Text

Tech Spec Change Request 77 Requesting Amend to App a of License DPR-72 to Incorporate Revised Reactor Core Safety Limits & Trip Setpoints for Reactor Thermal Power & Axial Power Imbalance
	ML20032E922
Person / Time
Site:	Crystal River
Issue date:	11/16/1981
From:	; FLORIDA POWER CORP.
To:	;
Shared Package
ML20032E919	List: ML20032E918; ML20032E922; ML20032E929;
References
	TAC-46962, NUDOCS 8111230501
	Download: ML20032E922 (6)
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TECHNICAL SPECIFICATION CHANGE REQUEST NO. 77 (Appendix A)

' Page-Replacement Delete and insert the pages in Appendix A of Operating License DPR-72 as indicated below:

DELETE INSERT i

2-3 2-3 2-7 2-7 B2-7 B2-7 3/4 1-2a 3/4 1-2a 3/4 1-7 3/4 1-7 3/4 1-10a 3/4 1-10a 3/4 1-13 3/4 1-13 i

3/4 1-14 3/4 1-14 3/4 1-16 3/4 1-16 3/4 1-17 3/4 1-17 3/4 1-25 3/4 1-25 i

3/4 1-27 3/4 1-27 2/4 1-28 3/4 1-27a 3/4 1-29 3/4 1-28 3/4 1-30 3/4 1-29 3/4 1-37 3/4 1-29a 3/4 1-38 3/4 1-30 3/4 1-39 3/4 1-37 3/4 2-1 3/4 1-38 3/4 2-2 3/4 1-38a 3/4 2-3 3/4 1-39 3/43-2 3/4 2-1 3/4 3-6 3/4 2-2 3/4 3-7 3/4 2-2a B3/4 1-2 3/4 2-3 B3/4 1-3 3/4 3-2 3/4 4-1 3/4 3-6 3/4 3-7 B3/4 1-2 B3/4 1-3 3/4 4-1 1

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Proposed Change These changes address the current reactor refueling for Cycle 4.

The changes are supported in BAW-1684, Crystal River Unit 3 - Cycle 4 Reload Report, June, 1981.

Some of the changes supported by BAW-1684 were previously approved by NRC in Amendment 41 to the Facility Operating License, as part of the Crystal River Unit 3 power level upgrade program.

Changes previously approved are not included in this submittal. Table 8-1 of BAW-1684 (Attachment 1) lists proposed Technical Specification changes. Those which were previously approved have been marked as such. Also, Table 3.3-2, as shown in BAW-1684, has been changed in accordance with a supplementary letter from B&W.

Proposed Technical Specification repalcement pages are given as.

These changes include revised:

1) Reactor core safety limits and trip set-points for reactor thermal power and axial power iabalance; 2) Reactor shut-down margin; 3) Minimum boric acid and, orated water volumes; 4) Reactor regulating rod group insertion; 5) Reactor axial power shaping rod group insertion; 6) Reactor axial power imbalcnce limits; and 7) Nuclear overpower instrumentation response times.

Reason for Proposed Change Crystal River Unit 3 will operate in Cycle 4 with 68 fresh fuel assemblies.

As stated in BAW-1684, certain Technical Specifications require revision.

The analyses summarized in BAW-1684 account for the Cycle 4 core characteris-tics.

Recent revisions of the RPS instrumentation delay times are the result of an instrument error analysis by B&W.

Safety Analysis of Proposed Change The licensing considerat1ons for operation of Crystal River Unit 3 with the Cycle 4 reload are described in BAW-1684.

These proposed changes will bring the plant Technical Specifications into agreement with the applicable portions of BAW-1684. The review and changes of the Technical Specifications ensures that the Final Acceptance Criteria ECCS limits will not be exceeded nor will the thermal design criteria be violated. The shutdown margin requirements were increased in order to assure that the reactor could be maintained sub-critical in case of a boron dilution accident during operation in MODES 4&5.

Nuclear overpower instrumentation response times were changed as a result of an instrument error analysis by B&W.

It is concluded that operation within the attached limits for Cycle 4 will not involve any unreviewed safety items.

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9 ATTACHMENT 1 i

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Table 8-1.

Technical Specification Changes Tech Spec No.

Report Page Nos.

( Figure, Table Nos. )

(Figure, Table Nos.)

Reason for Change (Figure 2.1-1)*

8-4 Revised for Cycle 4 operation.

(Figure 8-1)

(Figure 2.1-2) 8-5 Revised for Cycle 4 operation.

(Figure 8-2)

(Table 2.2-1)*

8-6 Added nuclear overpower based on (Table 8-2)

RCPPM trip, revised setpoints to

(

include RP5 instrument errer and

)

Cycle 4 reload.

(Figure 2.2-1) 8-7 Revised for Cycle 4 operation.

(Figure 8-3) 1 2.1.1, 2.1.2*

8-8 Revised text to indicate three-l pump operation is more restric-l tive on pressure / temp limit curve (Figure 2-1).

2.2.1*

8-9 Revised nuclear overpower trip 8-10 valve to include RPS instrument error. Added nuclear overpower trip based on RCPPMs.

(Figure 2.1)*

8-11 Revised pressure / temp limit (Figure 8-4) curve.

3.1.1.1.2 8-12 Shutdown margin was revised to 4.1.1.1.2.1 reflect the required mode 4 and 5 margin for Cycle 4 operation to account for the inadvertant dilution by sodium hydroxide addition.

3.1.2.2 8-13 Revised mode 4 shutdown margin as above.

3.1.2.4.2 8-14 Revised mode 4 shutdown margin as above.

3.1.2.7 8-15 Revised mode 4 shutdown margin as above.

3.1.2.9 8-16 Revised borated storage water volume and mode 4 shutdown margin as above.

3.1.3.6 8-17 Revised figure nunbers.

Previously approved by Amendment 41.

Table 8-1.

(Cont'd)

Tech Spec No.

Report Page Nos.

(Figure, Table Nos.)

(Figura, Table Nos.)

Reason for Change 8-18 thru 8-23 Revised regulating rod group (Figure 3.1-1)

(Figure 8-5) limits for three-and four-(Figure 3.1-la)

(Figure 8-6) pump operation for Cycle 4.

(Figure 3.1-2)

(Figure 8-7)

(Figure 3.1-3)

(Figure 8-8)

(Figure 3.1-3a)

(Figure 8-9)

(Figure 3.1-4)

(Figure 8-10) 3.1.3.9 8-24 Revised figure numbers.

8-25 thru 8-27 Revised APSR limits for Cycle 4 (Figure 3.1-9)

(Figure 8-11) operation.

(Figure 3.1-9a)

(Figure 8-12)

(Figure 3.1-10)

(Figure 8-13) 3.2.1 8-28 Revised figure number.

8-29 thru 8-31 Revised axial power imbalance (Figure 3.2-1)

(Figure 8-14) envelope for Cycle 4 operation.

(Figure 3.2-la)

(Figure 8-15)

(Figure 3.2-2)

(Figure 8-16) 8-32 Added nuclear overpower based (Table 3.3-1)

(Table 8-3) on RCPPMs trip.

8-33 Added nuclear overpower based (Table 3.3-2)

(Table 8-4) on RCPPMs trip.

8-34 Added nuclear overpower based (Table 4.3-1)

(Table 8-5) on RCPPMs trip.

Bases 3/4.1.2 8-35 Revised shutdown margin and 8-36 boron requirements to account for inadvertent dilution by sodium hydroxide.

Previously approved by Amendment 41.

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CRYSTAL RIVER -UNIT 3 2-7

LIMITING SAFETY SYSTEM SETTINGS BASES Reactor Containment Vessel Pressure - High The Reactor Containment Vessel Pressure - High Trip Se. i. int < 4 psig, provides positive assurance that a reactor trip will occur in ti.

oalikely event of a steam line failure in the containment vessel or a loss-t -coolant accident, even in the absence of a RCS Pressure - Low trip.

Nuclear Overpower Based on RCPPMS In connection with the Flux-Delta Flux-Flca Trip the Nuclear Overpower Based on RCPPM Trip prevents the minimum core DNBR from decreasing below 1.30 by tripping the reactor due to the loss of reactor coolant pumps.

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l 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL SHUTDOWN MARGIN - SHUTOOWN LIMITING CONDITION FOR OPERATION 3.1.1.1.2 The SHUTDOWN MARGIN shall be 2;3.5% Ak/k.

APPLICABILITY: MODES 4 and 5.

' ACTION:

With the SHUTDOWN MARGIN < 3.5% Ak/k, immediately initiate and continue boration at 2.10 gpm of 11,600 ppm boric acid solution or its equivalent, until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.2.1 The SHUTDOWN MARGIN shall be determined to be 2; 3.5% Ak/k:

a.

Within one hour 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 un-trippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the innov-able or untrippable control rod (s).

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by consideratior. 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.

CRYSTAL RIVER - UNIT 3 3/4 1-2a

REACTIVITY CONTROL SYSTEFG FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 Each of the following boron injection flow paths shall be OPERABLE:

a.

A flow path from the concentrated boric acid storage system via a boric acid pump and makeup or decay heat removal (DHR) pump to the Reactor Coolant System, and b.

A flow path from the borated water storage tank via makeup or DHR pump to the Reactor Coolant System.

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

ACTION:

MODES 1, 2, and 3:

a.

With the flow path from the concentrated boric acid storage system inoperable, restore the inoperable flow path to OPERABLE status i

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 equivalent to 1% Ak/k at 200 F within the next'6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the flow path 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 .

I b.

With the flow path from the borated water storage tank inoperable, restore the flow path to OPERABLE status within one 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 .

MODE 4:

a.

With the flow path from the concentrated boric acid storage system inoperable, restore the inoperable flow path to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be borated to a SHUTDOWN MARGIN equivalent to 3.5% ak/k at 200 F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the flow path 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 .

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REACTIVITY CONTROL SYSTEMS MAKEUP PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4.2 At least one makeup pump shall be OPERABLE.

APPLICABILITY: MODE 4*

ACTION:

With no makeup pump OPERABLE, restore at least one makeup pump to OPERABLE status within one hour or be borated to a SHUTDOWN MARGIN equivalent to 3.5% ak/k at 200 F and be ir. COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.4.2 Na additional Surveillance Requirements other than those required by Specification 4.0.5.

With RCS pressure > 150 psig.

CRYSTAL RIVER - UNIT 3 3/4 1-10a

REACTIVITY CONTROL SYSTEMS BORIC ACID PUMPS - OPERATING 4

LIMITING CONDITION FOR OPERATION 3.1. 2. 7 At least one boric acid pump in the boron injection flow path. required by Specification 3.1.2.2a shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if the flow path through the boric acid pump in Specifica-tion 3.1.2.2a is OPERABLE.

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

ACTION:

MODES 1, 2, and 3:

With no boric acid pump OPERABLE, restore at least one boric acid pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at leagt HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to 1% ak/k 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 one boric acid pump 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 .

4 MODE 4:

With no boric acid pump OPERABLE, restore at least one boric acid pump to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be borated to a SHUTDOWN MARGIN equivalent to 3.5% ak/k 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 one boric acid pump 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 .

SURVEILLANCE REQUIREMENTS 4.1.2.7 No additional Surveillance Requirements other than those required by Specification 4.0.5.

1 CRYSTAL RIVER - UNIT 3 3/4 1-13

REACTIVITY CONTROL SYSTEMS B0 RATED WATER SOURCES - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.8 As a minimum,-one of the following borated water sources shall be L

0PERABLE:

a.

A concentrated boric acid storage system and associated heat tracing with:

1.

A minimum contained borated water volume of 6,730 gallons, 2.

Between 11,600 and 14,000 ppm of boron, and 3.

A minimum solution temperature of 105 F.

b.

The borated water storage tank (BWST) with:

1.

A minimum contained borated water volume of 13,500 gallons, 2.

A minimum boron concentration of 2,270 ppm, and 3.

A minimum solution temperature of 40 F.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no borated water sources OPERABLE, suspend all operations involving CORE ALTERATION or positive reactivity changes until at least one borated water source is restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS 4.1.2.8 The above required borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the boron concentration of the water, 2.

Verifying the contained borated water volume of the tank, and i

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2, B0 RATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.9 Each of the following borated water sources shall be OPERABLE:

a.

The concentrated boric acid storage system and associated heat tracing with:

1.

A minimum contained borated water volume of 6,730 gallons, 2.

Between 11,600 and 14,000 ppm of boron, and 3.

A minimum solution temperature of 105 F.

b.

The borated water storage tank (BWST) with:

1.

A contained borated water volume of between 415,200 and 449,000 1

gallons, 2.

Between 2,270 and 2,450 ppm of boron, and 3.

A minimum solution temperature of 40 F.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

MODES 1, 2, and 3:

a.

. With the concentrated boric acid storage system inoperable, restore the storage system 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 equivalent to 1% Ak/k at 200 F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the concentrated boric acid storage system 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 borated water storage tank inoperable, restore the tank to OPERABLE status within one 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 .

MODE 4:

a.

With the concentrated boric acid storage system inoperable, restore the storage system to 0PEkt.BLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of be l

4 CRYSTAL RIVER - UNIT 3 3/4 1-16

O REACTIVITY CONTROL SYSTEMS ACTION:

(Continued) borated to a SHUTDOWN MARGIN equiv lent to 3.5% Ak/k at 200 F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the oncentrated boric acid storage system 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 borated water storage tank inoperable, restore the tank to OPERABLE status within one hour or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.1.2.9 Each borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1.

Verifying the boron concentration in each water source.

2.

Verifying the contained borated water volume of each water source, and 3.

Verifying the concentrated boric acid storage system solution temperature.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by vgrifying the BWST temperature when outside air temperature is < 40 F.

CRYSTAL RIVER - UNIT 3 3/4 1-17

o REACTIVITY CONTROL SYSTEMS R2GULATING R0D INSERTION LIMITS LI?11 TING CONDITION FOR OPERATION 3.1.3.6 The regulating rod groups shall be limited in physical insertion as shown on Figures 3.1-1, 3.1-la, 3.1-2, 3.1-3, 3.1-3a, and 3.1-4 with a rod group overlap of 25 5% between sequential withdrawn groups 5 and 6, and 6 and 7.

APPLICABILITY: MODES 1* and 2*#.

ACTION:

With the regulating rod groups inserted beyond the above insertion limits, or with any group sequence or overlap outside the specified limits, except for surveillance testing pursuant to Specification 4.1.3.1.2, either:

a.

Restore the regulating groups to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or b.

Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allesed by the rod group position using the above figures within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or c.

Be in at least H0T STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

See Special Test Exceptions 3.10.1 ano 3.10.2.

With Keff " 1.0.

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, - _-._. _- 30.. _. _ _ _ _ _.

t REACTIVITY CONTROL SYSTEMS AXIAL POWER SHAPING R0D INSERTION LIMITS t

LIMITING CONDITION FOR OPERATION 3.1.3.9 The axial power shaping rod group shall be limited in physical insertion as shown on Figures 3.1-9, 3.1-9a, and 3.1-10.

APPLICABILITY: MODES 1 and 2*.

ACTION:

With the axial power shaping rod group outside the above insertion limits, either:

a.

Restore the axial power shaping rod group to within the limits within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or b.

Reduce THERMAL POWER to less than or equal to.that fraction of RATED THERMAL POWER which is allowed by the rod group position using the above figure within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , or c.

Be in at least H0T STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.9 The position of the axial power shaping rod group shall be determined.

to be within the insertion limits at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

With Keff " 1.0.

t CRYSTAL RIVER - UNIT 3 3/4 1-37 hm-m_

ilo (32,102)

AM 90 (8,92)

(38,92)

OPERATION

-(0,80)

(38,80) 80

_a 70

%60 O

f50 (100.50)

Ei 34 40 e:

30 20 ACCEPTABLE OPERATION 10 O

O 10 20 30 40 50 60 70 80 90 10 0 ROD POSITION,% WITHDRAWN FIGURE 3.1-9 AXIAL POWER SHAPING ROD GROUP INSERTION LIMITS FROM O EFPD TO 50 (+10/-0) EFPD CRYSTAL RIVER -UNIT 3 3/4 1-38

l10 (32,102)

(8,92)

(43,92)

BLE 90 OPERATION (0,80)

(51,8 0) 80 j 70 E

$ so Sg so (ioo,so)

Ei

$ 40 c:

E2 30 20 ACCEPTABLE OPERATION lo i

e i

i i

i g

o 10 20 30 40 so so to 80 so 10 0 ROD POSITION,% WITHDRAWN FIGURE 3.1-9a AXIAL POWER SHAPING ROD GROUP INSERTION LIMITS FROM 50 (+10/-0) TO 270 i 10 EFPD CRYSTAL RIVER -UNIT 3 3M l-38a

llo (8,102)

(35,102)

TAM 90 (8,92)

(47,92)

OPERATION 8 0,80)

(55,80) g 80 R

70 j!$ 60 8

$ so (ioo,so) at 4o a:

30 20 ACCEPTABLE OPERATION 10 O

O 10 20 30 40 50 60 70 80 90 100 ROD POSITION, % WITHDRAWN FIGURE 3.1-10 AXIAL PONER SHAPING ROD GROUP INSERTION LIMITS AFTER 270 i 10 EFPD CRYSTAL RIVER -UNIT 3

)

3/4 3-39

3/4.2 POWER DISTRIBUTION LIMITS AXIAL POWER IMBALANCE LIMITING CONDITION FOR OPERATION 3.2.1 AXIAL POWER IMBALANCE shall be maintained within the limits shown on Figures 3.2-1, 3.2-la, and 3.2-2.

APPLICABILITY: MODE I above 40% of RATED THERMAL POWER.*

ACTION:

With AXIAL POWER IMBALANCE exceeding the limits specified above,- either:

a.

Restore the AXIAL POWER IMBALANCE to within its limits within 15 minutes, or b.

Be in at least HOT STANDBY within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

SURVEILLANCE RFQUIREMENTS 4.2.1 The AXIAL POWER IMBALANCE shall be determined to be within limits in each core quadrant at least once every 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when above 40% of RATED THERMAL POWER except when an AXIAL POWER IMBALANCE monitor is inoperable, then calculate the AXIAL POWER IMBALANCE in each core quadrant with an inoperable monitor at least once per hour.

See Special Test Exception 3.10.1.

l 1

l r

i i

CRYSTAL RIVER - UNIT 3 3/4 2-1

O l

110

(-14.4,10 2)

(+ n.4,102) g

(-18.5,92)

(+17,92)

(-19,80) 80

.(+i7,80)

I 1

r O

k a:

o 40 Y.

UNACCEPTABLE 30 OPERATION

_ -- 20 10 ACCEPTABLE

NAM, i

i i

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL PCMER IMBALANCE, %

FIGURE 3.2-1 AX1AL PCPNER IMBALANCE ENVELOPE FOR OPERATION FROM O EFPD TO 50(+10/-0)EFPD CRYSTAL RIVER -UNIT 3 3/42-2

e llO

(-15.3,102)

(+15.3,oz)

( '22.5,92)

(+25,92)

(-23,80) 80

(+ 30,80) a:

70 aa i

E i

UNACCEPTABLE ND 20 ACCEPTABLE 10 t

t 1

I I

f I

-50

-40

-30

-20

-10 0

10 20 30 40 50 AXIAL PONER IMBALANCE, %

FIGURE 3.2-la AXtAL POWER IMBALANT ENVELOPE FOR OPERATION FROM 50(+10/-0) TO 270110 EFPD CRYSTAL RIVER - UNIT 3 3/42-2o

11 0 l

(-19,10 2)

(+15. 3,102)

(-31,92)

(+25,92) 80

(+30,80)

(-32,80)

I t-w

- 60 iE g_ _ 30 m:

8_ _ 4o 6

g 30 UNACCtrIABLE l

l OPERATION

__. 20 ACCEPTABLE 10 OPERATION t

f f

f I

f i

f I

l

-50

-40

-30

-20

-10 O

10 20 30 40 50 l

AXIAL POWER IMBALANCE, %

FIGURE 3.2-2 AX1AL POWER INEALANCE ENVELOPE FOR OPERATION AFTER 27010 EFPD CRYSTAL RNER - UNIT 3 3/4 2-3

Og TABLE 3.3-1

-H E

REACTOR PROTECTION SYSTEM INSTRUMENTATION M

x e

Minimum Total No.

Channels channels Applicable c-

z:

Functional Unit of channels, to trip _

operai:l e modes Action U

l.

Manual Reactor Trip 1

1 1

1, 2, and

8 2.

Nuclear Overpower 4

2 3

1, 2 2#

3.

RCS Outlet Tenperature - High 4

2 3

1, 2 3#

4 Nuclear Overpower Based on RCS Flow and AXIAL POWER IMBALANCE 4

2(a) 3

1. 2 2#

5.

RCS Pressure - Low 4

2(a) 3 1, 2 3#

6.

RCS Pressure - High 4

2 3

1, 2 3#

wA 7.

Variable Low RCS Pressure 4

2(a) 3 1, 2 3#

8.

Nuclear Overpower Based on RCPPMs 4

2(a) 3 1, 2 3#

9.

Reactor Containment Pressure - High 4

2 3

1, 2 3#

10.

Intermediate Range Neutron Flux and Rate 2

0 2

1, 2 and

4 11.

Source Range, Neutron Flux and Rate A.

Startup 2

0 2

2#1 and

5 D.

Shutdown 2

0 1

3, 4 and 5 6

12. Control Rod Drive Trip Breakers 2/ trip 1/ trip 2/ trip 1, 2 and

7#

system system system 13.

Reactor Trip Module 2/ trip 1/ trip 2/ trip 1, 2 and

7#

system system system

)

14 Shutdown Bypass RCS Pressure - High 4

2 3

2**, 3**

i 4 * *. 5" l

I

..J

e.

TABLE 3.3-2 REACTOR PROTECTION SYSTEM INSTRUMENTATION RESPONSE TIMES 9

-c Functional Unit Response Times 1.

Manual Reactor Trip Not Applicable 9

2.

Nuclear Overpower

1 0.326 seconds 3.

RCS Outlet Temperature - High Not Applicable ta 4.

Nuclear Overpower Based on RCS Flow and AXIAL POWER IMBALANCE

1 1.79 seconds 5.

RCS Pressure - Low 1 0.5 seconds 6.

RCS Pressure - High 1 0.5 seconds 7.

Variable Low RCS Pressure Not Applicable

[

8.

Nuclear Overpower Based on RCPPMs*

1 0.47 sec;.nds 9.

Reactor Containment Pressure - High Not Applicable

Neutron detectors are exempt from response time testing.

Response time of the neutron flux signal portion of the channel shall be measured from detector output or input of first electronic component in channel.

e w

a TABLE 4.3-1 9g REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS r-3 Channel Modes in which 9

Channel Channel functional surveillance Functional Unit check calibration test g quired 1.

Manual Reactor Trip N.A.

N.A.

S/U(1)

N.A.

U 2.

Nuclear Overpower S

D(2) and Q(7)

M 1, 2 ca 3.

RCS Outlet Temperature - High S

R M

1, 2 4.

Nuclear Overpower Based on RCS Flow and AXIAL POWER IMBALANCE S(4)

M(3) and Q(7,8)

M 1, 2 S.

RCS Pressure - Low S

R M

1, 2 6.

RCS Pressure - High S

R M

1, 2 7.

Variable Low RCS Pressure 5

R H

1, 2 8.

Nuclear Overpower Based on RCPPMs S

R M

1, 2 9.

Reactor Containment Pressure - High S

R M

1, 2 w

10, Intennediate Range, Neutron Flux and Rate S

R(7)

S/U(1)(S) 1, 2 and *

11. Source Range, Neutron Flux and Rate S

R(7)

S/U(1)(S) 2, 3, 4 and 5

12. Control Rod Drive Trip Breaker N.A.'

N.A.

M and S/U(1) 1, 2, and

13.

Reactor Trip Module N.A.

N.A.

H 1, 2,and

14.

Shutdown Bypass RCS Pressure - High S

R M

2",3",4",5"

s v'

REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 525 F.

This limitation is required to ensure that (1) the moderator temperature coefficient is within its analyzed temperature range, (2) the protective instrumentation is within its nor-mal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reactor pressure vessel is above its minimum RT temperature.

NDT 3/4.1. 2 B0 RATION SYSTEMS The boron injection system ensures that negative reactivity control is available 4

during each mode of facility operation. The components required to perform this function include (1). borated water sources, (2) makeup or DHR pumps, (3) separate flow paths, (4) boric acid pumps, (5) associated heat tracing systems, and (6) an emergency power supply from 0PERABLE emergency busses.

With the RCS average temperature above 200 F, a minimum of two separate and redun-dant boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoperable. Allowable out-of-service periods ensure that minor component repair of corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.

The boration capability of eiths.r rystem is sufficient to provide a SHUTDOWN MARGIN from all operating conditions to 3.5% Ak/k after xenon decay and cooldown to 200 F.

The maximum boration capability requirement occurs from full power equilibrium xenon conditions and requires either 6,730 gallons.of 11,600 ppm boric acid solution from the boric acid storage tanks or 47,698 gallons of 2,270 ppm borated water from the i

borated water storage tank.

The requirements for a minimum contained volume of 415,200 gallons of borated water in the borated water storage tank ensures the capability for borating the PCS to the desired level. The specified quantity of borated water is consistent with the ECCS requirements of Specification 3.5.4.

Therefore, the larger volume of borated water is specified.

With the RCS temperature below 200 F. one injection system is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity change in the event the single injection system becomes inoperable.

The boron capability required below 200 F is sufficient to provide a SHUTDOWN MARGIN of 3.5% Ak/k after xenon decay and cooldown from 200 F to 140 F.

This condition requires either 300 gallons of 11,600 ppm boric acid solution from the boric acid storage system or 1,608 gallons of 2,270 ppm borated water from the borated water storage tank.

To envelop future cycle BWST contained borated water volume require-ments, a minimum volume of 13,500 gallons is specified.

CRYSTAL RIVER - UNIT 3 B 3/4 1-2 4

r a

,m.

m 7..

.,m.

,,,,,.,,,g,,,.y..,y.,,_.

y -,,,.,

e,

,y

.o o'

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics. The limits on containcd water volume and' boron concentration ensure a pH value of between 7.2 and 11.0 of the solution sprayed within the containment after a design basis accident.

The pH band minimizcs the evolution of iodine and minimizes the effect of chlorides and caustic stress corrosion cracking on mechanical systems and

. components.

The 0PERABIlliY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in MODE 6.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications ofx this:section (1) ensure that acceptable power distribution limits are maintained, (2) ensure that the minimum SHUTDOWN MARGIN is maintained, and (3) limit the potential effect of a rod ejection accident.

OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.

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

For example, misalignment of a safety or regulating rod requires a restriction in THERMAL POWER. The reactivity worth of a misaligned rod is limited for the remainder of the fuel cycle to prevent exceeding the assumptions used ir.

the safety analysis.

The position'of a rod declared inoperable due to misalignment should not be included in computing the average group position for determining the OPERABILITY of rods with lesser misalignments.

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

F L~

3/4.4 REACTOR COOLANT SYSTEM REACTOR COOLANT LOOPS LIMITING CONDITION FOR OPERATION 3.4.1 Both reactor ccolant loops and both reactor coolant pumps in each loop shall be in operation.

APPLICABILITY: As noted below, but excluding MODE 6.*

ACTION:

MODES 1 and 2:

a.

With one reactor coolant pump not in operation, STARTUP and POWER OPERATION may be initiated and may proceed provided THERMAL POWER is restricted to less than 79.92% of RATED THERMAL POWER and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the setpoints for the following trips have been reduced to the values specified in Specification 2.2.1'for operation with three reactor coolant pumps operating:

1.

Nuclear Overpower i

MODES 3, 4, and 5:

1 l-a.

Operation may proceed provided at least one reactor coolant loop is in operation wich an associated reactor coolant pump or decay j

heat removal pump.

b.

The provisions of Specifications 3.0.3 and 3.0.4 arn no' applicable.

4 t

SURVEILLANCE REQUIREMpiT_S 4.4.1 The Reactor Protective Instrumentation channels specified in the applicable ACTION statement above shall be verified to have had their trip setpoints changed to the values specified in Specification 2.2.1 for the j

applicable number of reactor coolant pumps operating either:

a.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after ret tching to a different pump combinatian i

if the switch is made waile operating, or b.

Pi:or to reactor criticality if the switch is made while shutdown.

i!

4 See Special Test Exception 3.10.3.

j CRYSTAL RIVER - UNIT 3 3/4 4-1 i

,

v t e Letter Sequence Other
TAC:46962, (Approved, Closed)
Initiation Request, Request, Request, Request, Request Acceptance... Administration Meeting Questions Answers Results Approval, Approval, Approval, Approval, Approval Other: ML19320D593, ML19331C271, ML19331C277, ML19340B529, ML19350C772, ML20003C510, ML20009H240, ML20009H245, ML20030C723, ML20030C729, ML20032E918, ML20032E922, ML20032E929, ML20033B435, ML20038C770, ML20038C776, ML20038C783, ML20039A978, ML20039A984, ML20039F150, ML20053D278
MONTHYEAR1981-12-08 [Table View]

ML20032E922

Text

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