U-600945, Forwards Changes to Chapter 14 of Fsar,Per License Condition 2.C.8
| ML20214U807 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 06/03/1987 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| U-600945, NUDOCS 8706110344 | |
| Download: ML20214U807 (3) | |
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U-600945 i
L30-87(06-03) 1A.120 ILLINDIS POWER 00MPANY CLINTON POWER STATION P.o. BOX ( 78. CLINTON. ILLINOIS 61727 10CFR50.59 June 3, 1987 Docket No. 50-461 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Clinton Power Station 10CFR50.59 Report
Dear Sir:
Pursuant to the Facility Operating License NPF-62, Condition 2.C.8, Illinois Power Company is hereby reporting changes to the programs described in Chapter 14 of the Clinton Power Station Final Safety Analysis Report (FSAR). These changes were made after evaluations were performed in accordance with the provisions of 10CFR50.59. These changes are described in Attachment 1.
If you need any additional information or have any questions, please contact me.
Sincerely yours,
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F. A. Sp gen rg Manager - Licensing ahid Safety DW/bsa Attachment cc:
B. L. Siegel, NRC Clinton Licensing Project Manager Regional Administrator, Region III, USNRC NRC Resident Office Illinois Department of Nuclear Safety hl o
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1.
Change Description FSAR Section 14.2.12.2.32 will be revised to delete all of the references to the testing of the steam condensing mode of the Residual Heat Removal (RHR) System. Table 14.2-4 will be revised to delete testing of the RHR System in Test Condition 1 to be consistent. FSAR Section 1.8 (Regulatory Guide 1.68) will be revised to indicate that the RHR steam condensing test will not be performed during the Startup Test Program.
If this mode of operation is to be used in the future, it will be evaluated for testing requirements at that time. FSAR Section 5.4.7.4 will also be revised to be consistent.
Safety Evaluation Summary Deletion of the RHR steam condensing mode testing does not affect any safety system or safe operation of the plant since for the Post-LOCA condition the RHR steam condensing mode is isolated and the associated RHR logic precludes the initiation of the steam condensing mode. The design capability of the RHR system can still be demonstrated in the suppression pool cooling and shutdown cooling mode per existing startup test procedures. During plant depressurization, an alternate way of using safety relief valves and/or Reactor Core Isolation Cooling (RCIC) operation will be used before placing the RHR system in the shutdown cooling mode for further cooldown.
This change has been evaluated in accordance with 10CFR50.59 per the appropriate procedures, and it has been determined that the change can be made per 10CFR50.59, 2.
-Change Description FSAR Section 14.2.12.2.13.4 will be revised to state "The turbine gland seal system shall be capable of preventing significant steam leakage to the atmosphere."
Safety Evaluation Summary This change clarifies that there may be some leakage from the turbine gland seal systen, but it will not be significant. The allowable leakage will be of a magnitude that will allow entrance into the RCIC Turbine room during and/or after the turbine has been operated. Any steam leakage will be contained within the boundary of the RCIC turbine bay, and the room will be surveyed by the Radiation Protection Department and posted accordingly.
This change has been evaluated in accordance with 10CFR50.59 per the appropriate procedures, and it has been determined that the change can be made per 10CFR50.59.
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Change Description Note ** on FSAR page 14.2-103 will be changed to:
" Individual CRD scram times will be determined from scram data taken during TC-1 or TC-2 Scram time data for control rods not fully withdrawn during the performance of test STP-05-2, up to the maximum of 32 control rods not occupying adjacent locations in any direction, including diagonal, are exempted under hot, pressurized conditions, provided they meet all other surveillance test requirements, and that all scram reactivity requirements of the plant safety analysis are met with no scram contribution from these rods. Any remaining rods neither exempted nor fully withdrawn in Test STP-05-2 will be individually scram tested, before exceeding 40% power."
FSAR Table 14.2-4 will also be revised to be consistent.
Safety Evaluation This change allows for the test to be performed in either Test Condition 1 or 2 when all the initial conditions are satisfied.
The scope and intent of the testing remains unchanged. The only change is the point in time when the test is performed.
This change has been evaluated in accordance with 10CFR50.59 per the appropriate procedures, and it has been determined that the change can be made per 10CFR50.59.
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