ML20203E430

Forwards Justification for Two Additional Leak Chase Channel Configurations Used in Pressure Suppression Pool That Were Not Bounded by Justification Provided in

ML20203E430
Person / Time
Site:	LaSalle
Issue date:	02/20/1998
From:	Dacimo F COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20203E435	List: ML20203E430 ML20203E457 ML20203E492 ML20203E501 ML20203E509 ML20203E520 ML20203E526 ML20203E536 ML20203E552 ML20203E565 ML20203E571 ML20203E580 ML20203E587 ML20203E614 ML20203E620 ML20203E622 ML20203E639 ML20203E651 ML20203E696 ML20203E782 ML20203E819 ML20203E834 ML20203E863 ML20203E902
References
NUDOCS 9802270050
Download: ML20203E430 (91)

Text

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%t.nu,lir= llbl4eiH T ltlHi% 4%"6'ol February 20, i998 Un'ted States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Supplemental Information regarding Containment Leak Chase Channels LaSalle County Station, Units 1 and 2 Facility Operating Licenso NPF 11 and NPF-18 NRC Dockot Nos. 50 373 and 50 374

Reference:

See Attachmont F in Reference (9), Commonwealth Edison Company (Comed), LaSallo County Nuclear Power Station, Units 1 and 2 (LaSalle), provided the United States Nuclear Regulatory Commission (NRC) with justification to demonstrate that the performance of containment integrated loak rato tests (CILRTs) with the leak chase channel plugs installed satisfies the requiroments of Title 10, Code of Federal Regulations, Part 50 (10 CFR 50),

Appendix J. This justification shows that (a) the leak chase channel welds are qualitatively equivalent to or better than those for the primary containment liner wolds and (b) the leak chase channels will maintain their integrity when subjected to the loading conditions of a postulated design basis accident (DBA) as well as during normal operation.

Subsequently, LaSalle has identified two additional leak chase channel configurations used in the pressure suppression pool (PSP) that were not bounded by the justification previously provided. Justification for those leak chaso channel configurations is provided in Attachments A through E of this letter. There are, however, oighteen (18) specific leak chase channels in this population for each unit that cannot be demonstrated to maintain their integrity during a postulated DBA due to their location with respect to the i

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dynamic effects of the PSP water inventory during the postulated event.

3 Disposition of these leak chase channels will be provided to the NRC in a j supplement to Licensee Event Report (LER) 50 373/97-030 00

[ Reference (8)].

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If there are any questions or comments concoming this lotter, please refer them to Perry Barnes, Regulatory Assuranco Managor, at (815) 357 6761, extension 2383.

Respectf Fred Dacimo Sito Vice President LaSailo County Station Attachments cc:

A. B. Beach, NRC Rogion lli Administrator M. P. Huber, NRC Senior Rosident inspector - LaSalle D. M. Skay, Project Manager NRR LaSalle F. Nizlolok, Offico of Nuclear Facility Safety IDNS 4

Attachment A Justification

The containment liners at LaSalle County Nuclear Power Station, Units 1 and 2 (LaSallo), were installed in accordance with Chicago Bridge and Iron (CBI) Contracts 73-6336 and 73-6337, for Units 1 and 2 respectively. The leak test channels installed under these original CBI contracts were evaluated and determined to be " equal to or better than" the liner welds. Justification for the performance of containment integrated leak rate tests (CILRTs) with plugs installed on those 'eak test channels was provided to the United States Nuclear Regulatory Commissico (NRC) on November 26,1997

[ Reference (9)].

Subsequently, it was noted that additional leak test channels were installed in support of the containment downcomer bracing and safety relief valve (SRV) KWU quencher modifications that were installed prior to the initial startup of each unit. These modifications were installed in accordance with CBI Contracts 83670 for Units 1 and 2, 83671 for Unit 1,83672 for Unit 2 and 83674 for Units 1 and 2. These modifications required additional embedment plates to be installed through the pressure suppression pool (PSP) liner into the PSP concrete wall. Closure and testing of the PSP liner welds around these embedment plates was accomplished in the same manner as the original liner welds.

LaSalle has evaluated these additional leak test channels and determined that, except for the leak test channels around the 18 embedmont plates numbered 34 through 51 between elevations 704' and 710' in both Unit 1 and Unit 2 PSPs, performance of CILRTs with the leak test channel plugs installed is acceptable because the containment pressure boundary can be redefined as the combined linor butt weld along with the pre-tested channel fillet welds and the leak test connections. The leak test channels around the 18 embedment plates numbered 34 through 51 between elevations 704' and 710' in both Unit 1 and Unit 2 PSPs are not able to withstand the upward hydro-dynamic loads associated with the initial pool swell during a design basis loss-of-coolant accident (DBLOCA) without plastic deformation.

The justification for the performance of CILRTs with plugs installed on these additional leak test channels is as follows:

A1

a.

The channel welds are auslitativolv eaulvalent to or better than those for the primary containment liner welds.

1.

Fabrication / Installation The leak test channel system was installed as a permanent attachment to the liner by CBI in accordance with Sargent and Lundy (S&L)

Specification J 2990, Downcomer Bracing Work, LaSalle County Station (LSCS)- Units 1 & 2. The leak test channel assembly is a Category l structure as specified on S&L drawings S 794 and S-795. The design, i

fabrication and erection of the containment downcomer bracing and SRV l

KWU quencher modifications was made to the requirements of Subsection NE of American Society of Mechanical Engineers (ASME)

Section Ill,1971 Code, Winter 1972 Addenda for Class MC.

S&L Specification J 2990, Downcomer Bracing Work, LSCS - Units 1 & 2 did not require detailed records for the permanent attachment welds, therefore, there are no weld control records that document the actual weld procedure, weld material or welder used. However; a.

CBI Welding Procedure Application Table Downcomer Bracing &

Quencher Support & Liner Work, WPAT 83670, specifies the welding procedures to be followed (See Attachment C). The CBI Welding Procedure Application Table required the samr welding procedures to be used for the leak test channel fillet weh.s as the liner plate butt welds. The CBI Welding Procedure Application Table also specified the same weld rod material to be used for both the leak test channel fillet welds and the liner plate butt welds. No exceptions were identified for the leak test channels. Therefore, it is reasonable to conclude that the same weld procedure and weld materials used for the liner butt weld joints were used for the fabrication of the leak test channel system.

b.

All CBI welders who worked on the containment downcomer bracing and SRV KWU quencher modifications were qualified in accordance with ASME Section IX for overhead, horizontal and vertical position butt welds (See Attachment D). As indicated on the qualification records, qualification on butt welds also qualified the welder for fillet welds, such as those used to weld the channel to the liner. The leak test channels were installed by the same CBI welders that installed the containment downcomer bracing and SRV KWU quencher modification liner plate butt welds. The same A4 gi r

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weld procedures were used for installation of the leak test channels 1

as were used for the containment downcomer bracing and SRV KWU quencher modifications liner plate butt weld, it is therefore reasonable to conclude that essentially the same quality of weld obtained on the liner butt weld joints was also obtained for the fabrication of the leak test channel system.

Based on the above, it is reasonable to conclude that the material quality of the leak test channel welds would be essentially the same as the containment downcomer bracing and SRV KWU quencher modifications liner plate butt welds.

2.

Testina The containment downcomer bracing and SRV KWU quencher modifications liner seam welds were tested by partial radiography and 100% liquid penetrant. Furthermcre, the leak tightness of the leak test channels and the liner welds were established during construction by pressure testing to contrainment design pressure.

Venting the leak test channels during the CILRT will not provide information on the leak tightness of the liner weld, since the liner is backed by concrete and is an integral part of the containment wall which will act as a leak tight membrane. The most effective procedure for performing the test on the liner weld is to test when it is not backed by concrete.

Documentation Neither thc f:&L design specification, nor the CBI Master Checklist, required detailed records for the installation of the leak test channels.

Therefore, complete documentation as required by ASME subsections NE-2000 and NE-4000 is not available. However, design and other documentation exists which provides reasonable assurance of the quality and type of materials used in the fabrication of the containment downcomer bracing and SRV KWU quencher modifications and leak test channel system.

Based on the above discussion, LSCS concludes that the PSP leak test channels installed for the containment downcomer bracing and SRV KWU quencher modifications have sufficient strength and were installed with the same material and with the samo quality as the containment liner. Therefore, it is A3'

reasonable to conclude that the channels are qualified to be used as part of the containment liner.

b.

The channels will maintain their intearity when subjected to the loadina conditions of a postulated desion basis accident as well as durina norma [

gpgation.

1.

Desian Assessment of the Containment Downcomer bracina and SRV KWU auencher modifications Leak Test Channels The welded steel plate liner, attached to the entire inside surface of the I

containment, serves as a leak tight membrane but not as a structural load carrying element. The liner seam welds are always in compression due to the pre stress condition in the containment concrete wall even though the CILRT pressure will relieve this compression force to some extent.

Therefore, the liner seam welds are considered non structural.

The liner to embendment plate seams in the suppression pool area are enclosed by stainless steelleak test channels (3/8" bent plate ASTM A-240, Type 304) which are attachert to the liner and embedment plate by 3/16 inch continuous fillet welds. The bolt cover assemblies on the l

embedment plates are inclosed in leak test channels (6" diameter seamless schedule 40 pipe, SA 312, type TP 304). The channels (except for the 18 channels on each unit noted above), the bolt cover channels and the associated liner welds are designed to withstand accident pressure and temperature stresses. The loads and load combinations for 4

which the channels and its welds are qualified, the applicable codes and acceptance criteria are listed below:

2.

Loads and Loe 1 Combinations The applicd.ne loss-of-coolant accident (LOCA), jet impingement, and pool hydrodynamic loads as defined in Section 3 and Table 3.4-1 of the LSCS-Mark ll Design Assessment Report (DAR) Revision 7, January 1980 (See Reference 9, Attachment I), are:

a.

SRV Actuation Loads in addition to the boundary loads, the SRV discharge loads include air bubble drag loads due to:

1.

All Valva and 2.

Single Valve Second Actuation.

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b.

LOCA Accident Loads The LOCA loads considered for this assessment are:

1.

LOCA Water Jet Loads, 2.

LOCA Charging Air Bubble Loads, 3.

Pool Swell and Fall Back Loads, 4.

Condensation Oscillation Loads, 5.

Chugging Loads, 6.

Accident Temperature and 7.

Jet Impingement Loads.

In addition to the pool hydrodynamic loads listed above, the leak test channelis assessed for the offect of hydrostatic pressure.

These loads were combined using the appropriate load combinations from Table 4.3 2 of LSCS Mark 11 DAR, Revision 7, January 1980.

3.

Calculations (Attachment El Calculation L-001337, Revision 2, provides an expanded assessment of the containment downcomer bracing and SRV KWU quencher modifications leak test channels for the governing loading combinations.

This calculation is the referenced calculation for the design margins discussed in Paragraph 5 below.

4.

Applicable Code and Acceptance Cnteria The acceptance criteria used for this assessment is the same as outlined in Subsection 4.3.2 of LSCS Mark 11 DAR, Revision 7, January 1980.

Thus, stresses per 1969 AISC specification are used for load combinations 1 through 3 defined in Table 4.3 2 of LSCS-Mark 11 DAR.

For load combinations involving abnormal or extreme environmental loads (combinations 4 through 7a), the stresses are limited to 0.95fy. The allowable stress used for the weld for all load combinations is 21000 psi.

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Marain Factors

- Margin factors, defined as the ratio between the allowable stress and the actual stress, were computed for the containment downcomer bracing and SRV KWU quencher modifications channel configurations in the suppression pool for the governing load combinations of Table 4.3-2 of LSCS-Mark ll DAR. This assessment has been performed using a 10%'

increase in the minimum specified material yield strength, as allowed in AISC Manual of Steel Construction, Seventh Edition, for SA240 Type 304 In accordance with S&L Specification J-2990.

All margin factors are greater than 1.0 thus demonstrating that all leak test channels have been found to meet the acceptance criteria and are thus able to serve as part of the containment pressure boundary.

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Ela 68 Ic** Ao' T'C-o 8 8 -13, 1 7 0' t'3 Gs7' %

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g g; g 4 c-AB 157'31' 7 d-9 48-/o!

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AZ 201". Elev. 697-1.

Ag 15"-17' Elev.686-43 1,'.

n-78 7

H'n 140.101.111.70.160.

1.23 R-36 1

H's 175,78,76.146.

i j

277,155,126.

A.B.C.D.E.F.J.K.L.E.N.

g,p,c,n y v.2.E.L.X.N.

1 A; 329". Elev. 697-1.

Ag 7". Elev. 697-1.

1,2.3.

E-29 2

H. - 8 7_67_115_ 274_ PP _

1_2.3.

R-37 1

E' r 141,158,72.148,150, l

119.137,172..

227.

A.B.C.D.E.F.J.K.L.k.U.

A.B. C. D. E. F.J.K.L.k A% 180". Elev. 706-101 Ag 310 Elev. 697-1.

h 1,2,3,4 R-30 1

H's 143.63,121.139,23D, 1.2.3 R-38 2

H' r 35,36,90,30.11,52, !!

35,112,134,206.111, 39 79*

A.B.C.D.C.F.J.K.L.K.H.

g, y, c D. E. F.J.I". L. fc. N.

l AZ 179", Elev. 687-73 A3 550 Elev. 697-1.

D 1.2.3.

R-31 2

H'c 270.163.226.73.220 1.2 3 R-39 1

33 216.1 h2.16 5.154.

ji 180.215.229 147,276.

0 A. B. C. D. E. F.J.K.L.ie.U.

A. B. C.D. E. F.J.K. L. M. N.

A; 15"-17' Elev.706-io3 ag 77o. Elev. 697-1.

tl 1.2.3.

R-12 1

H'c 83,49,89,12, 1, '. 3 2 hJ 1

p.r 23g,133,105,127,1394 1

190, A. B.C. D. E. F.J.K.L.L. fi.

A. 3. C. D. E. F.J.K. L. E.U.

b A; 57 -20' Elev.706-103 A.; I 03". Ele v.

697-1.

J

{

1,2,3, R-33 1

1.c 77.42.96.50.

1.23 E 41 1

!.,116. pot pe,7_187 g{

269

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it As 77~-40' Elev.706-10; A4 1270 Llev. 697-1.

1.2.1.

R-34 1

H'n 10.11.84.86.

1.2.3 E 42 1

3.c 292.194.234.114.65. 1 176.

i d

A. B.C.D. E.F.J.K.L.L.H.

A. B. C. D. E. F.J.K. L.E.H.

t A; 90"-20' Elev. 708-11 A; 151 s. Elev. 697-1.

i L

i l 97 1,2,3, R-35 1

H' c 32,44,93,3.

1.2.3 R h3 1

n.c 262,195,272.186,123 o

3 200 a.

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A P.C. D. E. F.J.E. L L. H.

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