ML20059E015
| ML20059E015 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/30/1993 |
| From: | Hopkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059E018 | List: |
| References | |
| NUDOCS 9401100194 | |
| Download: ML20059E015 (7) | |
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't UNITED STATES NUCLEAR REGULATORY COMMISSION g,
.lc wASHINoTON, D.C. 261 A...../
i TOLEDO EDIS0N COMPANY CENTERIOR SERVICE COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. I j
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 183 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 30, 1993, 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 j
in compliance with the Commission's regulations; j
1 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, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is'hereby amended to read as follows:
9401100194 931230 PDR ADOCK 05000346 P
PDR:
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. (a) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.183, 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 l
be implemented not later than 90 days after issuance.
r FOR THE NUCLEAR REGULATORY-COMMISSION
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/' Jon B. Hopkins, Sr. Project Manager f
Project Directorate III Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
December 30, 1993 1
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l ATTACHMENT TO LICENSE AMENDMt'NT NO. 183 FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 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 i
overleaf pages are also provided to maintain document completeness.
Remove Insert 3/4 6-25 3/4 6-25 B 3/4 6-4 B 3/4 6-4
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CONTAINMENT SYSTEMS CONTAINMENT HYDROGEN DILUTION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.4.3 Two independent containment hydrogen dilution systems shall be OPERABLE.
APPLICABILITY: MODES I and 2.
ACTION:
With one containment hydrogen dilution system inoperable, restore the
~l a.
inoperable system to OPERABLE status within 30 days 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 />.
b.
With both containment hydrogen dilution systems inoperable, restore at least one dilution 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 />.
SURVEILLANCE RE0VIREMENTS 4.6.4.3 Each containment hydrogen dilution system shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST basis by:
Verifying that the system can be started on operator action in the a.
control room, and b.
Verifying that the system operates for at least 15 minutes and the blower develops a discharge pressure of 15 psig.
DAVIS-BESSE, UNIT 1 3/4 6-25 Amendment No.183
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CONTAINMENT SYSTEMS HYDROGEN PURGE SYSTEM i
LIMITING CONDITION FOR OPERATION 3.6.4.4 A containment hydrogen purge system shall be OPERABLE.
APPLICABILITY: MODES 1 and 2.
ACTION:
l With the containment hydrogen purge system inoperable, restore the i
hydrogen purge system to OPERABLE status within 30 days or be in at i
least HJT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
i SURVEILLANCE REQUIREMENTS 4.6.4.4 The hydrogen purge system shall be demonstrated OPERABLE:
l a.
At least once per 18 months by initiating flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the heaters on.
b.
At least once per 18 months or (1) after any structural main-tenance on the HEPA filter or' charcoal adsorber housings, or (2) following painting, fire or chemical release in any venti-i lation zone communicating with the system by:
1.
Verifying that the cleanup system satisfies the in-place i
penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test p:ocedure guidance in Regulatory Positions C.5.a. C.S.c. and C.S.d of Regulatory Guide 1.52 Revision 2, March 1978, and the system flow ' '
rate is 100 cfm + 10%; and
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Verifying, within 31 days after removal,le obtained inthat a laboratory l
2.
analysis of a representative carbon samp accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2, March 1978, meets the laboratory
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l testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyliodide t
penetration of less than 1%.
I DAVIS-BESSE, UNIT 1 3/4 6-26 Amendment No.155
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i CONTAINMENT SYSTEMS BASES i
3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the Hydrogen Analyzers, Containment Hydrogen Dilution System, and Hydrogen Purge System ensures that this equipment i
will be available to maintain the maximum hydrogen concentration within the containment vessel at or below three volume percent following a LOCA.
The two redundant Hydrogen Analyzers determine the content of hydro-gen within the containment vessel.
The Hydrogen Analyzers, although they have their OPERABILITY requirements in this Specification, are considered part of the post-accident monitoring instrumentation of Specification 3/4.3.3.6, Post-Accident Monitoring Instrumentation.
The Containment Hydrogen Dilution (CHD) System consists of two full capacity, redundant, rotary, positive displacement type blowers to supply air to the containment. The CHD System controls the hydrogen concentra-tion by the addition of air to the containment vessel, resulting in a pressurization of the containment and suppression of the hydrogen volume fraction.
The Containment Hydrogen Purge System Filter Unit functions in conjunction with the CHD System and is designed to release air from the containment atmosphere through a HEPA filter and charcoal filter prior to discharge to the station vent.
As a backup to the CHD System and the Containment Hydrogen Purge System,.
the capability to install an external hydrogen recombination system has been provided.
3/4.6.5 SHIELD BUILDING 3 /4. 6. 5.1 EMERGENCY VENTILATION SYSTEM The OPERABILITY of the emergency ventilation systems ensures that containment vessel leakage occurring during LOCA conditions into the t
annulus will be filtered through the HEPA filters and charcoal absorber trains prior to discharge to the atmosphere. This requirement is neces-sary to meet the assumptions used in the safety analyses -and limit the site boundary radiation doses to within the limits of 10 CFR 100 during LOCA conditions, i
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DAVIS-BESSE, UNIT I B 3/4 6-4 Amendment No. FE.767,183
CONTAINMENT SYSTEMS BASES leakage rate are consistent with the assumptions used in the safety analyses.
The leak rate surveillance requirements assure that the leakage assumed for the system during the recirculation phase will not be exceeded.
Borated Water Storage Tank (BWST) outlet isolation valves DH-7A and DH-78 are ide-energized during MODES 1, 2, 3, and 4 to preclude postulated inadvertent iclosure of the valves in the event of a fire, which could result in a loss of
,the availability of the BWST. Re-energization of valves DH-7A and DH-78 is
' permitted on an intermittent basis during MODES 1, 2, 3 and 4 under adminis-ltakenwhenre-energizingthesevalvesundersuchcontrols. Station procedure trative controls.
Containment Emergency Sump Recirculation Valves DH-9A and DH-9B are de-ener-gized during MODES 1, 2, 3, and 4 to preclude postulated inadvertent opening of the valves in the event of a fire, which could result in draining the Borated Water Storage Tank to the Containment Emergency Sump and the loss of this water source for normal plant shutdown. Re-energization of valves DH-9A and DH-9B is permitted on an intermittent basis during MODES 1, 2, 3, and 4 under administrative controls. Station procedures identify the precautions which must be taken when re-energizing these valves under such controls.
3/4.6.2.2 CONTAINMENT COOLING SYSTEM The OPERABILITY of the containment cooling system ensurer that 1) the containment air temperature will be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
Containment isolation within the required time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
Containment isolation valves and their required isolation times are addressed in the USAR. The opening of a closed inoperable containment isolation valve on an intermittent basis during plant operation is pennitted under administrative control.
Operating procedures identify those valves which may be opened under administrative control as well as the safety precautions which must be taken when opening valves under such controls.
DAVIS-BESSE, UNIT 1 B 3/4 6-3 Amendment No. UE, f(7.182