ML20091S088
| ML20091S088 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 08/10/1995 |
| From: | Gershman A, Humphreys R, Petrich J SARGENT & LUNDY, INC. |
| To: | |
| Shared Package | |
| ML20091P894 | List: |
| References | |
| EMD-067927, EMD-67927, NUDOCS 9509070287 | |
| Download: ML20091S088 (64) | |
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SARGENT&LUNDY ENGINEERS CHICAQO 1
REPORT OF WALKDOWN TO VERIFY SEISMIC ADEQUACY OF MAIN STEAM DRAIN LINE AND CONDENSER FOR USE AS THE ALTERNATE MSIV LEAKAGE TREATMENT SYSTEM I-REPORT PREPARED FOR COMMONWEALTH EDISON COMPANY LASALLE COUNTY NUCLEAR STATION - UNIT 2 PROJECT NO.: 09606-069 WIN NO.: 2214 I
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SARGENT & LUNDY S&L FILE NO.: EMD-067927, Rev. 2 l
Aug.9,1995 PAGE 1 9509070287 950828 PDR ADOCK 05000373 c
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CAROENT G LUNDY EMD-067927 N'gs Proj. N3: 09606-069 Rev.: 2 Page 2 REPORT OF WALKDOWN TO VERIFY ADEQUACY OF MAIN STEAM DRAIN LINE AND CONDENSER FOR USE AS THE ALTERNATE MSIV LEAKAGE TREATMENT SYSTEM 1
COMMONWEALTH EDISON COMPANY LASALLE COUNTY NUCLEAR STATION - UNIT 2 PROJECT NO.: 09606-069 WIN NO.: 2214 i
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Prepared By:
d ml d
?/9/4 A. l. Ge an
- Reviewed By:
b!M M L Humpfhreys[
Approved By:
N Q. Petrich
- Tne review of this report was accomplished by performing a review of the typographical changes made to Rev. 2 only.
Note that the signatures for Revision 0 and Revision 1 are in file.
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t SARSENT 8 LUNDY EMD-067927 ENGINEEIS Proj. ND: 09606-069 CHICAGO Rev.: 2 Page 3 TABLE OF CONTENTS Section Description
.P_RELe Title P age...............................................
1 S ig nature P age...........................................
2 Table of Contents.........................................
3 1.
I ntroduction.............................................
4 2.
Purpose and Scope of Review.........~.....................
4 3.
Design of LaSalle Piping and Supports.........................
5 4.
Walkdown Criteria & Description..............................
6 5.
Turbine Building..........................................
7 6.
Main Turbine Condenser.........'..................... [....
8 7.
Main Steam and Drain Line/ Bypass Piping.......................
9 8.
Description of Outliers and Resolution..........................
11 9.
C oncl usion.............................................
13
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10.
' References..........
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Table 1: List of isolation Valves..............
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Table 1 A: List of Drain Path Valves............................
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Table 2: Piping System Design Parameters....,................
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Table 3: Outlier identification and Resolution...'..................
18 Figure 1: Isometric View of Leakage Control Path.................
20 Figure 2: Key Plan for LaSalle County Station Unhs 1 and 2.....................................
21 Figure 3: Condenser Outline Drawing..........................
22 Figure 4: Valve Operator Cantilever Length Umits.................
23 Figure 5: Seismic Verification Boundary.........................
24 m
2 ARDENT S LUNDY EMD-067927 "g8 Proj. No: 09606-069 Rev.: 2 Page 4 1
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1.
INTRODUCTION i
As a resolution to the Main Steam isolation Valve (MSIV) leakage and Leakage Control j
System (LCS) performance issues, the BWR Owner's Group (BWROG) proposed to use the main steam piping and condenser as a method for MSIV leakage treatment.
This method provides effective and reliable fission product attenuation for reducing the j
radiological consequences of MSIV leakage.
j The BWROG has also evaluated the capability of main steam piping and condensers to process MSIV leakage following a design basis accident coincident with a seismic event. Based on this comprehensive evaluation, the BWROG has concluded there is reasonable assurance that the main steam piping and condenser will remain functional following a design basis accident coincident with' a seismic event, as great as'the design basis earthquake, to mitigate the radiological consequences of MSlV leakage.
l This conclusion is in part based on performing a plant-specific verification of seismic 2
j adequacy of the main steam piping and condenser to provide reasonable assurance of the structuralintegrity of these components. This document summarizes the results of the walkdown to verify seismic adequacy of these components which will replace the 3
{j existing LCS of LaSalle County Nuclear Station-Unit 2 (Lasalle Unit 2).
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2.
PURPOSE AND SCOPE OF REVIEW i
The purpose of this report is to document the field walkdown performed to verify j
seismic adequacy of the main steam piping and condenser for use as the altemate l
MSIV leakage treatment system for LaSalle Unit 2.
i A seismic verification walkdown was performed based on the guidelines in NEDC-31858P (Reference 10.3) to provide reasonable assurance that the section of main steam piping between the outermost MSIV and High Pressure (HP) turbine stop valves including the condenser and associated unisolated branch lines, will maintain l
structural integrity with respect to the seismic event.
t The condenser forms the ultimate boundary of the leakage pathway.
Boundaries l
were established upstream of the condenser by utilizing existing valves to limit the extent of the seismic verification walkdown.
The criteria used to define the scope of j
review follows.
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1)
Normally closed valves that will not open and can be assured to remain closed i
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Normally open valves that can be assured to close and remain closed i
3)
Valves that may require operator action to assure closure and are powered from j
a reliable power source (i.e., powered by non-essential power supplied by essential busses) 4 4)
Drain lines connected to the condenser that will be utilized to carry the MSIV leakage to the condenser
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SARDENT G LUNDY EMD-067927 EmmEEIS Proj. No: 09606-069 CHICA10 I
Page 5 There does not exist any of the isolation valves that meet the criteria outlined above
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for Main Steam sample line up to the sample panel. This line will be walked only to the sample panel and the lack of automatic or powered isolation will be identified as an 1
outlier. MS LCS line was not included in the walkdown since this line will be cut and capped at the steam header as part of the system modification needed to initiate the j
attemative leakage control path.
i A list of isolation valves used to define seismic verification boundary is provided in j
Table 1, along with type of power, category number as previously defined and pertinent information on the isolation capability following a Safe Shutdown Earthquake j
(SSE).
Table 1A lists valves under category 4 defined above.
1 Drain lines, 2MS20AA/AB/AC/AD-2" and 2MS20BA/BB/BC/BD 1 1/2" are also within the boundary of the leakage pathway.
However, these lines were excluded from the i
walkdown since these lines were previously analyzed as ASME Section Ill, class 1.
1 These lines are bounded by valves 2B21-F067A/B/C/D and 2B21-F025A/B/C/D.
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An isometric sketch of LaSalle Unit 2 main ste'am system beyond the outboard MSIVs up to the condenser and some of the isolation valves is shown in Figure 1. It is to be i
noted that Figure 1.is only an overall representation of the attemate leakage control j
path and does not necessarily include all the MS branch lines. For a complete scope of seismic verification walkdown, a marked up P&lD in Figure 5 should be referred to.
j The structural integrity of the turt>ine building was also reviewed to provide reasonable assurance that the capability of main steam and condenser fluid pathways are not
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degraded due to building structural damage.
4 3.
DESIGN OF LASALLE PIPING AND SUPPORTS i
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Main steam and drain /by-pass piping including the warm-up and process sampling i
lines at the LaSalle plant were seismically analyzed in accordance with ASME Boiler j
and Pressure Vessel (B&PV) Code Section lil, class 2 and 3 rules, and their supports were also designed for the seismic loads using the ANSI B31.1 code, although they are designated as non-safety-related.
The only exception are drain lines from l'
mainsteam headers to the first anchors (subsystem 2MS-71) which is all class D.
As built configuration of these drain lines were checked for the items listed in Section i
7.0 for class D only, and no outliers were found.
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One analysis model included the main steam piping to the turbine and the by-pass line. The main steam drain and warm-up lines were decoupled from the above i
mentened main steam line and were analyzed up to the condenser and structural anchors, respectively. These piping subsystems consist of the majority of the piping and supports within the scope of review, and the design methods for these analyzed i
lines are consistent with seismic Category I qualification methods for LaSalle's safety-related piping and supports.
it is also to be noted that other non-safety-related piping at LaSalle had previously been analyzed and found to be rugged enough to survive the design basis earthquake t
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CARCENT a LUNDY EMD-067927 Egi proj. Ns: 09606-069 s
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through a Seismic Category 11 over Seismic Category I assessment previously performed (Reference 10.5). The same can be concluded for the non-safety-related piping in a Seismic Category ll buildings, since the piping and support designs are similar.
Specific design parameters used for the design of the piping and supports within the scope of review are described in Table 2.
4.
WALKDOWN A field walkdown was performed based on the guidelines in NEDC-31858P (Reference 10.3) to provide supplemental verification that a ' reasonable assurance of the integrity of the subject systems and components exists, and was focused only on the realistic hazards to verify design attributes important to seismic performance and to identify non-typical commodities with uncertain seismic capacity. The walkdown also took into account the good seismic performance of conventional power plant condensers (that are similar in construction to nuclear power plaint condensers) and the rugged design of the main steam piping and its branch lines.
Piping single line drawings falling under the scope of review were prepab for the walkdown by grouping and marking affected piping. The walkdown team consisted of one degreed and licensed structural engineer who has experience in structural seismic analysis and has completed EPRI sponsored courses: "A-46 Walkdown, Screening and Seismic Evaluation" and " Add-on Seismic IPE Training". A second team member is a degreed piping design engineer who is a licensed professional engineer experienced in piping seismic analysis.
The engineers in the walkdown team collectively possess the following knowledge and experience:
Knowledge of the performance of equipment, systems, and structures during strong motion earthquakes in industrial process and power plants.
Nuclear plant walkdown experience which includes: potential seismic interaction; ll/l issues; A-46 walkdown; and IPE screening walk-through.
Knowledge of nuclear design Codes and standards including the visual inspection requirements of ASME OM-3.
Experience in seismic design, seismic analysis, and test qualification practices for nuclear power plants.
The main steam line was walked through from the outermost Main Steam isolation Valves to the Main Steam Stop Valves, the Main Steam By-Pass Valves, and 2B21-F418A(B). The drain lines tapping off the MS piping within this boundary were walked through to the condenser and to the valves 2821-F071(73). The warm-up lines were walked to the valve 2B21-F?20.
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SAR2ENT G LUNDY EMD-067927
'g8 Proj.N3: 09606-069 Rev.: 2 Page 7 i
l Piping system anomalies (termed " outliers") that may lead to the loss of the system pressure boundary during a seismic event were identified, and they are discussed in Section 8.
5.
TURBINE BUILDING j
The turbine building seismic performance is of interest to the issue of MSIV leakage only to the extent that it will not degrade the capabilities of the selected main steam and condenser pathways. A BWROG survey of this type of indusuial structure has, in general, confirmed that excellent seismic capability exists. There are no known cases j
of structural collapse of either turbine buildings at power stations or structures of similar construction. At the LaSalle Station, the turbine building shares the north-south wall with the auxiliary building and the diesel generator room as shown in Figure 2.
i The turbine building was included in the seismic models (Reference 10,1). The shear walls and slabs were designed for the seismic loads obtained from the seismic l
analysis. The structural project design criteria (Reference 10.2) requires that Class ll l
structures be designed to ensure that a failure of any part of the Class ll structures will i
i not affect the structural integrity of Class I structures or systems. Furthermore, the criteria requires that Class ll structures be designed to resist the forces determined l
from the combined ' Class I and Class ll model.
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The exterior walls of the turbine building are reinforced concrete,3 feet thick below grade and 1 foot thick above grade similar to the Class I structures. The floor slabs i
with concrete framing are 18 inches thick and the floors supported on steel framing are
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i 6 inches thick. These thicknesses are also similar to the Class I structures. The turbine building above grade were also designed for wind loads and seismic loads in accordance with the Uniform Building Code of 1970. For tomado loading condition, the siding of the turbine building is designed to blow off at a predetermined wind pressure (about 71 psf) so that the structural frame is protected from excessive tomado j
pressures. Structural integrity of the bare frame is then checked for vented tomado l
pressures. The tomado pressures considered were 300 psf for windward and 166 psf for leeward. The final design of the turbine building was controlled by the forces l
resulting from the tomado pressures. The initial design was modified to accommodate l
those forces.
Horizontal and vertical truss systems were provided to transmit these loads down to the reinforced concrete walls. The design of the shear walls was checked to assure i
the capability of transmitting the forces to the basemat and the foundation material.
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j Based on the above description of the structure and structural design criteria, it is concluded that turbine building will not collapse under SSE at LaSalle Station.
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CAR 0ENT S LUNDY EMD-067927
"[lg8 Proj. No: 09606-069 Rev.: 2 Page 8 6.
MAIN TURBINE CONDENSER The LaSalle Unit 2 condenser is a single shell with three condenser extension necks, single pass construction with total effective tube surface area of 950,000 square feet.
The shell is 7/8" thick A285 Grade C flange quality steel. Figure 3 contains the outline drawing for the condenser. The design basis for the LaSalle Unit 2 condenser follows:
6.1 Design Code The condenser was designed based on the Heat Exchanges institute Standards (HEI).
i 6.2 Design Pressure a.
Shell was designed for 15 psig pressure and tested for 20 psig.
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Water boxes, tube sheets, etc. were' designed for 25 psig and tested for 30 j
Psig.
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6.3 Manufacturer
Westinghouse Electric Corporation j
6.4 Size, Weight, Dimensions Size:
Effective surface area of 950,000 square feet.
Weight: Empty = 2,880,000 lbs.
Operating = 6,026,000 lbs.
Test = 14,886,000 lbs.
Dimensions (shell):
Length = about 90' Width = about 35' Height = about 71' including condenser extension necks Shel! Material and Thickness: ASTM A-285C and 7/8" thick.
6.5 Anchorage Description The condenser is seated on 8 reinforced concrete piers which are supported by the Turbine Building foundation. Each seat consists of a base plate with shear bars. The shear bars are grouted to the top of the pier. The condenser is connected to the piers by 61-5/8"4 A36 anchor bolts at each pier for a total of l
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SARGENT & LUNDY EMD-067927 E W E:8 Proj. ND: 09606-069 4
Rev.: 2 Page 9
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48 anchors. The holes in the base plates and the bottom of the condenser ars j
arranged in a fashion to allow thermal growth.
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j 6.6 Condenser Evaluation i
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Method of Evaluation i
Appendix D of Reference 10.3 is used to compare the condenser to the 1
" Experience Data Base". Because the condenser size and weight are larger j
than the condensers in the " Experience Data Base", additional anchorage evaluations were performed to determine their adequacy for the design basis earthquake and beyond.
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The method of evaluation is summarized as follows.
i 1.
The condenser capacity and demand parameters were compared to the j
" Experience Data Base" contained in Reference 10.3.
l 2.
A simple anchorage review was' performed to estimate the anchorage capacity for seismic loads.
3.
Seismic capacity is compared to seismic demand to estimate the anchorage High Confidence of Low Probability of Failure (HCLPF) l capacity using seismic margin methods provided in Reference 10.4.
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Evaluation Results L
1.
The condenser seismic demand falls well within the bounds of the
" Experience Data Base".
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The condenser anchorage provides significantly greater " Resistance to Seismic Demand" than those in the " Experience Data Base".
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The condenser anchorage has a HCLPF greater than 0.30g which is l
well above the design basis SSE of 0.20g.
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7.
MAIN STEAM AND DRAIN LINE/ BYPASS PIPING l
All of the piping systems within the scope of the review are classified as non safety-l l
related. However, majority of the piping were seismically analyzed (class D+) in i
j accordance with ASME Section 111 class 2 and 3 rules using response spectrum analysis techniques. Seismically analyzed piping include main steam line (downstream
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piping from the most outboard main steam isolation valves to the main steam sfop valves, the main steam bypass valves and 2B21-F418A(B)), drain lines to the condenser except subsystem 2MS-71 described in Section 3, and the warm-up lines i
to valve 2B21-F020 as shown in Figure 1.
Small born instrument lines such as process sampling lines have also been designed seismically using a simplified i
procedure to support the piping / tubing. The design methods for all these lines are l
l consistent with Seismic Category I qualification methods and the design margins are expected to be adequate to assure good seismic performance.
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CARCENTGLUNDY EMD-067927
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ENGINEE:s Proj. No: 09606-069 Rev.: 2 Page 10 Pressure sensing instrument lines from the main steam line to the pressure sensors in the turbine building are classified as non-seismic (class D) and are designed to the requirements of the B31.1 code. These lines appeared to be dead load supported in general conformance to the recommendations of the B31.1 code using rigid rods and i
U-bolts. Review of the piping and support design codes and piping design parameters demonstrated that piping and supports fall within the bounds of design characteristics found in " Earthquake Experience Data base".
To further verify the reasonable seismic adequacy of the piping and supports within the 4
scope of the review, a walkdown has been performed to visually identify conditions of the piping and supporting configurations which may result in seismically induced pressure boundary failure and inventory release from the main steam and drain piping.
The approach utilized in the walkdown for verifying seismic adequacy of the subject piping is as outlined in Reference 10.3 and is consistent with Reference 10.4. The walkdown was focused on identifying potential failure of non-seismically designed piping, poorly installed and/or deteriorated piping supports, falling of non-seismically designed plant features that may impact the above mentioned piping systems (ll/l),
seismic interaction, and differential seismic buifding movement on piping systems.
During the walkdown, the following items were visually inspected and no.significant outliers were identified except those listed in Table 3.
7.1 Support and Anchorage:
The piping support and anchorage installation were visually inspected for (1) missing or disconnected parts such as bolts, nuts, pins, welds and anchors; (2) broken, grossly deformed, cracked or disconnected support components; (3) excessive corrosion; (4) spalling of concrete; (5) stanchion supports not being property seated; and (6) potential for the pipe to fall off due to insufficient distance to the edge of the support. In addition to the above, non-seismically 4
analyzed piping (Class D) were also checked for (1) heavy in-line components or long risers supported only by a spring hanger; (2) piping sections with a series l
of spring hangers without nearby rigid supports; (3) a long run of pipe (i.e.,4 to 5 vertical support spans) without any lateral support; and (4) Valve operator exceeding a cantilever length limit provided in Figure 4.
7.2 Seismic interaction:
Motor / air operated valvss (MOV/AOV) were checked for potential seismic impact by other plant features such as structure, cable trays, conduits, HVAC ducts, hangers, etc. due to inadequate seismic clearance. Small branch piping was checked for potential seismic impact or movement restriction due to a large and flexible header.
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CARGENT & LUNDY EMD-067927 W INEEOS proj. Ns: 09606-06g l
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7.3 ll Over i Review:
1 Piping and supports were checked for any potential damage due to impact j
caused by failure and falling of overhead or adjacent equipment, systems, or structures.
7.4 Differential Seismic Motions:
i The following conditions, which may impose differential seismic motions on the d
piping, were also checked to ensure that adequate piping flexibility exists to
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l preclude failure.
l (1) Terminal end equipment with inadeq'uste anchorage or supported on a i
j vibration isolator.
1 (2) Small bore piping or tubing connected to an equipment, valve or instrumentation, with insufficent flexibility to accommodate seismic motion j
between the equipment and adjacent support or structure (Class D only).
1 (3)
Pipe supports or anchors attached to adjacent and uncoupled buildings with inadequate piping flexibility (Class D only).
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(4) Rigidly supported branch piping close to a flexible header (Class D only).
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In summary, all of the piping within the scope of the review were seismically analyzed / designed in accordance with ASME section lil, class 2 and 3 rules, except I
small bore pressure sensing instrument lines which are similar to or better than the piping found in " Earthquake Experience Data Base".
i Minor issues concoming potential seismic interaction between motor operated valves j
and adjacent piping / valve, differential seismic anchor movements and support i
anchorage of process sampling line were identified during the walkdown, that could be j
potential sources of damage. These were evaluated and were found to be acceptable j
as shown in Table 3.
l For the pressure sensing instrument lines, each 1" NPS or smaller line was supported by vertical rod hangers and U-bolts; the piping penetrates a block wall where the valves and pressure sensors are mounted. It was demonstrated by tug test that the 4
i piping position retention will be reasonably maintained by the system dead weight supports under normal and earthquake loading, if the seismic adequacy of the block wall from which the piping is supported is verifed.
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J 8.
DESCRIPTION OF OUTLIERS AND RESOLUTION The outliers identified during the walkdown are described below along with the method of resolution or recommended action:
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CARGENT S LUNDY EMD-067927
'g'gs Proj. Na: 09606-069 Rev.: 2 Page 12 Motor operated valve (2B21-F070) located on main steam drain line (3"$) to the
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condenser has a potential seismic impact with the adjacent 4"4 rod supported piping.
The clearance between motor operator and adjacent pipe is about 1".
The point of potential interaction is about 11" away f:om the pipe penetration in the concrete wall which is filled with hard form material.
Resolution:
3"$ main steam drain line was previously analyzed seismically and the analysis result revealed that the combined thermal and seismic movement at the valve C.G. is less than 0.3".
The 4"$
rod supported pipe was also found to be rigid enough by tug test performed by the walkdown team.
Therefore, the outlier is determined to be acceptable as is.
Vertical wide flange support for 2MS25-2951C is located close (about 1") to the drain line,2MS25AC-2, and may potentially restrain the seismic movement of drain line which branches off from the 26"$ main steam header at about 2 feet from the potential interaction area.
Resolution:, The seismic movement of the drain line at the potential interaction area was reviewed and found to be less than 1".
Furthermore, the drain line moves away from the vertical WF during plant I
operation and the outlier is determined to be acceptable as is.
Potential seismic interaction exists between the motor operator of valve 2B21-
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F020 on line 2MS198-3 (warm-up by-pass line) and adjacent valve 2FWO70B (about 1" clearance).
j Resolution:
Review of the thermal and seismic movements of the valves from the existing piping analysis shows that the interaction will not i
j occur and the outlier is acceptable as is.
Process sampling line (2MSA1AB-3/4") branching off from the 26"4 MS line runs i
close to the structural wall (about 2" from the pipe insulation), which may restrict i
branch line seismic movement.
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Resolution:
The combined thermal and seismic movement of the header at the branch connection was reviewed from the existing piping analysis and found to be less than 1". Therefore, the outlier is j
acceptable as is.
i Process sampling line has no automatic or powered isolation valve to isolate leak path, i
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Resolbtion:
Not acceptable as is. One of the following actions needs to be taken.
- 1. Radiological effect of leakage path should be evaluated.
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8 ARDENT & LUNDY EMD-067927 EQEg8 proj. No: 09606-069
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Rev.: 2 Page 13 I
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- 2. Automatic / reliable powered isolation should be installed.
- 3. Manual isolation valve should be controlled closed administratively.
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Pressure sensing lines (2MS93AA/AB/AC/AD-1 and 2MS68AB/BB-1) penetrate a block wall, and valves and pressure sensors are mounted on the other side of i
the block wall. There are also block walls close to the pressure sensors. These walls may impact the sensors if they fail.
l Resolution:
Not acceptable as is. Seismic adequacy of the block walls should be verified for these lines. 'The walls should be reinforced, or isolation method be provided.
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1 9.
CONCLUSION l
LaSalle Unit 2 plant-specific verification of seismic adequacy of main steam piping, j
associated branch lines including drain, warm-up, process sampling lines _and condenser has been performed based on the guidelines in NEDC-31858P (Reference i
q 10.3), to provide reasonable assurance of the seismic integrity of these systems and components. The design method for the majority of the piping and supports under the scope of review is consistent with seismic Category l qualification method and design margins are expected to be adequate to ' assure good seismic performance.
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All outliers identified during the field walkdown were resolved by review of existing analysis or design drawing.
The two outliers requiring additional actions are listed below.:
1.
One of the following actions needs to be taken for the process sampling line.
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- 1. Radiological effect of leakage path should be evaluated.
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- 2. Automatic / reliable powered isolation should be installed.
- 3. Manual isolation valve should be controMd dased administratively.
4 2.
Seismic adequacy of the block wall where pressure sensing instrument lines i
are supported and the block walls located close to the pressure sensors I
need to be verified. If this shows an unacceptable condition, the walls j
should be reinforced or isolation method be provided for these lines.
i in addition, in all the areas walked down, the team observed that the cable trays, conduits, and HVAC ducts are well supported to consider them as seismically rugged.
i The turbine building has been shown through design document review to be capable of resisting the safe shutdown earthquake.
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CAR 2ENT & LUNDY EMD-067g27 E
igng Proj. No: 09606-06g Rev.: 2 Page 14 Review of the condenser location, shell thickness and test qualification, and the seismic capability of the anchorage indicates that the condenser design is adequate to resist the safe shutdown earthquake.
10.
REFERENCES l
10.1
" Seismic Response Spectra Design Criteria", LaSalle County Nuclear Power Station Units 1 and 2, DC-SE-02-LS, Rev. O, Sargent & Lundy Engineers i
10.2
" Structural Department Project Design Criteria", LaSalle County Nuclear Power j
Station Units 1 and 2, DC-SE-01-LS, Rev. 6, Sargent & Lundy Engineers 10.3 "BWROG Report For increasing MSIV Leakage Rate Limit and Elimination of Leakage Control Systems", NEDC-31858P, Rev. 2 10.4 "A Methodology for Assessment of Nuclear Plant Seismic Margin", EPRI NP-6041, Rev.1 W
10.5
" Assessment of Non-Category l Piping for Protection of Safety-Related Components During Seismic and Pool Related Events", EMD-027211, Rev. O, Sargent & Lundy Engineers 1
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SARGENT S LUNDY EMD-067927 Emig,E 8 Proj. ND: 09606-069 Rev.: 2 i
Page 15 TABLE 1: LIST OF ISOLATION VALVE 8 Valve No.
Operator Type Category Remarks 2821-F418A Motor Operator 3
M-116 Sh3; Une 2MS38AA-18; Powered from 1E MCC 236X-2 (D4) 2821-F4188 Motor Operator 3
M-116 Sh3; une 2MS38AB-18; Powered from 1E MCC 236X-2 (DS) l 2821-MSV1 HydrauEc Operator 3
M-116 Sh3; Une 2MS01CB-28; Non-1E Source, Fail Closed on Loss of Power 2B21-MSV2 HydrauEc Operator 3
'M-116 Sh3; une 2MS01CA-28; Non-1E Source, Fall Closed on Loss of Power 2821-MSV3 Hydrauic Operator 3
M-116 Sh3; Une 2MS01CD-28; Non-1E Source, Fail Closed on Loss of Power 2B21-MSV4 Hydraubc Operator 3
M-116 Sh3; Une 2MS01CC-28; Non-1E Source, Fail Closed on Loss of Power 2821-F339A Manual 1'
M-116 Sh3; Branch Une fIom 2MS01BA-
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26 2B21-F339B Manual 1
M-116 Sh3; Branch Une from 2MS01BB-26 2821-F3390 Manual 1
M-116 Sh3; Branch Une from 2MS01BD-26 2821-MSBPV1 Hydraulc Operator 3
M-116 Sh3; Une 2MS33AA-12; Non-1E Source, Fall Closed on Loss of Power 2821 MSBPV2 Hydraulc Operator 3
M-116 Sh3; Une 2MS33AB-12; Non-1E Source, Fail Closed on Loss of Power 2821-MSBPV3 HydrauEc Operator 3
M-116 Sh3; une 2MS33AC-12; Non-1E Source, Fail Closed on Loss of Power 2821-MSBPV4 HydrauEc Operator 3
M-116 Sh3; une 2MS33AD-12; Non-1E Source, Fall Closed on Loss of Power 2B21-MSBPVS HydrauEc Operator 3
M-116 Sh3; Une 2MS33AE-12; Non-1E Source, Fall Closed on Loss of Power 2821-F020 Motor Operator 1
M 116 Sh7; Une 2MS198-3; Powered from 1E MCC 236Y-1 (A2) 2821-F071 Motor Operator 3
M-116 Sh7; Une 2MS27A-1; Powered from 1E MCC 236X-3 (B3) 2B21-F073 Motor Operator 3
M-116 Sh7; une 2MS308-1; Powered from 1E MCC 236X-3 (C3)
SARGENT G LUNDY EMD-067927
'7ljjj' Proj. No: 09606-069 c
Rev.: 2 Page 16 TABLE 1: LIST OF ISOLATION VALVES Valve No.
Operator Type Category Remarks 2B21-F302A Manual 1
M
, -116 Sh7; Branch Une from 2MS25AA-2 2B21-F302B Manual 1
M-116 Sh7; Branch Une from 2MS25AB-2 2B21-F302C Manual 1
M-116 Sh7; Branch Une from 2MS25AC-2 2821-F302D Manual 1
M-116 Sh7; Branch Une from 2MS25AD-2 2B21-F306A Manual 1
M-116 Sh7; Branch Une from 2MS28AA-2 2821-F306B Manual 1
M-116 Sh7; Branch Une from 2MS28AB-2 2B21-F306C Manual 1
M-116 Sh7; Branch Une from 2MS28AC-2 2B21-F306D Manual 1
M-116 Sh7; Branch Une from 2MS28AD-2 2B21-F028A Air Operated 2
M-116 Sh2; Une 2MS01BA-26; RPS BUS "B", Fall Closed on Loss of Air 2821-F028B Air Operated 2'
M-116 Sh2; Une 2MS01BEi-26; RPS BUS "B", Fall Closed on Loss of Air 2821-F028C Air Operated 2
M-116 Sh2; Une 2MS01BC-26; RPS BUS "B", Fall Closed on Loss of Air 2B21-F028D Air Operated 2
M-116 Sh2; Line 2MS01BD-26; RPS BUS "B", Fail Closed on Loss of Air TABLE 1A: LIST OF DRAIN PATH VALVES Valve No.
Operator Type Category Remarks 2821-F070 Motor Operator 4
M-116 Sh7; Une 2MS25B-3, Powered from 236X-2(F2) 2B21-F072 Motor Operator 4
M-116 Sh7; Une 2MS28B-3, Powered from 236X-2(F3)
.. -.. _. - ~ -. -.
1 EMD-067927 Proj. No: 09606-069 Rev.: 2 Page 17 TABLE 2: PIPING SYSTEM DESIGN PARAMETERS SYSTEM DESCRIPTION PIPING DESIGN DESIGN PIPE SCH.OR DIT SUPPORT LOADINGS DESIGN TEMP.
PRESSURE SIZE THICKNESS TYPES CONSIDERED CODE
("F)
(psig) -
MSIVs to the MSVs, the ASME 111 575 1250 36" 1.335" 27 Spnngs Weight MS Bypass Valves and ANSI B31.1 26"
.967" min.
27 Struts Thermal 2821-F418A(B) 28" 1.041" min.
27 Concrete Seismic 18" Sch.80 19 anchors Steam Hammer MS Drain Lines to the ASME lil 575 1250 2"
Sch.80 11 Spnngs Weight Condenser and 2B21-ANSI B31.1 3"
12 Struts Thermal F071 (073). MS Drain 12" 19 Box types Seismic i
Branch Lines 1"
7 U-bolts Snubber Structural anchor MS Warm-up Bypass ASME lil 575 1250 3"
Sch.80 12 Springs Weight Unos to 2B21-F020 ANSI B31.1 2"
.11 Struts Thermal Snubbers Seismic Rod Hanger MS Process Samp5ng ASME Ill 575 1250 3/4" Sch.160 5
U-bolts Weight Line ANSI B31.1 1/2"
.109" min.
8 Tube clemps Thermal Seismic Pressure Sensing Line ANSI B31.1 575 1250 1"
Sch.80&160 7&5 Rod hanger We'ght 3/4" Sch.80 7
U-bolts Thermal 1/2" Sch.160 4
i
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EMD-067927 Proj. No: 09606-069 Rev.: 2 Page 18 TABLE 3: OUTLIER IDENTIFICATION AND RESOLUTION SYSTEM DESCRIPTION OUTUER DESCRIPTION RESOLUTION STATUS REQUIRED ACTION Main Steam Drain to MOV 2821-F070 located on the 3"$ drain Acceptable as is by analysis and None l
Condenser in The TB Ene has a potengal seismic interaction with field tug test performed for 4"$
the edpecent 4"$ piping (about 1" piping clearance).
I Vertical WF support for 2MS25-2951C is Acceptable as is by analysis. No None F
located close (about 1") to the drain Ene, iederaction wl5 occur based on the l
2MS25AC-2 and may potentially restrict analysis results.
branch pipe movement due to a large header The same condition also exists for Ine 2MS25AD-2. The drain Enes branch off from the 26"$ main steam Ene at about 2 R. from the supports.
Main Steam Warm-Up Potential seismic interaction exists between Acceptable as is by analysis No None Bypass the operator of MOV 2821-F020 on Ene interaction wl5 occur based on the 2MS19B-3 and adjacent valve 2FWO70B enelysis resuRs.
(about 1" clearance) r f
t i
l L
s 9
+ ~
r,w m.
w,-w o-,.v v
w-r,-
,-vm,-
w v
w w
,-w---v m
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...__.__..___.._______.___.____.____.-._m m.m._...
t TABLE 3: OUTLIER IDENTIFICATION AND RESOLUTION (CONT.) EMD-067927 Proi. No: 09606-069 Rev.: 2 Page 19 SYSTEM DESCRIPTION OUTLIER DESCRIPTION RESOLUTION STATUS REQUIRED ACTION Main Steam Process Samping Ene (2MSA1AB-3/4") branching Acceptable as is by analysis. No None
[
Samping off from the 26"4 MS Ene runs close to the interaction with the waN wiu occur structural waN (about 2* from the piping based on the analysis results.
insulation), wtuch may impose a potential restriction on pipe seismic movement.
Process samp5pg une has no automebc or Not acceptable as is.
One of the following actions l
t powered isolation to isolate leak path.
needs to be taken.
i
- 1. Radiological effect of i
leakage path should be i
evaluated.
L
- 2. Automabc/retable l
powered isolation should be installed.
[
- 3. Manualisolabon velve
(
should be controlled i
closed administratively.
l Main Steam Pressure Pressure sensing Enes Not acceptable as is.
Seismic adequacy of block f
Sensing Une (2MS93AA/AB/AC/AD-1 and 2MS68AB/BB-walls has to be vertfled.
{
- 1) penetrate the block war where valves Reinforcement or isolation and pressure sensors are mounted.
method should be provided if i
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EMD-067927 Proj. No. 09606-069 Rev.2 Page 23 Heavy Valve Operator Cantilever Limits 120 P.
Area OMIDEof l
p 109 w
e Earthquake Experience 7,,,
C Data Base e
80 e
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See Note (1) t o
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(1) Approximate Maximum Operator Weights Given for Various Rangen of Pipe Diameter Figure 4.
Valve Operator Cantilever Length Limits
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