ML18016B010

Proposed Tech Specs 3/4.2.2,3/4.2.3 & 3/4.2.5,providing Clarification & Reducing Burden of Addl License Amend Process by Implementing Guidance in GL 88-16 & NUREG-1431, Rev 1, Std Ts,W Plants.

ML18016B010
Person / Time
Site:	Harris
Issue date:	07/09/1999
From:	CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18016B009	List: ML18016B007 ML18016B010
References
RTR-NUREG-1431 GL-88-16, NUDOCS 9907150097
Download: ML18016B010 (32)

Text

ENCLOSURE 5 TO SERIAL: HNP-99-071 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT TECHNICALSPECIFICATION TS 3/4.2.2, TS 3/4.2.3, TS 3/4.2.5 TECHNICALSPECIFICATION PAGES E5-1 vvovxsoosv eeovav PDR ADOCK 05000400 P PDR ~

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4. 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE 3/4 2-1 FIGURE 3.2-1 (DELETED) 3/4 2-4 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F()(Z) 3/4 2-5 p6 FIGURE 3.2-2 (DELETED) 3/4 2-8 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 3/4 2-9

/der 3.2-3 FIGURE ALLOWED MEASURED REACTOR COOLANT SYSTEM TOTAL FLOW TE VERSUS POWER - THREE LOOPS IN OPERATION 3/4 2-10b (o

3/4.2.4 QU R TILT RATIO . 3/4 2-11 3/4.2.5 DNB PARAMETERS . 3/4 2-14 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-2 TABLE 3.3-2 (DELETED) 3/4 3-9 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-16 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-18 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 3/4 3-28 TABLE 3.3-5 (DELETED) 3/4 3-37 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-41 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring For Plant Operations 3/4 3-50 SHEARON HARRIS - UNIT 1 Amendment No. 50

TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR ALLOWANCE ERROR FUNCTIONAL UNIT ~TA Z ~S TRIP SETPOINT ALLOWABLE VALUE

1. Hanual Reactor Trip N.A. N.A. H.A. H.A. N.A.

2 ~ Power Range, Neutron Flux

a. High Setpoint 7.5 4.56 0 z 109% of RTP' z 111.1% of RTP" e o

b. Low Setpoint 8.3 4.56 0 ~ 25% of RTP" M 27.1% of RTP

3. Power Range, Neutron 1.6 0.5 0 a 5% of RTP with ~ 6.3% of RTP with Flux, High Positive Rate a time constant a time constant a 2 seconds ~ 2 seconds

4. Power Range, Heutron 1.6 0.5 0 z 5% of RTP with ~ 6.3% of RTP with Flux, High Negative Rate a time constant time constant

~ 2 seconds )

a 2 seconds

5. Intermediate Range, 17.0 8.41 0 x 25% of RTP ~ 30.9% of RTP Neutron Flux '.

Source Range, Neutron 17. 0 10.01 0 a 10 cps ~ 1.4 x 106 cps Flux

7. Overtemperature hT 8.7 6.02 Note 5 See Note 1 See Note 2

8. Overpower hT 4.7 1.50 1.9 See Note 3 See Note 4

9. Pressurizer Pressure-Low 5.0 2.21 1.5 z 1960 psig ~ 1946 psig

10. Pressurizer Pressure-High 7.5 5.01 0.5 z 2385 psig x 2399 psig Pressurizer Water Level- 8.0 2.18 1.5 a 92% of instrument ~ 93,8% of instrument High span span RTP = RATED THERMAL POWER

TABLE 2.2-1 Continued TABLE NOTATIONS NOTE 3: (Continued)

Ke 0.002/'F for T > T" and K, - 0 for T z T",

As defined in Note 1, Indicated T, at RATED THERHAL POMER (Calibration temperature for hT instrumentatfon, < 580.8'F),

S As defined in Note 1, and f,(hI) - 0 for all bl.

NOTE 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.3% hT span.

NOTE 5: The sensor error for temperature is 1.9 and 1. 1 for pressure.

NOTE 6: The sensor error for steam flow is 0.9, for feed flow is 1.5, and for steam pressure is 0.75.

NOTE . This ue is ociat with m sured flow ~ 93,540 gpm (1.0 ,)]. chnic S ificati 3/4.2. requir this s point t e reduced the r of 1. . of R for ch 1%

hat meas ed RCS ow is ow [2 ,540 gpm (1.0 + C,

I

~ ~

POWER DISTRIBUTION LIMI S 3 4. .2 HEAT FLUX HOT CHANNEL FACTOR - FQLZZ LIMITING CONDITION FOR OPERATION wi ig~ liini a S eci4'ied i++he C, 3.2.2 FQ(Z) shall be limited by the following relationshi s:

Qe,lcd~

FQ(Z) ( F RTP P

x K(Z) fOR P ) 0.5 FQ(Z) ( F RTP 0.5 x K(Z) FOR P s 0. 5 Where:

RTP FQ the FQ limit at RATED THERMAL POWER specified in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106, P = THERMAL POWER , and RATED THERMAL POWER K(Z) = the normalized FQ(Z) as a function of core height specified in the COLR.

APPLICABILITY: MODE 1.

ACTION:

With FQ(Z) exceeding its limit:

a ~ Reduce THERMAL POWER at least 1% for each 1% FQ(Z) exceeds the limit within 15 minutes and similarly reduce the Po Range Neutron Flux-High Trip Setpoint's within the next 4 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; POWER OPERATION may proceed for up to a total o 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; subsequent POWER OPERATION may proceed provided the Overpower hT Trip Setpoints have been reduced at least 1%

for each 1% FQ(Z) exceeds the limit.

b. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit required by ACTION 'a., above; THERMAL POWER may then be increased provided FQ(Z) is demonstrated through incore mapping to be within its limit.

SHEARON HARRIS - UNIT 1 3/4 2-5 Amendment No. 25

~ ~ POWER DISTRIBUTION LIS 3/4.2.3 CS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION 3.2.3 The combination of indicated Reactor Coolant System (RCS) total flow rate and THERMAL POWER shall be maintained within the regio of'rmissibl operation shown on Figure 3.2-3 for three loop operation an F, sha e maintained as follows:

Wt&xn he limi4 Speci+<c a F~( F~" L1.0 + PF~(1.0-P)] i~ Q~ ('.os,.

Where:

F,"" = F<< Limit at RATED THERMAL POWER specified in the CORE OPERATING LIMITS REPORT (COLR). plant procedure PLP-106, Power Factor Multiplier for F, specified in the COLR, THERMAL POWER RATED THERMAL POWER FhH Enthalpy rise hot channel factor obtained by using the movable incore detectors to obtain a power distribution map, with the measured value of the nuclear enthalpy rise hot channel factor F," increased by an allowance of 4X to account for measurement uncertainty.

APPLICABILITY: MODE 1.

ACTION:

'd With the combination of RCS total flow rate and THERMAL P R w t in e re i n of h o eration shown on Figure 3.2-3 or F>> outside e limits given in 3.2. Qd,e.

1. Within Q2hours either: ge.leW a) R tore the combination of RCS total flow rate and THERMA OWER re ion of permissible o r tion. an F, to within the limits given in . . a., or

'e.(~~

b) Restore the combination of RCS total flow rate and THERMAL POWER to within the region of restricted operation and corn ly with ACTION b. below, or

~riSB.Y I

/~4 ~<~pRHAifoWEk4 ~~<'+' ~ l~ Tfip5e.

P Ogfg. Mk, ~<g~u.go er R g e,h)c,u&n f itss or cymi~ SG% of RATEo TBERHt<t P ge.g4 45ou,ls, SHEARON HARRIS - UNIT 1 3/4 2-9 Amendment No. 50 Oek&

'OWER DISTRIBUTION L II% ga'le&

3/4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION A~CTION C NI d c) Reduce THERMAL POWER to less than 50K of RATED THERMAL POWER and reduce the Power Range Neutron Flux - High Trip Setpoint to less than or equal to 55K of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

b. With the combination of RCS total flow rate and THERMAL POWER within the region of restricted operation (flow rate less than

[293.540 gpm x (1.0 + C,)j, which includes measurement uncertainty for core flow, C,, as described in the Bases), within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> reduce the Power Range Neutron Flux-High Trip Setpoint to below the nominal setpoint by the same amount (X RTP) as the power reduction required by Figure 3.2-3 and maintain F, at a value that is less than or e ual to the value of F at ED THERNL POWE .

~<le%

c.. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> A

of'mtially bein within the region of prohibited o erat>on s own on C. lM Figure i

4 FA eit er:

W in o<<s,<e iona 4

<<,;, o,a.,foip

>em>'n 3 > 3.

eri y oug o ow ra ore flux mapping that the combination of RCS total flow rate and THERNL POWER are restored to within the region of permissible operation, and F<< to within the limits given in 3.2.3a., or

2. Verify through RCS total flow rate determination and incore flux mapping that the combination of RCS total flow rate and THERNL POWER are restored to within the region of restricted operation and comply with ACTION b. above, or

3. Reduce THERMAL POWER to less than 5X of RATED THERNL 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 />.

Identify and correct the cause of the out-of-limit condition prior to increasing THERNL POWER above the r 't re red by ACTION a.l. above. gubse uent POWER OPERATION ma roceed rovided that he corn anat>on o L PO an sn icated RCS to a ow ra e are emonstrated through RCS total flow rate comparison to be within the regions of estricted or ermissible o eration shown on Fi ure 3 -3 nd tha , is emonstrated throug encore f ux mapping o be within acceptab e limits prior to exceeding the following THERMAL POWER levels~h

1. A nomin 5 of TED THERMAL POWER,

o. pt.kcW

2. A nominal o RATED THERMAL POWER.~and Q

3. Within 24 o rs of attaining greater than or equal to 95K t TED g) THERMAL POWER.

iH;AI ~~Vcg~jrc~+s APNE:hOIJ 3.%.3.e IodTA-inef, reduce NER4%-Po<E

~ g% gf- Std)WELM4. poAEk wcg+j<qc.d- 4 (aors Tgfggg<POWEg doe~net haVC. +bC O.6~M+> C~pl~ WiK~'G QC.fLOtti.

SHEARON HARRIS - UNIT 1 3/4 2-10 Amendment No. 50

POWER DISTRIBUTION LI S O 3 4.2.3 RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR SURVEILLANCE REQUIREMENTS 4.2.3. 1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 F<< shall be determined to be within acceptable limits:

a. Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and plaice,a&~

b. At least once per 31 Effective Full Power Day/

4.2.3.3 The RCS total flow rate shall be verified to be within the regions of restricted or permissible operation of Figure 3.2-3:

a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by the use of main control board instrumentation or equivalent, and

b. At least once per 31 days by the use of process computer readings or digital voltmeter measurement.

4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.

4.2.3.5 The RCS total flow rate shall be determined by precision heat balance measurement at least once per 18 months. The measurement instrumentation shall be calibrated within 21 days prior to the performance of the calorimetric flow measurement.

SHEARON HARRIS - UNIT 1 3/4 2-10a Amendment No. 50

33.0 Prohibited Operation Region 32.0 { 100.0, 32.13 x {1.0 C1 ) ) ~

31.0 Pernties{b{e Operation Region K

U o 30.0

{ 100.0,29.354 x {1.0 + C1 ))

29.0 Reatricted Operation Region 28.0

{ 92.6, 27.89 x {1.0 + C1 ) )

27.0 88.0 90.0 92.0 94.0 98.0 98.0 100.0 102.0 104.0 Power (% RTP) gk Figure 3.2-3~$ eb&

>{ L{.&

Allowed Measured Reactor Coolant System Total Flow Rate versus Power-Three Loops in Operation SHEARON HARRIS - UNIT 1 3/4 2-10b Amendment. No. 50

POWER DISTRIBUTION L S 3 4.2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION

't 3.2.5 The following DNB-related parameters shall be maintained within the following limits:

a. Indicated Reactor Coolant System T, a 586. I'F after addition for Clc,late. instrument uncertainty, and

b. Indicated Pressurizer Pressure a 2185 psig after subtraction for ins rument uncertaint . )~f,g pgJ c +<~4, APPLICABILITY: MODE 1.

ACTION: ~O Wtfl < IAS se pg+t~lde With any of the above parameters e ceedin its indicated limit, restore the

-parameter to within its limit within ours or re uce THERMAL POWER to less than 5% of RATED:THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

m~'le& 'g RgJ SURVEILLANCE REQUIREMENTS

..6. I 4.2. Each of the parameters shown in Specification 3.2.5 shall be verified o e within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

).Z.<.2. Ye.ri~)'> 4y Pri-Clarion he~4 ba.'la,nCej <PAL R<P <Oka.) WIO~ ra)e, lSf mlkhl'6 ( fs t Ilvlif o 0 le.a &4 cyngp pram f

RC. S kko l Floou roke 2'R3p nfl gp[A cs.Am<

Su.bkt a.C.lid 6 far inSkr U.me.nf u.hC.Gda'54 This limit is not a licable during either Thermal Power Ramp in excess of a5% Rated Thermal Power er minute or a Thermal Power ste P chan g e in excess o z '. ated ermal Power.

wK %luau'tt'aJ. 40 be. pea orgone.J. ~Akto 2H houf 5 aRer + !5%

POSER,. KATE'Q,a.Q,RAL SHEARON HARRIS - UNIT 1 3/4 2-14 Amendment Ro.Q4~

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POWER DISTRIBUTION LI S BASES 3 4.2.2 AND 3 4.2.3 HEAT FLUX HOT CHANNEL FACTO RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel facto RCS flow rate, and enthalpy rise hot channel factor ensure that: (1) the design limits on peak local power density and minimum DNBR are not exceeded and (2) in the event of a LOCA the peak fuel clad temperature will ot exceed the 2200'F ECCS acce tance c a, ~ po~er i~'oq ~p 04;~g wQ Qc.

'm w4 d>h FAR,s w4 @arch(q XablC into<c de~~r SQS~- FAH un'Q(M) ach of these i easurable bu will normally only e e ermine periodically

~t+ as speci ied in Specifications 4.2.2 sufficient to ensure that the limits and 4.2,3. This periodic surveillance is are maintained provided:

a ~ Control rods in a single group move together with no individual rod insertion differing by more than + 12 steps, indicated, from the group demand position;

b. Control rod groups are sequenced with overlapping groups as described in Specification 3. 1.3.6; SHEARON HARRIS - UNIT 1 B 3/4 2-2a Amendment No. 25

POWER DISTRIBUTION LIM BASES HEAT FLUX HOT CHANNEL FACTO AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continued c, The control rod insertion limits of Specifications 3. 1.3.5 and 3.1.3.6 are maintained; and

d. The axial power distribution, expressed in terms of AXIAL FLUX DIFFERENCE, is maintained within the limits. (~~

F<<will be maintained within its limits provided Conditions a. through d.

a ve are maintained. he combination o measured RCS ow rate an HERMAL POWER must e maintained within the regions of permissible or restricted operation as shown in Figure 3.2-3 to ensure that the combination of RCS flow rate and THERMAL POWER are within the ranges considered in the mechanical and safety analyses and, along with the measurement of F<<, to ensure that the calculated DNBR will not be below the design DNBR value. The relaxation of F<< as a function of THERMAL POWER when in the region of permissible operation allows changes in the radial power shape for all permissible rod insertion limits.

cq) pm)()'~keg For the FSAR Chapter 15 analyses reliant on the Power Rang Neu ron ux-High Trip Setting trip function, reduction centa e as the required power reduction RCS flow rate) ensures DNBR mar in is maintained.

re f the int 3.2-3 1.5% RTP er 1%

When in t e region o restricted 'operation, e sn>ng 5 ~ as e equlva ent 5T at 100% RTP and

[293,540 gpm x (1.0 + C,)] (which includes measurement uncertainty for core flow) results in an effective OTQT setpoint reduction and maintains DNBR margins for those analyses reliant upon the OTQT trip. The additional restrictions on F<< when in the region of restricted operation ensure that the margins gained by the power and setpoint reductions are not reduced by the normally allowable increases in radial peaking at reduced power levels When an F<< measurement is taken, an allowance for measurement error must be applied prior to comparing to the F~~ limit(s) specified in the CORE OPERATING LIMITS REPORT (COLR). An allowance of 4% is appropriate for a full-core map taken with the Incore Detector Flux Mapping System.

Margin is maintained between the safety analysis limit DNBR and the design limit DNBR. The margin is more than sufficient to offset any rod bow penalty and transition core penalty.

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

allowance is appropriate for manufacturing tolerance.

The hot channel factor F (E) is measured periodically and increased by a cycle and height dependent power factor V(Z) to provide assurance that the SHEARON HARRIS - UNIT 1 B 3/4 2-4 Amendment No. 50

POWER DISTRIBUTION LI S BASES HEAT FLUX HOT CHANNEL FACTO AND RCS FLOW RATE AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continued limit on the hot channel factor, Fo(Z), is met. V(Z) accounts for the effects of normal operation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. The V(Z) function is specified in the COLR.

Deleted a) Deleted b) Deleted c) Deleted When RCS flow rate is measured, no additional allowance is necessary prior to comparison with the limit of Specification 3.2.3. A normal RCS flowrate error of 2. 1% will be included in C which will be modified as discussed below.

The measurement error for RCS total flow rate is based upon performing a precision heat balance and using the result to calibrate the RCS flow rate indicators', Pot'ential.fouling of the feedwater venturi which might not be detected could bias. the result from the precision heat balance in a non-conservative manners Therefore, a penalty of 0. 1% for undetected fouling of the feedwater venturi, raises the nominal flow measurement allowance, C to 2.2% for no venturi fouling. Any fouling which might bias the RCS flow rate measurement greater than 0. 1% can be detected by monitoring and trending various plant performance parameters. If detected, action shall be taken before performing subsequent precision heat balance measurements, i.e., either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.

The upper limit on measured RCS flow rate in Figure 3.2-3

[321,300 gpm x (1.0 - C,)] protects the mechanical design flow of 321,300 gpm per FSAR Table 5.1.0-1.

The 12-hour periodic surveillance of indicated RCS flow is sufficient to detect only flow degradation that could lead to operation outside the acceptable region of operation.

p,~Neck <<

SHEARON HARRIS - UNIT 1 8 3/4 2-5 HNP-97-025 February (6), 1997

POWER DISTRIBUTION LI BASES 3 4.2.4 UADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during STARTUP testing and periodically during power operation.

The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A limiting tilt of 1.025 can be tolerated before the margin for uncertainty in Fo is depleted. A limit of 1.02 was selected to provide an allowance for the uncertainty associated with the indicated power tilt.

The 2-hour time allowance for operation with a tilt condition greater than 1.02 but less than 1.09 is provided to allow identification and correction of a dropped or misaligned control rod. In the event such action does not correct the tilt, the margin for uncertainty on Fo is reinstated by reducing the maximum allowed power by 3% for each percent of tilt in excess of l.

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is done with"a full incore flux map or two sets of four symmetric thimbles. The preferred sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, E-5, E-ll, H-3, H-13, L-5, L-ll, N-8. If other locations must be used, a special report to NRC should be submitted within 30 days in accordance with 10CFR50,4.

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 that is equal to or greater than the design DNBR value throughout each analyzed transient. The indicated T,, value and the indicated pressurizer pressure value are compared to analytical limits of 586. 1'F and 2185 psig, respectively, after an allowance for measurement uncertainty is included.

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

pmc41 cnk Ne gd>

SHEARON HARRIS - UNIT 1 B 3/4 2-6 HNP-96-014 February 8, 1996

Insert "A" When RCS flow rate is measured, an additional allowance is necessary prior to comparison with the limit of Specification 3.2.5.c. Specifically for the precision calorimetric heat balance, a normal RCS flow rate error of 2.1% will be included.

Potential fouling of the feedwater venturi, which might not be detected, could bias the result from the precision heat balance in a non-conservative manner. Therefore, a penalty of 0.1% for undetected fouling of the feedwater venturi, raises the nominal flow measurement allowance to 2.2% for no venturi fouling. Any fouling which might bias the RCS flow rate measurement greater than 0.1% can be detected by monitoring and trending various plant parameters. Ifdetected, action shall be taken before performing subsequent precision heat balance measurements, i.e. either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.

Insert "B" Surveillance 4.2.5.1 ensures that temperature and pressure parameters, through instrument readout, are restored within their respective limits following load changes and other expected transient operation. The periodic surveillance of indicated RCS fiow is intended to detect flow degradation.

Sur veillance 4.2.5.2 allows entry into MODE 1, without having performed the surveillance, and placement of the unit in the best condition for performing the surveillance. Measurement of RCS flow rate by performance of a precision calorimetric heat balance allows the installed RCS flow instrumentation to be calibrated and verifies that the actual RCS flow rate is greater than or equal to the minimum required RCS flow rate. The frequency of 18 months reflects the importance of verifying flow following a refueling outage, where work activities were performed that could affect RCS flow.

Performance of a precision calorimetric at other times are unnecessary unless changes were introduced that would substantially reduce RCS flow and are likely to produce non-conservative results. The surveillance requirement to perform the precision calorimetric within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> aAer exceeding 95% RTP is intended to stress the importance of collecting plant flow data as soon as practical after reaching a stable power level that is sufficient for performing the test and in recognition that some plants have experienced feedwater venturi fouling and other phenomena that are more probable as time elapses. If the precision calorimetric data can not be collected in the required time period, it is necessary to reduce power to less than 95% RTP until preparations are complete for collecting precision calorimetric data. Reducing power to less than 95%, resets the allowable time period requirement to perform the precision calorimetric within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 95% RTP.

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4. 2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE 3/4 2-1 FIGURE 3.2-1 (DELETED) 3/4 2-4 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F()(Z) 3/4 2-5 FIGURE 3.2-2 (DELETED) 3/4 2-8 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 3/4 2-9 )

FIGURE 3.2-3 (DELETED) 3/4 2-10b I 3/4.2.4 QUADRANT POWER TILT RATIO . 3/4 2-11 3/4.2.5 DNB PARAMETERS . 3/4 2-14 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION 3/4 3-2 TABLE 3.3-2 (DELETED) 3/4 3-9 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-11 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-16 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 3/4 3-18 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 3/4 3-28 TABLE 3.3-5 (DELETED) 3/4 3-37 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-41 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring For Plant Operations 3/4 3-50 SHEARON HARRIS - UNIT 1 Amendment No.

TABLE 2.2-1 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS TOTAL SENSOR ALLOWANCE ERROR FUNCTIONAL UNIT ~TA Z ~S TRIP SETPQINT ALLOWABLE VALUE

1. Manual Reactor Trip N.A. N.A N.A. N.A.

2. Power Range, Neutron Flux

a. High Setpoint 7.5 4.56 0 ~ 109K of RTP ( 111.1C of RTP

b. Low Setpoint 8.3 4.56 0 ~ 25K of'TP" ( 27.1% of'TP

3. Power Range, Neutron 1.6 0.5 0 ~ 5R of RTP with ~ 6.3K of RTP with Flux. High Positive Rate a time constant a time constant

~ 2 seconds, o 2 seconds

4. Power Range. Neutron 1.6 0.5 0 c 5K of RTP with ~ 6.3g of RTP with Flux, High Negative Rate a time constant a time constant

~ 2 seconds ~ 2 seconds

5. Intermediate Range, 17.0 8.41 0 c 25K of RTP ~ 30.94 of RTP Neutron Flux

6. Source Range, Neutron 17.0 10.01 0 < 105 cps ~1.4 x 10'ps Flux

7. Overtemperature hT 8.7 6.02 Note 5 See Note 1 See Note 2

8. Overpower hT 4.7 1.50 1.9 See Note 3 See Note 4

9. Pressurizer Pressure-Low 5.0 2.21 1.5 w 1960 psig ~ 1946 psig

10. Pressurizer Pressure-High 7.5 5.01 0.5 c 2385 psig ~ 2399 psig

11. Pressurizer Water Level- 8.0 2.18 1.5 c 92K of instrument ~ 93.8l of instrument High span span RTP = RATED THERMAL POWER

TABLE 2.2-1 Continued TABLE NOTATIONS NOTE 3: (Continued)

K6 0.0021'F for T > T" and K, = 0 for T ~ T",

As defined in Note 1, Indicated T,, at RATED THERMAL POWER (Calibration temperature for hT instrumentat~ion. c 580.8'F),

S As defined in Note 1, and f,(EI) = 0 for all EI.

NOTE 4: The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than 2.3l hT span.

NOTE 5: The sensor error for temperature is 1.9 and l. 1 for pressure.

NOTE 6: The sensor error for steam flow is 0.9, for feed flow is 1.5, and for steam pressure is 0.75.

POWER DISTRIBUTION LIM 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR F~Z LIMITING CONDITION FOR OPERATION 3.2.2 F~(Z) shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

ACTION:

With F~(Z) exceeding its limit

a. Reduce THERMAL POWER at least lK for each 1X F~(Z) exceeds the limit within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; subsequent POWER OPERATION may proceed provided the Overpower GT Trip Setpoints have been reduced at least lX for each 1K F~(Z) exceeds the limit.

b. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced limit required by ACTION a., above; THERMAL POWER may then be increased provided F~(Z) is demonstrated through incore mapping to be within its limit.

SHEARON HARRIS - UNIT 1 3/4 2-5 Amendment No.

POWER DISTRIBUTION L S 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIHITING CONDITION FOR OPERATION 3.2.3 F,shall be within the limits specified in the COLR.

APPLICABILITY: NODE 1.

ACTION:

a. With F<< outside the limits given in 3.2.3:

1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

a) Restore F<< to within the limits given in 3.2.3, or b) Reduce THERNL POWER to less than 50'f RATED THERNL POWER to less and, reduce Power Range Neutron Flux Trip setpoints than or equal to 55K of RATED THERNL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

SHEARON HARRIS - UNIT 1 3/4 2-9 Amendment No.

4 POWER DISTRIBUTION LI S 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR LIMITING CONDITION FOR OPERATION ACTION Continued

2. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of F, initially being outside the limits of 3.2.3, verify through incore flux mapping that F>> is within the limits given in 3.2.3.

3. Subsequent POWER OPERATION may proceed provided that F, is demonstrated through incore flux mapping to be within acceptable limits prior to exceeding the following THERMAL POWER levels*:

a) 50K RATED THERMAL POWER b) 75K RATED THERMAL POWER c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of attaining greater than or equal to 95K RATED THERMAL POWER With the requirements of ACTION 3.2.3.a not met, reduce THERMAL POWER to less than 5X of RATED THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

• THERMAL POWER does not have to be reduced to comply with this ACTION.

SHEARON HARRIS - UNIT 1 3/4 2-10 Amendment No.

~'

~

POWER DISTRIBUTION L S 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 F<< shall be determined to be within acceptable limits:

Prior to operation above 75K of RATED THERNL POWER after each fuel loading, and

b. At least once per 31 Effective Full Power Days thereafter.

SHEARON HARRIS - UNIT 1 3/4 2-10a Amendment No.

Figure 3.2-3 Deleted SHEARON HARRIS - UNIT 1 3/4 2-10b Amendment. No.

lt POWER DISTRIBUTION L IM S v 3/4 2.5 DNB PARAMETERS LIMITING CONDITION FOR OPERATION 3.2.5 The following DNB-related parameters shall be maintained within the following limits:

a. Reactor Coolant System T,, ~ 586. 1'F after addition for instrument J uncertainty, and Pressurizer Pressure ~ 2185 psig after subtraction for instrument uncertainty. and [

c. RCS total flow rate > 293,540 gpm after subtraction for instrument uncertainty. (

APPLICABILITY: MODE 1.

ACTION:

With any of the above parameters not within its specified limit, restore the parameter to within its limit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce THERMAL POWER to less than 5X of RATED THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.2.5.1 Each of the parameters shown in Specification 3.2.5 shall be verified to be within its limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. /

4.2.5.2 Verify, by precision heat balance, that RCS total flow rate is within its limit at least once per 18 months.~ J This limit is not applicable during either a THERMAL POWER Ramp in excess of +5K RATED THERMAL POWER per minute or a THERMAL POWER step change in excess of +10K RATED THERMAL POWER.

Required to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after > 95K RATED THERMAL POWER.

SHEARON HARRIS - UNIT 1 3/4 2-14 Amendment No.

POWER DISTRIBUTION LI BASES 3/4.2.2 AND 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR The limits on heat flux hot channel factor and enthalpy rise hot channel factor ensure that: (1) the design limits on peak local power density and minimum DNBR are not exceeded and (2) in the event of a LOCA the peak tuel clad temperature will not exceed the 2200'F ECCS acceptance criteria limit F, is not directly measurable but is inferred from a power distribution map obtained with the movable incore detector system. F<< and F~(Z) will normally only be determined periodically as specified in Specifications 4.2.2 and 4.2.3. This periodic surveillance is sufficient to ensure that the limits are maintained provided:

Control rods in a single group move together with no individual rod insertion differing by more than + 12 steps, indicated, from the group demand position;

b. Control rod groups are sequenced with over lapping groups as described in Specification 3. 1.3.6; SHEARON HARRIS - UNIT 1 B 3/4 2-2a Amendment No.

POWER DISTRIBUTION L S BASES HEAT FLUX HOT CHANNEL FACTOR NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR I

~Cti d

c. The control rod insertion limits of Specifications 3. 1.3.5 and 3.1.3.6 are maintained; and

d. The axial power distribution, expressed in terms of'XIAL FLUX DIFFERENCE, is maintained within the limits.

F, will be maintained within its limits provided Conditions. a. through d.

above are maintained.

For the FSAR Chapter 15 analyses reliant on the Power Range Neutron Flux-High Trip Setting trip function, reduction of the Setpoint by approximately the same percentage as the required power reduction ensures DNBR margin is maintained.

When an F, measurement is taken, an allowance for measurement error must be applied prior to comparing to the F,"" limit(s) specified in the CORE OPERATING LIMITS REPORT (COLR). An allowance of 4K is appropriate for a full-core map taken with the Incore Detector Flux Mapping System.

Margin is maintained between the safety analysis limit DNBR and the design limit DNBR. The margin is more than sufficient to offset any rod bow penalty and transition core penalty.

When an F~ measurement is taken, an allowance for both experimental error and manufacturing tolerance must be made. An allowance of 5X is appropriate for a full-core map taken with the Incore Detector Flux Mapping System, and a'X allowance is appropriate for manufacturing tolerance.

The hot channel factor FQ~(Z) is measured periodically and increased by a cycle and height dependent power factor V(Z) to provide assurance that the SHEARON HARRIS - UNIT 1 B 3/4 2-4 Amendment No.

lib)

~ 'OWER DISTRIBUTION LI BASKS HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR Continued limit on the hot channel factor, F~(Z), is met. V(Z) accounts for the effects of normal oper ation transients and was determined from expected power control maneuvers over the full range of burnup conditions in the core. The V(Z) function is specified in the COLR.

SHEARON HARRIS - UNIT 1 B 3/4 2-5 Amendment No.

POWER DISTRIBUTION L S BASES 3/4.2.4 UADRANT POWER TILT RATIO The QUADRANT POWER TILT RATIO limit assures that the radial power distribution satisfies the design values used in the power capability analysis. Radial power distribution measurements are made during STARTUP testing and periodically during power operation.

The limit of 1.02, at which corrective action is required, provides DNB and linear heat generation rate protection with x-y plane power tilts. A limiting tilt of 1.025 can be tolerated before thetomargin for uncertainty in FG is an allowance for the depleted. A limit of 1.02 was selected provide uncertainty associated with the indicated power tilt.

The 2-hour time allowance for operation with a tilt condition greater than identification and correction of=-

1.02 but less than 1.09 is provided to allow a dropped or misaligned control rod. In the event such action does not correct the tilt, the margin for uncertainty on F, is reinstated by reducing the maximum allowed power by 3X for each percent of tilt in excess of l.

For purposes of monitoring QUADRANT POWER TILT RATIO when one excore detector is inoperable, the movable incore detectors are used to confirm that the normalized symmetric power distribution is consistent with the QUADRANT POWER TILT RATIO. The incore detector monitoring is done with a full incore flux map or two sets of four symmetric thimbles. The preferred sets of four symmetric thimbles is a unique set of eight detector locations. These locations are C-8, E-5. E-ll, H-3, H-13. L-5. L-11, N-8. If other locations must be used, a special report to NRC should be submitted within 30 days in accordance with 10CFR50.4.

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 that is equal to or greater than the design DNBR value throughout each analyzed transient. The indicated T,, value and the indicated pressurizer pressure value are compared to analytical limits of 586. 1 F and 2185 psig, respectively, after an allowance for measurement uncertainty is included.

When RCS flow rate is measured, an additional allowance is necessary prior to comparison with the limit of Specification 3.2.5.c. Specifically for the recision calorimetric heat balance, a normal RCS flow rate error of 2. 1X will e included.

Potential fouling of'he feedwater venturi, which might not be detected, could bias the result from the precision heat balance in a non-conservative manner.

Therefore, a penalty of 0. ll for undetected fouling of the feedwater venturi, raises the nominal flow measurement allowance to 2.2X for no venturi fouling.

Any fouling which might bias the RCS flow rate measurement greater than 0.1X can be detected by monitoring and trending various plant parameters.

SHEARON HARRIS - UNIT 1 B 3/4 2-6 Amendment No.

POWER DISTRIBUTION LI BASKS 3/4.2.5 DNB PARAMETERS Continued If detected, action shall be taken before performing subsequent precision heat balance measurements, i.e. either the effect of the fouling shall be quantified and compensated for in the RCS flow rate measurement or the venturi shall be cleaned to eliminate the fouling.

Surveillance 4.2.5. 1 ensures that temperature and pressure parameters, through instrument readout, are restored within their respective limits following load changes and other expected transient operation. The periodic surveillance of indicated RCS flow is intended to detect flow degradation.

Surveillance 4.2.5.2 allows entry into MODE 1, without having performed the surveillance. and placement of the unit in the best condition for performing the surveillance. Measurement of RCS flow rate by performance of a precision calorimetric heat balance allows the installed RCS flow instrumentation to be calibrated and verifies that the actual RCS flow rate is greater than or equal to the minimum required RCS flow rate. The frequency of 18 months reflects the importance of verifying flow following a refueling outage. where work activities were performed that could affect RCS flow. Performance of a precision calorimetric at other times are unnecessary unless changes were introduced that would substantially reduce RCS flow and are likely to produce non-conservative results. The surveillance requirement to perform the precision calorimetric within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 95K RTP is intended to stress the importance of collecting plant flow data as soon as practical after reaching a stable power level that is sufficient for performing the test and in recognition that some plants have experienced feedwater venturi fouling and other phenomena that are more probable as time elapses. If the precision calorimetric data can not be collected in the required time period, it is necessary to reduce power to less than 95K RTP until preparations are complete for collecting precision calorimetric data. Reducing power to less than 95K, resets the allowable time period requirement to perform the precision calorimeter within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 95K RTP.

SHEARON HARRIS - UNIT 1 B 3/4 2-6a Amendment No.