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Proposed Tech Specs Adding Rod Bank Insertion Limits & K(Z) Curves to COLR
	ML17352A724
Person / Time
Site:	Turkey Point
Issue date:	07/19/1994
From:	; FLORIDA POWER & LIGHT CO.
To:	;
Shared Package
ML17352A723	List: ML17352A722; ML17352A724; ML17352A725; ML17352A726;
References
	NUDOCS 9407210322
	Download: ML17352A724 (27)
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ATTACHMENT 3 PROPOSED TECHNICAL SPECIFICATIONS Marked-up Technical Specifications Pages, iV V

3/4 1-17 3/4 1-26 3/4 1-27 3/4 2-4 3/4 2-5 3/4 2-7 3/4 2-9 6-20 B 3/4 1-4 B 3/4 2-7 PDR 2i0322 940719 P ADO'< 05000250 PDR

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREMENTS SECTION PAGE 3/4. 0 APPLICABILITY 3/4 0-1 3/4. 1 REACTIVITY CONTROL SYSTEMS 3/4. 1. 1 BORATION CONTROL Shutdown Margin - T avg Greater Than 200'F. 3/4 1" 1 FIGURE 3. 1-1 REQUIRED SHUTDOWN MARGIN VERSUS REACTOR COOLANT BORON CONCENTRATION.. 3/4 1-3 Shutdown Margin - T avg Less Than or Equal to 200~F.. 3/4 1-4 Moderator Temperature Coefficient 3/4 1-5 Minimum Temperature for Criticality.. 3/4 1-7 3/4. 1. 2 BORAT ION SYSTEMS Flow Path - Shutdown. . ~

3/4 1-8 Flow Paths - Operating............... 3/4 1"9 Charging Pumps - Operating. 3/4 1-11 Borated Water Source - Shutdown. 3/4 1-12 Borated Water Sources - Operating..., 3/4 1-14 Heat Tracing. 3/4 1-16 3/4. 1.3 MOVABLE CONTROL ASSEMBLIES Group Hei ght. 3/4 1"17 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH ROD................ 3/4 1-19 Position Indication Systems - Operating.... ~... ., .. ~ 3/4 1-20 TABLE 4.1-1 ROD POSITION INDICATOR SURVEILLANCE REQUIREMENTS. 3/4 1-22 Pos i ti on Indi cati on System

- Shutdown... 3/4 1-23 Rod Drop Time. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 3/4 1-24 Shutdown Rod Insertion Limit........................ 3/4 1-25 Control Rod Insertion Limits..... 3/4 1-26

. TURKEY POINT - UNITS 3 8 4 1V AMENDMENT NOS. l37AND l32

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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE RE UIREHENTS SECTION PAGE 3 4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE...................................... 3/4 2-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR.... 3 4 2-NHSIN-&~K-H~

3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR.................. 3/4 2-11 3/4.2.4 QUADRANT POWER TILT RATIO................................. 3/4 2-13 3/4.2.5 DNB PARAMETERS............ 3/4 2-16 3 4.3 INSTRUHENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUHENTATION....................... 3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION.................... 3/4 3-2 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE(UIREMENTS........................................... 3/4 3-8 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................................... 3/4 3-13 TABLE 3.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................................... 3/4 3-14 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS............................ 3/4 3-23 TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS................. 3/4 3-29 3/4.3. 3 MONITORING INSTRUMENTATION Radiation Monitoring For Plant Operations... 3/4 3-35 TURKEY POINT - UNITS 3 8. 4 AMENDMENT NOS. 156 AND 150

A>aa,yydlkt REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION

3. 1.3. 1 All full length (shutdown and control) rods shall be OPERABLE and positioned within + 12 steps (Analog Rod Position Indication) of the group step counter demand position within one hour after rod motion.

APPLICABILITY: MODES 1" and 2*

ACTION:

With one or more full length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement of Specification 3. l. 1. 1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With more than one full length rod inoperable or misaligned from the group step counter demand position by more than + 12 steps (Analog Rod Position Indication), be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , C. With one full length rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group step counter demand position by more than + 12 steps (Analog Rod Position Indication), POWER OPERATION may continue provided that within .

one hour either:

1. The rod is restored to OPERABLE status within the above alignment requirements, or I

2. The remainder of the rods in the bank with the inoperable rod are aligned to within + 12 steps of the inoperable rod while int i the rod sequence and insertion limits of the THERMAL POWER level shall be. restricted pursuan o pecification 3. 1.3.6 during subsequent operation, or

3. The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3. 1. 1, 1 is satisfied. POWER OPERATION may then continue provided that:

See Special Test Exceptions 3. 10.2 and 3. 10.3.

TURKEY POINT - UNITS 3 8; 4 3/4 1-17 AMENDMENT NOS. l37AND l32

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REACTIVITY CONTROL SYSTEMS

'" CONTROL ROD INSERTION LIMITS LIMITING CONDITION FOR OPERATION

. 1. 3. 6 Th control banks shall be limit in hysical insertion

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APPLICABILITY: MODES 1* and 2" *"

ACTION:

With the control banks inserted beyond the above insertion limits, except for surveillance testing pursuant to Specification 4. 1. 3. 1. 2 either:,

a. Restore the control banks to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or.

within to less than or equal to that b.

fract'f Reduce tion THERMAL POWER T THERMAL two hours OWER or which is allowed by the bank posi-i< sag.w ( 5-) HER.C,

c. Be in at least HOT STANDBY within 6 hours.

SURVEILLANCE RE UIREMENTS

4. 1. 3. 6 The position of each control bank shall be determined to be within the insertion limits at 1'east once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , except during time intervals when the Rod Insertion Limit Monitor is inoperable, then verify the individual rod positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

"See Special Test Exceptions Specifications 3. 10.2 and 3. 10.3.

""With K greater than or equal to 1.0 eff TURKEY POINT - UNITS 3 6 4 3/4 1-26 AMENDMENT NOS.137AND 132

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96 24 10 20 X C 50 50 70 60 90 1 TURKEY POINT - UNITS 3 4 4 3/4 1-27 AHEHDMEHT HOS 137ANQ 132

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POWER DISTRIBUTION LIMITS 3I4.2.2 HEAT FLUX HOT CHANNEL FACTOR - F (Z)

LIMITING CONDITION FOR OPERATION 3.2.2 FQ(Z) shall be limited by the following relationships:

F~(Z) < [F ] X [K(Z)l for P > 0.5 F~(Z) < [F ] X [K(Z)] for P < 0.5 where: [F ] = 2.32 limit P = Thermal Power ate erma ower

[F ] = The Measured Value, and Q

APPLICABILITY: MOOE 1 (gSC(o< (A) - Her<.a ACTION:

With the measured value of FQ(Z) exceeding its limit:

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a. Reduce THERMAL POWER at least 1X for each 1X FQ(Z) exceeds FQ(Z) within 15 minutes and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION may proceed provided the Overpower Oelta-T Trip Setpoints (value of K~)

have been reduced at least 3X for each 1X F (Z) exceeds the F ( )

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b. Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced power 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.

TURKEY POINT - UNITS 3 8 4 3l4 2-4 AMENOMENT NOS. 137AN013

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POWER DISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS Continued

2) The following action shall be taken:

a) Comply with the requirements of Specification 3.2.2 for F (Z) exceeding its limit by the percent calculated above.

4.2.2. 2 HIDS

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Operation is permitted at power above PT where PT equals the ratio of [F ]

divided by [F ] if the following Augmented Surveillance (Movable Incore Detection System, MIDS) requirements are satisfied:

a. The axial power distribution shall be measured b HIDS when required iil iii ii ii iiii//P

~ i i ii. I((2j F.(Z) is the normalized axial power distt ibution from thimble j at core elevation (Z),

1. If F .(Z) exceeds [F .(Z)] " as defined in the bases by < 4X, immediately reduce thermal power one percent for every percent by which [F-(Z)] is exceeded.

2. If F-(Z) exceeds [F (Z)] by > 4X immediately reduce thermal power below PT. Corrective action to reduce F.(Z) below the limit will permit return to thermal power not to exceed current PL"" as defined in the bases.-

b. F (Z) shall be determined to be within limits by using HIDS to monitor the thimbles required per, Specification 4.2.2. 2. c at the following frequencies.

l. At least once every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; and

2. Immediately following and as a minimum at 2, 4 and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months following the events listed below and every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter.

1) Raising the thermal power above PT, or

2) Hovement of control-bank D more than an accumulated total of 15 steps in any one direction.

C. HIDS shall be operable when the thermal power exceeds PT with:

l. At least two thimbles available for which R and ~ as defined in the bases have been determined. 3

"[F-(Z)] is the alarm setpoint for MIDS.

""P, is reactor thermal power expressed as a fraction of the Rated Thermal P5wer that is used to calculate [F (1)] .

J s TURKEY POINT - UNITS 3 Ec 4 3/4 2-7 AMENDMENT NOS. 137AND 132

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POWER DISTRIBUTION LIMITS SURVEILLANCE RE UIREMENTS Continued

6) After 24 hou'rs have elapsed, take a full core flux map to determine F (Z) unless a valid full core flux map was taken within the time period specified in 4.2.2. ld.

d) Calculate PBL per 4.2.2.3b.

b. Base Load operation. is permitted provided:

'1. THERMAL POWER is maintained between PT and PBL or between PT and 100K (whichever is most limiting).

2. AFD (Delta-I) is maintained within a t 2X or + 3X target band.

3. Full core flux maps are taken at least once per 31 effective Full Power Days.

BL T are defined as:

PBL

= [F ] X K(Z)

Fq(Z) X W(Z) BL X 1.09

= L P PT [Fq] /[Fq]

where: F~(Z) is the measured F~(Z) with no allowance for manufactur-ing tolerances og measurement uncertainty. For the purpose of this f [Fg(Z) j shal 1 be obtai ned between el evati ons bounded by 10K and 90K of the active co're height. [F ] is the F limit.

K(Z) '.s given i W(Z) BL i s the cycl e dependent

+km function that accounts for limited power distribution trarisients C.oRC encountered during base load operation.

e p Qg,gY'i~ G, The functiori is given in the Peaking Factor Limit Report as.per Lt ~)WS Specification 6.9. 1.6. The 9X uncertainty factor accounts for R.CPoaW manufacturing tolerance, measurement error, rod bow and any burnup and power dependent peaking factor increases.

C. During Base Load operation, if the THERMAL POWER is decreased below PT, then the conditions of 4.2.2.3.a shall be satisfied before re-entering Base Load operation.

d. If any of the conditions of 4. 2.2.3b are not maintained, reduce THERMAL POWER to less than or equal to PT, or, within 15 minutes initiate the Augmented Surveillance (MIDS) requirements of 4. 2. 2. 2.

TURKEY POINT - UNITS 3 8 4 3/4 2-9 AMENDMENT NOS.l 37 AND

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ADMINISTRATIVE CON LS PEAKING FACTOR LIMIT REPORT (Continued)

Factor Limit Report, the Peaking Factor Limit Report shall be provided to the NRC Document Control desk with copies to the Regional Administrator and the Resident Inspector within 30 days of their implementation, unless otherwise approved by the Commission.

The analytical methods used to generate the Peaking Factor limits shall be those previously reviewed and approved by the NRC. If changes to these methods are deemed necessary they will be evaluated in accordance with 10 CFR 50.59 and if if submitted to the NRC'or review and approval prior to their use the change is determined to involve an unreviewed safety question ot such a change would require amendment of previously submitted documentation.

CORE OPERATING LIMITS REPORT 6.9. 1.7 Core operating limits shall be established and documented in the CORE OPERATING LIMITS R PO T COLR before each rel a c c e o ny remaining part of a reload cycle The analytical methods used to de ermine t e ims s s a e ose previously reviewed and approved by the NRC in:

1. WCAP-10216-P-A, "RELAXATION OF CONSTANT AXIAL OFFSET CONTROL Fq SURVEILLANCE TECHNICAL SPECIFICATION," June 1983.

.2. WCAP-8385, "POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES-TOPICAL REPORT," September 1974.

The A hall be determined such that all applicable limits of the safety analyses are cycle revisions or supplements Control Desk with copies to the Regional A mi 'nd e CORE OPERATING LIMITS REPORT, including any mid-hall be provided to the NRC Document Inspector, within 30 days after their implementation un es by the Commission.

the Resident

'se approved SPECIAL REPORTS l<~E<~ (3) - Herc.

6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report as stated in the Specifications within Sections 3.0, 4.0, or 5.0.

6. 10 RECORD RETENTION

6. 10. 1 In addition to the applicable record retention requirements of Title 10, Code of Federal. Regulations, the following records shall be retained for at least the minimum period indicated.

6. 10.2 The following records shall be retained for at least 5 years:

a. Records and logs of unit operation covering time interval at each power level;

b. Records and logs of principal maintenance activities, inspections, repair, and replacement of principal items of equipment related to nuclear safety; TURKEY POINT - UNITS 3 & 4 6-20 AMENDMENT NOS. 156 AND 150

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L-94-128 INSERT 1 specified in the Rod Bank Insertion Limits curve, defined in the CORE OPERATING LIMITS REPORT.

INSERT 2 K(Z) for a given core height, is specified in the K(Z) cuzve, defined in the CORE OPERATING LIMITS REPORT.

INSERT 3 CORE OPERATING LIMITS REPORT 6.9.1.7 (INSERT THE FOLLOWING)

The analytical methods used to determine the K(Z) curve shall be those previously reviewed and approved by the NRC in:

WCAP-9220-P-A, Rev. 1, "Nestinghouse ECCS Evaluation Model-1981 Version," February 1982.

2. WCAP-9561-P-A, ADD. 3, Rev. 1, "BART A-1: A Co'mputex Code fox the Best Estimate Analysis of Reflood Transients Special Report: Thimble Modeling W ECCS Evaluation Model."

The analytical methods used to determine the Rod Bank Insertion Limits shall be those previously reviewed and approved by the NRC in:

1. WCAP-9272-P-A, "Nestinghouse Reload Safety Evaluation Methodology," July 1985.

The AFD, K(Z), and Rod Bank Insertion Limits shall be determined such that all applicable limits of the safety analyses are met. The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and the Resident Inspector, unless otherwise approved by the Commission.

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REACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS (Continued)

The charging pumps are demonstrated to be OPERABLE by testing as required by Section XI of the ASHE code or by specific surveillance requirements in the specification. These requirements are adequate to determine OPERABILITY because no safety analysis assumption relating to the charging pump performance is more restrictive than these acceptance criteria for the pumps.

The boron concentration of the RWST in conjunction with manual addition of borax ensures that the solution recirculated within containment after a LOCA will be basic. The basic solution minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components. The temperature requirements for the RWST are based on the containment integrity and large break LOCA analysis assumptions.

The OPERABILITY of one Boron Injection System during REFUELING ensures that this system is available for reactivity control while in MODE 6.

The OPERABILITY requirement of 55 F and corresponding surveillance inter-vals associated with the boric acid tank system ensures that the solubility of the boron solution will be maintained. The temperature limit of 55'F includes a 5'F margin over the 50'F solubility limit of 3. 5 wt.X boric acid. Portable instrumentation may be used to measure the temperature of the rooms containing boric acid sources and flow paths.

(")One channel of heat tracing is sufficient to maintain the specified temperature limit. Since one channel of heat tracing is sufficient to maintain the specified temperature, operation with one channel out-of-service is permitted for a period of 30 days provided additional temperature surveillance is performed.

3/4. 1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that: (1) acceptable power distri-bution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of rod misalignment on associated accident analyses are limited. OPERABILITY of the control rod position indicators is required to deter-mine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits continue. OPERABLE condition for the analog rod position indicators is defined as being capable of indicating rod position to within 112 steps of the demand counter position. For the Shutdown Banks and Con-trol Banks A and B, the Position Indication requirement is defined as the group demand counter i icated position between 0 and 30 steps withdrawn inclusive, and between 200 an &2& teps withdrawn inclusive. This permits the operator to verify that th control rods in these banks are either fully withdrawn or fully inserted, the normal operating modes for these banks. Knowledge of these bank positions in these two areas satisfies all accident analysis assumptions concern-ing their position. For Control Banks C and D, the Position Indication is defined as the group demand counter indicated position between 0 and requ'ent steps withdrawn inclusive.

(")This is no longer applicable once boric acid tanks inventory and boric acid source and flow path inventories have been diluted to less than or equal to

3. 5 weight percent (wtX).

TURKEY POINT " UNITS 3 8c 4 8 3/4.1"4 AMENDHENT NOS. 144 AND 139

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POWER DISTRIBUTION LIMITS BASES HEAT FLUX HOT CHANNEL FACTOR AND NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR ont>nued b) PL is reactor thermal power expressed as a fraction of 1.

c) K(2) is the reduction in the F limit as a function of core elevat'on (Z) as op me.i'Ae J ir. eke Cea<

d) [F (Z)]s is the alarm setpoint for MIOS. P~<+<<+4 <<~<~8 J

e) R., for thimble j, is determined from n=6 incore flux maps covering the J'ull configuration of permissible rod patterns at the thermal power limit of PT.

n Z R where F meas.

iJ ~ ~ max and F lJ (Z) is the normalized axial distribution at elevation Z from thimble j in map i which has a measure peaking factor without uncertainties or densification allowance of F~; meas.

f) o. is the standard deviation, expressed as a fraction or percentage of j

7, and is derived from n flux maps and the relationship below, or 0.02 J'2X), whichever is greater.

1/2 g) The factor 1.03 reduction in the kw/ft limit is the engineering uncertainty factor.

h) The factors (1+ a.) and 1.07 represent the margin between (F.(Z)]L limit J J and the MIDS alarm setpoint [F.(Z)3 . Since (1 +o.) is bounded by a lower limit of 1.02, there is at least a 9X reduction of the alarm setpoint.

Operations are permitted in excess of the operational limit ( 4X while making power adjustment on a percent for percent basis.

TURKEY POINT - UNITS 3 8 4 B 3/4 2"7 AMENDMENT NOS.137 ANO 132

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ML17352A724

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