ML20126A302
| ML20126A302 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/08/1992 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126A303 | List: |
| References | |
| NUDOCS 9212180136 | |
| Download: ML20126A302 (7) | |
Text
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I'o UNITED STATES g
NUCLEAR REGULATORY COMMISSION WAWWO Wl, D. C. 205%
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1QLEDO EDISON C_0MPANY Q{ifRIO_R SERVICE COMPANY
$110 THE CLEVELAND ELECTRIG._1110MINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACillTY OPERATING LICENSE Amendment No.176 License No. NPF-3 1.
The Nuc1 car Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric illuminating Company (the licensees) dated May 1, 1992, 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Thera is reasonable assurance (i) that the activitice 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.
Ihe 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 Commission'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. NPF-3 is hereby amended to read as follows:
9212180136 921208 yDR ADOCK 05000346 PDR
(a) Jechnic61 SDecificuh The Technical Specifications contained in Appendix A, as revised through Amendment No.176 are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in ac.ordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall l
be implemented not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t
D7a t
Jon B. Hopkins, Sr. Project Manager Project Directorate 111-3 Division of Reactor Projects Ill/lV/V Office of Nuclear Reactor Regulation _
Attachment:
Changes to the Technical Specifications Date of issuance: December 8, 1992 1
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ATTACHMENT 10 llCENSE AMENDMENT NO.176 EatlllTY OPERATING LICENSE NO. NPE-3 DOCKET NO. 50-346 Replace the following pages of the Appendix "A" Technical $pecifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
The corresponding overleaf pages are also provided to maintain document completeness.
Remove insert 3/4 1-3 3/4 1-3 B 3/4 1-1 B 3/4 1-1 a
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REACTIVITY CONTROL SYSTEMS BORON DILUTION LIMITING CONDITION FOR OPERATION 3.1.1.2 The flow rate of reactor coolant through the Reactor Coolant System shall be > 2800 gpm whenever a reduction in Reactor Coolant System boron concentration is being mede.'
l APPLICABILITY: All MODES.
ACTION:
With the flow rate of reactor coolant through the Reactor Coolant System
< 2800 gpm, imediately suspend all operations involving a reduction in boron concentration of the Reactor Coolant System.
SURVEILLANCE REQUIREMENTS 4.1.1.2 The flow rate of reactor coolant through the Reactor Coolant System shall be determined to be > 2600 gpm within one hour prior to the start of and at least once per hour ~~during a reduction in the Reactor Coolant System boron concentration by either:
a.
Verifying at least one reactor coolant pump is in operation, or b.
Verifying that at least one DHR pump is in operation and supplying,>_ 2800 gpm to the Reactor Coolant System.
i l
- In MODE 6 the Reactor Coolant System (RCS) boron concentration may be i
greater than the boron concentration of water available for addition.
If i
the flowrate c' reactor coolant through the RCS is less than 2800 gpm, water of lower boron concentration than the existing RCS concentration may be added to the RCS trovided that the boron concentration of the water to i
be added is equal to or greater than the boron concentration corresponding to the more restrictive reactivity condition specified in Specification 3.9.1.
4 DAVIS-BESSE, UNIT 1 3/4 1-3 Amendment No.176
i E
REACTIVITY CONTROL SYSTEMS i
MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1. 3 The moderator temperature coefficient (MTC) shall be:
a.
Less positive than 0.9 x 10~4 Ak/k/*F whenever THERMAL POWER is < 95% of RATED THERMAL POWER, b.
Less positive than 0.0 x 10'4 ok/k/*F whenever THERMAL POWER is > 95% of RATED THERMAL POWER, and c.
Equal to or less negative than the limit provided in the CORE OPERATING 1
LIMITS REPORT at RATED THERMAL POWER.
APPLICABILITY: MODES 1 and 2*#.
ACTION:
t With the moderator temperature coefficient outside any 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 4.1.1.3.1 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.
4.1.1.3.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during cach fuel cycle:
a.
Prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.
l b.
At any THERMAL POWER. within 7 days after reaching a RATED THERMAL POWER L
equilibrium boron concentration of 300 ppm.
1 i
- With keff > 1.0.
- See Special Test Exception 3.10.2.
l DAVIS-BESSE. UNIT 1 3/4 1-4 Amendment No. AE,154 l
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3/4.1 REACTIVITY CONTROL SYSTEMS i
BASES 3/4.1.1 BORAT!0N CONTROL
- 4.1.1.l_ SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be mado 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 suberitical to preclude inadvertent criticality in the shutdown condition.
During Modes 1 and 2 the SKUTDOWN MARGIN is known to be within limits if all control rods are OPERABLE and-withdrawn to or beyond the insertion limit.
SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion. RCS boron concentration and RCS Tavg.
The most restrictive condition occurs at E0L, with Tava at no load operating temperature. The SHUTDOWN MARGIN required is consistent with FSAR safety analysis assumptions.
3/4.1.1.2 BORON DILUTION A minimum flow rate of at least 2800 gpm provides adequate mixing.
prevents stratification and ensures that reactivity changes will be gradual through the Reactor Coolant System in the core during boron concentration reductions in the Reactor Coolant System. A flow rate of at least 2800 gpm will circulate an equivalent Reactor Coolant System volume of 12.110 cubic feet in approximately 30 minutes. The reactivity change rate associated with boron concentration reduction will be within the capability for operator recognition and control.
In MODE 6. the RCS boron concentration is typically somewhat higher than the minimum boron concentration required by Specification 3.9.1 and could be higher than the boron concentration of nonnal sources of water addition.
At reduced inventory conditions in the RCS, in order to reduce the possibility of vortexing, the flowrate through the decay heat system may be procedurally restricted to somewhat less than 2800 gpm.
In this situation, if water with a boron concentration equal to or greater than the boron concentration required by Specification 3.9.1 is added to the RCS. the RCS is assured to remain above the Specification 3.9.1 requirement, and a flowrate of less than 2800 gpm is not of concern.
3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analyses-remain valid through each fuel cycle.
The surveillance requirement for measurement of the MTC 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 assurance that the coefficient will be maintained within acceptable values throughout each fuel cycle.
DAVIS-BESSE UNIT 1 B 3/4 1-1 Amendment No.176
REACTIVITY CONTROL SYSTEMS BASES 3 /4_.1.1. 4 MINIMUM TEMPERATURE POR CRITICALITY This spect!! cation ensures that the reactor vill not be made critinal with the reactor coolant systen everage temperature less than 323'F.
This limitation is required to ensure (1) the moderator temprature coefficient is within its analysed temperature range, (2) the protective instrumentation is within its normal operating range. (3) the pressuriser is capable of being in kn 0FERA3L2 status with a steam bubble, and (4) the reactor pressure vessel is above its minimus RT temperature.
MDT-3/4.1.2.
30 RATION STFrtMS The boron injection rysten ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this functi makeup or DHR pumps, (3) separate flow paths.on include (1) berated water sources, (2) associated heat tracing systems, and (6) an eme(4) boric acid pumps, (5)-
rgency power supply from operable energency-busses.
Vith the RCS average temperature above 200'F, a minimum of two. separate and redundant boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one of the systems inoperable. - A11ovable out-of-service periods ensure that einor.
component repair or corrective action may be completed without undue risk to overall facility safety from injection system failures during the repair period.
The boration capability of either system is sufficient to provide a SHUTDOVN KARGIN f rom all operating conditions of 1.0% ak/k af ter manon decay and craldown. to 200'F.
The maximum boration capability requirement occurs from full power equilibriua menon conditions and requires the equivalent of either 7373 gallons of 8742 ppa horated water i
from the boric acid storage tanks ~or 52,726 gallons of 1900 ppa borated water from the borated water storage tank.
The requirement for a miniaua available volume of 482,778 gallons of beratcd wit.c in the horated water storage tank ansures the capability l
for borating the RCS to the desired level. The specified quantity of borated vater is consistent with the ECCS requirements of Specification 3.5.4 1 therefore, the larger volume of berated water is specified.
Vith the RCS temperature belov 200'Y, one injection systen.As acceptable without single failure consideration on the basis of.the DAVIS-BESSE, UNIT 1 -
B 3/4 1-2 Amendment No~it.
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