ML20154D413
| ML20154D413 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/05/1998 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154D417 | List: |
| References | |
| NUDOCS 9810070216 | |
| Download: ML20154D413 (6) | |
Text
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UNITED STATES i
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NUCLEAR REGULATORY COMMISSION i
g WASHINGTON, D.C. 20e664001
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TOLED0 EDIS0N COMPANY CENTERIOR SERVICE COMPANY e.80 THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 227 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 18, 1997, as supplemented by letters dated October 10, 1997, and February 27 and September 8, 1998, 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, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
9810070216 981005 PDR ADOCK 05000346 P
PDR 97f(>(170 7lb
4 4 1 (2)
Technical Specifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No. 227, 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 120 days after issuance.
FOR THE U.S. 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: October 5, 1998
ATTACHMENT TO LICENSE AMENDMENT NO. 227 FACILITY OPERATING LICENSE N0. 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.
Remove Insert 3/4 7-17 3/4 7-17 3/4 7-18 3/4 7-18 B 3/4 7-4a
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PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM l
LIMITING CONDITION FOR OPERATION 3.7.6.1 Two independent control room emergency ventilation systems shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3 and 4.
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ACTION:
a.
With one control room e.nergency ventilation system inoperable, restore l
the inoperable system to OPERABLE status within 7 days or be in at least H0T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one channel of Station Vent Normal Range Radiation Monitoring instrumentation inoperable, restore the inoperable channel to OPERABLE status, or isolate the control room normal ventilation system and place at least one control room emergency ventilation system train in operation within 7 days.
c.
With both channels of Station Vent Normal Range Radiation Monitoring instrumentation inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, isolate the control room normal ventilation system and place at least one control room emergency ventilation system train in operation.
SURVEILLANCE RE0VIREMENTS 4.7.6.1 Each control room emergency ventilation system shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying that the control room air temperature is less than or equal to 110*F when the control room emergency ventilation system is operating.
b.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.
c.
At least once each REFUELING INTERVAL or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:
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DAVIS-BESSE, UNIT 1 3/4 7-17 Amendment No. 135,155,217,227
PLANT SYSTEfg SVRVEILLANCE RE0VIREMENTS (Continued) 1.
Verifying that the cleanup system satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance in Regulatory Positions C.S.a, C.5.c and C.5.d of Regulttory Guide 1.52, Revision 2, March 1978, and the system flow rate is 3300 cfm 110%;
2 '.
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C 6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a* of Regulatory Guide 1.52, Revision 2, March 1978, for a methyliodide penetration of less than 1%; and 3.
Verifying a system flow rate of 3300 cfm i10% during system operation when tested in accordance with ANSI N510-1980.
d.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Posi. tion C.6.a* of Regulatory Guide 1.52, Revision 2, March 1978, for a methyliodide penetration of less than 1%.
e.
At least once each REFUELING INTERVAL by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 4.4 inches Water Gauge while operating the system at a flow rate of 3300 cfm fl0%;
2.
Verifying that the control room normal ventilation system is isolated by a SFAS test signal and a Station Vent Normal Range Radiation Monitoring test signal; and The test is performed in accordance with ASTM D 3803-1979 with the following conditions:
- 1) equilibrate for 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> at 30*C/70% relative humidity (RH), 2) challenge for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30*C/70% RH, 3) elution for l
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 30*C/70% RH.
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DAVIS-BESSE, UNIT 1 3/4 7-18 Amendment No. 134,135,155,209,217,227 i
PLANT SYST @S BASES The Station Vent Normal Range Radiation Monitoring isolation function provides that under the required conditions, an isolation signal will be giver.
The Station Vent Normal Range Radiation Monitors provide isolation and shutdown of the control room normal ventilation system.
With one or both channels of Station Vent Normal Range Radiation Monitoring instrumentation inoperable, the provisions of Action statements b or c, respectively, are applicable.
The provisions of Action statement a arc not applicable.
Under the Action statements for inoperable Station Vent Normal Range Radiation Monitoring instrumentation, should the control room normal ventilation system be isolated and at least one train of the control room emergency ventilation system be placed in operation, these systems would be in a state equivalent to that which they would be in following an actual high radiation condition.
Plant operation can continue indefinitely in this state, provided that control room temperature can be maintained in an acceptable range, with the control room emergency ventilation system obtaining fresh-air makeup as described in the Updated Safety Analysis Report Section 9.4.1,
" Control Room."
Surveillance Requirement 4.7.6.1.e.2 requires verification that the control room normal ventilation system can be isolated by a Station Vent Normal Range Radiation Monitoring test signal.
Additional testing requirements for the Station Vent Normal Range Radiation Monitoring instrumentation are provided in the ODCM for gaseous effluent releases, l
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DAVIS-BESSE, UNIT 1 B 3/4 7-4a Amendment No. 227