ML20116B573
| ML20116B573 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/22/1996 |
| From: | Querio R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20116B576 | List: |
| References | |
| NUDOCS 9607300129 | |
| Download: ML20116B573 (3) | |
Text
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Osmmonwcalth litiv>n Osmpan) 14tsalle (.cncrating Station
.Wil North 21st Road Marseilles, !!. 613 a l-9?s" Tel f415 357C6I July 22,1996 United States Nucleer Regulatory Commission - Region 111 801 Warrenville Road Lisle,IL 60532 l
Attention:
H. B. Clayton, Projet t Branch Chief - Region 111 i
United States Nuclear Regulatory Commission i
Subject:
LaSalle County Nuclear Power Station Units 1 and 2 Submittal of Additional Information discussed during the July 19,1996 Call Regarding Lake Screen House Water Tunnel Issues NRC Docket Nos. 50-373 and 50-374
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Dear Mr. Clayton,
The purpose of this letter is to provide the additional information that was requested during the July 19,1996 teleconference between Region lil and LaSalle Station.
The enclosed attachments transmit the design engineering calculations and overall review of the piping and pipe components for portions of the Service Water (WS) and Residual Heat Removal (RHR) Systems in the Lake Screen House.
If there are any questions or comments concerning this letter, please refer them to Petros Antonopoulos, Site Engineering Manager, at (815) 357-6761, extension 2703.
l Respe"f%,
R. E. O erio @
Site Vice President LaSalle County Station I
Enclosure i~ (
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A. B. Beach, NRC Region 111 Administrator M. P. Huber, NRC Senior Resident inspector - LaSalle Central File 960750'0129 960722
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PDR ADOCK 05000373 P
PDR A Unicum Lompany
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COMED NUCLEAR DESIGN INFORMATION TRANSMITTAL O SAFETY-RELATED Originating Organizaton:
NDIT No.: LAS-ENDIT-0150 NON-SAFETY-RELATED Section:
PSM Upgrade:
0 0 REGULATORY RELATED Company:
Sargent & Lundy Page 1
of 2
Station:
LaSalle County Units: 1,2 System:
To: Egan, D. L. - Comed, DE Design Change Authority No.:
Subject:
Screen House Water Tunnelissues.
Upgrade of Class D, non-seismic service water, and residual heat RH removal system piping in the Lake Screen House, to Class D, seismic w
piping that perform safety-related function.
WS Pressh!mer, M. A.
Project Manager
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o 7/5/96 Preparer Posstion 64natuse U
D:,e o
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_ /g /g Milad, Milad A Senior Project Engineer 7/5/96 Reviewer Positen
.gnatute Date Pressburger, M. A.
Project Manager
[/tgy 7
7/5/96 App #ower Posetson signatute C
Date Status of information:
Approved for Use Unverified Venfication Method: N/A 1
Engineenng Judgement Schedule:
Purpose of issuance:
To transmit S&L evaluations for Comed's use Source of Information:
Calculation EMD-023757, Revision 00, Addendum A Calculation L-000556, Revision 0 Calculation L-000561, Revision 0 Calculation L-000566, Revision 0 NDIT LAS-ENDIT-014, Upgrade 0 Description of Inforrnation:
DESCRIPTION An overall review of the piping and pipe components for portions of the Service Water (WS) and Residual Heat Removal (RHR) Systems in the Lake Screen House has been performed. The piping systems were procured as Class D and were considered non-safety related, non-seismic. An evaluation was performed to " upgrade" these lines to non-safety related, seismic piping that perform a safety-related function.
It was determined that the piping and components are capable of performing their required functon for loading including the design-basis earthquake; they are designed adequately.
See Page 2 l
Distribution: SEAG Parson, Raynumd A - Sargent A bmdy, MPED McQueen, Donald L - Sargent A bmdy, MPED i
Duth, Donal<t 1 Sargent A Lundy, MPED l
Petrich, Joseph O. - Sargent A bmdy, PDED-SPE I
WIN No.:
f7 d-COMED NUCLEAR DESIGN INFORMATION TRANSMITTAL SAFETY RELATED Onginating Organeation:
NDIT No.: LAS-ENDIT-0150 NON-SAFETY RELATED Section:
PSM Upgrade:
0 0 REGULATORYRELATED Company:
Sargent & Lundy Page 2
of 2
The independent evaluations to support this conclusion include the following:
1.
Calculaton EMD-023757, Revision 00, Addendum A This calculaten address piping Subsystems 1WS15 through 1WS20 (Lines OWS07AA through OWS07AF-36"). Paping analysis was performed to now include both the OBE and DBE seismic conditons. All piping stresses remain well within code allowable levels for all loading conditions. All anchor loads remain within the acceptance craeria. A seismic Category 11 over Category I review was also performed and demonstrates that the piping and other components in the area either will not be subject to catastrophic failure due to a seismic event or will not adversely affect the 36" piping systems.
2.
Calculation L-000556, Revision 0 This calculaton was performed to assess the 54" buried Traveling Screen Bypass Line ORH01 AA for loads imposed by overburden and seismic rnotion. The seismic stresses were found to be very small compared to the allowable. Overburden load tvas approximately 58% of capacity and deflection is less thrn 6% of the pipe diameter. The piping systern was, therefore, deemed able to sustain knposed loads safety.
3.
Calculation L-000561, Revision 0 This calculation was performed to evaluate the 36" Crane gate valves (0WS015A through F)in Subsystems 1WS15 through 1WS20 for seismic loads. The calculation determined that the loads and accelerations that the valves are subjected to during the postulated seismic events, would not adversely effect the valves and therefore the valves would maintain pressure and structural integnty and would remain open after enduring such loading values.
1 4.
Calculation L-000566, Revision 0 This calculation was performed to evaluate the 54-inch Pratt Butterfly valve No. OE12-F300, in the Traveling Screen Bypass Line, for seismic loads. The calculation determined that the loads and accelerations that the valve is subjected to during the postulated seismic events would not adversely effect the valve and therefore the valve would maintain its pressure and structuralintegrity and would maintain its closed or open l
position (normally closed but could be opened)in case of a seismic event.
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l S.
Nuclear Design Informaton Transmittal (NDIT) LAS-ENDIT-0144, Upgrade 0 j
This NDIT performed a comparison of pipe Class C versus Class D requirements for the Service Water Pipe Lines OWS07AA through OWS07AF and RHR Pipe Line ORH01 AA. The comparison included the material, fabncaten, testing, and examination requirements, as well as the allowable stresses.
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l CONCLUSION 1
Based on the above, it is concluded that the piping systems (Lines OWS07AA through OWS07AF-36" and ORH01 AA-54") are adequately designed and are capable of performing their required functions for design-basis loading including the design-basis earthquake. These lines can be upgraded from Class D, non-seismic to Class D seismic piping that perform safety-related functions.
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l SEAG l
Comed - Nuclear Operations Disivion
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