ML20215E610
| ML20215E610 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/11/1986 |
| From: | Richard Lee Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215E612 | List: |
| References | |
| NUDOCS 8612230028 | |
| Download: ML20215E610 (8) | |
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((. e. < Ig UNITED STATES g
NUCLEAR REGULATORY COMMISSION L
'j WASHINGTON, D. C. 20555 ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 81 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Connission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licensee) dated April 25, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's regulations set forth in 10 CFP Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Comnission; C.
There is reasonable assurance (1) 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 conipliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment, and paragraph.C.(2) of Facility Operating License No. NPF-6 is hereby amended ad as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 81, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
l 8612230028 861211 PDR ADOCK 05000368 P
2-3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0FNISSION I
o rt S. L roject anager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance: December 11, 1986 s
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December 11. 1986
~ ATTACHMENT TO LICENSE AMENDMENT NO. 81 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 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 areas of change. The corresponding overleaf pages are also provided to maintain document completeness.
Remove Page Insert Page 3/4 1-1 3/4 1-1 3/4 1-5 3/4 1-5 3/4 1-15 3/4 1-15 d
3/4 5-7 3/4 5-7 B 3/4 1-1 B 3/4 1-1 e
i
3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL SHUTDOWN MARGIN - T,yg > 200'F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be > 5.5% Ak/k.
APPLICABILITY: MODES 1, 2*, 3 and 4.
ACTION:
With the SHUTDOWN MARGIN < 5.5% ak/k, immediately initiate and continue l
boration at > 40 gpm of 1731 ppm boric acid solution or equivalent until the required SHUTDOWN MARGIN is restored.
SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be > 5.5% ak/k:
l Within one hour after detection of an inoperable CEA(s) and at a.
least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the CEA(s) is inoperable.
If the inoperable CEA is imovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrippable CEA(s),
b.
When in MODES 1 or 2, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that CEA group withdrawal is within the Transient Insertion Limits of Specification 3.1.3.6.
c.
When in MODE 2N, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical CEA position is within the limits of Specification 3.1.3.6.
d.
Prior to initial operation above 5% RATED THERMAL POWER after
.A each fuel loading, by consideration of the factors of e below, with the CEA groups at the Transient Insertion Limits of Specification 3.1.3.6.
l See Special Test Exception 3.10.1.
With Keff > 1.0.
- F With Keff < l.0.
ARKANSAS - UNIT 2 3/41-1 Amendment No. 81
REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1. 4 The moderator temperature coefficient (MTC) shall be:
Less positive than 0.5x10~4 ok/k/ F whenever THERMAL 0
a.
POWER is <JO% of RATED THERMAL POWER, U
b.
Less positive than 0.0 ak/k/ F whenever THERMAL POWER is >70% of RATED THERMAL POWER, and
~4 c.
Less negative than -3.4x10 ok/k/ F at RATED THERMAL POWER.
APPLICABILITY:
MODES 1 and 2*.
ACTION:
With the moderator temperature coefficient 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 />.
SURVEILLANCE REQUIREMENTS 4.1.1.4.1 The MTC shall be detennined to be within its limits by confirmatory measurements. MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.
4.1.1.4.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle:
j a.
Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.
b.
At any THERMAL POWER, prior to reachina a RATED l
THERMAL POWER equilibrium boron concentration of 800 ppn.
c.
At aar THERMAL POWER, within 14 EFPD after reaching a RATED l
THERMAL POWER equilibrium boron concentration of 300 ppm.
- With Ke f f > 1. 0.
i ARKANSAS - UNIT 2 3/4 1-5 Anendment No. 74,SP,81 l
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REACTIVITY CONTROL SYSTEMS B0 RATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.8 Each of the following borated water sources shall be OPERABLE:
a.
At least one boric acid makeup tank and one associated heat tracing circuit per tank with the contents of the tank in accordance with Figure 3.1-1, and b.
The refueling water tank with:
1.
A contained borated water volume of between 464,900 and 500,500 gallons (equivalent to an indicated tank level of between 91.7% and 100%, respectively),
2.
Between 1731 and 2250 ppm of boron, 3.
A minimum solution temperature of 40*F, and 4.
A maximum solution temperature of 110*F.
l APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
a.
With the above required boric acid makeup tank inoperable, restore the make up tank to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUiDOWN MARGIN equivalent to at least 5% ak/k at 200"F; restore the above required boric acid makeup tank to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With the refueling water tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY wtphinthenext6hoursandinCOLDSHUTDOWNwithinthe fo lowing 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE-REQUIREMENTS 4.1.2.8 Each of the above required borated water sources shall be demonstrated OPERABLE:
ARKANSAS - UNIT 2 3/4 1-15 Amendment No. %(,81
1 EMERGENCY CORE COOLING SYSTEMS REFUELING WATER TANK LIMITING CONDITION FOR OPERATION om 3.5.4 The refueling water tank shall be OPERABLE with:
a.
A contained borated water volume of between 464,900 and 500,500 gallons (equivalent to an indicated level between 91.7%
and100%,respectively),
b.
Between 1731 and 2250 ppm of boron, c.
A minimum solution temperature of 40'F, and d.
A maximum solution temperature of 110*F.
l APPLICABILITY: MODEL 1, 2, 3 and 4.
ACTION:
With the refueling water tank inoperable, restore tank to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or 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 /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.5.4 The RWT shall be de'monstrated OPERABLE:
a.
At least once per 7 days by:
f 1.
Verifying the contained borated water volume in the tank, and 2.
Verifying the boron concentration of the water.
b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWT temperature.
ARKANSAS - UNIT 2 3/4 5-7 Amendment No. 81
3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 B0 RATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T The most restrictive condition occurs at E0L, with T atnofMdoperating temperature,andisassociatedwithapostuiMedsteamlinebreakaccident and resulting uncontrolled RCS cooldown. In the analysis of this accident, a minimum SHUTDOWN MARGIN of 5.5% ak/k is required to control the l
reactivity transient. Accordingly, the SHUTDOWN MARGIN requirement is based upon this limiting condition and is consistent with FSAR safety analysis assumptions. With T
< 200*F, the reactivity transients result-ing from any postulated accid 8M are minimal and a 5% ak/k shutdown margin provides adequate protection.
3/4.1.1.3 BORON DILUTION A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 3000 GPM will circulate an equivalent Reactor Coolant System volume of 9,975 cubic feet in approximately 25 minutes. The reactivity change rate associated with boron concen-tration reductions will therefore be within the capability of operator recognition and control.
3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) l The limitations on MTC are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle.' The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured MTC value is within its limit provides assurances that the coefficient will be maintained within acceptable values throughout each fuel cycle.
l ARKANSAS - UNIT 2 B 3/4 1-1 Amendment No. fg,81
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