ML20081J216
| ML20081J216 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/22/1995 |
| From: | Gundrum L NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20081J217 | List: |
| References | |
| NUDOCS 9503270159 | |
| Download: ML20081J216 (9) | |
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->t UNITED STATES
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j NUCLEAR REGULATORY COMMISSION f.
WASHINGTON, D.C. 3000H21
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TOLEDO EDISON COMPANY CENTERIOR 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 l
Amendment No.'l97 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
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Service Company, and the Cleveland Electric Illuminating Company (the licensees) dated December 6, 1994, 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 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, 9503270159 950322 PDR ADOCK 05000346 P
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. and. paragraph 2.C.(2) of facility Operating License No. NPF-3 is hereby a T ch al So tions The Technical Specifications contained in Appendix A, as revised l
through Amendment No. 197, are' hereby incorporated in the license, j
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-cfter issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION-All)')Q
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Linda L. Gundrum, Project Manager
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Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 22. 1995 t
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l ATTACHMENT TO LICENSE AMENDMENT NO. 107 FACILITY OPERATING LICENSE NO. NPF-3 j
t DOCKET NO. 50-346 l
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are. identified by amendment number and i
contain vertical lines indicating the area of change.
Remove Insert 3/4 0-2 3/4 0-2 B 3/4 0-3 B 3/4 0-3 l
3/4 1-9 3/4 1-9 3/4 1-10 3/4 1-10 3/4 1-12 3/4 1-12 3/4 1-13 3/4 1-13
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APPLICABILITY SURVEILLANCE RE0VIREMENTS 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for.
Operation unless otherwise stated in an individual Surveillance Requirement.
4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25 percent of the specified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation.
The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.
The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable (equipment inoperability) outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Surveillance requirements do not have to be performed on inoperable equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified applicability condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:
a.
Inservice inspection of ASME Code Class 1, 2 and 3 components and i
inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a.
b.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:
DAVIS-BESSE, UNIT 1 3/4 0-2 Amendment No. 77,IAB,IA5,197
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APPLICABILITY BASES ACTION requirements, e.g., Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial measures would be required that may preclude cor: 'etion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.
If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.
Surveillance Requirements do not have to be performed on inoperable equipment because the ACTION requirements define the remedial measures that apply.
However, the Surveillance Requirements have to be met to demonstrate that inoperable equipment has been restored to OPERABLE status.
4.0.4 This specification ensures that the surveillance activities associated with a Limiting Condition for Operation have been performed within the specified time interval prior to entry into an OPERATIONAL MODE or other applicable condition.
The intent of this provision is to ensure that surveillance activities have been satisfactorily demonstrated on a current basis as required to meet the OPERABILITY requirements of the Limiting Condition for Operation.
Under the terms of this specification, for example, during initial plant startup or following extended plant outages, the applicable surveillance activities must be performed within the stated surveillance interval prior to placing or returning the system or equipment into OPERABLE status.
4.0.5 This specification ensures that inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boller and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.
This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.
This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.
DAVIS-BESSE, UNIT I B 3/4 0-3 Amendment No. Jff,197
l REACTIVITY CONTROL SYSTEMS MAKEUP PUMP-- SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.3 At least one makeup pump in the boron injection flow path required by Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE essential bus.
APPLICABILITY: MODE 5*.
ACTION:
With no makeup pump OPERABLE, suspend all operations involving positive reactivity changes until at least one makeup pump is restored to OPERABLE status.
SURVEILLANCE RE0VIREMENTS 4.1.2.3 No additional Surveillance Requirements other than those required by Specification 4.0.5 are applicable.
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- With RCS pressure ? 150 psig.
DAVIS-BESSE, UNIT 1 3/4 1-9 Amendment No.197
REACTIVITY CONTROL-SYSTEMS MAKEUP PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 Two makeup pumps shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4*.
ACTION:
With only one makeup pump OPERABLE, restore the inoperable pump 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 and borated to a SHUTDOWN MARGIN equivalent to 1% Ak/k at 200 F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore two pumps 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 />.
l SURVEILLANCE REQUIREMENTS 4.1.2.4 No additional Surveillance Requirements other than those required by Specification 4.0.5 are applicable.
- With RCS pressure 2 150 psig.
DAVIS-BESSE, UNIT 1 3/4 1-10 Amendment No. 175,197
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REACTIVITY CONTROL SYSTEMS BORIC ACID PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.6 At least one boric acid pump shall be OPERABLE and capable of being powered from an OPERABLE essential bus if only the flow path through the boric acid pump in Specification 3.1.2.la is OPERABLE.
APPLICABILITY: MODES 5 and 6.
ACTION:
With no boric acid pump OPERABLE as required to complete the flow path of Specification 3.1.2.la, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one boric acid pump is restored to OPERABLE status.
SURVEILLANCE RE0VIREMENTS 4.1.2.6 No additional Surveillance Requirements other than those required by Specification 4.0.5 are applicable.
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l DAVIS-BESSE, UNIT 1 3/4 1-12 Amendment No.197
r REACTIVITY CONTROL SYSTEMS BORIC ACID PUMPS - OPERATING-LIMITING CONDITION FOR OPERATION 3.1.2.7 At least one boric acid pump in the boron injection flow path t
required by Specification 3.1.2.2a shall be OPERABLE and capable of being powered from an OPERABLE essential bus.
APPLICABILITY: MODES 1, 2, 3 and 4.
i ACTION:
With no boric acid pump OPERABLE, restore at least one boric acid pump 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 and borated to a SHUTDOWN MARGIN equivalent to 1% Sk/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least one boric acid pump 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 />.
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SURVEILLANCE RE0VIREMENTS 4.1.2.7 No additional Surveillance Requirements other than those required by Specification 4.0.5 are applicable.
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P DAVIS-BESSE, UNIT 1 3/4 1-13 Amendment No.197 4
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