Text

Proposed Tech Specs 3.1.1.2 Re Relocating Shutdown Margin Vs Boron Concentration Curve to COLR
	ML18022A949
Person / Time
Site:	Harris
Issue date:	02/06/1995
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML18022A948	List: ML18022A947; ML18022A949;
References
	HNP-95-016, HNP-95-16, NUDOCS 9502160361
	Download: ML18022A949 (30)
	v • d • e

INDEX 3.0/4.0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4 ' APPLICABILITY..~ ~ oe ~ ~ o ~ ~ ~ ~ 'o.o........ ~ ..o ~ ~ ~ .o ~ o ~ oo ~ . ~ oo. ~ o 3/4 0-1 3/4el REACTIVITY CONTROL SYSTEMS 3/4 ~ 1 ~ 1 BORATION CONTROL Shutdown Margin - MODES 1 and 2. ~ ~ .. ~ . ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ,...,. 3/4 1-1 Shutdown Margin - MODES 3, 4, and 5...................... 3/4 1-3 FIGURE 3.1-1 UT WN GIN ERS RCS ORON CONC TRAT N M ES 4 D 5 ~ ~ ~ ~ ~ o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 1-3a p(O) Moderator Temperature Coeffxcxent........................ 3/4 1-4

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Mxnxmum Temperature for Crxticalxty. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ .. 3/4 1-6 3/4.1 ~ 2 BORATION SYSTEMS Flow Pa'th Shutdown o ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 1-7 Flow Paths - Operatxngo.e....oo....o....o.woo,.woo..oo... 3/4 1-.8 Charging Pump >> Shutdown................................. 3/4 1-9 Charging Pumps Operating............................... 3/4 1"10 Borated Water Source - Shutdown.......................... 3/4 1-11 Borated Water Sources - Operating........................ 3/4 1"12 3/4+1.3 MOVABLE CONTROL ASSEMBLIES Group Helght ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ot ~ ~ ~ ~ 3/4 '1"14 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE ROD. ~ . ~ o ~ ~ o ~ ~ ~ o ~ ~ o ~ o.ohio. ~ ~ o.o... 3/4 1-16 Position Indication Systems - Operating. ~ .. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 1-17 Position Indication System Shutdown... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 1-18 m~

Rod Drop Tlmeo ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 1"19 Shutdown Rod Insert@on Lamxt.............................

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3/4 1-20 Control Rod Insertion Laments......... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 1-21 FIGURE 3.1-2 (DELETED) . ~ ~ ~ ~ ~ ~ . . . ..

~ ~ ~ ~ ~ ~ ~ .. ~ ~ ~ ~ ~ ~ ~ . ~ ~ ~ ~ ~ ~ ~ ~ ~ o... ~ 3/4 1-22 SHEARON HARRIS - UNIT 1 LU Amendment No. g, ]5 95021603'6i 950206 PDR ADOCK 05000400 P PDR

REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - MODES 3 4, AND 5 LIMITING CONDITION FOR OPERAT10N 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to the limit~o~@

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APPLICABILITY: MODES 3, 4, AND 5. gg~ys'pkp7RY (C0<RQJ pkAITpgoa'C/uN PZ~-/0W.

ACTION:

With the SHUTDOWN MARGIN less than the required value imnediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE RE UIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the required value:

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter whil'e the rod(s) is inoperable.

If the inoperable control rod is ilmsovabl.c or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the iamovable or untrippable control rod(s); and

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1) Reactor Coolant System boron concentration,

2) Control rod position,

3) Reactor Coolant System average temperature,

4) Fuel burnup based on gross thermal energy generation,

5) Xenon concentration, and

6) Samarium concentration.

SHEARON HARRIS - UNIT 1 3/4 1-3 Amendment No. 7

(2600,7700

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~ye~'ODES (2600 ,2600)

NODE 3, NODE 4 3 I 4

IT LEAST ONE IN OPERATION (Isoo,l170)

(350,100 0.4 0.8 1.2 1.6 2 2.4 2.8 (Thousands)

REQUJRED RCS BORON CONCENTRATiON pm Applicable to Node 4, with or without RCPs in operation FIGURE 3.1-1 SHUTDOWN MARGIN VERSUS RCS BORON CONCENTRATION MODES 3, 4 AND 5/DRAINED

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Sheet A FIGURE 3.1-1 SHUTDOWN MARGIN VERSUS RCS BORON CONCENTRATION MODES 3 4 AND 5/DRAINED This figure is deleted from Technical Specifications and is controlled by the CORE OPERATING LIMITS REPORT, plant procedure PLP-106.

SHEARON HARRIS - UNIT I 3/4 I-3a Amendment No.

REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following three boron injection flow paths shall be OPERABLE:

a. The flow path from the boric acid tank via a boric acid transfer pump and a charging/safety injection pump to the Reactor Coolant System (RCS), and

b. Two flow paths from the refueling water storage tank via charging/

safety injection pumps to the RCS.

APPLICABILITY: MODES 1, 2, and 3. SPEc+t I ppg 0 Ffg7f>cr Lgwx7$

ACTION: ggpg~ (Qaggg phd~~~ / 0 With only one of the'bove required boron injection flow paths to the RCS OPERABLE, restore at least two boron injection flow paths to the RCS to OPERABLE status within 72 hours or b in at, least HOT STANDBY and borated to a SHUTDOWN MARGIN as r u ed ur . at 200'F within the next 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sT restore at least two flow paths to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE RE UIREMENTS 4.1.2.2 At least two of the above required f'low paths shall be demonstrated OPERABLE:

a ~ At least once per 7 days by verifying that the temperature of the flow path between the boric acid tank and the charging/safety injec-tion pump suction header tank is greater than or equal to 6S'F when a flow path from the boric acid tank is used;

b. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position;

c. At least once per 1& months during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal> and

d. At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2a. delivers at least 30 gpm to the RCS.

SHEARON HARRIS - UNIT 1 3/4 1"8 Amendment No. 7> 36

REACTIVITY CONTROL SYSTEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3, 1'.2.4 At least two charging/safety injection pumps shall be OPERABLE.

APPLICABILITY: MODES i, 2, and 3.

ACTION:

With only one charging/safety injection pump, OPERABLE, restore at least two charging/safety injection pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN as u d r ~ at 200'F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging/safety injection pumps to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 'URVEILLANCE RE UIREMENTS 4.1.2.4 At least two charging/safety injection pumps shall be demonstrated OPERABLE by verifying, on recirculation flow or in service supplying flow to the Reactor Coolant System and reactor coolant pump seals, that a differential pressure across each pump of greater than or equal to 2446 psid is developed when tested pursuant to Specification 4.0.5.

sp~~ i~ iw e4 COe Ppsu~r/WS WmJ 7sRE'WW (Cosy~, pz >pwczt~w pZp-Jgd SHEARON HARRIS - UNIT 1 3/4 1-10 Amendment No. 7, 36

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REACTIVITY CONTR SYSTEMS BORATED WATER SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 As a minimum, the following borated water source(s) shall be OPERABLE as required by Specification 3.1.2.2:

a. The boric acid tank with:

A minimum contained borated water volume of 24,150 gallons, which is ensured by maintaining indicated level of greater than or equal to 74%,

2~ A boron concentration of between 7000 and 7750 ppm, and 3 ~ A minimum solution temperature of 65'F.

b. The refueling water storage tank (RWST) with:

A minimum contained borated water volume of 436,000 gallons, which is equivalent to 92'4 indicated level.

2. A boron concentration of between 2400 and 2600 ppm, 3 ~ A minimum solution temperature of 40'F, and

4. A maximum solution temperature of 125'F.

APPLICABILITY MODES 1, 2, 3, and 4.

ACTION:

a~ With the boric acid tank inoperable and being used as one of the above required borated water sources, restore the boric acid tank to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN~

e ir b Fi re .1-1 at 200'F; restore the boric acid tank to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With the RWST inoperable, restore the tank to OPERABLE status within 1 hour or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

~pcogsz'g ~~ +i@ CO/Pg gPE+g f5' 4g~+F4 E~WIV (~~ /go p4ee7'p~cs JJgg PgP gpss SHEARON HARRIS UNIT 1 3/4 1-12 Amendment No. 30

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ADMINISTRATIVE ROLS 6.9.1.6 CORE OPERATING LIMITS REPORT 6.9. 1.6. 1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106, prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the fol 1 owing:

4g. Moderator Temperature Coefficient Positive and Negative Limits and 300 ppm surveillance limit for Specification 3/4. 1. 1.3, cP. Shutdown Bank Insertion Limits for Specification 3/4. 1.3.5, Control Bank Insertion Limits for Specification 3/4. 1.3.6, e, )f. Axial Flux Difference Limits for Specification 3/4.2. 1, gP'. Heat Flux Hot Channel Factor, F,"", K(Z), and V(Z) for Specification 3/4.2.2, Enthalpy Rise Hot Channel Factor, F~R", and Power Factor Multiplier, PF~ for Specification 3/4.2.3.

h g/. Boron Concentration for .Specification 3/4.9.1.

6.9. 1.6.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC at the time the reload analyses are performed, and the approved revision number shall be identified in the COLR.

a. XN-75-27(A), latest Revision and Supplements, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," Exxon Nuclear Company, Richland WA 99352..

(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits,, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor, and 3.9. 1 - Boron Concentration).

b. ANF-89-151(A), latest Revision, "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events,"

Advanced Nuclear Fuels Corporation, Richland WA 99352.

(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

c~ XN-NF-82-21(A), latest Revision, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,"

Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

SHEARON HARRIS - UNIT 1 6-24 Amendment No. 44

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Statement 1

a. SHUTDOWN MARGIN limits for Specification 3/4.1.1.2, Statement 2 3.1.1.2 - SHUTDOWN MARGIN - MODES 3, 4 AND 5,

ADMINISTRATIVE ROLS 6.9.1.6 CORE OPERATING LIMITS REPORT (Continued)

h. ANF-88-054(A), latest Revision, "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2," Advanced Nuclear Fuels Corporation, Richland WA 99352.

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(Methodology for Specification 3.2. 1 - Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor).

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",

July 1985 (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor fJ and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

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j. WCAP-10266-P-A, Rev. 2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).

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

k. WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", January 1990 (W Proprietary).

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

EMF-92-081(A), latest Revision and Supplements, "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors,"

Siemens Power Corporation, Richland WA 99352.

4 (Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

m. EMF-92-153(A), latest Revision and Supplements, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"

Siemens Nuclear Power Corporation, Richland WA 99352.

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

XN-NF-82-49(A), latest Revision and Supplements, "Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

SHEARON HARRIS - UNIT 1 6-24b Amendment No. 44

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3/4.1 REACTIVZrt CONTROL SVSTEMS BASES 3/4. 1 ~ 1 BORATION CONTROL 3/4.1 ~ 1.1 and 3/4.1. L~2 SHUTDOWN MARGIN A sufficieat SHUTDOWN MARCIN ensures that: (1) thc reactor can be made sub-critical from all operating conditions, (2) the reactivity transients associated with postulated accident conditions are controllable within acceptable Limits, and (3) 'the reactor vill be maintained sufficiently subcziticaL to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS Tavg. In MODES 1 and 2 the most restrictive condition occurs at EOL, with T at no Load operating temperature, aad is associated with a postufa(cd steam Line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a, minimum SHUTDOWN MARCIN of 1770 pcm is required to control the reactivity transient. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limitiag condition and i.s consistent with FSAR-safety analysis assumptions.

In MODES 3, 4, aad 5, the most. restrictive condition occurs at BOL, when the boron concentration is the greatest. In these modes, thc requizcd SHUTDOWN MARGIN is composed of a constant requircmcat and a variable requirement, which, is a function of the RCS boron concentration. The constant SHUTDOWN MARGIN requirement is based on an uncontrolled RCS cooldown from a steamline break accident, as is the case for MODES 1 and 2. The variable SHUTDOWN MARGIN rcquiremcnt is based oa thc results of boron dilution accident analyses, where the SHUTDOWN MARGIN is varied as a function of RCS boron concentration, to guarantee a minimum of 15 minutes for operator action prior to a lass of SHUTDOWN MARCIN>>

r ~ 1 must be used with a curve giving the required shutdown boron concentrations for various temperatures as a function of coze burnup. This cycL'e dcpcadeat relationship is provided for each cycle in the plant Curve Book. From the Curve Bookl a required boron concentration that will provide adequate SHUTDOWN MARCZN can be determined and this concentration may be used to enter e . 1 to determine the specific required SHUTDOWN MARGIN for that conditions The boron dilutioa analysis assumed a conmon RCS volume aad dilution flow rate for MODES 3 and 4, which differed fzom the voLume aad flow rate assumed for MODE 5 aaalysis ~ The MODE 5 conditions assumed limited mixing in the RCS and cooLing with the RHR system only. Ia MODES 3 and 4, it was assumed that at least one reactor coolaat pump was operating. If at least one reactor coolant pump is not operating in MODE 4, then the SHUTDOWN MARGIN requirements for MODE 5 shall apply, provided that the dilution flow rate assumed ia the MODE 5 Boron Dilhtion analysis is not excecdect.

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SHEARON HARRIS - UNIT 1 B 3/4 1-1 Amendment No. 7

~g INDEX

3. 0/4. 0 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4. 0 APPLICABILITY 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4. 1. 1 BORATION CONTROL Shutdown Margin - MODES 1 and 2 3/4 1-1 Shutdown Margin - MODES 3, 4, and 5 . 3/4 1-3 FIGURE 3. 1-1 (DELETED) . 3/4 1-3a (

Moderator Temperature Coefficient . . . . . . . . . 3/4 1-4 Minimum Temperature for Criticality... 3/4 1-6 3/4.1. 2 BORATION SYSTEMS Flow Path - Shutdown 3/4 1-7 Flow Paths - 3/4 1-8 Operating Charging Pump - Shutdown 3/4 1-9 Charging Pumps - Operating . 3/4 1-10 Borated Water Source - Shutdown . . . . . . . . . 3/4 1-11 Borated Water Sources -

Operating . . . . . . . . . . . . 3/4 1-12 3/4.1.3 HOVABLE CONTROL ASSEMBLIES Group Height . 3/4 1-14 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE ROD . 3/4 1-16 Position Indication Systems - Operating ~ . . . . . . . . 3/4 1-17 Position Indication System - Shutdown . ~ . . . 3/4 1-18 Rod Drop Time........ 3/4 1-19 Shutdown Rod Insertion Limit ~ ~ 3/4 1-20 Control Rod Insertion Limits . 3/4 1-21 FIGURE 3. 1-2 (DELETED) ~ ~ ~ ~ ~ ~ ~ . 3/4 1-22 SHEARON HARRIS - UNIT 1 1V Amendment No.

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REACTIVITY CONTRO STEMS SHUTDOWN MARGIN - MODES 3 4 AND 5 LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to the limit specified in the CORE OPERATING LIMITS REPORTS (COLR), plant procedure PLP-106.

APPLICABILITY: MODES 3, 4, AND 5.

ACTION:

With the SHUTDOWN MARGIN less than the required value immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the required value:

a. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable control rod(s) and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod(s) is inoperable. If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod(s); and

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideration of the following factors:

1) Reactor Coolant System boron concentration,

2) Control rod position,

3) Reactor Coolant System average temperature,

4) Fuel burnup based on gross thermal energy gener ation,

5) Xenon concentration, and

6) Samarium concentration.

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

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t FIGURE 3.1-1 SHUTDOWN MARGIN VERSUS RCS BORON CONCENTRATION MODES 3 4 AND 5/DRAINED This figure is deleted from Technical Specifications and is controlled by the CORE OPERATING LIMITS REPORT, plant procedure PLP-106.

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

REACTIVITY CONTRO STEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following three boron injection flow paths shall be OPERABLE:

a. The flow path from the boric acid tank via a boric acid transfer pump and a charging/safety injection pump to the Reactor Coolant System (RCS), and

b. Two flow paths from the refueling water storage tank via charging/

safety injection pumps to the RCS.

APPLICABILITY: MODES 1, 2, and 3.

ACTION With only one of the above required boron injection flow paths to the RCS OPERABLE, restore at least two boron injection flow paths to the RCS to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN as specified in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106 at 200 F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two flow paths to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 6 hours.

SURVEILLANCE REQUIREMENTS 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying that the temperature of the flow path between the boric acid tank and the charging/safety injection pump suction header tank is greater than or equal to 65 F when a flow path from the boric acid tank is used;

b. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; C. At least once per 18 months during shutdown by verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal; and At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2a. delivers at least 30 gpm to the RCS.

SHEARON HARRIS - UNIT 1 3/4 1-8 Amendment No.

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REACTI VITY CONTRO STEMS CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION

3. 1.2.4 At least two charging/safety injection pumps shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

With only one charging/safety injection pump OPERABLE, restore at least two charging/safety injection pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN as specified in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106 at 200'F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore at least two charging/safety injection pumps to OPERABLE status within the next 7 days or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.2.4 At least two charging/safety injection pumps shall be demonstrated OPERABLE by verifying, on recirculation flow or in service supplying flow to the Reactor Coolant System and reactor coolant pump seals, that a differential pressure across each pump of greater than or equal to 2446 psid is developed when tested pursuant to Specification 4.0.5.

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

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REACTIVITY CONTRO STEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 As a minimum, the following borated water source(s) shall be OPERABLE as required by Specification 3.1.2.2:

a. The boric acid tank with:

A minimum contained borated water volume of 24,150 gallons, which is ensured by maintaining indicated level of greater than or equal to 744,

2. A boron concentration of between 7000 and 7750 ppm, and 3 ~ A minimum solution temperature of 65'F.

b. The refueling water storage tank (RWST) with:

. A minimum contained borated water volume of 436,000 gallons, which is equivalent to 924 indicated level.

2. A boron concentration of between 2400 and 2600 ppm,

3. A minimum solution temperature of 40'F, and A maximum solution temperature of 125'F.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a. With the boric acid tank inoperable and being used as one of the above required borated water sources, restore the boric acid tank to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and borated to a SHUTDOWN MARGIN specified in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106 at 200'F; restore the boric acid tank to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. With the RWST inoperable, restore the tank to OPERABLE status within 1 hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SHEARON HARRIS - UNIT 1 3/4 1-12 Amendment No.

g4 0 e ~

ADMINISTRATIVE CO LS 6.9.1.6 CORE OPERATING LIMITS REPORT 6.9.1.6. 1 Core operating limits shall be established and documented in the CORE OPERATING LIHITS REPORT (COLR), plant procedure PLP-106, prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

a. SHUTDOWN MARGIN limits for Specification 3/4. 1. 1.2,

b. Moderator Temperature Coefficient Positive and Negative Limits and 300 ppm surveillance limit for Specification 3/4.1.1.3,

c. Shutdown Bank Insertion Limits for Specification 3/4.1.3.5,

d. Control Bank Insertion Limits for Specification 3/4. 1.3.6,

e. Axial Flux Difference Limits for Specification 3/4.2.1,

f. Heat Flux Hot Channel Factor, F~" , K(Z), and V(Z) for Specification 3/4.2.2,

g. Enthalpy Rise Hot Channel Factor, F

"" , and Power Factor Multiplier, PF~ for Specification 3)k.2.3.

h. Boron Concentration for Specification 3/4.9.1.

6.9.1.6.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC at %he time the reload analyses are performed, and the approved revision number shall be identified in the COLR,

a. XN-75-27(A). latest Revision and Supplements, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3. 1. 1.2 - SHUTDOWN MARGIN - MODES 3, 4 and 5, 3.1.1.3 - Moderator Temperature Coefficient, 3. 1.3.5-Shutdown Bank Insertion Limits, 3.1.3.6 - Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor, and 3.9.1 - Boron Concentration).

b. ANF-89-151(A), latest Revision, "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events," Advanced Nuclear Fuels Corporation, Richland WA 99352.

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

C. XN-NF-82-21(A), latest Revision, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

SHEARON HARRIS - UNIT 1 6-24 Amendment No.

~4 v)

I 4 I*

4g ADMINISTRATIVE CO LS 6,9.1.6 CORE OPERATING LIMITS REPORT (Continued)

h. ANF-88-054(A), latest Revision, "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2,"

Advanced Nuclear Fuels Corporation, Richland WA 99352.

(Methodology for Specification 3.2.1 - Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor).

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY", July 1985 (W Proprietary).

(Methodology for Specification 3.1.1.2 - SHUTDOWN HARGIN - MODES 3, 4 AND 5, 3.2.2 - Heat Flux Hot Channel Factor and 3.2.3-Nuclear Enthalpy Rise Hot Channel Factor).

A WCAP-10266-P-A, Rev. 2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).

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

k. WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", January 1990 (W Proprietary).

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

EHF-92-081(A), latest Revision and Supplements, "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors,"

Siemens Power Corporation, Richland WA 99352.

(Methodology for Specification 3. 1.1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6-Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

EHF-92-153(A), latest Revision and Supplements, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Nuclear Power Corporation, Richland WA 99352.

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

n. XN-NF-82-49(A), latest Revision and Supplements, "Exxon Nuclear Company Evaluation Model EXEH PWR Small Break Model," Exxon Nuclear Company, Richland WA 99352.

(Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

SHEARON HARRIS - UNIT 1 6-24b Amendment No.

3/4. 1 REACTIVITY ~ ROL SYSTEMS BASES 3/4.1. 1 BORATION CONTROL 3/4.1. 1.1 and 3/4. 1. 1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that: (1) the reactor can be made sub-critical from all operating conditions, (2) the reactivity'ransients associated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T,,. In MODES 1 and 2 the most restrictive condition occurs at EOL, with T., at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 1770 pcm is required to control the reactivity transient. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions.

In MODES 3, 4, and 5, the most restrictive condition occurs at BOL, when the boron concentration is the greatest. In these modes, the required SHUTDOWN MARGIN is composed of a constant requirement and a variable requirement, which is a function of the RCS boron concentration. The constant SHUTDOWN MARGIN requirement is based on an uncontrolled RCS cooldown from a steamline break accident, as is the case for MODES 1 and 2. The variable SHUTDOWN MARGIN requirement is based on the results of boron dilution accident analyses, where the SHUTDOWN MARGIN=is varied as a function of RCS boron concentration, to guarantee a minimum of 15 minutes for operator action prior to a loss of SHUTDOWN MARGIN.

In modes 3, 4, and 5, the figure specified in the CORE OPERATING LIMITS REPORT (COLR) must be used with a curve giving the required shutdown boron concentrations for various temperatures as a function of core burnup. This cycle dependent relationship is provided for each cycle in the plant Curve Book. From the Curve Book, a required boron concentration that will provide adequate SHUTDOWN MARGIN can be determined and this concentration may be used to enter the figure specified in the COLR to determine the specific required SHUTDOWN MARGIN for that condition.

The boron dilution analysis assumed a common RCS volume and dilution flow rate for MODES 3 and 4, which differed from the volume and flow rate assumed for MODE 5 analysis. The MODE 5 conditions assumed limited mixing in the RCS and cooling with the RHR system only. In MODES 3 and 4, least one it was assumed that at reactor coolant pump was operating. If at least one reactor coolant pump is not operating in MODE 4, then the SHUTDOWN MARGIN requirements for MODE 5 shall apply, provided that the dilution flow rate assumed in the MODE 5 Boron Dilution analysis is not exceeded.

SHEARON HARRIS - UNIT 1 8 3/4 1-1 Amendment No.

ML18022A949

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