U-600359, Forwards Details Re Termination of Seismic Interaction Program Initiated in Response to Noncompliance Noted in Insp Rept 50-461/80-17 & FSAR Meb Item 3
| ML20137G548 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/14/1986 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| U-600359, NUDOCS 8601210079 | |
| Download: ML20137G548 (3) | |
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U-600359 L42 -86(01-14)-L 1A.120
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/LLINDIS POWER 00MPANY CLINTod POWER STATION. P.o. box 678. CLINTON. ILLINOIS 61727 January 14, 1986 Docket No. 50-461 FRIORUYROU/IES Mr. James G. Keppler f[h &
Regional Administrator
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R Region III j!-
.gS U.S. Nuclear Regulatory Commission N
Y Glen Ellyn, Illinois 60137
' %Z "C 799 Roosevelt Road gj "
Subject:
Clinton Power Station Termination of Seismic Interaction Progran
Dear Mr. Keppler:
In response to an item of noncompliance (461/80-17-01) and to MEB Item Number 3 in the Clinton Final Safety Analysis Report (FSAR),
Illinois Power (IP) committed to implement an ongoing interaction analysis program. Area walkdowns have been conducted, and as of December 31, 1985, 8522 Seismic Potential Interaction Reports (PIRs) have been generated and 7443 have been dispositioned with no impact ou plant hardware due to seismic interactions. The remainder of the PIRs are still in the disposition process.
These results indicate that both the plant arrangement and design of the safety-related components provide a high degree of assurance that they will perform their safety function. There is also a high degree of assurance that with construction greater than 98% complete, further walkdowns will not find additional interactions that will impact plant hardware. Therefore, Illinois Power believes that the commitment to implement an interaction analysis program has been met and intends to terminate the Seismic Interaction Program walkdowns immediately, disposition all outstanding PIRs, and then terminate the program entirely. Additional details are provided in the attachment.
If further information is required, please advise.
Sincerely yours, 7^
8601210079 860114 gDR ADOCK 0 1
F.A.fpan bert Manager - icens:.ng and Safety DW/cke Attachment cc: Director, Office of I&E, USNRC, Waahington, D.C.
20555 B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Illinois Department of Nuclear Safety
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Director, Nuclear Reactor Regulation.
USNRC, Washington, D.C.
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'S Attachment I TERMINATION OF THE SEISMIC INTERACTION PROGRAM I.
SEISMIC INTERACTION PROGRAM AT CLINTON POWER STATION In response to MEB (DSER) Item Number 3 in the Clinton FSAR, Illinois Power Company (IP) has committed to the following:
" Class D piping and other non-safety-related components shall be evaluated to assure that any interaction with a safety-related component will not impair the capability of the safety-related component to perform its intended function."
a rield verification by an area walkdown basis will ensure adequate cicarance exirts around all safety-related components. Situatirns which violate the clearaace criteria will be identified and resolved by either detailed calculations (to shoe that the corponents will not interact or that the interaction is not detrimental to the safety-related component) or by a redesign to eliminate the interaction."
lilinois Power Company implemented an ongoing Seismic Interaction Analysis Program in 1980 in response to an item of noncompliance (461/80-17-01) for non-seismically supported drain lines being in close proximity to Class IE cable trays in the Fuel Building.
Schedules for area walkdowns were established based on area availability and coupleteness of installation. Project Instruction PI-CP-034 was issued to provide technical and administrative requirements.
The first version of Project Instruction PI-CP-034 provided an interim clearance criterion of 4 inches for all components. This interim criterion was very conservative and af ter further evaluation was ultimate 1/ replaced with more detailed clearance criteria and in many cases generic acceptance of interactions between ccrtain components. These criteria and generic acceptances were implemented through revisions to PI-CP-034 Walkdown cycles of three months for congested areas and six months for non-congested areas have taken place since April 1984.
Congested areas are defined as the Containment Building, Auxiliary Building, Elevation 762' of the Diesel Generator Building,-
Elevation 781' of the Control Building, and Elevation 712' of the Fuel Building. Non-congested areas are the remaining areas which contain safety-related components. Prior to April 1984, walkdown schedules were based on area availability and completeness of construction.
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DESIGN IMPACT OF SEISMIC INTERACTION INVESTIGATIONS During the period from April 1984 through October 1985, six complete walkdowns have been conducted in the congested areas of the plant and a minimum of three walkdowns in each of the non-congested areas. These walkdowns occurred during the last phases of plant construction, which is currently greater than 98%
complete. These walkdowns, along with the walkdowns prior to April 1984, have resulted in over 8000 Seismic Potential Interaction Reports (PIRs) being written, a majority of which identify more than one potentia) interaction. As of December 31, 1985, 7443 have been dispositioned with no impact on plant hardware due to seismic interactions. The remainder of the PIRs are in the disposition process.
The table below summarizes the results of the Seismic Interaction Program through December 31, 1985.
TABLE 1 Seismic Interaction PIRs Written 8522 Seismic Interaction PIRs Dispositioned 7443 On Hold for Construction Completion 323 In Process at IPC 278 In Process at S&L 473 III.
SUMMARY
AND CONCLUSIONS Area walkdowns (100%) have been conducted on three (3) and six (6) month cycles. Six (6) complete walkdowns of congested areas and three (3) walkdowns of non-congested areas have been completed. As of December 31, 1985, these walkdowns have generated 8522 Seismic Potential Interaction Reports of which 7443 have been distositioned with no impact on plant hardware. The remaindt-are in process as described in Table 1.
These results indicate that both the plant arrangement and design of safety-related components provide a high degree of assurance that they will perform their safety function. There ic also a high degree of assurance that with construction 98% complete, further walkdowns will not find additional interactions that will impact plant hardware.
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