit of Specification 3.2.4.a.1.

This is done to detect any subsequent significant changes in QPTR.

Specification 3.2.4.a.4.b) states that the quadrant power tilt is not reset until after the reevaluation of the safety analysis has determined that core conditions at RATED THERMAL POWER are within the safety analysis assumptions (i.e., Specification 3.2.4.a.4.a)). This format is intended to prevent any ambiguity about the required sequence of actions.

1 SUMMER - UNIT 1 B 3/4 2-4b Amendment No.

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a.4.c) Once the quadrant power tilt is reset (i.e., Specification  !

3.2.4.a.4.b) is performed) it is acceatable to return to full power operation. However, as a,n added cLieck that the core power distribution at RATED THERMAL POWER is consistent with the safety analysis assumptions, Specification 3.2.4.a.4.c) rec,uires verification that F 9(z) and F% are within their specified limits within24hoursofreachingRATED THERMAL POWER. Asan added precaution, if the core power does not reach RATED THERMAL POWER within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> but is increased slowly, then the peaking factor surveillances must be performed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the time when the ascent to power was begun. These completion times are intended to allow adequate tune to increase THERMAL POWER to above the limit ofSpecification 3.2.4.a.1, while not permitting the core to remain with unconfirmed power distributions for extended periods of time. i Specification 3.2.4.a.4.c) states that the peaking factor surveillances may only be done after quadrant power tilt has I been reset to within acceptable limits (i.e., Specification 3.2.4.a.4.b)). The intent of this format is to have the peakin ;

factor surveillances performed at operating power levels, which can only be accomplished after quadrant power tilt has been reset and the core returned to power.

If Specifications 3.2.4.a.1. through 3.2.4.a.4.c) are not completed within their associated completion times, the unit must be brought to a MODE or condition in which the requirements do not apply. To achieve this status, THERMAL POWER must be reduced to s 50% of RATED l THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. The allowed completion time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is reasonable, based on operating experience regarding the amount of time required to reach the reduced power level without challenging plant systems.

SURVEILLANCE REQUIREMENTS:

Surveillance Requirement 4.2.4.1 is modified by a footnote which allows QPTR to be calculated with three power range channels if THERMAL POWER is

< 75% of RATED THERMAL POWER and the input from one Power Range Channel is inoperable.

This Surveillance verifies that the QPTR, as indicated by the Nuclear Instrumentation System (NIS) excore channels, is within its limits. The frequency of 7 days when the QPTR alarm is OPERABLE is acceptable because of the low probability that this alarm can remain inoperable without detection.

When the QPTR alarm is inoperable, the frequency is increased to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

This frequency is adequate to detect any relatively slow changes in QPTR, because for those causes of QUADRANT POWER TILT that occur quickly (e.g., a dropped rod), there typically are other indications of abnormality that prompt a verification of core power tilt.

SUMMER - UNIT 1 B 3/4 2-4c Amendment No.

POWER DISTRIBUTION LIMIT ~

BASES QUADRANT POWER TILT RATIO (OPTR) (Continued)

Surveillance Reg uirement 4.2.4.2 states thatit is required only when the input from one Power Jtange Channelis inoperable and the THERM AL POWER is a 75% of RATED THERMAL POWER.

With an NIS power range channel inoperable, tilt monitoring for a portion of the reactor core becomes degraded. Large tilts are likely to be detected with the remaining channels, but the capability for detection of small power tilts in some

quadrants is decreased. Performing Surveillance Requirement 4.2.4.2 at a .

{ Frequency of12 hours provides an accurate alternative means for ensuring that any tilt remains within itslimits.

For purposes of monitoring the QPTR when one power range channel is inoperable, the moveable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the indicated QPTR and any previous data indicating a tilt. The incore detector monitoring is performed with a full-core flux map or two sets of four thimble locations with quarter core symmetry.

The two sets of four symmetric thimbles is a set of eight unique detector locations.

These locations are C-8, E-5, E-11, H-3, H-13, L-5, L-11, and N-8.

The symmetric thimble flux map can be used to generate symmetric thimble

" tilt." This can be compared to a reference symmetric thimble tilt, from the most recent full-core flux map used for peaking factor surveillance, to generate an incore tilt which is equivalent to the QPTR. Therefore, incore tilt can be used to confirm that QPTRis within limits.

With one NIS channel inoperable, the indicated tilt may be changed from the value indicated with all four channels OPERABLE. To confirm that no change in tilt has actually occurred, which might cause the QPTR limit to be exceeded, the incore result may be compared a gainst previous flux maps either using the symmetric thimbles as described above or a full-core flux map. When poweris between 50% and 75% of RATED THERMAL POWER, the remainin g three channels may be compared against the previous QPTR recalculated using the same three channels. Nominally, quadrant tilt from the Surveillance should be within 2% of the tilt shown by the most recent flux map data.

3/4.2.5 DNB PARAMETERS The limits on the DNB related parameters assure that each of the parameters are maintained within the normal steady state envelope of operation assumed in the transient and accident analyses. The limits are consistent with the initial FSAR assumptions and have been analytically demonstrated adequate to maintain a minimum DNBR in the core at or above the design limit throughout each analyzed transient. The maximum indicated Tavg limit of 589.2*F and the minimum indicated pressure limit of 2206 psig correspond to anal psig respectively, read from control board indications. ytical limits of 591.4*F and 2185 The 12-hour periodic surveillance of these parameters through instrument readout is sufficient to ensure that the parameters are restored within their limits following load changes and other expected transient operation.

SUMMER - UNIT 1 B 3/4 2-5 Amendment No. 45,56,60,75, 88(c),119,

. Document Contr:1 Drsk At't chrtuntII TSP 950003 RC-96-0076 Page 1 of2 SAFETY EVALUATION FOR REVISING THE SPECIFICATION FOR QUADRANT POWER TILT RATIO (QPTR)

IN THE VIRGIL C. SUMMER NUCLEAR STATION TECHNICAL SPECIFICATIONS Description of AmendmentReauest The Virgil C. Summer Nuclear Station (VCSNS) Technical Specifications (TS) is being revised to change TS 3/4.2.4, QUADRANT POWER TILT RATIO (QPTR),the Bases for QPTR, and TS 3/4.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION, Table 3.3-1, " Table Notation, Action Statement 2.c.".

The intent of the proposed request to TS 3.2.4 is to complete analyses and calibrate excore detectors when necessary. This chang improved Westinghouse Standardized Techm,e is consistent cal Specifications with (STS), the guidance NUREG 1431, of the Rev.1. The proposed TS amendment request will enhance the Limiting Condition for Operation and the Surveillance Requirements.

The Bases for this TS (Bases 3/4.2.4) is being revised to reflect the guidance of the STS and other reviews.

TS Table 3.3 1 is being revised to be consistent with the changes requested for QPTR when one Power Range Channel is inoperable.

Safety Evaluation The QPTR limit ensures that the gross radial power distribution remains consistent with the design values used in the safety analyses. Precise radial power distribution measurements are made during startup testing, after refueling, and periodically during power operation.

The QPTR limits ensure that F"an and Fq (z) remain below their limiting values by preventing an undetected change in the gross radial power distribution. In MODE 1, the F"An and Fq(z) limits must be maintamed to preclude core aower distributions

' from exceeding design limits assumed in the safety analyses. '"'he QPTR satisfies

- Criterion 2 of the NRC Policy Statement.

1 The QPTR limit of1.02, at which corrective action is required, provides a margin of protection for both the departure from nucleate boiling ratio and linear heat generation rate contributing to excessive power peaks resulting from X-Y plane power tilts. A limiting QPTR of 1.02 can be tolerated before the margin for uncertainty in Fq(z) and (F"an) is possibly challenged. With the QPTR exceeding its limit, a 70wer level reduction of 3% from RATED THERMAL POWER for each 1% by which t le QPTR i exceeds 1.00 is a conservative tradeoff of total core power with peak linear power.

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Page 2 of 2 The Power Range Neutron Flux trip setpoint reduction is not required since incore flux measurements are not expected to change solely due to the loss of a Power Range Channel. These setpoints were previously reduced m order to account for flux uncertainties which will now be monitored and corrected, if necessary, per TS 3.2.4.

1 Pursuant to the above informs + ion, the proposed amendment request does not involve

) a reduction in margin of safety since the changes do net have an adverse impact on containment integrity, systems, or components important to safety or any other design feature.

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1 NO SIGNIFICANT HAZARDS EVALUATION l FOR REVISING THE SPECIFICATION FOR i

' QUADRANT POWER TILT RATIO (QPTR)

IN THE VIRGIL C. SUMMER NUCLEAR STATION

. TECHNICAL SPECIFICATIONS 1

i Description of AmendmentRequest '

I The Virgil C. Summer Nuclear Station (VCSNS) Technical Specifications (TS) is

being revised to change TS 3/4.2.4, QUADRANT POWER TILT RATIO (QPTR),the

, Bases for QPTR, and TS 3/4.3.1, REACTOR TRIP SYSTEM INSTRUMENTATION, l Table 3.3-1, " Table Notation, Action Statement 2.c.". '

The intent of the proposed request to TS 3.2.4 is to complete analyses and calibrate

excore detectors when necessary. This change is consistent with the guidance of the improved Westinghouse Standardized Technical Specifications (STS), NUREG 1431, l i Rev.1. The proposed TS amendment request will enhance the Limiting Condition for

j. Operation and the Surveillance Requirements.

' s The Bases for this TS (Bases 3/4.2.4) is being revised to reflect the guidance of the STS and other reviews.

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', TS Table 3.3-1 is being revised to be consistent with the changes requested for QPTR when one Power Range Channel is inoperable.

Basis for No Significant Hazards Consideration Determination l South Carolina Electric & Gas Company (SCE&G) has evaluated the proposed 4 chan ges to the VCSNS TS described above against the Significant Hazards Criteria of  ;

10 Ch R 50.92 and has determined that the changes do not involve any significant '

i hazard for the following reasons:

1. The probability or consequences of an accident previously evaluated in the FSAR is not significantlyincreased, i

i The QPTR limits ensure that F"6H and Fo(z) remain below their limiting values by

, preventing an undetected change in the gross radial power distribution. In MODE 1, the FN6H and F z) limits must be maintained to ?reclude core power

distributions from*(exceeding design limits assumet in the safety analyses.

QPTR satisfies Criterion 2 of the NRC Policy Statement.

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. RC-96-0076 Page 2 of 3 The QPTR limit of 1.02, at which corrective action is required, provides a margin of protection for both the departure from nucleate boiling ratio and linear heat 1 generation rate contributing to excessive power peaks resulting from X-Y plane power tilts. A limiting QPTR of1.02 can be tolerated before the margin for uncertainty in F (z) a and (F"an) is possibly challenged. With the QPTR exceeding its limit, a power' level reduction of 3% from RATED THERMAL POWER for each 1% by which the QPTR exceeds 1.00 is a conservative tradeoff of total core power with peak linear power.

The Power Range Neutron Flux trip setpoint reduction is not req uired since incore flux measurements are not expected to change concurrent with t he loss of a Power Range Channel. These setpoints, which were previously reduced in order to .

account for uncertainties, will now be monitored and corrected, if necessary, per l TS 3.2.4.

Any change in the QPTR would be detected by requiring a check of the QPTR once I per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. If the QPTR indicates an increase, THERMAL POWER has to be '

reduced accordingly. A 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> completion time is sufficient because any additional change m QPTR would be relatively slow.

The improvement of TS 3/4.2.4 to reflect the improved STS in no way impacts the accident analysis of the FSAR. Therefore, the probability or consequences of a previously evaluated accident has not been increased. '

2. The possibility of an accident or a malfunction of a different type than any previously evaluated is not created.

The proposed amendment request does not necessitate physical alteration of the plant nor changes in parameters governing normal plant operation. Therefore, the change does not create the possibility of a new or different kind of accident or malfunction.

3. The margin of safety has not been significantly reduced.

This proposed amendment request precludes core power distributions that may lead to violation of the following fuel design criteria:

a. During a large break loss of coolant accident, the peak cladding temperature must not exceed 2200*F;

b. During a loss of forced reactor coolant flow accident, there must be at least 95% probability at the 95% confidence level (the 95/95 departure from nucleate boiling (DNB) criterion) that the hot fuel rod in the core does not experience a DNB condition; i

c. During an ejected rod accident, the energy deposition to the fuel must not exceed 280 cal /gm; and

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d. The control rods must be capable of shutting down the reactor with a minimum required shutdown mar control rod stuck fully withdrawn. gin with the highest worth The improvement of TS 3/4.2.4 ensures that the gross radial power distribution remains consistent with the design values used in the safety analyses.

The core peakin g factors and the quadrant tilt must be evaluated because they are the factors that 3est characterize the core power distribution. This reevaluation is required to ensure that the reactor core conditions are consistent with the assumptions in the safety analyses. Therefore, the margin of safety has not decreased. ,

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l Pursuant to 10CFR50.91, the preceding analyses provides a determination that the l proposed TS amendment request poses no significant hazard as delineated by 100FR50.92.

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