ML20044B953
| ML20044B953 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/08/1993 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20044B954 | List: |
| References | |
| NUDOCS 9303150238 | |
| Download: ML20044B953 (7) | |
Text
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UNITED STATES 8
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NUCLEAR REGULATORY COMMISSION a,5 WASHINGTON, D. C. 20553 O
4 TOLEDO EDISON COMPANY CENTER 10R SERVICE COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.178 License No. NPF-3 1.
The Nuclear 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 April 30, 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; 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 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 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
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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*
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i 9303150238 930308 i
PDR ADOCK 05000346 p
2 (a)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.178, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Jon B. Hopkins, S. Project Manager Project Directorate III-3 Division of Reactor Projects llI/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 8,1993 f
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ATTACHMENT TO LICENSE AMENDMENT NO.178 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346
- 'I Replace 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 overleaf pages are also provided to maintain document completeness.
Remove insert 3/4 1-19 3/4 1-19 t
3/4 1-20 3/4 1-20 3/4 1-22 3/4 1-22 3
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1 REACTIVITY CONTROL SYSTEMS
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3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT - SAFETY AND REGULATING ROD GROUPS LIMITING CONDITION FOR OPERATIONS 3.1.3.1 All control (safety and regulating) rods shall be OPERABLE and positioned within + 6.5% (indicated position) of their group average height.
APPLICABILITY: MODES 1* and 2*.
ACTION:
With one or more control rods inoperable due to being immovable a.
as a result 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 one hour and 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 />.
b.
With more than one control rod inoperable or misaligned from its group average height by more than + 6.5% (indicated position), 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 />.
c.
With one control rod inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group average height by more than + 6.5% (indicated position), POWER OPERATION may continue provided that'within one hour either:
1.
The control rod is restored to OPERABLE status within the above alignment requirements, or s
2.
The control rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.
POWER OPERATION may then continue provided that:
a)
An analysis of the potential ejected rod worth is performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and the rod worth is deter-mined to be < 1.0% tk at zero power and < 0.65%
ok at RATED THERMAL POWER for the remainFer of the fuel cycle, and I
I b)
The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, i
and I
'See Special Test Exceptions 3.10.1 and 310.2.
DAVIS-BESSE, UNIT 1 3/4 1-19 Amendment No.178
REACTIVITY CONTROL SYSTEMS GROUP HEIGHT - SAFETY AND REGULATING ROD GROUPS LIMITING CONDITION FOR OPERATIONS ACTION:
(Continued) c)
A power distribution mgp is obtained from the incore detectors and Fg and Flimitswithin7chours&Nand l
are verified to be within their d)
Either the THERMAL POWER level is reduced to 1 60% of the THERMAL POWER allowable for the reactor coolant pump combination within one hour and within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> the High Flux Trip Setpoint is reduced to 1 70% of the THERMAL POWER allowable for the reactor coolant pump combination, or e)
The remainder of the rods in the group with the inoperable-rod are aligned to within + 6.5% of the inoperable rod within one hour while maintaining the position of the rods within the limits provided in the CORE OPERATING LIMITS REPORT; the THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation.
i SURVEILLANCE REOUIREMENTS 4.1.3.1.1 The position of each control rod shall be determined to be within the group average height limit by verifying the individual rod positions 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 asyntnetric rod monitor is inoperable, then verify the individual rod position (s) of the rod (s), with the inoperable asymmetric rod monitor at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.3.1.2 Each control rod not fully inserted shall be determined to be OPERABLE by movement of at least 2% in any one direction at least once every 31 days.
DAVIS-BESSE, UNIT 1 3/4 1-20 Amendment No. JM,MN ME/,178
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GROUP HEIGHT - AXIAL POWER SHAPING ROD GROUP
_ LIMITING CONDITION FOR OPERATION 3.1.3.2 All axial power shaping rods (APSR) shall be OPERABLE, unless fully withdrawn, and shall be positioned within + 6.5% (indicated position) of their group average height.
APPLICABILITY: M30ES 1* and 2*.
ACTION:
With a maximum of one APSR inoperable or misaligned from its group average height by more than + 6.5% (indicated position), operation may continue provided that within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
a.
The APSR group is positioned such that the misaligned rod is restored to within limits for the group average height, or b.
It is determined that the imbslance limits of Specification 3.2.1 are satisfied and movement of the APSR group is pre-vented while the rod remains inoperable or misaligned.
SURVEILLANCE REQUIREMENTS 4.1.3.2.1 The position of each APSR rod shall be detennined to be within the group average height limit by verifying the individual rod positions 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 asymetric rod monitor il inpperable, then verify the individual rod position (s) of the rod (s), with the inoperable'a'synnetric rod monitor at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
4.1.3.2.2 Unless all APSR are fully withdrawn, the APSR shall be determined to be OPERABLE by moving the APSR rods at least 2% at least once every 31 days.
- See Special Test Exceptions 3.10.1 and 3.10.2.
DAVIS-BESSE, UNIT 1 3/4 1-21 Amendment No. 162
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l REACTIVITY CONTROL SYSTEMS POSITION INDICATOR CHANNELS i
LIMITING CONDITION FOR OPERATION
.t 3.1.3.3 All safety, regulating and axial power shaping control rod absolute position indicator channels and relative position indicator channels shall be OPERABLE and capable of determining the control rod group average positions within + 1.5%.
APPLICABILITY: MODES 1 and 2.
ACTION:
With a maximum of one absolute position indicator channel per a.
control rod group or one relative position indicator channel per control rod group inoperable either:
1.
Reduce THERMAL POWER to < 60% of the THERMAL POWER allow-able for the reactor cooTant pump combination and reduce the High Flux Trip Setpoint to < 70% of the THERMAL POWER allowable for the reactor coolaiit pump combination within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or 2.
STARTUP and POWER OPERATION may continue provided:
l a)
The position of the control rod with the inoperable position indicator is verified within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> by actuating its 0%, 25%, 50%, 75% or,100% position 2
reference indicator, and b)
The control rod group (s) containing the inoperable position indicator channel is subsequently maintained at the 0%, 25%, 50%, 75% or,100% withdrawn position and verified at this position 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, and c)
Operation is within the limits of Specification 3.1.3.5, 3.1.3.6. or 3.1.3.9. as applicable.
b.
With more than one relative position indicator channel per control rod group inoperable. STARTUP and POWER OPERATION may continue provided that the requirements of either Action a.1 or a.2 above i
have'been complied with and the absolute position indicator channels are OPERABLE for the affected control rod assemblies.
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The provisions of Specification 3.0.4 are not applicable.
c.
E DAVIS-BESSE, UNIT 1 3/4 1-22 Amendment No./M2,178
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