ML20215M317
| ML20215M317 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/04/1987 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20215M322 | List: |
| References | |
| NUDOCS 8705130188 | |
| Download: ML20215M317 (8) | |
Text
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o BA1.TIMORE GAS AND ELECTRIC COMPANY DOCKET NO. 50-318 CALVERT CLIFFS NUCLEAR PLANT UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.108 License No. DPR-69 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Baltimore Gas & Electric Comoany (the licensee) dated February 6,1987, as supplemented by the March 17, March 25, March 27, April 7 and April 17, 1987'submittals, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of Facility Operating License No.
DPR-69 is hereby amended to read as follows:
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-2 (1) Technical Specifications The Technical Specifications contained in Appendix A, as revised revised through Amendment No. 108, are hereby incorporated in the license. The licensee shall operste the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY CDPNISSION
~~RM a. Cw Robert A. Capra, Acting Director Project Directorate I-1 Division of Reactor Projects, I/II
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 4, 1987 l
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ATTACHMENT TO LICENSE AMENDMENT NO.108 FACILITY OPERATING LICENSE NO. DPR-69 DOCKET NO. 50-318 Revise Appendix A as follows:
Remove Pages Insert Pages 2-11 2-11 3/4 1-1 3/4 1-1 3/4 1-5 3/4 1-5 3/4 1-Sa B 3/4 1-1 B 3/4 1-1 l
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I (0,1.20) 1.20 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION REGION REGION 1.10 5y 1.00
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0.2 0.t 0.6 PERIPHERAL AXIAL SHAPE INDEX, Y y Figure 2.2-1 Peripheral Axial Shape Index, Yi vs Fraction of Rated Thermal Power CALVERT CLIFFS - UNIT 2 2-11 Amendment No. 41,108
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3 /4.1 REACTIVITY CONTROL SYSTEMS 3 /4.1.1 BOR ATION CONTROL SHUTDOWN M ARGIN - T.ug
> 2000F LIMITING CONDITION FOR OPERATION 3.1.1.1 The SHUTDOWN MARGIN shall be a 4.5%'d k/k.
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APPLICABILITY: MODES 1, 2**, 3 and 4.
ACTION:
With the SHUTDOWN MARGIN < 4.5%* 6 k/k, immediately initiate and continue l
boration at a 40 spm of 2300 ppm boric acid solution or equivalent until the required SHUTDOWN MARGIN is restored.
SURVEILLANCE REOUTREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be a 4.5%* 4 k/k:
l a.
Within one hour after detection of an inoperable CEA(s) and at 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 immovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untr,ippable CEA(s).
b.
When in MODES l' 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 3
CEA group withdrawal is within the Transient Insertion Limits of I
Specification 3.1.3.6.
c.
When in MODE 2"", 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 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.
Adherence to Technical Specification 3.1.3.6 as specified in Surveillance Requirements 4.1.1.1.1 assures that there is sufficient available shutdown margin to match the shutdown margin requirements of the safety analyses.
See Special Test Exception 3.10.1.
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l CALVERT CLIFFS - UNIT 2 3/4 1-1 Amendment No. 9d, 108 l
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s REACTIVITY CONTROL SYSTEM MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPER ATION 3.1.1.4 The moderator temperature coefficient (MTC) shall be:
a.
Less positive than the limit line of Figure 3.1-la, and b.
Less negative than -2.7 x 10-4 d k/k/0F at RATED THERMAL POWER.
APPLICABILITY: MODES I 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 REOUIREMENTS 4.1.1.4.1 The MTC shall be determined 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.
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j-See Special Test Exception 3.10.2.
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l CALVERT CLIFFS - UNIT 2 3/4 1-5 Amendment No. 9d,108 l
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4 3 /4.1 REACTIVITY CONTROL SYSTEMS BASES 3 /4.1.1 BOR ATION 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 suberitical 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 suberitical 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 Tavg.
The minimum available SHUTDOWN MARGIN for no load operating conditions at beginning of life is 3.5% 4 k/k and at end of life is 4.5% 4 k/k. The SHUTDOWN MARGIN l
is based on the safety analyses performed for a steam line rupture event initiated at no load conditions. The most restrictive steam line event occurs at EOC conditions.
For the steam line rupture event at beginning of cycle i
conditions, a minimum SHUTDOWN MARGIN of less than 3.5% 4 k/k is required to control the reactivity transient, and end of cycle conditions require 4.5% d k/k. Accordingly, the SHUTDOWN MARGIN requirement is based upon
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this limiting condition and is consistent with FSAR safety analysis assumptions.
With Tavg s 2000F, the reactivity transients resulting from any postulated accident are minimal and a 3% 0 k/k shutdown margin provides adequate protection.
With the pressurizer level less than 90 inches, the sources of non-borated water are restricted to increase the time to criticality during a l
boron dilution event.
t 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 9,601 cubic feet in approximately 24 minutes. The reactivity change rate associated with boron concentration reductions will therefore be within the capability of operator recognition and control.
3 /4.1.1.4 MODER ATOR TEMPER ATURE COEFFICIENT (MTC)
The limitations on MTC are provided to ensure that the assumptions used in the accident and transient analyses remain valid through each fuel cycle.
The surveillance requirements for measurement of the MTC during the 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
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values throughout each fuel cycle.
CALVERT CLIFFS - UNIT 2 B 3/4 1-1 Amendment No. 96,108