ML20100A561
| ML20100A561 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/13/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Toledo Edison Co, Cleveland Electric Illuminating Co |
| Shared Package | |
| ML20100A564 | List: |
| References | |
| NPF-03-A-084 NUDOCS 8503260097 | |
| Download: ML20100A561 (6) | |
Text
'
UNITED STATES r
't' NUCLEAR REGULATORY COMMISSION j
.g WASHINGTON, D. C. 20555 e
...../
TOLE 00 EDIS0N COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-RESSE NilCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.~84 License No. NPF-3 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applications for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) dated May 5, 1982, and March 22, 1984, comply 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 confonnity with the applications, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance fi) 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; 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 emendment is in accordance with 10 CFR Part 51 of the Comission'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:
8503260097 850313 PDR ADOCK 05000346 p
2_
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, 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.
FOR THE NUCLEAR REGllLAT03Y COMMISSION l
John F. Stolz, Chief-Op ating Reactors Branch #4 1 vision of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 13,1985
ATTACHMENT TO LICENSE AMENDMENT NO. 84 FACILITY OPERATING LICENSE N0. NPF-3 DOCKET NO. 50-346 Peplace the followino pages of the Appendix "A" Technical Specifications with the enclosed paaes. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.
Paoes 3/4 3-4Ra (New pagei 3/4 3-50a (New page) 6-14a e-i O
r__ - _ _ -.. - _ _
E
- 5 il TABLE 3.3-10 (Continued)
E El POST-ACCIDENT MONITORING INSTRUMENTATION P
MINIMUN
-d CHANNELS INSTRUMENT OPERABL E 31.
Containment Normal Sump Level 1
32.
Containment Wide Range Level 1
33.
Containment Wide Range Pressure 1
34 Incore Thermocouples 2 per core quadrant 35 Reactor Coolant Hot Leg Level (Wide Range) 1 ls P
.e ait e
.O
TABLE 4.3-10 (Continued)
~.
POST-ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL y
INSTRUMENT CHECK CALIBRATION D;
g 31.
Containment Normal. Sump Level.
-M R
32.
Containment Wide Range Level M
R g
33.
Containment Wide Range Pressure M
R
[
34 Incore Thermocouples M
R 35 Reactor Coolant Hot Leg Level (Wide Range)
M R
i 4
3 Y
8 4
5 5
a it 3"
i 2
i t
i
r ADMINISTRATIVE CONTROLS 6.8.4 (Cont.)
c.
Post-Accident Sampling A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant caseous effluents, and containment atmosphere samples under accident conditions. The program shall include the following:
(i)
Training of personnel, (ii)
Procedures for sampling and analysis, (iii)
Provisions for maintenance of sampling and analysis equipment.
6.9 REPORTING REOUIREMENTS ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the appropriate Regional Office unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testin shall be submitted following (1) receipt of an operating license, (2) g amendment to the licensee involving a planned increase in power level, (3) installation of fuel that has a different design or has been manu-factured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic perfor-mance of the plant.
6.9.1.2 The report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifica-tions. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other commitments shall be in-cluded in this report.
6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial DAVIS-BESSE, UNIT 1 6-14a Amendment No. U, 84