Text

Amend 92 to License NPF-16,modifying TSs for Selected cycle-specific Reactor Physics Parameters to Refer to St Lucie Unit 2 Core Operating Limits Rept for Limiting Values
	ML17229A822
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Site:	Saint Lucie
Issue date:	07/24/1998
From:	Hebdon F; NRC (Affiliation Not Assigned)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHIAGTON, D.c. 20555-0001 0

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Amendment No. 92 License No. NPF-16 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Florida Power 8 Light Company (FPL), dated December 29, 1997, as supplemented June 15, 1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities willbe conducted in compliance with the Commission's regulations; D.

The issuance of this amendment willnot be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-16.

(2) e ni al e '

The Technical Specifications contained in Appendices A and B, as revised through Amendment No.

92 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specification.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 30 days of receipt.

FOR THE NUCLEAR REGULATORYCOMMISSION Fred rick J. Hebdon, Director Proje t Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

Ouly 24, 1998

LIC N D

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P-Replace the following pages of the Appendix "A"Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

R ve INDEX Page I

INDEX Page XIX INDEX Page XXI Page 1-2 Page 3/4 1-5 Page 3/4 1-18 Page 3/4 1-19 Page 3/4 1-19a Page 3/4 1-20 Page 3/4 1-26'age 3/4 1-28 Page 3/4 2-1 Page 3/4 2-2 Page 3/4 2-3 Page 3/4 2A Page 3/4 2-5 Page 3/4 2-6 Page 3/4 2-7 Page 3/4 2-9 Page 3/4 2-11 Page 3/4 2-12 Page 3/4 2-15 Page 3/4 9-1 Page B 3/414 Page B 3/4 2-1 Page B 3/4 9-1 Page 6-20 insert insert insert insert IEKIZRUS INDEXPage I

INDEXPage XIX INDEXPage XXI Page 1-2 Page 3/4 1-5 Page 3/4 1-18 Page 3/4 1-19 deleted Page 3/4 1-20 Page 3/4 1-26 deleted Page 3/4 2-1

'age 3/4 2-2 Page 3/4 2-3 deleted deleted deleted Page 3/4 2-7 Page 3/4 2-9 Page 3/4 2-11 deleted Page 3/4 2-15 Page 3/4 9-1 Page B3/41M Page B 3/4 2-1 Page B 3/4 9-1 Page 6-20 Page 6-20a Page 6-20b Page 6-20c Page 6-20d

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.6-16 ANNUALREPORTS

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92

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1 FIGU~

2.1-1 REACTOR CORE THERMALMARGINSAFETY LIMITLINES FOUR REACTOR COOLANTPUMPS OPERATING

...,....,.............,.....................2Q 2.2-1 2.2-2 LOCALPOWER DENSITY-HIGH TRIP SETPOINT PART 1 (FRACTION OF RATED THERMALPOWER VERSUS QR,).

LOCALPOWER DENSITY-HIGH TRIP SETPOINT PART 2 2-7 (QR, VERSUS Y,)

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2.2P THERMALMARGIN/LOWPRESSURE TRIP SETPOINT PART 2 (FRACTION OF RATED THERMALPOWER VERSUS QR,)....................................2-10 B 2.1-1 AXIALPOWER DISTRIBUTIONFOR THERMALMARGIN SAFETY LIMITS................,,,............................................,B22 3.1-1 MINIMUMBORIC ACIDSTORAGE TANKVOLUMEAS A FUNCTION OF STORED BORIC ACID CONCENTRATION......,.........,.... ~ ~ ~ ~ ~~...,.....................

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3.4-1 DOSE EQUIVALENTI-131 PRIMARYCOOLANTSPECIFIC ACTIVITY LIMITSVERSUS PERCENT OF RATED THERMALPOWER WITHTHE PRIMARYCOOLANTSPECIFIC ACTIVITY)1 pCi/GRAM DOSE EQUIVALENT1-131...........,.....,.......,.......

..3/4 4-28 3.4-2 REACTOR COOLANTSYSTEM PRESSURE TEMPERATURE LIMITATIONSFOR 15 EFPY, HEATUP ANDCORE CRITICAL...........,....3/4 4Q1 a ST. LUCIE-UNIT2 XXI Amendment No. B, 68;78, 92

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1.6 A CHANNELFUNCTIONALTEST shall be the injection of a simulated signal into the channel as close to the primary sensor as practicable to verifyOPERABILITYincluding alarm and/or trip functions.

1.7 CONTAINMENTVESSEL INTEGRITYshall exist when:

a.

Allcontainment vessel penetrations required to be closed during accident conditions are either:

1.

Capable of being closed by an OPERABLE containment automatic isolation valve system, or 2.

Closed by manual valves, blind flanges, or deactivated automatic valves secured in their closed positions, except forvalves that are open on an intermittent basis under administrative control ~

b.

Allcontainment vessel equipment hatches are closed and sealed, C.

d.

Each containment vessel air lock is in compliance with the requirements of Specification 3.6.1.3, The containment leakage rates are within the limits of Specification 3.6.1.2, and e.

The sealing mechanism associated with each penetration (e.g., weids, bellows or 0-rings) is OPERABLE.

0 OLL 0 EA 1.8 CONTROLLED LEAKAGEshall be the seal water flowsupplied from the reactor coolant pump seals.

CO L

0 1.9 CORE ALTERATIONshall be the movement or manipulation of any fuel, sources, reactivity control components, or other components affecting reactivity within the reactor vessel with the vessel head removed and fuel in the vessel.

Exceptions to the above include shared (4 fingered) control element assemblies (CEAs) withdrawn into the upper guide structure (UGS) or evolutions performed with the UGS in place such as CEA latching/unlatching or verification of latching/unlatching which do not constitute a CORE ALTERATION. Suspension of CORE ALTERATIONSshall not preclude completion of movement of a component to a safe position.

0 E

6 1.9a The COLR is the unit-specific document that provides cycle specific parameter limits forthe current operating reload cycle. These cycle-specific parameter limits shall be determined for each reload cycle in accordance with Specification 6,9.1.11.

Plant operation within these limits is addressed in individual Specifications.

ST. LUCIE - UNIT2 1-2 Amendment No. 85, 88/2

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CON L'S MS MODE 3.1.1.4 The moderator temperature coefficient (MTC) shall be maintained within the limits specified in the COLR. The maximum positive limitshall be:

a.

Less positive than+5 pcmPF at s 70% RATED THERMALPOWER, and b.

Less positive than+3 pcmPF at > 70% RATED THERMALPOWER.

SBJBNJUD:

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With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBYwithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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4.1.1.4.1 The MTC shall be determined to be within its limits by confirmatory measurements.

MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits, 4.F 1.4.2 The MTC shall be determined at the followingfrequencies and THERMALPOWER

'conditions during each fuel cycle:

a.

Prior to initial operation above 5% of RATED THERMALPOWER, after each fuel loading.

b.

Atany THERMALPOWER, within 7 EFPD after reaching a RATED THERMAL POWER equilibrium boron concentration of 800 ppm, c.

Atany THERMALPOWER, within 7 EFPD after reaching a RATED THERMAL POWER equilibrium boron concentration of 300 ppm.

WithKgreater than or equal to 1.0.

¹See Special Test Exceptions 3.10.2 and 3.10.5.

ST. LUCIE-UNIT2 3/4 1-5 Amendment No.44,95,66,92

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S 3.1.3.1 The CEA Block Circuit and all full-length (shutdown and regulating) CEAs which are inserted in the core, shall be OPERABLE with each CEA of a given group positioned within 7.0 inches (indicated position) of all other CEAs ln its group.

MODES 1* and 2.

hQXLQH:

aO With one or more full-length CEAs inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGINrequirement of Specification 3.1.1.1 is satisfied within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and be in at least HOT STANDBYwithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With the CEA Block Circuit inoperable, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either.

With one CEA position indicator per group inoperable take action per Specification 3.1.3.2, or 2.

With the group overlap and/or sequencing interlocks inoperable maintain CEA groups 1, 2, 3 and 4 fullywithdrawn and the CEAs in group 5 to less than 15%

insertion and place and maintain CEA drive system in either the "Manual" or "Off" position, or 3.

Be in at least HOT STANDBY.

c, With more than one full-length CEA inoperable or misaligned from any other CEA in its group by more than 15 inches (indicated position), be in at least HOT STANDBYwithin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

d.

With one full-length CEA misaligned from any other CEA in its group by more than 15 inches, operation in MODES 1 and 2 may continue, provided that the misaligned CEA is positioned within 15 inches of the other CEAs in its group in accordance with the time constraints shown in COLR Figure 3.1-1 a.

See Special Test Exceptions 3.10.2, 3.10.4 and 3.10.5.

ST. LUCIE-UNIT2 Sf4 1-18 Amendment No.g 92

~~: (Continued) e.

With one full-length CEA misaligned from any other CEA in its group by more than 15 inches beyond the time constraints shown in COLR Figure 3.1-1a, reduce power to 5 70% of RATED THERMALPOWER prior to completing ACTION e.1 or e.2.

1.

Restore the CEA to OPERABLE status within its specified alignment requirements, or Declare the CEA inoperable and satisfy SHUTDOWN MARGINrequirement of Specification 3.1.1.1. Afterdeclanng the CEA inoperable, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3.1.3.6 provided a)

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the remainder of the CEAs in the group with the inoperable CEA shall be aligned to within 7.0 inches of the inoperable CEA white maintaining the allowable CEA sequence and insertion limits shown on COLR Figure 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.

b)

The SHUTDOWN MARGINrequirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Othetwise, be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months With one or more'full-length CEA(s) misaligned from any other CEAs in its group by more than 7.0 inches but less than or equal to 15 inches, operation in MODES 1 and 2 may continue, provided that within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the misaligned CEA(s) is either.

1.

Restored to OPERABLE status within its above specified alignment requirements, or 2.

Declared inoperable and the SHUTDOWN MARGINrequirement of Specification 3.1.1,1 is satisfied. Afterdeclaring the CEA inoperable, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3.1.3.6 provided:

a)

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the remainder of the CEAs in the group with the inoperable CEA shall be aligned to within7.0 inches of the inoperable CEA while maintaining the allowable CEA sequence and Insertion limits shown on COLR Figure 3.1-2; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.

b)

The SHUTDOWN MARGINrequirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Othenvlse, be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With one full-length CEA inoperable due to causes other than addressed by ACTION a., above, and inserted beyond the Long Term Steady State Insertion Limits but within its above specified alignment requirements, operation in MODES 1 and 2 may continue pursuant to the requirements of Specification 3.1.3.6.

Ifthe pre-misalignment ASI was more negative than -0.15, reduce power to 6 70% of RATED THERMAL POWER or 70% of the THERMALPOWER level prior to the misalignment, whichever is less, prior to completing ACTIONe.2.a) and e.2.b).

ST. LUCIE-UNIT2 3/4 1-19 Amendment No. 8,89, 92

~.

BQILQH: (Continued) h.

With one full-length CEA inoperable due to causes other than addressed by ACTIONa.,

above, but within its above specified alignment requirements and either fullywithdrawn or within the Long Term Steady State Insertion Limits ifin full-length CEA group 5, operation in MODES 1 and 2 may continue.

4.1.3.1.1 The Position of each full-length CEA shall be determined to be within 7.0 inches (indicated position) of all other CEAs in its group at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time Intetvals when the Deviation Circuit ancVor CEA Block Circuit are inoperable, then verify the individual CEA positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full-length CEA not fullyinserted in the core shall be determined to be OPERABLE by movement of at least 7.0 inches in any one direction at least once per 92 days.

4.1.3.1.3 The CEA Block Circuit shall be demonstrated OPERABLE at least once per 92 days by a functional test which verifies that the circuit prevents any CEA from being misaligned from all other CEAs in its group by more than 7.0 inches (indicated position),

4.1.3.1.4 The CEA Block Circuit shall be demonstrated OPERABLE by a functional test which verifies that the circuit maintains the CEA group overlap and sequencing requirements of Specification 3.1.3.6 and that the circuit prevents the regulating CEAs from being inserted beyond the Power Dependent Insertion Limitof COLR Figure 3.1-2:

a.

Prior to each entry into MODE 2 from MODE 3, except that such verifIcation need not be performed more often than once per 92 days, and b.

At least once per 6 months.

The licensee shall be excepted from compliance during the initial startup test program for an entty into MODE 2 from MODE 3 made in association with a measurement of power defect.

ST. LUCIE-UNIT2 3/4 1-20 Amendment No. 8-,59; 92

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ONT OLS 8

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IN E 3.1.3,6 The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown on COLR Figure 3.1-2 (regulating CEAs are considered to be fully withdrawn in accordance with COLR Figure 3.1-2 when withdrawn to greater than or equal to 129.0 inches), with CEA insertion between the Long Term Steady State Insertion Limits and the Power Dependent Insertion Limits restricted to:

a.

Less than or equal to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval, b.

Less than or equal to 5 Effective Full Power Days per 30 Effective Full Power Day Intetval, and c.

Less than or equal to 14 Effective Full Power Days per calendar year.

SHJllcLIIY: MODES 1' hGILOH:

a.

With the regulating CEA groups inserted beyond the Power Dependent Insertion Limits, except for surveillance testing pursuant to Specification 4.1,3.1,2, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either.

1.

Restore the regulating CEA groups to within the limits, or 2.

Reduce THERMALPOWER to less than or equal to that fraction of RATED THERMALPOWER which is allowed by the CEA group position and insertion limits specified in the COLR.

b.

With the regulating CEA groups inserted between the Long Term Steady State Insertion Limits and the Power Dependent Insertion Limitsfor intervals greater than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months intetval, operation may proceed provided either.

1.

The Short Term Steady State Insertion Limits are not exceeded, or 2.

Any subsequent increase in THERMALPOWER is restricted to less than or equal to 5% of RATED THERMALPOWER per hour.

See Special Test Exceptions 3.10.2, 3.10.4 and 3.10.5.

¹With Kgreater than or equal to 1.0, ST. LUCIE-UNIT2 Sf4 1-26 Amendment No. 92

42 POW D

UU ON LIMITS LINE 3.2.1 The linear heat rate shall not exceed the limits specified in the COLR.

IIPPULAILI 0 MDDE1.

hQItQ5:

With the linear heat rate exceeding its limits, as indicated by four or more coincident incore channels or by the AXIALSHAPE INDEXoutside of the power dependent control limits of COLR Figure 3.2-2, within 15 minutes initiate corrective action to reduce the linear heat rate to within the limits and either.

a.

Restore the linear heat rate to within its limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , or b.

Be in at least HOT STANDBYwithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

4.2.1.1 The provisions of Specification 4.0.4 are not applicable.

4.2.1.2 4.2.1.3 The linear heat rate shall be determined to be within its limits by continuously monitoring the core power distribution with either the excore detector monitoring system or with the incore detector monitoring system.

E cor ni

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- The excore detector monitoring system may be used for monitoring the linear heat rate by:

a.

Verifyingat least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months that the full-length CEAs are withdrawn to and maintained at or beyond the Long Term Steady State Insertion Limitof Specification 3.1.3.6.

b.

Verifying at least once per 31 days that the AXIALSHAPE INDEXalarm setpoints are adjusted to within the limitshown on COLR Figure 3.2-2.

ST. LUCIE-UNIT2 3/4 2-1 Amendment No.92

~

p BU 0 C.

Verifyingthat the AXIALSHAPE INDEXis maintained within the allowable limits of COLR Figure 3.2-2, where 100% of maximum allo'wable power represents the maximum THERMALPOWER allowed by the following expression:

MxN where:

1.

M is the maximum allowable THERMALPOWER level forthe existing Reactor Coolant Pump combination.

2.

N is the maximum allowable fraction of RATED THERMALPOWER as determined by the F'utve of COLR Figure 3.2Q.

4.2.1.4 Inc re De or M i orin S

¹ - The incore detector monitoring system may be used for monitoring the linear heat rate by verifying that the incore detector Local Power Density alarms:

a.

Are adjusted to satisfy the requirements of the core power distribution map which shall be updated at least once per 31 days of accumulated operation in MODE 1 ~

b.

Have their alarm setpoint adjusted to less than or equal to the limits shown on COLR Figure 3.2-1

¹ Ifincore system becomes inoperable, reduce power to M x N within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and monitor linear heat rate in accordance with Specification 4,2,1.3.

ST. LUCIE-UNIT2 3/4 2-2 Amendment No.~

92

Pages 3/4 24 (Amendment 42), 3/4 2-5 (Amendment 8), and 3/4 2-6 (Amendment 17) have been deleted from the Technical Specifications. The next page is 3/4 2-7.

ST. LUCIE-UNIT2 3/4 2-3 Amendment No. 92

0

/

r E

DIS B T ALPEA C 0 3.2.2 The calculated value ofF'hall be within the limits specified in the COLR.

MODE 1

~C~IO WithF'ot within limits, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a.

Reduce THERMALPOWER to bring the combination of THERMALPOWER and F'o within the limits of COLR Figure 3.2Q and withdraw the full length CEAs to orLeyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6; or b.

Be in HOT STANDBY.

4.2.2.1 4.2.2.2 The provisions of Specification 4.0.4 are not applicable.

F'hall be caiculatedby the expression F' F(1+T) when F is calculated with a non-full core power distribution analysis code and shall be calculated as F' F when calculations are performed with a fullcore power distribution analysis code, F'hall be determined to be within its limitat the following intervals:

a.

Prior to operation above 70% of RATED THERMALPOWER after each fuel

loading, b.

At least once per 31 days of accumulated operation in MODE 1, and c.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ifthe AZIMUTHALPOWER TILT(T) is > 0.03.

See Special Test Exception 3.10.2.

ST. LUCIE-UNIT2 3/4 2-7 Amendment No.e, 92

0 E

DS B

LIMP 0

LI EGR TEDRADIALPEAKINGFA TO S-F, 3.2.3 The calculated value of F,'hall be within the limits specified in the COLR.

MODE 1.

hQlLQH:

With F,'ot within limits, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either:

a, b.

Be in at least HOT STANDBY,or Reduce THERMALPOWER to bring the combination of THERMALPOWER and F,'o within the limits of COLR Figure 3.2-3 and withdraw the full-length CEAs to or beyond the Long Term Steady State Insertion Limits of Specification 3.1.3.6. The THERMALPOWER limitdetermined from COLR Figure 3.2-3 shall then be used to establish a revised upper THERMALPOWER level limiton COLR Figure 3.2A (truncate COLR Figure 3.2-4 at the allowable fraction of RATED THERMAL POWER determined by COLR Figure 3.2Q) and subsequent operation shall be maintained within the reduced acceptable operation region of COLR Figure 3.2A.

4.2.3.1 4.2.3.2 The provisions of Specification 4.0.4 are not applicable.

F,'hall be calculated by the expression F,'

F,(1+T,) when F, is calculated with a non-full core power distribution analysis code and shall be calculated as F,'= F, when calculations are performed with a full core power distribution analysis code. F,'hall be determined to be within its limitat the following intervals:

a.

Prior to operation above 70% of RATED THERMALPOWER after each fuel

loading, b.

At least once per 31 days of accumulated operation in MODE 1, and c,

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ifthe AZIMUTHALPOWER TILT(T) is ) 0.03.

See Special Test Exception 3.10.2.

ST. LUCIE-UNIT2 3/4 2-9 Amendment No.e-,se>

92

The limitation on linear heat rate ensures that in the event of a LOCA, the peak temperature of the fuel cladding willnot exceed 2200'F.

Either of the two core power distribution monitoring systems, the Excore Detector Monitoring System and the Incore Detector Monitoring System, provides adequate monitoring of the core power distribution and are capable of veNying that the linear heat rate does not exceed its limits. The Excore Detector Monitoring System performs this function by continuously monitoring the AXIALSHAPE INDEXwith the OPERABL'E quadrant symmetric excore neutron fluxdetectors and verifying that the AXIALSHAPE INDEXis maintained within the allowable limits of COLR Figure 3.2-2.

In conjunction with the use of the excore monitoring system and in establishing the AXIALSHAPE INDEXlimits, the following assumptions are made:

(1) the CEA insertion limits of Specifications 3.1.3.5 and 3.1.3.6 are satisfied, (2) the AZIMUTHALPOWER TILTrestrictions of Specification 3.2.4 are satisfied, and (3) the TOTALPLANARRADIALPEAKING FACTOR does not exceed the limits of Specification 3.2.2.

The Incore Detector Monitoring System continuously provides a direct measure of the peaking factors and the alarms which have been established forthe individual incore detector segments ensure that the peak linear heat rates willbe maintained within the allowable limits of COLR Figure 3.2-1. The setpoints forthese alarms include allowances, set in the conservative directions, for (1) a measurement-calculational uncertainty factor, (2) an engineering uncertainty factor, (3) an allowance for axial fuel densification and thermal expansion, and (4) a THERMALPOWER measurement uncertainty factor.

423 d

2 L

N D

P'NDF,'

U L 0 E

D E

S-The limitations ofF'nd T, are provided to ensure that the assumptions used in the analysis for establishing the Linear Heat Rate and Local Power Density - High LCOs and LSSS setpoints remain valid during operation at the various allowable CEA group insertion limits. The limitations on F,'nd T, are provided to ensure that the assumptions used in the analysis establishing the DNB Margin LCO, the Thermal Margin/Low Pressure LSSS setpoints remain valid during operation at the various allowable CEA group insertion limits. IfF', F,'r T, exceed their basic limitations, operation may continue under the additional restrictions imposed by the ACTIONstatements since these additional restrictions provide adequate provisions to assure that the ST. LUCIE-UNIT2 B 3/4 2-1 Amendment No.~ 92

Page 3/4 2-12 (Amendment 42) has been deleted from the Technical Specifications. The next page is 3/4 2-13.

ST. LUCIE-UNIT2 3/4 2-11 Amendment NO. 6, 92

ls

~

R E

FOUR REACTOR COOLANTPUMPS OP Cold Leg Temperature (Narrow Range)

Pressurizer Pressure Reactor Coolant Flow Rate AXIALSHAPE INDEX 5350F' T ~ 549oF 2225 psia**5 P~ 5 2350 psia 2 363,000 gpm COLR Figure 3.24 Applicable only ifpower level 2 70% RATED THERMALPOWER.

Limitnot applicable during either a THERMALPOWER ramp increase in excess of 5% of RATED THERMALPOWER or a THERMALPOWER step increase of greater than 10% of RATED THERMALPOWER.

ST. LUCIE-UNIT2 3/4 2-15 Amendment No. B

E 0

BO ONC N

E The limitations on reactivity conditions during REFUELING ensure that: (1) the reactor willremain subcritical during CORE ALTERATIONS,and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel.

These limitations are consistent with the initial conditions assumed forthe boron dilution incident in the safety analyses.

The value specified in the COLR for Kincludes a 1% delta k/k conservative allowance for uncertainties.

Similarly, the boron concentration value specified in the COLR includes a conservative uncertainty allowance of 50 ppm boron.

I ST UM The OPERABILITYof the startup neutron fluxmonitors ensures that redundant monitoring capability is available to detect changes in the reactivity condition of the core.

DE A T The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor pressure vessel ensures that sufficient time has elapsed to allow the radioactive decay of the short lived fission products. This decay time is consistent with the assumptions used in the safety analyses.

CON I

E TB D

G E

The requirements on containment penetration closure and OPERABILITYensure that a release of radioactive material within containment willbe restricted from leakage to the environment. The OPERABILITYand closure restrictions are sufficient to restrict radioactive material release from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE.

N The requirement for communications capability ensures that refueling station personnel can be promptly informed of significant changes in the facilitystatus or core reactivity condition during CORE ALTERATIONS.

ST. LUCIE-UNIT2 B 3/4 9-1 Amendment N0.92

3 9

E UELI G 0

S 0

0 E

TION 3.9.1 With the reactor vessel head closure bolts less than fullytensioned or with the head removed, the boron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained within the limitspecified in the COLR.

JKhlklQX: MODE F.

hGXlQH:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONSor positive reactivity changes and initiate and continue boration at greater than or equal to 40 gpm of a solution containing 1720 ppm boron or greater to restore boron concentration to within limits.

4.9.1.1 The boron concentration limitshall be determined prior to:

a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full length CEA in excess of 3 feet from its fullyinserted position within the reactor pressure vessel.

4.9.1.2 The boron concentration of the reactor coolant system and the refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

V The reactor shall be maintained in MODE 6 whenever fuel is in the reactor vessel with the reactor vessel head closure bolts less than fullytensioned or with the head removed.

ST. LUCIE-UNIT2 3/4 9-1 Amendment No. 92

0

EACTIV 0

S MS OV BLEC OL S

B S

i Overpower margin is provided to protect the core in the event of a large misalignment (2 15 inches) of a CEA. However, this misalignment would cause distortion of the core power distribution. This distribution may, in turn, have a significant effect on (1) the available SHUTDOWN MARGIN,(2) the timeMependent long-term power distributions relative to those used in generating LCOs and LSSS setpoints, and (3) the ejected CEA worth used in the safety analysis. Therefore, the ACTIONstatement associated with the large misalignment of a CEA requires a prompt realignment of the misaligned CEA.

The ACTIONstatements applicable to misaligned or inoperable CEAs include requirements to align the OPERABLE CEAs in a given group with the inoperable CEA. Conformance with these alignment requirements bring the core, within a short period of time, to a configuration consistent with that assumed in generating LCO and LSSS setpoints.

However, extended operation with CEAs significantly inserted in the core may lead to perturbations in (1) local bumup, (2) peaking factors, and (3) available shutdown margin which are more adverse than the conditions assumed to exist in the safety analyses and LCO and LSSS setpoints determination.

Therefore, time limits have been imposed on operation with inoperable CEAs to preclude such adverse conditions from developing.

The requirement to reduce power in certain time limits depending upon the previous F,'s to eliminate a potential nonconservatism for situations when a CEA has been declared inoperable.

A worst~se analysis has shown that a DNBR SAFDLviolation may occur during the second hour after the CEA misalignment ifthis requirement is not met. This potential DNBR SAFDL violation is eliminated by limitingthe time operation is permitted at fullpower before power reductions are required.

These reductions willbe necessary once the deviated CEA has been declared inoperable. This time allowed for continued operation at a reduced power level can be permitted forthe following reasons:

2.

3.

4.

5, The margin calculations which support the Technical Specifications are based on a steady-state radial peak of F,'

the limits of Specification 3.2.3.

When the actual F,'

the limits of Specification 3.2.3, significant additional margin exists.

This additional margin can be credited to offset the increase in F,'ith time that can occur followinga CEA misalignment.

This increase in F,'s caused by xenon redistribution.

The present analysis can support allowing a misalignment to exist without correction, if the time constraints and initial F,'imits of COLR Figure 3.1-1 a are met.

ST. LUCIE-UNIT2 B3/41M Amendment N0,8;95, 92

6.9.1.9 D

OGC LE 0

E L

(Continued) 4 At least once every 5 years, an estimate of the actual population within 10 miles of the plant shall be prepared and submitted to the NRC.

6.9.1.10 At least once evety 10 years, an estimate of the actual population within 50 miles of the plant shall be prepared and submitted to the NRC.

6.9.1.11 CO E

E GL S

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

Specification 3.1.1,4 Specification 3.1.3.1 Specification 3.1.3.6 Specification 3.2.1 Specification 3.2.2 Specification 3.2.3 Specification 3.2.5 Specification 3,9.1 Moderator Temperature Coefficient Movable Control Assemblies - CEA Position Regulating CEA Insertion Limits Linear Heat Rate Total Planar Radial Peaking Factors -

F'otal Integrated Radial Peaking Factor -

F,'NB Parameters - Axial Shape Index Refueling Operations - Boron Concentration b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, as described in the following documents or any approved Revisions and Supplements thereto:

1.

WCAP-11596-P-A, "Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores," June 1988 (Westinghouse Proprietary).

2.

NF-TR-9541, "Nuclear Physics Methodology for Reload Design of Turkey Point 8 St. Lucie Nuclear Plants," Florida Power 8 Light Company, Januaty 1995.

3.

CENPD-199-P, Rev. 1-P-A, "C-E Setpoint Methodology: CE Local Power Density and DNB LSSS and LCO Setpoint Methodology forAnalog Protection Systems," January 1986.

4.

CENPD-266-P-A, "The ROCS and DITComputer Code for Nuclear Design,"

April 1983.

5.

CENPD-275-P, Revision 1-P-A, "C-E Methodology for Core Designs Containing Gadolinia-Urania Burnable Absoibers," May 1988.

6.

CENPD-188-A, "HERMITE: A Multi-Dimensional Space - Time Kinetics Code for PWR Transients," July 1976.

ST. LUCIE-UNIT2 6-20 Amendment No.48;B~

92

TNG b.

(Continued)

L (Continued) 7.

8.

9.

10.

12.

13.

14.

15.

16.

17.

18.

CENPD-153-P, Rev. 1-P-A, "Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System,"

May 1980.

CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 1:

CE Calculated Local Power Density and Thermal Margin/Low Pressure LSSS for St. Lucie Unit 1," December 1979.

CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 2:

Combination of System Parameter Uncertainties in Thermal Margin Analyses for St, Lucie Unit 1," January 1980.

CEN-123(F)-P, "Statistical Combination of Uncertainties Methodology Part 3:

CE Calculated Departure from Nucleate Boiling and Linear Heat Rate LimitingConditions for Operation for St. Lucie Unit 1," February 1980, CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981.

Letter, J.W. Miller(NRC) to J.R. Williams, Jr. (FPL), Docket No. 50489, Regarding Unit 2 Cycle 2 License Approval (Amendment No. 8 to NPF-1 6 and SER), November 9, 1984 (Approval of CEN-123(F)-P (three parts) and CEN-1 91(B)-P).

CEN-371 (F)-P, "Extended Statistical Combination of Uncertainties,"

July 1989.

Letter, J.A. Norris (NRC) to J.H. Goldberg (FPL), Docket No. 50-389, "St. Lucie Unit 2 - Change to Technical Specification Bases Sections '2.1.1 Reactor Core'nd '3/4.2.5 DNB Parametets'TAC No. M87722)," March 14, 1994 (Approval of CENQ71 (F)-P).

CENPD-161-P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986.

CENPD-1 62-P-A, "Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975.

CENPD-207-P-A, "Critical Heat Rux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-uniform Axial Power Distribution,"

December 1984.

CENPD-206-P-A, "TORC Code, Verification and Simplified Modeling Methods," June 1981.

ST. LUCIE-UNIT2 6-20a Amendment No. 92

E

CO b.

(Continued)

OL (Continued) 19.

20.

2'I.

23.

24.

25.

26.

27.

28.

29.

30.

31, 32.

33, CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 1983.

CENPD-1 39-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974.

CEN-1 61 (B)-P-A, "Improvements to Fuel Evaluation Model," August 1989.

CEN-1 61(B)-P, Supplement 1-P-A, "Improvements to Fuel Evaluation Model," January 1992.

CENPD-1 32, Supplement 3-P-A, "Calculative Methods forthe C-E Large Break LOCA Evaluation Model for the Analysis of C-E and E Designed NSSS," June 1985.

CENPD-1 33, Supplement 5-A, "CEFLASHQA,A FORTRAN77 Digital Computer Program for Reactor Biowdown Analysis," June 1985.

CENPD-134, Supplement 2-A, "COMPERC-II, a Program for Emergency Refill-Reflood of the Core," June 1985.

CENPD-1 35-P, Supplement 5, "STRIKIN-II,A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977.

Letter, R.L, Baer (NRC) to A.E. Scherer (CE), "Evaluation of Topical Report CENPD-135, Supplement ¹5," September 6, 1978.

CENPD-137, Supplement 1-P, "Calculative Methods forthe C-E Small Break LOCA Evaluation Model," January 1977.

CENPD-133, Supplement 3-P, "CEFLASHAAS,A Computer Program for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident,"

January 1977.

Letter, K. Kniel (NRC) to A.E. Scherer (CE), "Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement1-P,"

September 27, 1977.

CENPD-138, Supplement 2-P, "PARCH, A FORTRAN-IVDigital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977.

Letter, C. Aniel (NRC) to A.E. Scherer (CE), "Evaluation of Topical Report CENPD-138, Supplement 2-P," April 10, 1978.

Letter, W.H. Bohike (FPL) to Document Control Desk (NRC), "St. Lucie Ui, ~

k N.,P p

de A

d

," L-91Q25, December 17, 1991.

ST. LUCIE-UNIT2 Amendment No. 92

P

S EP b.

(Continued)

L (Continued) 34.

Letter, J.A. Norris (NRC) to J.H. Goldberg (FPL), "St. Lucie Unit 2-Issuance of Amendment Re: Moderator Temperature Coefficient (TAC No.

M82517)," July 15, 1992.

35.

Letter, J.W. Williams, Jr. (FPL) to D.G. Eisenhut (NRC), "St. Lucie Unit No. 2, D

k M.

P p

dLiiA d

L4-148, June 4, 1984.

36.

Letter, J.R. Miller(NRC) to J.W. Williams, Jr. (FPL), Docket No. 50489, Regarding Unit2 Cycle 2 License Approval (Amendment No. 8 to NPF-16 and SER), November 9, 1984 (Approval of Methodology contained in L-84-1 48).

37.

Letter, A.E. Scherer Enclosure 1-P to LD-82401, "CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam Supply System,"

December 1981.

C.

d.

38.

Safety Evaluation Report, "CESEC Digital Simulation of a Combustion Engineering Steam Supply System (TAC No,: 01142)," October 27, 1983.

39.

CENPD-282-P-A, Volumes 1, 2 and 3, and Supplement 1, "Technical Manual for the CENTS Code," Februaiy 1991, February 1991, October 1991, and June 1993, respectively.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SHUTDOWN MARGIN, transient analysis limits, and accident analysis limits) of the safety analysis are met.

The COLR, including any mid cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

6.9.2 Special reports shall be submitted to the NRC within the time period specified for each report.

ST. LUCIE-UNIT2 Amendment No. 92

ECO 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.

6,10.1 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.

c.

AllREPORTABLE EVENTS.

d.

Records of surveillance activities; inspections and calibrations required by these Technical Specifications.

e.

Records of changes made to the procedures required by Specification 6.8.1.

(continued on page 6-21)

ST. LUCIE-UNIT2 Amendment No. 92

ML17229A822

Text

Attachment:

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