Text

Amend 169 to License NPF-6,deleting TS Requirments Associated W/Part Length Control Assemblies
	ML20093H721
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/12/1995
From:	Kalman G; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20093H722	List: ML20093H721; ML20093H732;
References
	NPF-06-A-169 NUDOCS 9510200318
	Download: ML20093H721 (23)
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lt UNITED STATES NUCLEAR REGULATORY COMMISSION If WASHINGTON, D.C. 30666-0001

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ENTERGY OPERATIONS. INC.

l DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.169 License No. NPF-6 1.

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

A.

The application for amendment by Entergy Operations, Inc. (the licensee) dated April 4,1995, 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 facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable ass _urance:

(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 will be conducted in compliance with the Commission's regulations; D.

The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and i

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.

9510200318 951012 PDR ADOCK 05000368 P

PDR

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-6 is hereby amended to read as follows:

(2) Technical Specifications l

The Technical Specifications contained in Appendix A, as revised through Amendment No.169, are hereby incorporated in the license.

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

3.

The license amendment is effective within 30 days of the issuance date.

FOR THE NUCLEAR REGULATORY COMMISSION j

George Kalman, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: October 12, 1995 i

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ATTACHMENT TO LICENSE AMENDMENT NO. 169 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. The corresponding i

overleaf pages are also provided to maintain document completeness.

REMOVE PAGES INSERT PAGES IV IV 3/4 1-17 3/4 1-17 3/4 1-18 3/4 1-18 3/4 1-19 3/4 1-19 3/4 1-22 3/4 1-22 3/4 1-23 3/4 1-23 3/4 1-25 3/4 1-25 4

3/4 1-26 3/4 1-26 3/4 1-27 4

3/4 2-3 3/4 2-3 3/4 3-5b 3/4 3-5b 3/4 3-5c 3/4 3-Sc 3/4 9-1 3/4 9 2 3/4 9-7 3/4 9-7 3/4 10-1 3/4 10-1 3/4 10-2 3/4 10-2 B 3/4 1-5 B 3/4 1-5 5-4 5-4 6-21 6-21 6-21a 6-21a

INDEX LIMITING COMDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0-APPLICABILITY.........................................

3/4 0-1 4.

3/4.1 REACTIVITY CONTROL SYSTEMS t

3/4.1.1 BORATION CONTROL Shutdewn Margin - Tavg > 2 00'F......................

3/4 1-1 Shutdown Ma rgin - Tavg s; 2OO'F......................

3/4 1-3 Boron Dilution......................................

3/4 1-4 Moderator Temperature coefficient...................

3/4 1-5 j

Minimum Temperature for criticality.................

3/4 1-6 3/4.1.2 BORATION SYSTEMS

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Flow Paths - Shutdown...............................

3/4 1-7 Flow Paths - Operating..............................

3/4 1-8 Charging Pump Shutdown..............................

3/4 1-9 Charging Pumps Operating............................

3/4 1-10 Boric Acid Makeup Pumps - Shutdown..................

3/4 1-11 L

Boric Acid Makeup Pumps - Operating.................

3/4 1-12 Borated Water Sources - Shutdown....................

3/4 1-13 Borated Water Sources - Operating...................

3/4 1-15 3/4.1.3 CONTROL ELEMENT ASSEMBLIES l

CEA Position........................................

3/4 1-17 Position Indicator Channels - Operating.............

3/4 1-20 Position Indicator Channels - Shutdown..............

3/4 1-22 CEA Drop Time.......................................

3/4 1-23 Shutdown CEA Insertion Limit........................

3/4 1-24 Regulating and Group P CEA Insertion Limits.........

3/4 1-25 l

l ARKANSAS - UNIT 2 IV Amendment No. M,40,157

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REACTIVITY CONTROL SYSTEMS 3/4.1.3 CONTROL ELEMENT ASSEMBLIES l

CEA POSITION LIMITING CONDITION FOR OPERATION 3.1.3.1 All CEAs shall be OPERABLE with each CEA of a given group positioned l

within 7 inches (indicated position) of all other CEAm in its group.

I APPLICABILITY: MODES 1* and 2*.

ACTION:

a.

With one or more CEA(s) inoperable due to being immovable as a result l

of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN requirement 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 STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one CEA trippsble but inoperable due to causes other than l

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

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pursuant to the requirements of Specification 3.1.3.6.

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c.

With one CEA trippable but inoperable due to causes other than l

l addressed by ACTION (a), above, but within its above specified j

alignment requirements and either fully withdrawn or within the Long Term steady State Insertion Limits if in CEA group 6 or l

group P, operation in MODES 1 and 2 may continue.

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d.

With more than one CEA trippable but inoperable due to causes other than addressed by ACTION (a), above, restore the inoperable e

CEA(s) 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

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STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l e.

With one or more CEA(s) trippable but udsaligned from any other CEA l

in its group by more than 7 inches but less than or equal to 19 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with the limits specified in the CORE OPERATING LIMITS REPORT and within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the misaligned 1

CEA(s) is either:

1.

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

See Special Test Exceptions 3.10.2 and 3.10.4.

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ARKANSAS - UNIT 2 3/4 1-17 Amendment No. M,M&,-149,

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REACTIVITY CONTROL SYSTEMS, ACTION: (Continued) 2.

Declared inoperable and the SNUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied. After declaring the i

CEA inoperable, operation in MODES 1 and 2 may continue i

pursuant to the requirements of Specification 3.1.3.6 provided:

a) Within one hour the remainder of the CEAs in the group with the inoperable CEA shall be aligned to within 7 4

inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits specified in the CORE OPERATING LIMITS REPORT; the THERMAL POWER level shall be restricted pursuant to Specification l

3.1.3.6 during subsequent operation.

f b) The SHUTDOWN MARGIN requirement 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 .

Otherwise, 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 .

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f.

With one CEA trippable but udsaligned from any other CEA in its l

group by more than 19 inches, operation in MODES 1 and 2 may continue, provided that core power is reduced in accordance with

-the limits specified in the CORE OPERATING LIMITS REPORT and within i

one hour, the misaligned CEA is either:

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1.

Restored to OPERABLE status within its above specified j

alignment requirements, or 2.

Declared inoperable and the SHUTDOWN MARGIN requirement of i

specification 3.1.1.1 is satisfied. After declaring the l

CEA inoperable, operation in MODES 1 and 2 may continue pursuart to the requirements of Specification 3.1.3.6 l

provides.

l a) Mithin one hour the remainder of the CEAs in the group with the inoperable CEA shall be aligned to within 7 i

inches of the inoperable CEA while maintaining the allowable CEA sequence and insertion limits specified in the CORE OPERATING LINITS REPORT; the THERMAL POWER 1

level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.

4 b) The SHUTDOWN MARGIN requirement 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 .

1 Otherwise, 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 , l

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i ARKANSAS - UNIT 2 3/4 1-18 Amendment No. M,4-24,4M

REACTIV7TY CONTROL SYSTEMS a

ACTION (Continued) g.

With more than one CEA trippable but misaligned from any other CEA in its group by more than 19 inches (indicated position),

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

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The position of each CEA shall be determined to be within l

7 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 .

4.1.3.1.2 Each CEA not fully inserted in the core shall be determined l

to be OPERABLE by movement of at least 5 inches in any one direction at least once per 31 days.

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4 ARKANSAS - UNIT 2 3/4 1-19 Amendment No. M,M6

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REACTIVITY CONTROL SYSTEMS

'4 POSITION INDICATOR CHANNELS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.3.3 At least one CEA Reed Switch Position Transmitter indicator channel shall be OPERABLE for each CEA not fully inserted.

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APPLICABILITY: MODES 3*, 4* and 5*.

I ACTION:

I With less than the above required position indicator channel (s) OPERABLE, inwnediately open the reactor trip breakers.

SURVEILLANCE REQUIREMENTS 1

4.1.3.3 Each of the above required CEA Reed switch Position Transmitter indicator channel (s) shall be determined to be OPERABLE by performance of a l

CHANNEL IVNCTIONAL TEST at least once per 18 anonths.

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With the reactor trip breakers in the closed position.

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i ARKANSAS - UNIT 2 3/4 1-22 Amendment No.169

REACTIVITY CONTROL SYSTEMS CEA DROP TIME LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual CEA drop time, from a fully withdrawn position, l

shall be s 3.5 seconds and the arithmetic average of the CEA drop times of all CEAs, from a fully withdrawn position, shall be s 3.2 seconds from l

when the electrical power is interrupted to the CEA drive mechanisms until the CEAs reach their 90 percent insertion positions with:

T 2525'F, and j

a.

ayg 1

b.

All reactor coolant pumps operating.

APPLICABILITY: MODES 1 and 2.

ACTION:

4 a.

With the CEA drop times determined to exceed either of the above limits, restore the CEA drop times to within the above limits prior to proceeding to MODE 1 or 2.

f b.

With the CEA drop times within limits but determinea at less than full reactor coolant flow, operation may proceed provided THERMAL j

POWER is restricted to less than or equal to the maximum THERMAL POMR level allowable for the reactor coolant pump combination i

operating at the time of CEA drop time determination.

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SURVEILLANCE REQUIREMENTS

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4.1.3.4 The CEA drop time of all CEAs shall be demonstrated through l

measurement prior to reactor criticality:

a.

For all CEAs following each removal of the reactor vessel

head, b.

For specifically affected individuals CEAs following any l

maintenance on or modification to the CEA drive system which could affect the drop time of those specific CEAs, and c.

At least once per 18 months.

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ARKANSAS - UNIT 2 3/4 1-23 Amendment No. 84,94, MG

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REACTIVITY CONTROL SYSTEMS REGULATING AND GROUP P CEA INSERTION LIMITS l

LIMITING CONDITION POR OPERATION 1

3.1.3.6 The regulating CEA groups and Group P CEAs shall be limited l

to the withdrawal sequence and to the insertion limits specified in the 4

j CORE OPERATING LIMITS REPORT with:

a.

CEA insertion between the Long Tern Steady State Insertion Limit and the Transient Insertion Limit restricted tot 1.

5 5 Effective Full Power Days per 30 Effective Full Power Day intervals, and 1

2.

1 14 Effective Full Power Days per calendar year.

i b.

CEA insertion between the Short Term Steady State Insertion Limit and the Transient Insertion Limit shall be restricted to f

5 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.

APPLICABILITY: MODES 1* and 2**

4 ACTION:

With the regulating CEA groups or Group P CEAs inserted beyond l

a.

the Transient Insertion Limit, except for surveillance testing pursuant to Specification 4.1.3.1.2, within two hours either i

1.

Restore the regulating CEA groups or Group P CEAs to within l

the limits, or l

2.

Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the CEA group position using the CORE OPERATING LIMITS REPORT i

b.

With the regulating CEA groups or Group P CEAs inserted between l

the Long Tern Steady State Insertion Limit and the Transient Insertion Limit for intervals > 5 EFPD per 30 EFPD interval or i

> 14 EFPD per calendar year, either:

[

1.

Restore the regulating groups or Group P CEAs to within l

the Long Term Steady State Insertion Limit within two hours, t

or 2.

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

See Special test Exceptions 3.10.2 and 3.10.4

'With Fwit 21.0.

l ARKANSAS - UNIT 2 3/4 1-25 Amendment No. M,MS i

REACTIVITY CONTROL SYSTEMS

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LIMITING CONDITION FOR OPERATION o

l ACTION:

Continued) i s

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With the regulating CEA groups or Group P CEAs inserted between l

I the ShortTerm Steady State Insertion Limit and the Transient Insertion Limit for intervals > 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, operation may proceed provided any subsequent increase in thermal power is restricted to 5 5% of rated thermal power per hour.

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SURVEILLANCE REQUIREMENTS 4.1.3.6 The position of each regulating CEA group and Group P CEAs shall l

be determined to be within the Transient Insertion Limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the PDIL Alarm is 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 .

The accumulated times during which the regulating CEA groups or Group P CEAs l

are inserted beyond the Long Term Steady State Insertion Limit or the Short Term Steady State Insertion Limit but within the Transient Insertion Limit shall be determined at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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i ARKANSAS - UNIT 2 3/4 1-26 Amendment No. 47

POWER DISTRIBUTION LIMITS AZIMUTHAL POWER - Tq LIMITING CONDITION IVR OPERATION 3.2.3 The AZIMUTHAL POWER TILT (T ) shall be less than or equal to the q

AZIMUTHAL POWER TILT Allowance used in the Core Protection Calculators (CPCs).

APPLICABILITY: MODE 1 above 20% of RATED THERMAL POWER.*

ACTION:

a.

With the measured AZIMUTHAL POWER TILT determined to exceed the AZIMUTHAL POWER TILT Allowance used in the CPCs but within the limit specified in the CORE OPERATING LIMITS REPORT, within two hours either correct the power tilt or adjust the AZIMUTHAL POWER TILT Allowance used in the CPCs to greater than or equal to the measured value, b.

With the measured AZIMUTHAL POWER TILT determined to exceed the limit specified in the CORE OPERATING LIMITS REPORT:

1.

Due to misalignment of a CEA, within 30 minutes verify l

that the Core Operating Limit Supervisory System (COLSS)

(when COLS5 is being used to monitor the core power distribution per Specifications 4.2.1 and 4.2.4) is detecting the CEA misalignment.

2.

Verify that the AZIMUTHAL POWER TILT is within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Linear Power Level - High trip setpoints to 5 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Identify and correct the cause of the out of limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the AZIMUTHAL POWER TILT is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified acceptable at 95% or greater RATED THERMAL 5

POWER.

See Special Test Exception 3.10.2.

ARKANSAS - UNIT 2 3/4 2-3 Amendment No. 44, W t

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I TABLE 3.3-1 (Continusd)

ACTION STATEMENTS 1

l ACTION 4 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of

,i specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

i ACTION 5 -

With the number of channels OPERABLE one less than required j

by the Minimum Channels OPERABLE requirement, place the reactor i

trip breakers of the inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance 3

testing per Specification 4.3.1.1.1.

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ACTION 6 -

a.

With one CEAC inoperable, operation may continue for up to 7 days provided that at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , each CEA is verified to be within 7 inches (indicated position) or all other CEAs in its group. After 7 days, operation may continue provided that ACTION 6.b is met.

d b.

With both CEACs inoperable, operation may continue provided that:

a 1.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the margin required by j

Specification 3.2.4.b (COLSS in service) or Specification 3.2.4.d (COLSS out of service) is satisfied.

2.

Within 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s:

a)

All CEA groups are withdrawn to and l

i subsequently maintained at the " Full Out" position, except during surveillance l

testing pursuant to the requirements of Specification 4.1.3.1.2 or for control when CEA group 6 may be inserted no further than 127.5 inches withdrawn.

4 b)

The "RSPT/CEAC Inoperable" addressable constant in the CPCs is set to both CEACs inoperable.

l c)

The Control Element Drive Mechanism Control l

System (CEDMCS) is placed in and subsequently maintained in the "OFF" mode except during CEA motion permitted by a) above, when the CEDMCS may be operated in either the " Manual Group" or " Manual Individual" mode.

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ARKANSAS - UNIT 2 3/4 3-5b Amendment No. 24,49,-79,449, 449,169

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TABLE 3.3-1 (Continund)

ACTION STATEMENTS 3.

At least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , all CEAs are l

verified fully withdrawn, except as permitted 4

by 2. a) above, then verify at least once per

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4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months that the inserted CEAs are aligned within 7 inches (indicated position) of all other CEAs j

in their group, j

j ACTION 7 With three or more auto restarts of one non-bypassed calculator during a 12-hour interval, demonstrate calculator 3

OPERABILITY by performing a CHANNEL FUNCTIONAL TEST within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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With the number of OPERABLE channels one less than the ACTION 8 2

Minimum Channels OPERABLE requirement restore the inoperable channel tc OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the l

affected reactor trip breakers within the next hour. The trip breakers associated with the inoperable channel may be closed for up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months for surveillance testing per j

Specification 4.3.1.1.

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ARKANSAS - UNIT 2.

3/4 3-Sc Amendment No. 49,49,M 9,169 4

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3/4.9 REFUELING OPERATIONS BORON CONCENTRATION LIMITING CONDITION FOR OPERATION 3.9.1 With the reactor vessel head unbolted or ramoved, the boron concentration of the reactor coolant and the refueling canal shall be J

maintained uniform and sufficient to ensure that the more rentrictive of l

following reactivity conditions is met:

a.

Either a Keff of 0.95 or less, which includes a 1% Ak/k conservative allowance for uncertainties, or b.

A boron concentration of 22500 ppm, which includes a 50 ppm conservative allowance for uncertainties.

i APPLICABILITY: MODE 6*.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes and initiate and continue boration at 2 40 gpm of Keff is reduced to s 0.95 or the boron concentration is restored to 2 2500 ppm, whichever is the more restrictive. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any CEA in excess of 3 feet from its l

fully inserted position within the reactor pressure vessel.

4.9.1.2 The boron concentration of the reactor coolant 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 .

The reactor shall be naintained in HODE 6 when the reactor vessel head is unbolted or removed.

l ARKANSAS - UNIT 2 3/4 9-1 Amendment No. 4G

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REFUELING OPERATIONS 1

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REFUELING MACHINE OPERABILITY LIMITING CONDITION FOR OPERATION d

3.9.6 The refueling machine shall be used for movement of fuel assemblies i

and shall be OPERABLE with:

a.

A minimum capacity of.3750 pounds, b.

An overload cut, off limit of s 100 pounds plus the combined i

weight of one fuel assembly, one CEA, and the grapple l

l in the " fuel only" region, and i'

An overload cut off limit of s 100 pounds plus the combined c.

weight of one fuel assembly, one CEA, the grr.pple, l

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and the hoist box in the " fuel plus hoist box" region.

l APPLICABILITY: During movement of CEAs or fuel assemblies within the j

reactor pr.tssure vessel.

ACTION:

With the requirements for refueling machine OPERABILITY not satisfied, suspend its use from operations involving the movement of CEAs and fuel f

assemblies within the reactor pressure vessel. The provisions of specification 3.0.3 are not applicable.

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A SURVEILLANCE REQUIREMENTS 4.9.6 The refueling machine shall be demonstrated EPERABLE within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to-the start of movement of fuel assemblies within the reactor pressure vessel by performing a load test of at least 3750 pounds and demonstrating automatic load cut offs when the crane loads exceed 100 l

pounds plus the applicable loads.

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l ARKANSAS - UNIT 2 3/4 9-7 Amendment No.44 I

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k 3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN l

LIMITING CONDITION FOR OPERATION 3.10.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 may be suspended for measurement of CEA worth and shutdown margin provided J

reactivity equivalent to at least the highest estimated CEA worth is available for trip insertion from OPERABLE CEA(s).

APPLICABILITY: MODE 2.

ACTION:

a.

With any CEA not fully inserted and with less than the above l

reactivity equivalent available for trip insertion, immediately initiate and continue boration at 240 gpm of 2500 ppm boric acid 4

l solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

b.

With all CEAs inserted and the reactor subcritical by less than l

4

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the above reactivity equivalent, immediately initiate and continue boration at 2 40 gpm of 2500 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

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SURVEILLANCE REQUIREMENTS 1

J 4.10.1.1 The position of each CEA required either partially or fully l

l withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each CEA not fully inserted shall be demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 7 4

days prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.

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i ia ARKANSAS - UNIT 2 3/4 10-1 Amendment No. M,43

e SPECIAL TEST EXCEPTIONS l

GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION i

i 3.10.2 The group height, insertion and power distribution limits of Specifications 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.2, 3.2.3, 3.2.7 l

and the Minimum Channels OPERABLE requirement of Functional Unit 15 of Table 3.3-1 may be suspended during the performance of PHYSICS TESTS provided:

a.

The THERMAL POWEn is restricted to the test power plateau which shall not exceed 85% of RATED THERMAL POWER, and i

j b.

The linear heat rate limit shall be maintained by either:

i 1.

Maintaining COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on linear heat rate (when COLSS is in service); or 2.

Operating within the region of acceptable operation as specified in the CORE OPERATING LIMITS REPORT using any operable CPC channel (when COLSS is out of service.)

APPLICABILITY: During startup and PHYSICS TESTS.

ACTION:

l i

With any of the above limits being exceeded while any of the above l

requirements are suspended, either a.

Reduce THERNAL POWER sufficiently to satisfy the requirements of the above Specification, or b.

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

SURVEILLANCE REQUIREMENTS 4.10.2.1 The THERMAL POWER shall be determined at least once per hour during PHYSICS TESTS in which any of the above requirements are suspended and shall be verified to be within the test power plateau.

i 4.10.2.2 The linear heat rate shall be determined to be within its limits during PHYSICS TESTS above 5% of RATED THERHAL POWER in which any of the above requirements are suspended.

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ARKANSAS - UNIT 2 3/4 10-2 Amendment No. M,4M,M-7 t

J REACTIVITY CONTROL SYSTEMS 4

BASES j

j CEA positions and OPERABILITY of the CEA position indicators are required 1

to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with more frequent verifications required if an automatic monitoring channel is inoperable.

l These verification frequencies are adequate for assuring that the applicable LCo's are satisfied.

i The average CEA drop time restriction is consistent with the assumed CEA drop time used in the accident analysis.

The maximum CEA drop time restriction is used to limit the CEA drop time distribution about the j

average to that used in the accident analysis. Measurement with T 1

avg j

525'r and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a reactor trip at operating conditions.

The establishment of LSSS and LCOs require that the expected long and short term behavior of the radial peaking factors be determined. The long i

term behavior relates to the variation of the steady state radial peaking i

factors with core burnup and is affected by the amount of CEA insertion assumed, the portion of a burnup cycle over which such insertion is assumed and the expected power level variation throughout the cycle. The short term behavior relates to transient perturbations to the steady-state radial

]

peaks due to radial xenon redistribution.

The magnitudes of such perturbations depend upon the expected use of the CEAs during anticipated l

power reductions and load maneuvering. Analyses are performed based on the

^

expected mode of operation of the NSSS (base load, load following, etc.)

and from these analyses CEA insertions are determined and a consistent set of radial peaking factors are defined. The Long Term Steady State and Short Term Insertion Limits are determined based upon the assumed mode of i

operation used in the analyses and provide a means of preserving the assumptions on CEA insertions used. The lindts specified serve to limit the behavior of the radial peaking factors within the bounds determined from analysis. The actions specified serve to limit the extent of radial xenon redistribution effects to those accommodated in the analyses. The Long and Short Term Insertion Limits of Specification 3.1.3.6 are specified l

p for the plant which has been designed -for primarily base loaded operation but which has the ability to accommodate a limited amount of load maneuvering.

The Transient Insertion Limits of Specification 3.1.3.6 and the Shutdown CEA Insertion Limits of Specification 3.1.3.5 ensure that 1) the minimum SNUTDOWN MARGIN is maintained, and 2) the potential effects of a CEA ejection accident are limited to acceptable levels.

Long term operation at the Transient Insertion Limits is not permitted since such operation could have effects on the core power distribution which could invalidate assumptions used to determine the behavior of the radial peaking i

factors.

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l ARKANSAS - UNIT 2 B 3/4 1-5 Amendment No. 44,&44

9 DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 54 psig and a temperature of 300*F.

5.3 REACTOR CORE IVEL ASSEMBLIES The reactor core s'all contain 177 fuel assemblies with each fuel h

5.3.1 assembly containing a maximum of 236 fuel rods clad with 11rcaloy-4. Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of 2114 grams uranium. The initial core loading shall have a maximum enrichment of 2.99 weight percent U-235.

Reload fuel shall be of low enrichment and similar in physical design to the initial core loading.

CONTROL ELEMENT ASSEMBLIES 5.3.2 The reactor core shall contain 81 control element assemblies.

l 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

a.

In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant of the applicable Surveillance Requirements, b.

For a pressure of 2500 psia, and c.

For a temperature of 650'F, except for the pressurizer which is 700*F.

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J ARKANSAS - UNIT 2 5-4 Amendment No. 44 4

4 e

ADMINISTRATIVE CONTROL i

CORE OPERATING LIMITS REPORT i

{

6.9.5 The core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT prior to each reload cycle or any remaining part of a reload cycle.

6.9.5.1 The analytical methods used to determine the core operating limits i

addressed by the individual Technical Specifications shall be those previously reviewed and approved by the NRC for use at ANO-2, specifically:

1)

"The ROCS and DIT Computer Codes for Nuclear Design", CENPD-266-P-A,

)

April 1983 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 J

for Shutdown Margins, 3.1.1.4 for MTC, 3.1.3.6 for Regulating i

and Group P CEA Insertion Lindts, and 3.2.4.b for DNBR Margin).

l t

2)

"CE Method for pontrol Element Assenbly Ejection Analysis,"

CENPD-0190-A, January 1976 (Methodology for Specification 3.1.3.6 for Regulating and Group P CEA Insertion Limits and l

3.2.3 for Azimuthal Power Tilt).

3)

" Modified Statistical Combination of Uncertainties, CEN-356(V)-P-A, Revision 01-P-A, May 1988 (Methodology for Specification 3.2.4.c and 3.2.4.d for'DNBR Margin and 3.2.7 for ASI).

4)

" Calculative Methods for the CE Large Break LOCA Evaluation Model,"

CENPD-132-P, August 1974 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

l 5)

" Calculational Methods for the CE Large Break LOCA Evaluation Model,"

CENPD-132-P, Supplement 1, February 1975 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

3 i

6)

" Calculational Methods for the CE Large Break LOCA Evaluation Model,"

CENPD-132-P, Supplement 2-P, July 1975 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

7)

" Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS," CEN-132, Supplement 3-P-A, June 1985 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

8)

" Calculational Methods for the CE Small Break LOCA Evaluation Model,"

CENPD-137-P, August 1974 (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI).

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ARKANSAS - UNIT 2 6-21 Amendment No. 444,444 l

T w

--m.

m-

_ ~.. _.. _

e ADMINISTRATIVE CONTROL CORE OPERATING LIMITS REPORT J

9)

"CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam i

Supply System," December 1981 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margin, 3.1.1.4 for MTC, 3.1.3.1 for Movable Control Assemblies - CEA Position, 3.1.3.6 for Regulating CEA and Group P Insertion Limits, and 3.2.4.b for DNBR Margin).

10) Letter:

0.D.

Parr (NRC) to F.M. Stern (CE), dated June 13, 1975 (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model). NRC approval for 6.9.5.1.4, 6.9.5.1.5, and 6.9.5.1.8 methodologies.

1

.11) Letter:

0.D.

Parr (NRC) to A.E. Scherer (CE), dated December 9, 1975 (NRC Staff Review of the Proposed Combustion Engineering ECCS j

Evaluation Model changes).

NRC approval for 6.9.5.1.6 methodology.

1

12) Letter:

2CNA038403, dated March 20, 1984, J.R. Miller (NRC) to J.M. Griffin (AP&L), "CESEC Code Verification." NRC approval for 6.9.5.1.9 methodology.

4 6.9.5.2 The core operating limits shall be determined so that all applicable limits (e.g. fuel thermal-mechanical limits, core thermal-hydraulic limits,

+

ECCS limits, nuclear limits such as shutdown margin, and transient and accident i

analysis lim 4ts) of the safety analysis are met.

6.9.5.3 The CORE OPERATING LIMITS REPORT, including any ndd-cycle revisions or supplements thereto, shall be provided upon issuance to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

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ARKANSAS - UNIT 2 6-21a Amendment No. 144,144 i

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'Q

'l

\\

X X X

X X

i X

X X

X e

X X

X P

X X

P X

X X

X l

X P

X X

X P

X X

X e

X X

P X

X X

P X

X~

X X

X

/

X X

X

- FULL LENGTH CEA's 73 P

- PART LENGTH CEA's 8

TOTAL =

81 ARKANSAS POWE LIGHT CO.

CONTROL ELEMENT ASSEMBLY LOCATIONS Nuclear One - Unit 2 4.2-19

.

ML20093H721

Text

Attachment:

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