ML20245D555
| ML20245D555 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/20/1989 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Illinois Power Co |
| Shared Package | |
| ML20245D558 | List: |
| References | |
| NPF-62-A-022 NUDOCS 8905010046 | |
| Download: ML20245D555 (4) | |
Text
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UNITED STATES
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',i NUCLEAR REGULATORY COMMISSION g
er WASHINGTON, D. C. 20655 ILLIN0IS POWER COMPANY, ET AL.
DOCKET NO. 50-461 CLINTON POWER STATION, UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 22 License No. NPF-62 1
1.
The Nuclear Regulatory Commission (the Comission) has found that:
The application for amendment by(the licensees) dated January 26,IllinoisP j.
.A.
Soyland Power Cooperative, Inc.
1989, complies with the standards and re Energy Act of 1954, as amended (the Act)quirements of the Atomic
, and the Commission's rules and regulations set forth in 10 CFR Chapter I; o-B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
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 issuance of this amendment wi11 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 M indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-62 is hereby amended to read as follows:
- Illinois Power Company is authorized to act as agent for Soyland Power
^
Cooperative, Inc. and has exclusive responsibility and control over the
. physical construction, operation and maintenance of the facility.
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Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 22, are hereby incorporated into this license.
Illinois Power Company shal' cperate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: April 20, 1989 u________.___
L ATTACHMENT T0 LICENSE AMENDMENT NO. 22 L
FACILITY OPERATING LICENSE NO. NPF-62 l
DOCKET NO. 50-461 Replace the following peges of the Appendix "A" Technical Specifications with i.
the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
1 Remove Insert 3/4 4-3 3/4 4-3 l
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REACTOR COOLANT SYSTEM RECIRCULATION LOOPS SURVEILLANCE REQUIREMENTS 4.4.1.1.1 Each reactor coolant system recirculation loop flow control valve shall be demonstrated OPERABLE at least once per 18 months by:
Verifying that the control valve fails "as is" on loss of hydraulic a.
pressure at the hydraulic control unit, and b.
Verifying that the average rate of control valve movement is:
1.
Less than or equal to 11% of stroke per second opening, and 2.
Less than or equal to 11% of stroke per second closing.
4.4.1.1.2 When THERMAL POWER is within the restricted zone of Figure 3.4.1.1-1, and one or two pumps are in operation, establish a baseline APRM and LPRM*
neutron flux noise value within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of entering this operating region unless baselining has previously been performed in the region since the last CORE ALTERATION, and Determine the APRM and LPRM* noise levels at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and a.
b.
Determine the APRM and LPRM* noise levels within 30 minutes after the completion of a THERMAL POWER increase of at least 5% of RATED THERMAL POWER.
4.4.1.1.3 With one reactor system recirculation loop not in operation, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify that:
Reactor THERMAL POWER is 5 70% of RATED THERMAL POWER.
a.
b.
The recirculation flow control system is in the Local Manual (Position Control) mode, c.
The volumetric flow rate of the operating loop is 5 33,000 gpm**, and d.
Core flow is greater than (39)#% when THERMAL POWER is within the restricted zone of Figure 3.4.1.1-1.
4.4.1.1.4 With one reactor coolant system recirculation loop not in operation, within no more than 15 minutes prior to either THERMAL POWER increase or recir-culation loop flow increase, verify that the following differential temperature
- Detector levels A and C of one LPRM string per core octant plus detectors A and C of one LPRM string in the center of the core should be monitored.
- This value represents the design volumetric recirculation loop flow which produces 100% core flow at 100% THERMAL POWER.
- Value to be established during Startup Test Program.
(Core flow with both recirculation pumps at rated speed and minimum control valve position.)
CLINTON - UNIT 1 3/4 4-3 AMENDMENT NO. 22 i
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