ML20115C784
| ML20115C784 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 04/03/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20115C787 | List: |
| References | |
| NPF-03-A-085 NUDOCS 8504180562 | |
| Download: ML20115C784 (6) | |
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UNITED STATES y
g NUCLEAR REGULATORY COMMISSION 5
- j WASHINGTON, D. C. 20555 TOLED0 EDIS0N 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. 85 License No NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated November 20, 1984, 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 Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and 4
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 comon l
defense and security or to the health and safety of the public; and i
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.
l 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:
l 8504180562 850403 PDR ADOCK 05000346 P
PDR 1
-2 Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
hereby incorporated in the license.
85, are 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 issuanc FOR THE NUCLEAR REG LATORY COMMISSIO Johi F. Stolz, Chief 0 rating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: April 3,1985
ATTACHMd' NT TO LICENSE AMENDMENT NO. 85
_ FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50-346 Replace the followin the enclosed pages..g pages of the Appendix "A" Technical Specifications with The revised pages are identified b contain a vertical line indicating the area of change. y Amendment number and The correspondina overleaf pages are also provided to maintain document completeness.
Pages 3/4 4-32 B 3/4 4-13
REACTOR COOLANT SYSTEM SURVEILLANCEREOUIREMENTS(Continued) b.
Each internals vent valve shall be demonstrated OPERABLE at least once per 18 months during shutdown,* by:
1.
Verifying through visual inspection that the valve body and valve disc exhibit no abnormal degradation, 2.
Verifying the valve is not stuck in an open position, and 3.
Verifying through manual actuation that the valve is fully open when a force of < 400 lbs. is applied vertically upward.
- Ferformance of this Surveillance Requirement may be deferred until diay 30, 1950 to coincide with the.first refueling outage.
DAVIS-BESSE. UNIT 1 3/4 4-31 Amendment No. 23
e i
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM VENTS LIMITING CONDITION FOR OPERATION 3.4.11 The following reactor coolant system vent paths shall be oper-able:
a.
Reactor Coolant System Loop 1 with vent path through valves RC 4608A and RC 46088.
b.
Reactor Coolant System Loop 2 with vent path through valves RC 4610A and RC 46108.
Pressurizer; with vent path through' EITHER valves RC11 and c.
RC2 (PORV) OR valves RC 239A and RC'200.
APPLICABILITY:
Modes 1, 2 and 3 ACTION:
a.
With one of the above vent paths inoperable, restore the inoperable vent path to OPERABLE status within 30 days, or, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN i
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 two of the above vent paths inoperable, restore at least one of the inoperable vent paths 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 HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SETfDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
c.
With three of the above vent paths inoperable, restore at-least two of the inoperable vent paths 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 HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
d.
The provisions of specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.4.11 Each reactor coolant system vent path shall be demonstrated OPERABLE at least once per 18 months by:
1.
Verifying all manual isolation valves in each vent path are locked in the open position, and l
2.
Cycling each valve in the vent path through at least one
[
coerplete cycle of full travel from the control room during COLD SHUTDOWN or REFUELING, and 1
3.
Verifying flow through the reactor coolant vent system vent paths during COLD SRlfrDOWN or REFUELING.
DAVIS-BESSE, UllIT 1 3/4 4-32 Amendment tio. 85
il REACTOR COOLANT SYSTEM BASES 2
3/4.4.10 STRUCTURAL INTEGRITY except steam generator tubes, ensure that the s these components will be maintained at an acceptable level throug the life of the plant.
for these components is in compliance with Section XI and Pressure Vessel Code.
The internals vent valves are provided to relieve the pressure generated by steaming in the core following a LOCA so that the core remains sufficiently covered.
Inspection and manual actuation of the internals vent valves 1) ensure OPERABILITY, 2) ensure that the valv valves are fully open at the forces equivalent to the pressures assumed in the safety analysis.
3/4.4.11 HIGH POINT VENTS 0737 item II.B.1 requirements.The Reactor Coolant System high p The operability of the system ensures cooling system to restore natural circulation follo loss of coolant accident.
t i
f 4
, DAVIS.BESSE, UNIT 1 5 3/4 4-13 Amendment No.* C5
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