ML20134L876

Forwards Station Blackout Evaluation Rept & Program for Compliance W/Tmi Action Plan Item I.G.1,`Training During Low Power Testing,' Per Generic Ltr 83-24,TMI Action Plan Item I.G.1,NUREG-0737 & SER (NUREG-0853)

ML20134L876
Person / Time
Site:	Clinton
Issue date:	08/28/1985
From:	Spangenberg F ILLINOIS POWER CO.
To:	Butler W Office of Nuclear Reactor Regulation
Shared Package
ML20134L879	List: ML20134L876 ML20134L887 ML20134L892
References
REF-GTECI-A-44, REF-GTECI-EL, RTR-NUREG-0737, RTR-NUREG-0853, RTR-NUREG-737, RTR-NUREG-853, TASK-1.G.1, TASK-A-44, TASK-OR, TASK-TM GL-83-24, NUDOCS 8509030449
Download: ML20134L876 (2)

Text

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U-600188 L30-85(08-29)-L 1A.120

/LLIND/S POWER COMPANY LP CLINTON PoMR STAflON P.o. BCX 678 CLINTON. ILLINOIS 61727 Docket No. 50-461 August 28, 1985 Director of Nuclear Reactor Regulation Attention: Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U. S. Nucicar Regulatory Commission Washington, D. C. 20555 Clinton Power Station Station Blackout Evaluation Report SER Confirmatory Licensing Issue #42 TMI Action Plan Item I.G.1

Dear Mr. Butler:

Attachment #1 provides the "Clinton Power Station Station Black-out Evaluation Report". This report presents the results of an evalua-tion of the current capabilities of the Clinton Power Station (CPS) to withstand a Station Blackout (SBO) of extended duration. This report provides justification for not performing a full scale in-station SB0 Test at CPS. As such, the requirements of NRC Ceneric Letter 83-24 are fully addressed. Attachment #2 provides details of the program for CPS compliance to the NRC requirements contained in TML Action Plan Item I.G.1, " Training During Low Power Testing". This program is considered by Illinois Power Company (IP) to be in compliance with the NRC accepted generic program developed by the Boiling Water Reactor Owner's Group for TMI Activities (BWROG).

The requirement for performing an in-station SB0 Test arose from THI Action Plan Item 1.G.I. In an October 27, 1981 letter from the NRC, IP was requested to commit to performing an SB0 Test. In Appendix D of the CPS Finni Safety Analysis Report, TMI Item 1.G.1 response, IP com-mitted to perform a low power test training program to be developed using the guidelines provided in the report entitled "BWR Owner's Group Program for Compliance with NUREG-0737 Item 1.G.I. Training During Low Power Testing". IP also committed to performing an SB0 Test if the results of similar tests that were to be performed at the LaSalle and Grand Culf stations indicated that the test could be performed safely and would provide useful information and training for CPS.

In NRC Generic Letter 83-24, dated June 29, 1983, the NRC stated

. ...if it can be demonstrated that temperature and/or other SB0 test conditions would adversely impact and pose a hazard to plant equipment, the BWR Owner's Group recommendations by themselves would constitute O compliance with Item 1.G.1....". The results of the CPS SB0 Evaluation ,

concludes the following key points (see Attachment #1):

1. Risks to plant equipment from performance of this test could .

occur. Drywell temperature concerns due to the loss of cool-ing are of primary significance in the short-term. As a result, performance of this test may require replacement of some equipment; .,, y gy y rit.t /A;6 /cy

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2. Restrictions in any proposed test procedures, which are necessary to prevent damage to plant equipment, would not allow an accurate representation of extended SB0 conditions, resulting in significantly reduced training benefits from such testing;

3. CPS has the capability to safely withstand an actual SB0 event for a minimum of 2.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if the Reactor Core Isolation Cooling (RCIC) System remains available for the event duration. The plant safety limit exceeded at this time is the Suppression Pool Heat Capacity Temperature Limit. IP considers this calculation to be conservative. Estimates indicate that significant concerns would not be reached until approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> into the SB0 event. If the RCIC system is not available, core cooling can be maintained for at least 30 minutes through core inventory boil off; and 4 Tests on individual systems will be performed that will provide information relative to the ability of equipment to perform their function under SB0 conditions.

Attachment #2 provides a more detailed description of the CPS program to comply with TML Action Plan Requirement I.G.1, and includes all aspects of training during low power testing (i.e., not limited to S30-related tests and training). Based on the conclusions of Attachment

1. 1, IP does not propose to perform an SB0 Test. Therefore, Attachment

1. 2 provides the compliance required by Generic Letter 83-24. As such, the information attached herein is considered complete and adequate to address the requirements of THI Action Plan item I.G.1 and result in Staff closure of CPS Safety Evaluation Report (NUREG-0853) Confirmatory Licensing Issue #42.

Following your review of this material, if you should have any questions on this issue, please call me.

Sincerely yours, D. us. LOM L F. A. Spangenberg Director - Nuclear Licensing and Configuration Nuc1 car Station Engineering TLR/ lab Attachments (2) cc: B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office NRC Administrator, Region III office Illinois Department of Nuclear Safety