ML20128G917
| ML20128G917 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 10/03/1996 |
| From: | Pickett D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128G919 | List: |
| References | |
| NPF-62-A-107 NUDOCS 9610090169 | |
| Download: ML20128G917 (9) | |
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UNITED STATES ye NUCLEAR REGULATORY COMMISSION e
f WASHINGTON. D.C. 20666 4 001 Q '.... *#g ILLIN0IS POWER COMPANY. ET AL.
DOCKET N0. 50-461 CLINTON POWER STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.107 License No. NPF-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
1 A.
The application for amendment by Illinois Power Company * (IP), and Soyland Power Cooperative, Inc. (the licensees) dated June 28, 1996, and supplemented by letter dated September 17, 1996, complies with the standards and requirements of the Atomic Energy i
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 l
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 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 Specifi-cations as 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.
9610090169 961003 PDR ADOCK 05000461 P
1 (2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.107, are hereby incorporated into this license.
Illinois Power Company shall operate 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
~
Douglas V. Pickett, Project Manager Project Directorate III-3 1
Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 3, 1996
ATTACHMENT TO LICENSE AMENDMENT NO.107 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 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 arer. a? change.
Remove Paoes Insert Paaes 3.6-16 3.6-16 3.6-17 3.6-17 3.6-18 3.6-18 3.6-19 3.6-19 3.6-19a 3.6-19b
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PCIVs 3.6.1.3 i
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY 4
NOTES------------------
1.
Valves and blind flanges in high radiation areas may be verified by use of administrative means.
2.
Not required to be met for PCIVs that are open under administrative controls.
l Verify each primary containment 31 days isolation manual valve and blind flange that is located outside primary containment, drywell, and steam tunnel and is required to be closed during accident conditions is closed.
(continued)
I CLINTON 3.6-16 Amendment No.107
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.3
NOTES------------------
1.
Valves and blind flanges in high radiation areas may be verified by use of administrative means.
2.
Not required to be met for PCIVs that are open under administrative controls.
3.
Not required to be met for the Inclined Fuel Transfer System (IFTS) penetration when the associated primary containment blind flange is removed, provided that the fuel building fuel transfer pool water level is maintained 2 el. 753 ft.
and the IFTS transfer tube drain valve (s) remain (s) closed, except j
that the IFTS tube drain valve (s) may be opened under administrative controls.
j Verify each primary containment Prior to isolation manual valve and blind flange entering MODE 2 that is located inside primary or 3 from containment, drywell, or steam tunnel MODE 4, if not and is required to be closed during performed accident conditions is closed.
within the previous 92 days (continued) i CLINTON 3.6-17 Amendment No.107
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.4 Verify the isolation time of each power In accordance operated and each automatic PCIV, except with the MSIVs, is within limits.
Inservice Testing Program SR 3.6.1.3.5
NOTE------------------
Only required to be met in MODES 1, 2, and 3.
Perform leakage rate testing for each Once within 92 primary containment purge valve with days after resilient seals.
opening the valve AND In accordance with the Primary Containment Leakage Rate i
Testing Program SR 3.6.1.3.6 Verify the isolation time of each MSIV In accordance is e 3 seconds and s 5 seconds.
with the Inservice Testing Program SR 3.6.1.3.7 Verify each automatic PCIV actuates to 18 months the isolation position on an actual or simulated isolation signal.
(continued)
CLINTON 3.6-18 Amendment No.107
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE.
FREQUENCY SR 3.6.1.3.8
NOTE------------------
Only required to be met in MODES 1, 2, and 3.
Verify the combined leakage rate for all In accordance secondary containment bypass leakage with the paths is s 0.08 L, when pressurized to Primary 2: P.
Containment a
Leakage Rate Testing Program SR 3.6.1.3.9
NOTE------------------
Only required to be met in MODES 1, 2, and 3.
Verify leakage rate through each main In accordance steam line is s 28 scfh when tested at with the at P.
Primary 3
Containment Leakage Rate Testing Program SR 3.6.1.3.10
NOTE------------------
Only required to be met in MODES 1, 2, and 3.
Verify combined leakage rate through In accordance hydrostatically tested lines that with the penetrated the primary containment is Primary within limits.
Containment Leakage Rate Testing Program (continued)
CLINTON 3.6-19 Amendment No. 107
PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.11 Verify each instrumentation line excess 18 months flow check primary containment isolation valve actuates within the required _ range.
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CLINTON 3.6-19a Amendment No. 107 i
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CLINTON 3.6-19b Amendment No.107 J