ML20102A675
| ML20102A675 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/01/1985 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.18, TASK-TM U-0791, U-791, NUDOCS 8502080507 | |
| Download: ML20102A675 (2) | |
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U-0791 P04-85(02-01)-L i-N33-85(02-01)-L ILLINDIS POWER 00MPANY IP CLINTON PCmER STATION. P.O. BOX 678. CLINTON. ILLINOIS 61727 February 1, 1985 o
Docket No. 50-461 Director of Nuclear Reactor Regulation
. Attention: Mr. A. Schwencer, Chief
~ Licensing Branch No. 2'
. Division of Licensing.
U.' S. Nuclear Regulatory Comission Washington, D. C. 20555
Subject:
Clinton Power Station (CPS) Unit 1 Autmatic Depressurization System Actuation logic
-(SER Confirmatory Issue # 28)
Dear Mr. Schwencer:
This is in response to a request fr m the NRC Staff regarding clarification of Appendix D, IMI Action Plan Its II.K.3.18 of the
~ linton Power Station (CPS) Final Safety Analysis Report (FSAR).
C The following clarifies our response to Its II.K.3.18. The high drywell pressure portion of the logic-circuit is bypassed and the
. Automatic Depressurization System (ADS) initiates on the low reactor ressure vessel (RPV) water level (Irvel 1) signal alone, when the
- p' bypass" timer and the 105 second timer are out. A time delay of six udnutes for the high drywell pressure bypass logic was chosen,
. consistent with the calculated analytic limit. The detailed analysis performed was based upon:
1.
Avoidance of excessive fuel cladding heatup using 10CER50 Appendix K models and the most limiting transient as described in Figure 6.3-72 of the CPS FSAR Section 6.3.3 (assm es no operator action).
2.
Providing sufficient time to allow recovery of the RPV water level above level 1 during an ATWS event.
Following receipt of level 1 signal and.once the bypass timer and the system level timer times out, the ADS initiation is sealed in and h
' the system does not automatically reset. For additional information see CPS FSAR Section 7.3.1.1.1.4.
M 8502080507 850201
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U-0791 P04-85(02-01)-L N33-85(02-01)-L 1A.120 It is our understanding that the above information provides the clarification requested by the NRC Staff regarding TMI Item II.K.3.18.
required to close SER Confirmntory Issue # 28. The CPS FSAR Appendix D will be revised to reflect the above clarification.
Sincerely yours,
(:
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F. A. Sp enb'rg Director Nuc ear Licensing and Configuration Nuclear Station Engineering TIE /ls cc:
B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III USNRC Illinois Department of Nuclear Safety m
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