ML20066F115
| ML20066F115 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/05/1982 |
| From: | Clark R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066F118 | List: |
| References | |
| NUDOCS 8211180024 | |
| Download: ML20066F115 (9) | |
Text
[& e a:.Ig UNITED STATES J
{.g NUCLEAR REGULATORY COMMISSION j
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated July 8,1982, as supplemented October 6,1982, 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; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and secuiity or to the health and safety of the,public, and l
E.
The issuance cf this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable l
requirements have been satisfied.
8211180024 821105 l
PDR ADOCK 05000368 P
e.
2.
Ac:ordingly, 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 The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 37, are hereby incorpor-ated in the license. The licensee shall operate the facility in accordance with the Technical Specifications, except where otherwise stated in specific license conditions.
3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COM4ISSION G(L 1
M Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 5, 1982 9
-a,,
ATTACHMENT TO LICENSE AMENDMENT NO. 37 FACILITY OPERATING LICENSE NO. NPF-6 DOCKETNO.Sb-368 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines. indicating the area of change. Cor-responding overleaf pages are pravided to maintair, document completeness.
Remove Pages Insert Pages III III 3/4 1-25 3/4 1-25 3/4 1-26 3/4 1-26 3/4 1-27 3/4 1-27 3/4 1-28 l
3/4 1-29 3/4 10-2 3/4 10-2 B 3/4 1-5 B.3/4.1-5
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY...........................................
3/40-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL Sh utdown Ma rgi n - T,,g > 200* F....................... 3/41-1 Shutdown Ma rg i n - T,,g < 200* F....................... 3/4 1-3,
Boron Dilution...................................... 3/4 1-4 Moderator Temperature Coefficien t................... 3/4 1-5 Minimum Temperatu re for Criticality.................. 3/4 1-6 3/4.1.2 B0 RATION SYSTEMS Fl ow Pa th s - S hu tdown................................ 3/4 1-7 Flow Paths - Operating...............................
3/4 1-8 C ha rg i ng Pump - S hu tdown............................. 3/4 1-9 Cha rgi ng Pumps - O perati ng...........................
3/4 1-10 Boric Acid Makeup Pumps - Shutdown...................
3/4 1-11 Boric Acid Makeup Pumps - Operating.................. 3/4 1-12 Borated Water Sources - Shutdown.....................
3/4 1-13 Borated Water Sources - Operati ng.................... 3/4 1-15 3/4.1.3 MOVABLE CONTROL ASSEMBLIES C EA P o s i ti o n.........................................
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 Sh u td own C EA In s e rtion Limi t......................... 3/4 1-24 Regul ating C EA Inserti on Limi ts...................... 3/4 1-25 Part Length CEA Insertion Limits.....................
3/4 1-28 l
ARKANSAS - UNIT 2 III knendment No. 37
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 LINEAR HEAT RATE........................................ 3/4 2-1 3/4.2.2 RADIAL PEAKING FACTORS..................................
3/4 2-4 3/4.2.3 AZIMUTHAL POWER TILT....................................
3/4 2-5 3/4.2.4 DNBR MARGIN.............................................
3/4 2-7 3/4.2.5 RCS FLOW RATE...........................................
3/4 2-11 3/4.2.6 REACTOR COOLANT COLD LEG TEMPERATURE....................
3/4 2-12 3/4.2.7 AXIAL SHAPE INDEX.......................................
3/4 2-13 3/4.2.8 PRESSURIZER PRESSURE....................................
3/4 2-14 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTIVE INSTRUMENTATION...................... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION.......................................
3/4 3-10 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation....................
3/4 3-24 Incore Detectors........................................
3/4 3-28 Se i smi c In s trum enta tion.................................
3/4 3-30 Meteorological Instrumentation.......................... 3/4 3-33 Renote Shutdown Instrumentation......................... 3/4 3-36 Post-Accid ent Instrumentation...........................
3/4.3-39 Chl ori ne Detectio n Sys tems..............................
3/4 3-42 Fire Detection Instrumentation..........................
3/4 3-43 3/4.3.4 TlRBINE OVERSPEED PROTECTION...e........................
3/4 3-45 ARKANSAS - UNIT 2 IV Amendment No. 24
REACTIVITY CONTROL SYSTEMS REGULATING CEA INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.6 The regulating CEA groups shall be limited to the withdrawal sequence and to the insertion limits shown on Figure 3.1-2 with:
"t H a.
CEA insertion between the Long Term Steady State Insertion Limit and the Transient Insertion Limit restricted to:
1.
< 5 Effective Full Power Days per 30 Effective Full Power Day intervals, and i
2.
5,14 Effective Full Power Days per calendar year.
~
b.
CEA insertion between the Short Tenn Steady State Insertion Limit and the Transient Insertion Limit shall be restricted to 3,4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval.
APPLICABILITY: MODES 1* and 2*#.
ACTION:
With the regulating CEA groups inserted beyond the Transient a.
Insertion Limit, except for surveillance testing pursuan'. to Specification 4.1.3.1.2, within two hours either:
s s
1.
Restore the regulating CEA groups to within the limits, or 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 above figure.
b.
With the regulating CEA groups inserted between the Long Term Ste'ady State Insertion Limit and the Transient Insertion Limit for intervals > 5 EFPD per 30 EFPD interval or > 14 EFPD per calendar year, either:
1.
Restore the regulating groups to within the Long Term Steady State Insertion Limit within two hours, or 2.
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 />.
- See Special Test Exceptions 3.10.2 and 3.10.4.
- With K,ff >,1.0.
ARKANSAS - UNIT 2 3/4 1-25 mendment No. 37
i REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION ACTION:
(Continued) c.
With the regulating CEA groups inserted between the Short Term Steady State Insertion Limit and the Transient Insertion Limit for intervals > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> per 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> interval, operation may proceed provided any subsequent increase in thermal power is restricted to < 5% of rated thermal power per hour.
SURVEILLANCE REQUIREMENTS 4.1. 3. 6 The position of each regulating CEA group shall be determined to be s
within the Transient Insertion Limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
The accumulated times during which the regulating CEA groups 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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I ARKANSAS - UNIT 2 3/4 1-27 Amendment No. 37,
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REACTIVITY CONTROL SYSTEMS PART LENGTH CEA INSERTION LIMITS LIMITING CONDITION FOR OPERATION 3.1.3.7 The part length CEA group shall be limited to the insertion limits shown on Eigure 3.1-3 with.PLCEA insertion between the Long Term Steady State Insertion Limit and the Tran,ient Insertion Limit restricted to:
t a.
l< 5 Effective Full Power Days per 30 Effective Full Power Day interval, and b.
< 14 Effective Full Power Days per calendar year.
APPLICABILITY: MODE 1*.
F.
ACTION:
t't a.
With' the part length CEA groups inserted beyond the Transient insertion Limit, except for surveillance testing pursuant to Specification 4.1.3.1.2, within two hours either:
l.
Restore the part length CEA group to within the limits, or
?
2.
Reduce THERMAL POWER to less than or equal to that fraction of RATED THERMAL POWER which is allowed by the PLCEA group position,using figure 3.1-3.
b.
With the part length CEA groups inserted between the Long Term Steady State Insertion Limit and the Transient Insertion Limit for intervals > 5 EFPD per 30 EFPD interval or > 14 EFPD per calendar year, either:
1.
Restore the part length group to within the Long Term Steady State Insertion Limits within two hours, or 2.
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 REQUIREMENT 4.1.3.7,.The position of the part length CEA group shall be determined to be
.a within the Transient Insertion Limit at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The accumulated time during which the partlength CEA group is inserted beyond the Long Term Steady State Insertion Limit but within the Transient Insertion Limit shall be determined at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i ARKANSAS - UNIT 2 3/4 1-28 knendment Pb. 37
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s ARKANSAS - UNIT 2 3/4 1-29 Agendment No. 37
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3/4.10 SPECIAL TEST EXCEPTIONS SHUTDOWN MARGIN 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 reactivity equivalent to at least the highest estimated CEA worth is available fcr trip insertion from OPERABLE CEA(s).
l APPLICABILITY: MODE 2.
ACTION:
a.
With any full length CEA not fully inserted and with less than the above reactivity equivalent available for trip insertion, immediately initiate and continue boration at > 40 gpm of 1731 ppm boric acid solution or its equivalent untiT the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored, b.
With all full length CEAs inserted and the reactor suberitical by less than the above reactivity equivalent, immediately initiate and continue boration at > 40 gpm of 1731 ppm boric acid solution or its equivalent until the SHUTDOWN MARGIN re-quired by Specification 3.1.1.1 is restored.
SURVEILLANCE REQUIREMENTS 4.10.1.1 The position of each full length CEA required either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reducing the SHUTDOWN MARGIN to less than the limits of Specification 3.1.1.1.
ARKANSAS - UNIT 2 3/4 10-1
SPECIAL TEST EXCEPTIONS GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION 3.10.2 The group height, insertion and power distribution limits of Specifica-tions 3.1.1.4, 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.1.3.7, 3.2.2, 3.2.3, 3.2.7 and the l
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 POWER is restricted to the test power plateau which shall not exceed 85% of RATED THERMAL POWER, and b.
The limits of Specification 3.2.1 are maintained and determined as specified in Specification 4.10.2.2 below.
l APPLICABILITY: During startup and PHYSICS TESTS.
ACTION:
With any of the limits of Specification 3.2.1 being exceeded while any of the above requirements are suspended, either:
a.
Reduce THERMAL POWER sufficiently to satisfy the requirements l
of Specification 3.2.1, or b.
Be in 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 4.10.2.1 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.
4.10.2.2 The linear heat rate shall be determined to be within the limits of Specification 3.2.1 by monitoring it continuously with the Incore Detector Monitoring System pursuant to the requirements of Specifications 4.2.1.3 and 3.3.3.2 during PHYSICS TESTS above 5% of RATED THERMAL POWER in which any of the above requirements are suspended.
ARKANSAS - UNIT 2 3/4 10-2 Amendment No.37,
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REACTIVITY CONTROL SYSTEMS BASES I
CEA positioris and OPERABILITY of the CEA 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 more frequent verifica-tions required if an automatic monitoring channel is inoperable. These verifi-cation frequencies are adequate for assuring that the applicable LCOs are satisfied.
The maximum CEA drop time restriction is consistent with the assumed CEA drop time.used in the accident analyses. Measurement with T
> 525'F and with all reactor coolant pumps operating ensures that the measure 9 drop times will be representative of insertion times experienced during a reactor trip at operat-ing 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 term behavior relates to the variation of the steady state radial peaking 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 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 operation used in the analyses and provide a means of preserving-l the assumptions on CEA insertions used. The limits specified serve to limit the l
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 Specifications 3.1.3.6 and 3.1.3.7 are specified for the plant which l
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 Limit of Specification 3.1.3.5 ensure that 1) the minimum SHUTDOWN 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 factors.
ARKANSAS - UNIT 2 8 3/4 1-5 Amend.aent No. 37
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