ML20101A071
| ML20101A071 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/07/1996 |
| From: | Marcus G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20101A080 | List: |
| References | |
| NUDOCS 9603130007 | |
| Download: ML20101A071 (4) | |
Text
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p UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 30606-0001 TOLEDO EDISON COMPANY CENTERIOR SERVICE COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY QQCXET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION. UNIT NO. 1 8215 aENT TO FACILITY OPERATING LICENSE l
Amendment No. 208 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) nas found that:
A.
The application for amendment by the Toledo Edison Company, Centerior Service Company, cnd the Cleveland Electric Illuminating Company (the licensees) dsted March 6,1996, complies with the standards and requirements 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; 4
D.
The issm.e 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accord'ingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph F.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
i 9603130007 960307 PDR ADOCK 05000346 e,
P PDR Y
I i (2)
Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 208, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance i
with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COPMISSION all H. Marcus, Project Director Project Directorate III-3 l
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the. Technical Specifications Date of issuance:
March 7, 1996 l
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e ATTACMENT TO LICENSE AMENDMENT NO. 208 FACILITY OPERATING LICENSE NO. NPF-3 I
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 5-4 3/4 5-4 I
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)i Revised by NRC Letter Dated 1
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.s June 6, 1995
' SURVEILLANCE REQUIRFM NTS fContinued)
$ i9 b. At.least once per 18 months, or prior to operation after ECCS piping has
+
) 'f been drained,by. verifying that the ECCS piping is full of water t
theECCS.pumpcasingsanddischargepipinghighpoints.**
L pQe(4ic.; By a vikualiins'pection which verifies that no loose debris (rags, tras t
o E
clothing,*etc.) is present in the containment which could be transported Q,
3 to'the containment emergency sump and cause restriction of the pump Q; %'$
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' psuction during J.0CA conditions. This visual inspection shall be f
performed:
y e-
- g a
. m&
.~g, _ p,,.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 work (containment closeout) when CONTAINNENT INTEGRITY is f
established.
d.
At least once per 18 months'by:
1.
Verifying that the interlocks:
a)
Close DH-11 and DH-12 and deenergize the pressurizer heaters, if either DH-Il or DH-12 is open and a simulated reactor coolant system pressure which is greater than the trip setpoint
(<438 psig) is applied. The interlock to close DH-11 and/or DH-12 is not required if the valve is closed and 480 V AC power is dhconnected from its motor operators.
b)
Prevent the opening of DH-ll and DH-12 when a simulated or actual reactor coolant system pressure which is greater than 4
the trip setpoint (<438 psig) is applied.
L 2.
a)
A visual inspection of the containment emergency sump which verifles 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 c.orrosion.
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 575 seconds after the operator manually pushes the control switch to open the Containment Emergency Sump Valve HV-DH9A (HV-DH98) which should be verified
.to open in $75 seconds.
3.
Deleted
[** 1he requirements of this surveillance may be deferred until the Tenth Refueling
_0utage for the ECCS flowpath which does not have manual high point venting capability.
DAVIS-BESSE, UNIT 1 3/4 5-4 Arendment No. 4,25,08,-
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%,77,in,100,1%, l'Xr,208
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