ML20086H077
| ML20086H077 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/22/1991 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086H082 | List: |
| References | |
| NUDOCS 9112060353 | |
| Download: ML20086H077 (6) | |
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UNITED STATES 3o i
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NEBRASKA PUBLIC POWFR DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.150 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commissian) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated July 19, 1991, 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;
- t..
There is reasonable assurance:
(1) 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 issuarice of this license 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.
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. 2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendrent No.150, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGUl.ATORY COMMISSION
/-
John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects Ill, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: November 22, 1991 i
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 150
[ACILITYOPERATINGLICENSENO.DPR-46 DOCKET NO. 50-298 Replace the following pages of the Appendix A Technical Specifications with the Snclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES
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3,7.B 6 3.7.c BASES (cont'd) liigh efficiency particulate absolute (HEPA) filters are installed before and after the charcoal adsorbers to minimize potential release of particulates to the environment and to prevent clogging of the iodine adsorbers.
The charcoal adsorbers are installed to reduce the potential release of radiciodiae to the environment. The in place test result s should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and llEPA filters.
The laboratory carbon sample test results should indicate a radioactive methyl iodide removal ef ficiency of at least 99 percent for expected accident conditions.
If the performance of the llEPA filters and charcoal adsorbers are as specif.ed, the resulting doses will be less than the 10 CPR 100 guidelines for the accidents analyzed.
Only one of the two standby gas treatment systems is needed to cleanup the reactor building atmosphere upon containment isolation. If one system is found to be inoperable, there is no immediate threat to the containment system performance and reactor operation or re'
.ing operation may ecutinue while repairs are being made.
If neither system is operab u, the plant is brought to a condition where the standby gas treatment system is not required.
4.7.B 6 4.7.C LASES Standbv Ons Treatment System and Secondary containment Initiating reactor building isolation and operation of the standby gas treatment system to maintain at least a 1/4 inch of water vacuum within the secondary containment provides an adequate test of the operation of the reactor building isolation valves, leak tightness of the reactor building and performance of the standby gas treatment system. Functionally testing the initiating sensors and associated trip channels dernonstrates the capability for automatic actuation. Periodic testing gives suf ficient confidence of reactor building l
integrity and standby gas treatment systett performance capability.
Pressure drop across the combined llEPA filters and charcoal adsorbers of less than 6 inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
A 7.8 kw heater is capable of maintaining relative humidity below 70%.
licater capacity and pressure drop should be determined at least once per operating cycle to show system performance capability.
The frequency of tests and sample analysis are necessary to show that the llEPA filters and charcoal adsorbers can perform as evaluated. Tests of the charcoal adsorbers with halogenated hydrocarbon refrigerant shall be performed in accordance with ANSI N5101980.
The test canisters that are installed with the adsorber trays should be used for the charcoal adsorber ef ficiency test.
Each sample should he at least two inches in diameter and a length equal to the thickness of the bed.
If
.t results are unacceptable, all adsorbent in the system shall be replaced Amenament N]. 20,82,83,102,150 182-
_ _ _, ~.
v 6.0, ADMINISTRATIVE CONTROLS 6.1 ORGANIZATION 6.1.1 Responsibility The Division Manager of Nuclear Operations shall have the over-all fulltime onsite responsibility for the safe operation of the Cooper Nuclear Station.
During periods when the Division Manager of Nuclear Operations is unavailable, this responsibility automatically shifts to either the Senior Manager of Operations, the-Senior Manager of Technical Support Services, or the Senior Manager of Staff Support (in that order).
During periods when none of these individuals are available, the responsibility may be delegated in writing to one of the mana6ers in the Nuclear Operations Division.
6.1.2 Offsite and ongjte Orcanizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
A.
Lines of authority, responsibility, and communication shall be established and defined for the highest' management levels through intermediate levels to and including all operating organization positions.
These reistionships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for. key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in the USAR.
B.
The Division Manager of Nuclear Operations shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
C.
The Nuclear-Power Group Manager shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance - of the staff in operating, maintain.ng, and
.providing technical support to the plant to ensure nuclear safety.
D.
The individuals who train. the operating staff and those who carry out health ~ physics and quality assurance functions may report to the appropriate. onsite manager;
- however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
'6.1,3 Plant Staf f - Shift Complement The shift complement at the station shall at all times meet the following requirements.
Note:
Higher grade licensed operators may take the place of lower grade licensed or unlicensed operators.
l-A.;
A licensed senior reactor operator (SRO) shall be present at the station at all times when there is any fuel in the reactor.
B.
A licensed reactor operator shall be in the control room at all times when-there is any fuel-in the reactor.
C.
Two licensed reactor operators shall be in the control room during all startup.. shutdown and other periods involving significant planned control rod manipulations. A licensed SRO shall either be in the Control Roam l
or immediately available to the Control Room during such periods.
Amendment No. 66,82,83,99,131,132, 150 219-
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