ML20138L058
| ML20138L058 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/10/1997 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20138L063 | List: |
| References | |
| NUDOCS 9702200347 | |
| Download: ML20138L058 (9) | |
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'a UNITED STATES g
j NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20066-0001 49.....,o TOLEDO EDISON COMPANY i
CENTEii10R SERVICE COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1
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AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No. 213 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Comission) 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 August 7, 1996, complies with the standards and require;:ents of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 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. NPF-3 is hereby amended to read as follows:
9702200347 970210 ADOCK0500g6 DR
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 213, 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 no later than 120 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Allen G. Hansen, Project Manager Project-Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
February 10, 1997 i
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ATTACHMENT TO LICENSE AMENDMENT N0. 213 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 5
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.
Remove Insert 1-6b 1-6b l
3/4 6-11 3/4 6-11
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3/4 6-15 3/4 6-15 i
B 3/4 0-2 B 3/4 0-2 B 3/4 0-3 B 3/4 0-3 8 3/4 0-4 B 3/4 0-4 3
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DEFINITIONS UNRESTRICTED AREA 1.39 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. The definition of UNRESTRICTED AREA used in implementing the Radiological Effluent Technical Specifications has been expanded over that in 10 CFR 20.3(a)(17). The UNRESTRICTED AREA boundary may coincide with the exclusion (fenced) area boundary, as defined in 10 CFR 100.3(a), but the UNRESTRICTED AREA does not include areas over water bodies.
The concept of UNRESTRICTED AREAS, estab-
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lished at or beyond the SITE BOUNDARY, is utilized in the LIMITING CONDITIONS FOR OPERATION to keep levels of radioactive materials in liquid and gaseous effluents as low as is reasonably achievable, pursuant to 10 CFR 50.36a.
1.40 Deleted j
CORE OPERATING LIMITS REPORT l
1.41 The CORE OPERATING LIMITS REPORT is the unit-specific document that provides core operating limits for the current reload cycle. These cycle-specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.1.7.
Plant operation within these core operating limits is addressed in individual specifications.
REFUELING INTERVAL 1.42 A REFUELING INTERVAL is a period of time s 730 days.
4 DAVIS-BESSE, UNIT 1 1-6b Amendment No. OC, 144, 170, 213
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CONTAINMENT SYSTEMS l
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS j
CONTAINMENT SPRAY SYSTEM i
LIMITING CONDITION FOR OPERATION 3.6.2.1 Two independent containment spray systems shall be OPERABLE with each spray system capabic of taking suction from the BWST on a j'
containment spray actuation signal and manually transferring suction to the containment emergency sump during the recirculation phase of operation.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
With one containment spray system inoperable, restore the inoperable spray system 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 />; restore the inoperable spray system 3
to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 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 4.6.2.1 Each containment spray system shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position, is in i
l its correct position.
i b.
At least once each REFUELING INTERVAL, by:
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1.
Verifying that each automatic valve in the flow path I
actuates to its correct position on a containment spray test signal.
fi 2.
Verifying that each spray pump starts automatically on j
a SFAS test signal.
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i DAVIS-BESSE, UNIT 1 3/4 6-11 Amendment No. -3fr; 213 i
-I CONTAINMENT SYSTEMS SURVEILLANCE RE0VIREMENTS (Continued) 4.6.3.1.2 Each isolation valve shall be demonstrated OPERABLE at least once each REFUELING INTERVAL, by:
a.
Verifying that on a containment isolation test signal, each automatic isolation valve actuates to its isolation position.
b.-
Verifying that on a Containment Purge and Exhaust isolation test signal, each Purge and Exhaust automatic valve actuates to its isolation position.
4.6.3.1.3 The isolation time of each power operated or automatic valve shall j
be determined to be within its limit when tested pursuant to Specification 4.0.5.
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DAVIS-BESSE, UNIT 1 3/4 6-15 Amendment No. -t+77 213
_ 7 APPLICABILITY
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BASES 4.0.1 This specification provides that surveillance activities necessary to insure the Limiting Conditions for Operation are met and will be performed during the OPERATIONAL MODES or other conditions for which the Limiting Condi-tions for Operation are applicable.
Provisions for additional surveillance activities to be performed without regard to the applicable OPERATIONAL MODES or other conditions are provided in the individual Surveillance Requirements.
4.0.2 The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those specified in the nominal surveil-lance interval.
These tolerances are necessary to provide operational flexibil-ity because of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance 4
value and permits the performance of more frequent surveillance activities.
i The allowable tolerance for performing surveillance activities is suffi-ciently restrictive to ensure that the reliability associated with the surveil-lance activity is not significantly degraded beyond that obtained from the nominal specified interval.
It is not intended that the allowable tolerance be i
used as a convenience to repeatedly schedule the performance of surveillances at the allowable tolerance limit.
The allowable tolerance for performing surveillance activities also provides flexibility to accommodate the length of a fuel cycle for surveillances that are specified to be performed at least once each REFUELING l
INTERVAL.
It is the intent that REFUELING INTERVAL surveillances be performed in an OPERATIONAL MODE consistent with safe plant operation, j
4.0.3 This specification establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Under the provisions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.
However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance inter-DAVIS-BESSE, UNIT 1 B 3/4 0-2 Amendment No. 14^, 145, 213
APPLICABILITY BASES val was exceeded. Completion of the Surveillance Requirement within the allow-able (equipment inoperability) outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.
- However, this does not negate the fact that the failure to have performed the surveil-4 lance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action.
Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.
If 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 /> or a shutdown is required to comply with 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 completion 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 i
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 scrveillance 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.
DAVIS-BESSE, UNIT 1 B 3/4 0-3 Amendment No. 445, 213
APPLICABILITY BASES 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 Boiler 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.
Under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.
For example, the requirements of Specification 4.0.4 to perform surveillance activities prior to entry into an OPERATIONAL MODE or other specified applicability condition takes precedence i
over the ASME Doiler and Pressure Vessel Code provision which allows pumps to be tested up to one week after return to normal operation and for example, the Technical Specification definition of OPERABLE does not grant a grace period i
before a device that is not capable of performing its specified functions is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel provision, which allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.
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DAVIS-BESSE, UNIT I B 3/4 0-4 Amendment No. 145, 107, 213 l