ML20058E034

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Amend 137 to License DPR-51,revising Tech Specs 2.1,2.3, 3.1.7 & 3.5.2 to Support Reload for Cycle 10
ML20058E034
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 10/29/1990
From: Quay T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20058E037 List:
References
NUDOCS 9011060410
Download: ML20058E034 (23)
v • d • e


Text

.

, h [M. s* *\\oug[o,, i UNITED STATES

'. 7, NUCLEAR REGULATORY COMMISSION Ej WASHINGTON, D, C. 20$$$

\\...+./

ENTERGY OPERATIONS INC.

DOCKET NO. 50-313

-ARKANSAS NUCLEAR ONE. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 137 License No. DPR-51 1.-

The Nuclear Regulatory Commission (the Comission) has found that:

'l A.-

The application for amendment by Entergy Operations, Inc. (the licensee)datedAugust8 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission's rules and regulations set -forth in 10 CFR Chapter I; L

l' B.

.The facility will operate in conformity with the application, the J

provisions of the Act, and the rules and regulations of the L

Comission;:

L L

C.

There is reason 6ble assurance:

(1)thattheactivitiesauthorized' by this amendment can be conducted without endangering the health

- andcsafety of the public, and (ii) that such activities will be f

conducted in compliance with the Comission's regulations; t

.D.

The issuance of this license amendment.will not be inimical to the C

and~

common defense and security-or to the--health and safety.of Lthe public; 1

E.

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

1o L

E l

9011060410 901029 PDR-ADOCK 05000313

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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.

L DPR-51 is hereby amended to read as follows:

2.

Technical Specifications i

The Technical Specifications contained in Appendix A, as revised through Amendment No.137, are hereby incorporated

.in.the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

The license' amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION U$4< cNtu-.0-9 Theodore R. Quay, Acting Director o

Project Directorate IV-1 Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor. Regulation

Attachment:

l Changes to the Technical h

Specifications L

Date of! Issuance:

October 29, 1990 t i l

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ATTACHMENT TO LICENSE AMENDMENT NO. 137 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Revise the following pages of the Appendix "A" Technical Spr;ifications with the attached pages. The revised pages are identifie<' oy Amendment number and contain vertical lines indicating the area of change.

REMOVE PAGES

_ INSERT PAGES, iv iv v

v 9b 9b 14b 14b 30 30 47 47 48 48 48b 48b 48c 48c 48d-48d 48e-48e 48f 4Bf 48g 489 48h 48h 481 481 48j-4Bj 48k 48k 481 481 48m -

48m 48n 48n

. e' e

i j

LIST OF FIGURES l

Number Tit 1e

,P_aae 2.1-1 CORE PROTECTION SAFETY LIMITS 9a 2.1-2 CORE PROTECTION SAFETY LIMITS 9b 2.1-3 CORE PROTECTION SAFETY LIMITS 9c

]

2.3-1 PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINT 14a 2.3-2 PROTECTIVE SYSTEM MAXIMUM ALLOWABLE SETPOINTS 14b 3.1.2-l' REACTOR COOLANT SYSTEM HEATUP AND C00LDOWN LIMITATIONS 20a 3.1.2-2 REACTOR COOLANT SYSTEM NORMAL OPERATION-HEATUP 20b LIMITATIONS

-3.1.2-3 REACTOR COOLANT SYSTEM, NORMAL OPERATION COOLDOWN 20c LIMITATIONS

'3.1.9-1 LIMITING PRESSURE VS. TEMPERATURE FOR CONTROL R00 DRIVE 33 OPERATION WITH 100 STD CC/ LITER H O 2

3.2-1 BORIC ACID ADDITION TANK VOLUME AND CONCENTRATION VS. RCS 35a AVERAGE TEMPERATURE 3.5.2-1A R0D POSITION SETPOINTS FOR FOUR-PUMP OPERATION FROM 0 48t to 30 +10/-0 EFPD - ANO-1 CYCLE 10 3.5.2-1B ROD POSITION SETPOINTS FOR FOUR-PUMP OPERATION FROM 48c

[

30 +10/-0 TO 335 +10/-10 EFPD - ANO-1 CYCLE 10 l.-

3.5.2-1C ROD POSITION SETPOINTS FOR FOUR-PUMP OPERATION AFTER 48d>

p

'335 +10/-10 EFPD ANO-1 CYCLE'10 l-3.5.2-2A ROD POSITION SETPOINTS FOR THREE-PUMP OPERATION FROM 0 48e TO 30'+10/-0'EFPD - ANO-1 CYCLE 10 3.5.2-2B'

~ ROD POSITION SETPOINTS FOR THREE-PUMP OPERATION FROM 48f l

30 +10/-0 TO 335 +10/-10 EFPD - ANO-1 CYCLE 10 3.5.2-2C ROD POSITION SETPOINTS FOR THREE-PUMP OPERATION AFTER 48g 335 +10/-10 EFPD - ANO-1 CYCLE 10 x

Amendment No. 52, 72, 92, 105, II3, iv 137

=

  • 3.5.1 3A ROD POSITION SETPOINTS FOR TWO PDMP OPERATION FROM 0 48h TO 30 +10/ 0 EFPD - ANO-1 CYCLE 10 3.5.2-3B ROD POSITION SETPOIN15 FOR TWO-PUMP OPERATION FROM 481 30 +10/-0 TO 335 +10/-10 EFPD - ANO-1 CYCLE 10 3.5.2-3C ROD POS!110N SETPOINTS FOR TWO-PUMP OPERATION AFTER 48j 335 +10/-10 EFPD - ANO-1 CYCLE 10 3.5.2 4A OPERATIONAL POWER IMBALANCE SETP01 HTS FOR OPERATION FROM 48k 0 TO 30 +10/-0 EFPD - ANO-1 CYCLE 10 3.5.2-4B OPERATIONAL POWER IMBALANCE SETPOINTS FOR OPERATION FROM 481 30 +10/-0 TO 335 +10/-10 EFPD - ANO-1 CYCLE 10 3.5.2-4C OPERATIONAL POWER IMBALANCE SLTPOINTS FOR OPERATION AFTER 48m 335 +10/-10 EFPD - ANO CYCLE 10 3.5.2-5 LOCA LIMITED MAXIMUM ALLOWABLE LINEAR HEAT RATE 48n ANO CYCLE 10 3.5.4-1 INCORE INSTRUMENTATION SPECIFICATION AXIAL IMBALANCE 53a INDICATION 3.5.4-2 INCORE INSTRUMENTATION SPECIFICATION RADIAL FLUX TILT 53b INDICATION 3.5.4-3 INCORE INSTRUMENTATION SPECIFICATION 53c 3.24-1 HYDROGEN LIMITS FOR ANO-1 WASTE GAS SYSTEM 110be 4.4.2-1 NORMALIZED LIFTOFF FORCE - HOOP TENDONS 85b I

4.4.?-2 NORMALI2ED LIF10FF FORCE - DOME TENDONS BSc L

4.4.2-3 NORMALIZED LIFTOFF FORCE - VERTICAL TENDONS 85d l

l l

Amendment No. 52, 80, 86. 92, 93, v

97, 105,',i13, 137

t Core Protection Safety Limits - ANO-1 Figure 2.1-2 O

a Thermal Powcr Ls,el

% FP

. 120

. (-33.5.112.0)

,(33.5,112)

ACCEPTABLE l 4 PUMP 1

,(42.6.103.6) 100 g

(-49.7,96.9) l C ERATION

(-33.5,90.75)

(33.5.90.75) l m

I l ACCEPTABLE I

3&4 PUMP (42,6,82.35)

- 80

(-49.7,75.65)i l OPERATION l

l l

1 l

l-1 (-33.5,64.08)

(33.5,64.08)l l

l'

- 60 l ACCEPTABLE I

2,3M PUMP (42.6,55.68) l OPERATION 1

(-49.7,48.98),

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l I

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- 40 l

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l

- 20 l

1 l

l 1

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11 1

1

-60

-40

-20 0

20 40 60 80 Reactor Power labalance, 1 Amendment No. E, 22, 3I, A3, 52, 57, 9b l

7I, 92, 113, 137

)

l 4

L

=

Protective System Maximum Allowable Setpoints ANO-1. Figure 2.3-2

^

o Thermal Power Level, 1 FP 120

(-18.0.107) _

_ (18.0.107) 100 ACCEPTABLE l

4 PUMP l

(3I'8*93 2)

(-38.5,86.5)

OPERATION l

(-18.0,79.9) l 80 I

(18.0,79.9)

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l ACCEPTABLE (31.8,66.1) 384 PUMP

(-38.5,59.4) g OPE TION 60 l

(-18.0,52.6) l l

(18.0,52.6)

^

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l 40 ACCEPTABLE..

> (31.3,38.8) 2

(-38.5.32.1 )

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l 20 g

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l l-1 l

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0 I

il il is l

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-60

-40

-20 0

20 40 60 Reactor Power Imbalance, 5 i

i Amendment No. 5, ZI, 3I, 43, 52, 57, 7I, 92, 14b I13, 137,

3.1.7 Moderator Temperature Ceefficient of Reactivity Specification 3.1.7.1 The moderator temperature coefficient (MTC) shall be non positive whenever thermal power is 29;% of rated thermal power and shall be less positive than 0.9 x IO

  • ok/k/'F whenever thermal power is (95% of rated thermal power and the reactor is not shutdown.

3.1.7.2 The MTC shall be determined to be within its limits by confirmatory measurements prior to initial operation above 5% of rated thermal power after each fuel loading.

MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the limits in 3.1.7.1 above.

3.1. 7. 3 With the MTC outside any one of the above limits, 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 />.

Bases A non positive moderator coefficient at power levels above 95% of rated power is specified such that the maximum clad temperatures will not exceed the Final Acceptance Criteria based on LOCA analyses.

Below 95% of ra+.ed power, the Fina.1 Acceptance Criteria will not be exceeded with a positive moderator temperature coefficient of +0.9 x 10 4 Ak/k/*F corrected to 95% of rated power.

The most limiting event for positive MTC, the Startup Accident', has been analyzed for a range of moderator temperature coefficients including +0.9 x 10 4 Ak/k/'F.

l Amendment No. fl. JZ, 57,137 30

6.

If a control rod in the regulating or axial power shaping groups is declared inoperable per Specification 4.7.1.2 operation above 60 percent of the thermal power allowable for i

the reactor coolant pump combination may continue provided the rods in the group are positioned such that the rod that was declared inoperable is contained within allowable group average position limits of Specification 4.7.1.2 and the withdrawal limits of Specification 3.5.2.5.3.

3.5.2.3 The worth of single in,terted control rods during criticality are limited by the restrictions of Specification 3.1.3.5 and the Control Rod Position Lisits defined in Specification 3.5.2.5.

4 3.5.2.4 Quadrant tilt:

1.

Except for physics tests, if quadrant tilt exceeds 4.24%,

reduce power so as not to exceed the allowable power level for the existing reactor coolant pump combination less at least 2% for each 1% tilt in excess of 4.24%.

2.

Within a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the quadrant power tilt shall be ceduced to less than 4.24% except for physics tests, or the j

following adjustments in setpoints and limits shall be made:

'a.

The protection system maximum allowable setpoints (Figure 2.3-2) shall be reduced 2% in power for each 1%

tilt in excess of 4.24%.

l b.

The control rod group and APSR withdrawal limits shall be reduced 2% in power for each 1% tilt in excess of i

4.24%.

I P

c.

The operational imbalance limits shall be reduced 2% in power for each 1% tilt in excess of 4.24%.

3.

If quadrant tilt is in excess of 25%, except for physics tests or diagnostic testing, the reactor will be placed in the F.4 shutdown condition.

Diagnostic testing during power j

operr.cion with a quadrant power tilt is permitted provided the thermal power allowable for the reactor coolant pump l

combination is testricted as stated in 3.5.2.4.1 above.

4.

Quadrant tilt shall be monitored on a minimum frequency of once every two hours during power operation above 15% of rated power.

l l

AmendmentNo.6.21,yI,#3,92,105, 47 123, 1 l

1

i I 3.

Except for physics tests or exercising control rods, the control rod withdrawal linits are specified on Figures

3. 5. 2-1( A-C), 3. 5. 2-2( A-C), and 3. 5. 2-3( A-C) for 4, 3, and 2 pump operation respectively.

If the applicable control rod position limits are exceeded, corrective measures shall be taken immediately to achieve an acceptable control rod position.

Acceptable control rod positions shall be attained within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.

Except for physics tests or exercising axial power shaping rods (APSRs), the following limits apply to APSR position:

Up to 345 EFPD, the APSRs may be positioned as necessary for l

transient imbalance control, however, the APSRs shall be fully withdrawn by 345 EFPD.

After 345 EFPD, the APSRs shall l

not be reinserted.

With the APSRs inserted after 345 EFPD, corrective measures shall be taken immediately to achieve the full withdrawn position.

Acceptable APSR positions shall be attained within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

3.5.2.6 Reactor Power Imbalance shall be monitored on a frequency not to expeed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during power operation above 40% rated power.

Except for physics tests, imbalance shall be maintained within the envelope defined by Figure 3.5.2-4(A-C).

If the imbalance is not within the envelope defined by Figure 3.5.2-4(A-C), corrective measuras shall be taken to achieve an acceptable imbalance.

If an acceptable imbalance is not achieved within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, reactor power shall be reduced until imbalance limits are met.

3.5.2.7 The control rod drive patch panels shall be locked at all times with limited access to be authorized by the Superintendent.

Bases The power-imbalance envelope defined in Figure 3.5.2-4(A-C) is based on LOCA analyses which have defined the maximum linear heat rate (see Figure 3.5.2-5), such that the maximum cladding temperature will not exceed the Final Acceptance Criteria.

Corrective measures will be taken immediately should the indicated quadrant tilt, rod position, or imbalance be outside their specified boundaries.

Operation in a situation that would cause the Final Acceptance Criteria to be approached should a LOCA occur is highly improbable because all of the power distribution parameters (quadrant tilt, rod position, and imbalance) must be at their limits while Amendment No. 5, 2Z, II, #3, 92, 105, 48 ZI3,137 I

Rod Position Setpoints for 4-Pump Operation From 0 to 30 +10/-0 EFPD AND-1 Cycle 10 8

l a

Figure 3.5.2-1A 110 i

(200.9.102)

(300,102)

(272.9.102);

100 SHUTDOWN (270.5,90) 90 MARGIN LIMIT OPERATION IN THl$

j 30 REGION IS NOT s

E ALLOWED OPERATION (255.5.78) 70 RESTRICTED N

60 g

we c 50 (109.5,48)

(227.5.48)

I a-40 PERM 15$1BLE 30 OPERATING REGIM 20 10 (73.5.13)

.(0,0) 0 l

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Rod Position Setpoints for 4-Pump Operation From 30 +10/-0 to 335 +10/-10 EFPD ANO-1 Cycle 10 l

Figure 3.5.2-1B 110 (300.102)

(200.9.102)

(27).1.102) 4 100 SHUTDOWN (266.5,90) 90 i

MARGIN LIMIT E

(251.5,78)

~

ce OPERATION IN THl$

$ 70 REGION IS NOT ALLOWED OPERATION o

RESTRICTED w 60 u'

f 50 (109.5.48)

(227.5.48).

40 30 PERMISSIBLE OPERATING REGION 20 10 (73.5.13)

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--_._-__---_-_----_._.-_--____--------_.-__._____._---_____--_____--_____-___A

Rod Position Setpoints for 4 - Pump Operation After 335 010/-10 EFPD AND-1 Cycle 10 figure 3.5.2-1C

.o 110 (215.0.102)

(300,102)

.1.102);

100 - -

SHUTDOWN MARGIN (266.5.90)p 90 OPERATION IN THIS LIMIT REGION IS NOT

[

g 80 AROWD (251.5,78)

=$ 70 N

OPERATION RESTRICTED

, 60 u

g 50 (121.5.48)

(227.5,48) a.

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p l-Rod Position Setpoints for 3-Pump Operation From 0 to 30 +10/-0 EFP0 -- AND-1 Cycle 10 l

Figure 3.5.2-2A

, a 110 100 90 (300,77) 80 (202.0,77)

(273.0,77)

^

N SHUTDOWN 70 MARGIN (270.5,67)

OPERATION IN THIS LIMIT

{60 REGION IS NOT (255.5,58) o ALLOWED

" 50 J

OPERATION l40 RESTRICTED (109.5,36)

(227.5,35.5) 30 1

PERMISSIBLE 20 OPERATING 10 REGION (73.5,9.8) 1 I

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... ~. - _ - _..

Rod Position Setpoints for 3-Pump Operation From 30 +10/-0 to 335 +10/-10 EFP0 -- ANO-1 Cycle 10 figure 3.5.2-20 i

110 100 90 (202.0,77)

@0.7M 80 (270.3,77) 7 E

SHUT 00WN 70 MARGIN (266.5,67) f OPERATION IN THIS LIMIT

/

60 REGION IS NOT (251.5,58) o ALLOWE0

~

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40 RESTRICTE0 l

m (109.5.36)

(t

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REGION (0,0) 0 1

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Rod Position Setpoints for 3-Pump Operation l

After 335 +10/-10 EFPD -- ANO-1 Cycle 10 l

Figure 3.5.2-2C o

110 100 90 (300,77) 80 (270.3,77)

(216.1,77) s E

g 70 OPERATION IN THIS SHUTDOWN (266.5,67) i u

RrGiON IS NOT MARGIN g 60 ALLOWED LIMIT (251.5.58)

I e

g 50 OPERATION g

RESTRICTED 40 (121.5.36)

(227.5.35.5) 30 20 PERMISSIBLE 10 OPERATil66 (79.5.9.8)

(0, REGION g

g

)

0' 20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 0

20 40 60 80 100 i-i i

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l Amendment No. If!5, II3,137 48g

Rod Position Setpoints for 2-Pump Operation l

From 0 to 30 +10/-0 EFPD -- ANO-1 Cycle 10 Figure 3.5.2-3A a

110 100 90 g 80

$ 70 N

o 60 (204.3.52)

(300,52)

(273.2,52)

^

5-g 50 OPERATION IN THIS SHUT 00WN F

A REGION IS NOT MARGIN (270.5,44) i ALLOWED LIMIT 40 (255.5.38)

OPERATION 30 RESTRICTED (109.5.24)

(227.5,23) g PERMISSIBLE 10 OPERATING (73.5,6.5)

REGION (0,0)0 1

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. -. _ _ ~ _ _ - - -.

, ~ _.. - -.

Rcd Position Setpoints for 2-Pump Operation from 30 10/-0 to 335 o10/-20 EFPD -- ANO-1 Cycle 10 l

Figure 3.5.2-3B s

110 4

100 90 g 80 no 70 s

~

(300,52) c (204.3,52)

(270.5,52) -

r

[

50 OPERATION IN THIS n.

REGION IS NOT SHUTDOWN (266.5,44)

ALLtWED MARGIN 40 LIMIT (251.5,38) 30 OPERATION (109.5.24)

RESTRICTED (227.5,23)

PERMISSIBLE 10 (73.5,6.5 OPERATING REGION (0,0) 0: - -

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20 40 60 80 100 120 140 160 180 200 220 240 260 280 300 s

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20 40 60 80' 100 l

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j Rod Position Setpoints for 2-Pump Operation I

Af ter 335 +10/-10 EFP0 -- ANO-1 Cycle 10 l

Figure 3.5.2-3C l

l.

110 t

100 90 I

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-[ 80 f70 o,60 (300,52)

OPERATION IN THIS SHUTDOWN (218.4.52)

(270.5,52);

50 L

REGION IS NOT

-MARGIN (266.5,44)-

ALLOWED LIMIT.

40 (251.5.38) t L

1 30 (121.5.24)

OPERATION l

RESTRICTED (227.5.23) r 20 PERMISSIBLE (79.5,6.5 OPERATING 10 1

REGION 1

-(0,0) 0, I

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Operational Power Imbalance Setpoints for Operation From 0 to 30 +10/-O'EFPD -- ANO-1. Cycle 10 figure 3.5.2-4A i

1

(

- 110 i

(-15.05.102)

- (13.93,102)

"100

(-16.15,92)

(16.97.92)

-90

(-22.10,80)

.80

>(20.05,80)

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.Og RESTRICTED

@g

}g REGION g

g REGION l

E E-

[w-

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10-20 30 40 50 Axial Power Imbalance, 5 Y

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Amendment No. 'IB5, IZ3, 137, 48k e

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Operational Power Imbalance Setpoints for Operation From 30 +10/-0 to 335 +10/-10 EFPD -- ANO-1, Cycle 10 l

Figure 3.5.2-4B o

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-- 110

(-19.61,102)

- (17.53,102)

" " 100

(-20.72,92) 90

, (20.59,92)

(-23.80,80)<

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1

-50 30 -20

-10' 0

to 20 30 40 50 Axial Power Imbalance, 5 I

t i

4

'j'.

Amendment No. If 5, III,137, 481 i

l

-. ~ - -

Operational Power Imbalance Setpoints for Operation After 335 +10/-10 EFPD -- ANO-1, Cycle 10 l

Figure 3.5.2-4C a

- - 110

(-20.47,102)

- (17.58,102)

(-21.59,92) 90 (21.59.92) 80

>(23.71,80)

(-23.71.80)< >

RESTRICTED 70 RESTRICTED REGION g!

g!

REGION ens eus E5G 60E"bW G

EbW E

50

(-24.19,50)

> (24.19,50) a E

40 k

30 o

IPO 20 uI 10

a. - -

-t i

i i

I i

i i

i 1

' 40 -30

-20

-10 0

-10 20 30 40 50 Axial Power Imbalance, 1

~

Amendment No IS5, IZ3, 137, 48m

LOCA Liaited Maxt:tum Allowable Linear Heat Rate -- ANO-1 Cycle 10 Figure 3.5.2-5 l

i 20

{18 2

a eI

~

$16 f

/

/

.3

/

14

-=

g

[ 12 O to 1000 mwd /mtU t

l.

Af ter 1000 mwd /mtU 10 i

i e

i i

i i

i i

a n.

O.

2 4

16 8

10 12 Axial Location From Bottom of Core.-ft f

i Amendment No. 11 52, 7I, 92, Z85, 48n IZ3,157 I

-

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