ML20138L044
| ML20138L044 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 02/11/1997 |
| From: | Hansen A NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20138L047 | List: |
| References | |
| NUDOCS 9702200323 | |
| Download: ML20138L044 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30seMo01 1
i TOLEDO EDIS0N COMPANY CENTERIOR SERVICE COMPANY an i
THE CLEVELAND ELECTRIC ILLLBlINATING COMPANY DOCKET NO. 50-346 l
DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 i
i AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 214 License No. NPF-3 i
l 1.
The Nuclear Regulatory Commission (the Commission) has found that:
j A.
The application for amendment by the Toledo Edison Company, Centerior Service Company, and The Cleveland Electric Illuminating Company (the licensees) dated September 12, 1996, 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; 4
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l
Commission; i
i C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and i
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, 4
and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
9702200323 970211 PDR ADOCK 05000346 j
P PDR A.
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i 4j,, (2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 214, are hereby incorporated in the license.
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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, ard shall be implemented no later than 120 days after issuance.
FOR THE NUCLEAR REGULATORY COMMISSION hk.
Allen G. Hansen, Project Manager Project Directorate III-3 s
Division of Reactor Projects III/IV 1
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
't Date of issuance:
February 11, 1997 i
4 i
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i ATTACHMENT TO LICENSE AMENDMENT NO. 214 l
FACILITY OPERATING LICENSE NO. NPF-3 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 contain vertical lines indicating the area of change.
Remove Insert 4
3/4 1-24 3/4 1-24 3/4 5-4 3/4 5-4 i
4
REACTIVITY CONTROL SYSTEMS ROD DROP TIME j
LIMITING CONDITION FOR OPERATION 3.1.3.4 The individual safety and regulating rod drop time from the fully withdrawn position shall be 11.58 seconds from power interruption at the control rod drive cabinets to 3/4 insertion with:
T,1525'F, and a.
j b.
All reactor coolant pumps operating.
APPLICABILITY: MODES I and 2.
i ACTION:
a.
With the drop time of any safety or regulating rod determined to exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE I and 2.
1 b.
With the rod drop times within limits but determined with less i
than 4 reactor coolant pumps operating, operation may proceed provided that THERMAL POWER is restricted to less than or equal to the THERMAL POWER allowable for the reactor coolant pump combination operating at the time of rod drop time j
measurement.
SURVEILLANCE REOUIREMENTS 4.1.3.4 The rod drop time of safety and regulating rods shall be demon-strated through measurement prior to reactor criticality a.
For all rods following each removal of the reactor vessel
- head, b.
For specifically affected individual rods following any main-terrce on or modification to the control rod drive system which could affect the drop time of those specific rods, and c.
At least once each REFUELING INTERVAL.
l DAVIS-BESSE, UNIT 1 3/4 1-24 Amendment No. 214
Revised by NRC Letter Dated June 6, 1995 l
SURVEILLANCE RE0VIREMENTS (continued) b.
At least once each REFUELING INTERVAL, or prior to operation after ECCS l
piping has been drained by verifying that the ECCS piping is full of water by venting the ECCS pump casings and discharge piping high points.
l c.
By a visual inspection which verifies that no loose debris (rags, trash, clothing, etc.) is present in the containment which could be transported to the containment emergency sump and cause restriction of the pump suction during LOCA l
conditions. This visual inspection shall be performed:
l.
For all accessible areas of the containment prior to establishing CONTAINMENT INTEGRITY, and 2.
For all areas of containment affected by an entry, at least once daily while work is ongoing and again during the final exit after completion of 4
work (containment closeout) when CONTAINMENT INTEGRITY is established.
1 l
d.
At least once per 18 months by:
1.
Verifying that the interlocks:
4 a)
Close DH-11 and DH-12 and deenergize the pressurizer heaters, if either DH-ll or DH-12 is open and a simulated reactor coolant system pressure which is greater than the trip setpoint (<438 psig) is a) plied. The interlock to close DH-11 and/or DH-12 is not required if t1e valve is closed and 480 V AC power is disconnected from its motor operators.
i b)
Prevent the opening of DH-ll and DH-12 when a simulated or actual reactor coolant system pressure which is greater than the trip 3
setpoint (<438 psig) is applied.
2.
a)
A visual inspection of the containment emergency sump which verifies that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
b)
Verifying that on a Borated Water Storage Tank (BWST) Low-Low Level interlock trip, with the motor operators for the BWST outlet isolation valves and the containment emergency sump recirculation valves energized, the BWST Outlet Valve HV-DH7A (HV-DH78) automatically close in s75 seconds after the operator manually pushes the control switch to open the Containment Emergency Sump Valve HV-DH9A (HV-DH9B) which should be verified to open in s75 seconds.
3.
Deleted i
DAVIS-BESSE, LINIT 1 3/4 5-4 gndungo.3,2j,2 0,77,
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