U-601068, Forwards Description of Changes to Programs in Chapter 14 to FSAR
| ML20235Z498 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 10/16/1987 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| U-601068, NUDOCS 8710210175 | |
| Download: ML20235Z498 (2) | |
Text
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,g L30-87 (10-16)-L 1A.120 a
/LLINDIS POWER COMPANY IP CLINTON POWER STATION, P.O. BOX 678. CLINTON ILLINOIS 61727 10CFR50.59 October 16, 1987 iE l
a Docket.F,o 5C-461 lGj c$
1 i-U.S. Nticlear Regulatory Commission 3M Document Control Desk i
Washington,.D.C.
20555 9
Subject:
Clinton Power Station a
1CCFR50.59 Report U1
Dear Sir:
1-Pursuant to the Facility Operating License NPF-6, Condition 2.C.8, 2
(7 Illinois Power Company is hereby reporting changes to the programs described in Chapter 14 of the Clinton Power Station Final Safety I
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 questiona, please' contact me.
Sincerely yours, F. A. Spa genbe f, III Manager - Licens..ng and Safety SFB/ckc Attachment cc:
B. L. Siegel, NRC Clinton Licensing Project Manager Regional Administrator, Region III, USNRC NRC Resident Inspector Illinois Department of Nuclear Safety
/p(O 8710210175 871016 3
PDR ADOCK 05000461 I
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~)nge Description.
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l Sol s(ction 1G2)l,2.2.20.4D of the FSAR. currently has:
'"Haximum speed attained shall not exceed the speeds which will give thz following flows with the normal complement of pumps operating.
- y. a) 130% flow at 1080 psia.
b).
138% flow.~at rated pressure of 1040 psia."
This change will.use the revised percentages of 139% and 144%
rei ectively.
Safdt9 Evaluation In compliance with FSAR Section 14.2.12.2.20, using Startup Test STP-23D-6, Rev. O, the maximum feedwater runout capacities (FWRC) were determined. The measured feedwater pump runout capacity is an e<pivalent of 139% Nuclear Boiler Rated (NBR) at a vessel pressure l'
of 1080 psia; this as--tested flow exceeds the flows of the Startup Test Specification.22A7217 R/5 Test #23D and FSAR Subsection 14.2.12.2.20.4D.""The test specification is based on an FSAR
-analysis value of'130% NBR for the feedwater controller failure j}VjF)toamaximumdemandevent. This value coincided with the
),
valuts used in the Transient Safety Analysis Design Report Volume 2 j
GFfr7355 March 1985'.
Feedwater controller failure to maximum j/demandistheonly' event f
T I
that is affected by FWRC. It has been
', ' ' concluded, based on reanalysis, that the increased feedrater runout
' i. capacity has a small effect on the FSAR safety analysis, and the
,Idnuit is still bounded by current FSAR analysis for another evat
/. )(doss of feedwater heating). This change does not affect nuclear VL
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safety or constitute an unreviewed safety question.
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This change has been evaluated in accordance with 10CFR50.59 per the appropriate' procedures, and it has been determined that the v
ichange can be made per 10CFR50.59.
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