ML19308D746

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Tech Spec Change Request 32 Re Tech Specs 3.1,3.2,4.1 & 4.2, Incorporating Limiting Condition for Operation,Surveillance Requirement & Related Bases on Physical Insertion of Axial Power Shaping Rod Group
ML19308D746
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/21/1978
From:
FLORIDA POWER CORP.
To:
Shared Package
ML19308D743 List:
References
NUDOCS 8003120917
Download: ML19308D746 (7)
v • d • e


Text

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A O TECHNICAL SPECIFICATION CHANGE REQUEST NO. 32 [ Appendix A]

Add the attached pages 3/4 1-37 and 38 and replace pages III, B3/41-4, B3/4 2-1 and 2 with the revised attached pages III B3/4 1-4, B3/4 2-1 and 2.

Proposed Change This proposed change incorporates a Limiting Condition for Operation, a Surveillance Requirement, and an Associated Bases on physical insertion of the Axial Power Shaping Rod Group.

Reason for Proposed Change As a result of damage to a fuel assembly, a partial shuffle of the fuel in the core was required to accommodate the replacement fuel. This shuffle placed four fuel assemblies in location with APSR's .that had been unrodded until 250 EFPD and had been partially rodded with Group 7 rods until shutdown at 269 EFPD.

The limit on APSR insertion is required to insure that power peaking limits are not exceeded.

Safety Analysis Justifying Proposed Change The damaging of one fuel assembly has necessitated its replacement and the replacement of the three symetrical assemblies. The replacement assemblies will be placed in location containing Group 7 Regulating Rods and the assemblies they replace will be installed in the APSR locations. Because of the difference in the exposure of the APSR fuel assemblies, limits need to be placed en APSR insertion so that power peaking limits are not exceeded. The insertion limit. curve of Figure 3.1-9 is based on LOCA analyses which have defined the maximum linaar heat rate such that the maximum clad temperature will not exceed the Final Acceptance Criteria 6f 2200*F following a LOCA.

i Tne proposed Technical Specifications will implement those limits.

e 8003120ff

INDEX 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 B0 RATION CONTROL Shutdown Margin...................................... 3/4 1-1 Boron Oilution ...................................... 3/4 1-3 Moderator Temperature Coef ficient. . . . . . . . . . . . . . . . . . . . 3/4 1-4 Minimum Temperature for Cri ticali ty. . . . . . . . . . . . . . . . . . 3/4 1-5 3/4.1.2- B0 RATION SYSTEMS Fl ow Pa th s - S hu tdown . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-6 Fl ow Pa ths - Op e ra ti ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-7 Makeup Pump - Shutdown............................... 3/4 1-9 Makeup Pumps - 0perating............................. 3/4 1-10 Decay Heat Removal Pump - Shutdown. . . . . . . . . . . . . . . . . . . 3/4 1-11 Boric Acid Pump - Shutdown........................... 3/4 1-12 Boric Ac id Pumps - 0pera ti ng . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-13 Borated Water Sources - Shutdown..................... 3/4 1-14

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Bora ted Wa ter Sources - Opera ti ng. .'. . . '. . . . . . . . . . . . . . . 3/4 1-15

. 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height . Safety and Regulating Rod Groups. ... .. 3/4 1-18 Group Height - Axial Power Shaping Rod Group......... 3/4 1-20 Posi tion Indi ca tor Channel s . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-21 Rod Drop Time........................................ 3/4 1-23 Sa fe ty - Rod - In se rti on Limi t. . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-24 Regul a ti ng Rod Ins ertion Limi ts. . . . . . . . . . . . . . . . . . . . . . 3/4 1-25 Rod Program.......................................... 3/4 1-33 X e n o n R e a c t i v i ty . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 1-36

, Axial Power Shaping Rod Insertion Limi ts. . . . . . . . . . . . . 3/4 1-37 .I

,t CRYSTAL RIVFR - UNIT 3 III

(7 REACTIVITY CONTROL SYSTEMS AXIAL POWER SHAPIllG RCD INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.9 The axial power shaping rod group shall be limited in physical insertion as shown en Figure 3.1-9.

APPLICABILITY: M0nES 1 and 2*.

ACTION:

With the axial powersshaping rod group outside the above insertion limits , ei ther:

a. Restore the axial power shaping red group to within the limits within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or
b. Reduce THERMAL POWER to less than or equal to that fraction of RATCD THERMAL POWER which is allowed by the rod groun po-sition using the above figure within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, or
c. Be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SURVEILLANCE REQUIREMENTS , 4.1.3.9 The position of the axial power shaping rod group shall be determined to be within the insertien limits at least once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. .

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CRYSTAL RIVER - UNIT 3 3/4 1-37

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110 100 - t (28.102) 1(27,92),

90 .

l 5 ' ' ~

(32,80) 80 -

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E 70 -

5 60 -

3 50 -

. (100,50)

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f 40 -

30 -

20 -

10 -

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0 10 20 30 40 50 50 70 SO 90 100 Rod Posi tion (5 wi tnarawn)

Figure 3.1-9 Axial Power Shaping Rod Group Insertion Limits After 268.8 EFPD /

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CRYSTAL RIVER - UNIT 3 3/4 1-38 l

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REACTIVITY CONTROL SYSTEMS -.

BASES 3/4.1.3 MOVABLE CONTROL ASSEMBLIES (Continued)

The maximum rod drop time permitted is consistent with the assumed rod drop time used in the safety analyses. Measurement with T

> 525aF and with reactor coolant pumps operating er.sures that LEE measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with frequent verifications required if an automatic monitoring channel is inoperable. These verification frequencies are adequate for assuring that the applicable LC0's are satisfied.

The limitation on THERMAL POWER based on xenon reactivity is necessary to ensure that power peaking limits are not exceeded even with specified rod insertion limits satisfied.

The limitation on Axial Power Shaping Rod insertion is necessary '

to enstre that power peaking limits are not exceeded.

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CRYSTAL RIVER ~ UNIT 3 B 3/4 1-4

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3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel integr-ity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency) events by: (a) maintaining the minimum DNBR in the core 3 2.1.30 during normal operation and during short term transiente, (b) main-taing the peak linear power density 118.0 kw/ft during normal operation, and (c) maintaining the peak power density 119.7 kw/ft during nort term transients. In addition, the above criteria must be met in order to meet the assumptions used for the loss-of-coolant accidents.

The power-imbalance envelope defined in Figure 3.2-1 and the inser-tion limit curves, Figures 3.1-1, 3.1-2, 3.1-3, 3.1-4 and 3.1-9 are based l on LOCA analyses which have defined -he maximum linear heat rate such that the maximum clad temperature will not exceed the Final Acceptance Criteria of 2200*F following a LOCA. Operation outside of the power-imbalance anvelope alone does not constitute a situation that would cause the Final iteceptance Criteria to be exceeded should a LOCA occur. The power-imba;ance envelope represents the boundary of operation limited by the Final J.cceptance Criteria only if the control rods are at the inser-tion limits , as defined by Figures 3.1-1, 3.1-2, 3.1-3, 3.1-4 and 3.1-9, l and if a 4 aercent QUADRANT POWER TILT exists. Additional conservatism is introducted by application of:

a. Nuclear uncertainty factors.
b. Thermal calibration uncertainty.
c. Fuel densification effects.

. d. Hot rod manufacturing tolerance factors.

The conservative application of the above peaking augmentation factors compensates for the potential peaking penalty due to fuel rod bow.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensures that the original criteria are met.

The definitions of the design limit nuclear power peaking factors as used'in these specifications are as follows:

Fq Nuclear Heat Flux liot Channel Factor, is defined as the maximum local fuel rod linear power density divided by the average fuel rod linear power density, assuming nominal fuel pellet and rod dimensions.

CRYSTAL RIVER - UNIT 3 8 3/4 2-1 I

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POWER DISTRIBUTION LIMITS BASES FN Nuclear Enthalpy Rise Hot Channel Factor, is defined as the AH ratio of the integral of linear power along the rod on which minimum DNBR occurs to the average rod power.

It has been determined by extensive analysis of possible operating power shapes that the design limits on nuclear power peaking and on mini-mum DNBR at full power are met, provided:

Fg ~< 3.12; FN < 1,71 l AH" l i

Pcwer Peaking is not a directly observable quantity and therefore limits have been established on the bases of the AXIAL POWER IMBALANCE produced by the power peaking. It has been determined that the above hot channel factor limits will ~ e c met provided the following conditions are maintained.

1. Control rods in a single group move together with no individual l rod insertion differing by more that + 6.5% (indicated positon) from the group average height.
2. Regulating rod groups are sequenced with overlapping groups as required in Specification 3.1.3.6.
3. The regulating rod insertion limits of Specification 3.1.3.6 and the axial power shaping rod insertion limits of Specifica-tion 3.1.3.9 are maintained.
4. AXIAL POWER IMBALANCE limits are maintained. The AXIAL POWER IMBALANCE is a measure of the difference in power between the top and bottom halves of the core. Calculations of core aver-age axial peaking factors for many plants and measurements from operating plants under a variety of operating conditions have been correlated with AXIAL POWER IMBALANCE. The correlation shows that the design power shape is not exceeded if the AXIAL POWER IMBALANCE is maintained between +15 percent and -17 per-cent at RATED THERMAL POWER.

The design limit power peaking factors are the most restrictive cal-culated at full power for the range from all control rods fully withdrawn to minimum allowable control rod insertion and are the core DNBR design basis. Therefore, for operation at a fraction of RATED THERMAL POWER, the design limits are met. When using incore detectors to make power distribution maps to determine FA and FN :

AH

a. The measurement of total peaking factor FM eas, shall be l increased by 1.4 percent to account for ma ufacturing toler- ,

ances and further increased by 7.5 percent to account for j measurement error. j 1

CRYSTAL' RIVER - UNIT 3 8 3/4 2-2  !

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