ML20207P209

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Forwards Info Demonstrating Acceptability of ASME Code Case N-411 Calculations for Safety/Relief Valve Discharge Lines Off Main Steam Lines & for Annulus Pressurization Load for Lower Portion of Head Spray Line.Evaluation Discussed
ML20207P209
Person / Time
Site: Limerick Constellation icon.png
Issue date: 01/13/1987
From: Kowalski S
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Butler W
Office of Nuclear Reactor Regulation
References
CON-#187-2266 OL, NUDOCS 8701150235
Download: ML20207P209 (33)
v • d • e


Text

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T PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 12153841-4502 S. J. KOWALSKI VIC E-P R ESID E N T January 13, 1987 Dr. Walter Butler, Director BWR Project Directorate 4 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Use of ASME Code Case N-411 for Limerick Unit 2

References:

(1) Letter, W. R. Butler (USNRC) to E. G. Bauer (PECo),

dated May 30, 1986 - Same Subject (2) Summary of Meeting between NRC Staff and PECo on October 8, 1986 - Same Subject Prepared by R. E. Martin (USNRC), dated October 16, 1986 (3) -Summary of Meeting between NRC Staff and PECo on November 7, 1986 - Same Subject Prepared by R. E. Martin (USNRC), dated November 21, 1986 (4) Meeting between NRC Staff and PECo on December 3, 1986 -

Same Subject (5) Conference Call between NRC Staff and PECo on December 11, 1986 - Same Subject (6) Letter S. J. Kowalski (PECo) to W. R. Butler (USNRC),

dated December 24, 1986 - Same Subject

Dear Dr. Butler:

This letter and its attachments demonstrate the acceptability of the ISM (ABS)/N-411 calculations for each of the 14 SRV discharge lines off the main steam (MS) lines and of the ISM (ABS)/N-411 calculations for the annulus pressurization (AP) load case only for the lower portion of the head spray line, the main steam drain line and the recirculation drain line.

I. Acceptability of ISM (ABS)/N-411 Analyses for the SRV Discharge Lines off the MS Lines.

As stated in the reference 6 letter, MS line D was analyzed by the time history (TH) methodology using FSAR OBE damping. This TH analysis confirmed the acceptability of previous ISM (ABS)/N-411 analyses performed on all MS lines. Similarly, we have now completed TH analyses of all four MS D SRV discharge lines. The results of these analyses now permit comparison of the results of the remaining MS SRV discharge

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lines that were analyzed using ISM (ABS)/N-411 with the results of the four SRV discharge lines that were analyzed by TH. As can be seen from attachment 2, the TH results demonstrate that the existing record calculations using. ISM (ABS)/N-411 are adequately conservative for all four MS D SRV discharge lines.

A comparison was made of stress results from the ISM (ABS)/N-411 analysis of the governing upset load case (OBE plus SRV lift), as shown in attachment 3. This comparison demonstrates that the SRV discharge lines on MS lines A, B, and C, although not identical to SRV discharge lines on MS line D, react to the governing load case with stress ranges

& restraint loads similar to those of the MS D SRV discharge lines.

Since MS line D and its SRV discharge lines have been demonstrated acceptable using various analytical techniques (i.e. TH and ISM (ABS)/N-411) and since that line and its associated SRV discharge lines has significant similarities to MS lines A, B, C and their SRV discharge lines, then analysis of these other similar lines (i.e. MS A, B & C and associated SRV discharge lines) would produce similar analytical results with the application of these same techniques. Therefore, extension of the TH analysis of MS line D plus its four SRV discharge lines to the remaining MS lines provides a demonstration of the adequacy of the SRV discharge lines off the remaining MS lines.

In addition to these reactive similarities (pipe stress and restraint loads), there are geometric and restraint similarities, as shown in attachment 4, which also demonstrate that the response of all SRV branch lines is similar. The MS SRV discharge piping restraints are configured to provide similar restraining characteristics such that the majority of these lines (13 out of 14) have between 3 and 5 restraints.

Additional similarities are that the SRV lines connect to the MS lines at similar elevations (291' and 281'-9"), that the safety relief valves and vacuum breakers are all at similar locations and that all SRV lines descend in the drywell and exit through flued heads at elevation 239'-4".

It is for the above reasons and after considering the similarities between all MS lines and the SRV branches that the TH analysis performed on MS line D and its SRV branches demonstrates the acceptability of the ISM (ABS)/N-411 analysis for SRV branch piping off all four MS lines.

II. Acceptability of ISM (ABS)/N-411 Analyses for Annulus Pressurization.

As was previously stated, ISM (ABS)/N-411 was utilized for the analysis of 3 lines (RHR head spray, MS drain and recirculation drain) for the AP load case only. Our evaluation indicates that these analyses are acceptable as shown below:

A) RHR head spray:

The lower portion RHR head spray calculation used an enveloped spectra with N-411 damping for all load cases except AP which used ISM (ABS)/N-411. This calculation has high stress margins in the AP load cases, and although the benefits of N-411 are small, it was more expedient to re-analyze with ISM (ABS)/N-411 than to re-run the calculation with other response spectra.

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The majority of modes are excited at the peak where N-411 has no affect (i.e. greater than 20hz). This is demonstrated by figure 1, wherein the worst spectrum curves for AP load cases are shown corresponding to N-411 and-constant (2%) damping. The shaded region between 3.7 hz and 20 bz has 11 modes where the use of N-411 resulted in lower spectral levels. The maximum AP load is conservatively estimated by evaluation of participating modal responses, to increase by a factor of 1.14 from 5% damping to 2% damping.

Stress re-evaluation utilizing this factor increases the maximum AP stress from 9.6 kai to 11.0 ksi. This increase results in a maximum estimated level D stress of 26.4 ksi which is still far less than the allowable stress of 38.16 ksi.

B) Main Steam Drain:

Enveloped spectra were used for all load cases except AP, which used ISM (ABS)/N-411 damping to qualify one valve.

All pipe stress and pipe restraint designs used enveloped spectra methodology.

The one valve in question is located next to the containment penetration, which has a low spectrum of 1.4g peak for the AP load case. However, in order to consider the worst case spectrum, the RPV spectrum is used to estimate the impact of ISM /1.61. The RPV spectrum is. extremely remote from the valve and has a significant large spectral peak of 11g. The increase in valve acceleration is conservatively estimated by evaluation of participating modal responses to be a factor of 1.3 from 5%

damping to 2% damping (figure 2). Utilizing this factor increases the valve's AP acceleration from 3.4g to 4.42g. This increase, when added to the enveloped N-411 seismic acceleration of 1.4g, results in an estimated ISM /1.61 acceleration of 5.82g which is less than the maximum acceptable acceleration of 8.0g for this valve.

C. Recirculation Drain:

The recirculation drain line calculation used enveloped spectra with N-411 damping for all load cases except AP, which used ISM (ABS)/N-411. This calculation has high stress margins in the Eq. 9 Level D evaluation, and although the benefits of N-411 are small it was more expedient to re-analyze using ISM (ABS)/N-411 then to re-run the calculation with other response spectra.

6-5 The majority of modes are excited at the peak where N-411 results in no reduction in accelerations (i.e. greater than 20 hz). This is demonstrated by figure 3, wherein the worst spectrum curve for AP loads corresponding to N-411 and the constant 2% damping is shown. . The shaded region between 2.9 hz and 20 hz has four modes where the N-411 analysis would have lower spectral levels. The maximum AP load increase is conservatively estimated by evaluation of participating modal response to be a factor of 1.51 from 5% damping to 2% damping (figure 3). Stress re-evaluation utilizing this factor increases the maximum AP stress from 10.8 ksi to 16.3 ksi.

This increase results in a maximum level D stress of 22.8 ksi which is still far less than the allowable stress of 36.0 ksi.

Confirmatory evaluations for the remaining items presented on attachment 1, which have not been previously documented, will be submitted for your review at a later date (item 1. group A(3), item 1. group B (2) and all of item 2.). Attachment I was provided to your staff at the reference 4 meeting.

Please contact us if you have any questions concerning the information presented in this letter and its attachments.

Sincerely, KAH/pd12188606 Attachment Copy to: See Attached Service List

Copy to: Troy B. Conner, Jr. Esq. (w/ enclosure)

Ann P. Hodgdon, Esw. (w/ enclosure)

Mr. Frank R. Ronono (w/ enclosure)

Mr. Robert L. Anthony (w/ enclosure)

Ms. Phyllis Zitzer (w/ enclosure)

Charles W. Elliot, Esq. (w/cnclosure)

Barry M. Hartnen, Esq. (w/ enclosure)

Mr. Thanas Gerusky (w/ enclosure)

Director, Penna Energency (w/ enclosure)

Managenent Agency Angus R. Love, Esq. (w/ enclosure)

David Wersan, Esq. (w/ enclosure)

Robert J. Sugarran, Esq. (w/ enclosure)

Kathryn S. Lewis, Esq. (w/ enclosure)

Spence W. Perry, Esq. (w/ enclosure) day M. Gutierrez, Esq. (w/ enclosure)

Atomic Safety & Licensing (w/ enclosure)

Appeal Board Atomic Safety & Licensing (w/ enclosure)

Board Panel Docket & Service Section (w/ enclosure)

Mr. E. M. Kelly (w/ enclosure)

Mr. Timothy R. S. Chanobell (w/ enclosure)

KAN/pd12248602

, page I cd 4 .

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Att.achment.1 .__

Eurther analyses' t6 be Terfomed demonstrating the acceptability.of use

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of ISM (ABS)fN-411 at Limerick Uni ~t 2: , ,

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1. Bechtel' scope of calculations inside containment consists of (Attachment 1):

-Y Group A 6 calculations that are branches to main steam and recirculation imes Group B 4 calculations that used ISM (ABS)/N-411 for all load' cases Group C 3 calculations that used ISM ( ABS)/N-411 for AP' load case g Approach for justification of ISM (ABS) witn N-411 as acceptable as

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record calculation for above lines is as follows:

Group A (1) RHR return line on recirculabn leep ATs acceptable lA for comparison of ISM (ABS)/N-411 with time history study (2) Perfom TH analysis of MSRV branch lines on MS.line D-and show acceptability of ISM ( ABS)/N-411. Use these results and simliarity of other MSRV branch lines and comparison of frequencies and input loading for HPCI and RCIC branch piping with MSRY lines to justify acceptability of ISM ( ABS) with N-411 for remaining MSRY's, HPCI and RCIC branch piping.

(3) Perform a study calculation for RWCU line using ISM (ABS)/R.G.1.61 for critical load cases and show acceptability of record calculation (ISM /N-411).

Group B (1) Feedwater lines A and B are acceptable by-comparison of time history study results with ISM (ABS)/N-411.

(2) ~ Study calculation for the remaining three calculations will be perfomed for critical load cases using ISM (ABS)/R.G. 1.61 or Envelop /N-411.

ISM (ABS)/N-411 record will be retained if the study calculation shows acceptable results. ld Group C These calculations have used ISM (ABS)/N-411 only for AP loading. Damping for R.G.1.61 is greater than or equal

.~ to N-411 damping above 20 Hz. These calculations will be lb reviewed to assess the effect of AP loading for .

in frequencies below 20 Hz and document the rationale for id

- acceptability with the. record calculation (ISM /N-411). .

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2. Bechtel scope of calculations outside containment in snubber reduction program consists of (pge t.- of 4 )

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Group A 6 calcu_lations' which have stress ratios greater than 0.80.

'l Ica'lc01ation (RHR) for which' time history study has been u Group'B

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~ complethd and sho@s ISM _( ABS)/N-411 as acceptable. [ jpg ,

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Group C 9 calculations with stress ratios less than 0.80. ,

The following approach to-be taken for the justification of ISM

( ABS)/N-411 as ' record calculations for the above lines:

Group A Reanalysis of these calculations will be performed ,

using ISM (ABS)/R.G.1.61 or URS/N-411 for all- g{g calculations in' this group. When the. con t rolling load cases shows the piping configuration as

' a.cceptable;(i.e. no' changes to snubber .

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. configuration), these calculations will be . treated as -

study calculations.- If the ' configuration ~ requires change, the reocrd calculation will be changed.

Group B Time history study justifies the present record calculation as acceptable (ISM ( ABS)/N-411).

Group C The nine calculations will be analyzed for critical i

-load cases using ISM (ABS)/R.G.1.61 or URS/N-411.

These study calculations will be used to justify the record calculation in this group.

FOR DISCUSSION WITH NRC STAFF ON 12/3/86.

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_ ~ATTAC.HMENT i -

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Bechtel . scope of calculatioris

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Inside contain' ment calc.u1ations -

Total 13 .

GROUP A Branch lines of MS & Recirc. piping

1. RHR return (Recirc. Loop A)

RHR return, RHR ' supply and RWCU (Recirc. Loop B) 2.

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3. MSRV, .linef (E,J , A) *

(MS line A)

.I4. RCIC steIm supply'& M'SRV lines (KNBF) (MS line B) -

5. HPCI steam supply & MSRY lines (CGL) (MS line C)

- 6. MSRV lines (DHMS) .(MS line D) lg GROUP B 'Other. lines using ISM ( ABS)/N-411 for all load cases .

1. Feedwater (2)
2. Cored spray (2)
3. RPV vent line
4. SLCS GROUP C Lines with ISM (ABS)/N-411 for AP only-

'l. Head spray (lower)

2. MS drain
3. Recirc. drain

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(1) HIGi STRESS MARGIN, AT LEAST 20 (2) RIGID SYSTD4, AT HIST 5 ICDES LN)ER 10 HZ, WilOf E LESS CAIN F1EN N-411 THAN F1.EXIBLE SYSTD'S (3) SYSID4 HAS DI.Y l#GE BORE PIPitG #0 THJS E MINIRM (F 2% 04PDG (4) Due to rework of the piping model this calculation will be re-r-un using ISM /1.61 or enveloped N-411, and is no longer part of study cale. scope.

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UPSET RESTRAINT LOADS (LBS)

MS-A MS-B MS-C MS-D

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MSRV'A :MSRV K :MSRV L :MSRV D  :
- - - - -:= - -- -
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i  : NODE LOAD : NODE LOAD : NODE LOAD : NODE LOAD  :

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265 5540  : 456 19451  : 475 6449 : 752 10339  :
266 10232  : 475 12080  : 477 6666 : 755 7497  :
269 18098  : 477 11614  : 490 16925 : 763 19716  :
286 7665  : 485 4735  : 505 3948 :  :
:  : 505 14055 :  :
=============================:==============:===============
MSRV E' MSRV F :MSRV G :MSRV H  :
NODE LOAD : NODE LOAD : NODE LOAD : NODE LOAD :

, :____ ---_:_=- _ _ - - -_:- __:___.___________:

162 21074  : 870 8186 : 603 7369 : 547 5189 :
163 4598  : 872 10941 : 620 7683  : 567 9679 :
165 6475  : 878 11422 : 621 6647  : 570 9755 :
170 6835  : 900 7662 : 635 21637  : 577 22945  :
: 910 14501 : 655 5242  : 585 5779  :
==============:============== ==============:===============
MSRV J MSRV B :MSRV-C :MSRV M  :
---- =
NODE LOAD : NODE LOAD : NODE LOAD : NODE LOAD :
357 10650  : 730 5677  : 763 15420 : 345 14972 :

l  : 365- 18905  : 738 13520  : 770 8860 : 352 7051 :

380 8811  : 751 10683  : 773 5125 : 355 6517 :

7443  : 759 5015  : 790 10657 :  :

381 7898  : 775 13633 :  :  :
390
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:MSRV N  : :MSRV S  :

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: NODE LOAD :  : NODE LOAD :

i  :  :------=-  :  : -------:

: 585 10055  :  : 150 21206  :
: 586 9482 :  : 165 6941  :

l 9965  :

: 598 16555  :  : 167
: 622 5046 :  : 173 5598  :

I  :  : 622 17511 :  : 174 10521  :

:  :  : 183 8000  :
:  :  : 185 5784  :
:  :  : 195 4970  :
==============:=============================:==============:

4 i

I

, , , , . - - , - _ . . _ . _ . _ . _ . . . _ , _ . _ _ - , . _ _ _ . . ~ _ _ , , _ _ _

ATTACHMENT 3 pg. 2 of 2 LEVEL B STRESSES (PSI)

MS-A MS-B MS-C MS-D

MSRV A :MSRV K :MSRV L :MSRV D

_==____:  :

NODE STRESS : NODE STRESS : NODE STRESS : NODE STRESS  :

____- - ___:= -

_:________  :== - - -- _ _ _ _ _ :

218 10982 : 412 9440 : 437 6671 : 712 11021 :
225 14312 : 420 11375 : 445 4203 : 720 14541 :
250 17368 : 440 16287 : 465 8477 : 740 17881 :
268 11307 : 450 17503 : 485 7532 : 760 16072 :
275 12139 : 455 16364  : 500 9887  : 775 12827 :
290 14983 : 480 11632  : 520 9597  : 785 15236  :
: 495 11414 : 525 10365 :  :
: 505 8570  :  :  :
: 510 11194  :  :  :
============================================ ==============:
MSRV E :MSRV F iMSRV G :MSRV H  :
NODE STRESS : NODE STRESS : NODE STRESS : NODE STRESS :
118 7720 : 838 7021 : 565 7195 : 512 9557 :
125 9974 : 845 8546 : 570 7850  : 520 12064  :
150 14761 : 850- 10720 : 585 10924 : 540 10925  :
168 9021 : 875 12021 : 605 11248 : 555 16283  :
180 12689 : 890 10032 : 610 14018 : 560 17380 :
190 10970 : 905 10499 : 630 11871 : 575 11488 :
: 930 10414 : 660 13084 : 590 12008 :
: 935 13111 : 665 15898 : 600 11127 :
==============:============================================:
MSRV J :MSRV B :MSRV C :MSRV M  :
_=_ -
NODE STRESS : NODE STRESS : NODE STRESS : NODE STRESS :
==- - - - =

===----- =: - - - - - - ---:---- -------:

318 10166  : 686 8245  : 712 7371 : 308 8261  :
325 12793  : 695 10559  : 720 8455 : 320' 10067  :
337 11840  : 705 11114  : 730 8663  : 325 11269  :
350 15386  : 735 12195  : 760 8900  : 340 12764  :
370 14589  : 740 14301  : 765 9159  : 350 12816  :
382 11597  : 765 13311  : 785 9161  : 370 10803  :
394 14293  : 770 13459  : 795 9661  : 375 12045  :
398 14267  : 795 10905  : 815 13084  : 390 17891  :
=============================:============== ==============
:MSRV N  : :MSRV S  :

--:  :-==- -=----:

: NODE STRESS :  : NODE STRESS :
: 538 7765 :  : 112 7004  :
: 550 9702 :  : 120 8232  :
: 570 11859 :  : 125 7767  :
: 595 8708 :  : 145 12794  :
: 615 11630 :  : 155 9219  :
: 635 9536 :  : 175 8702  :
: 640 10815 :  : 167 8631  :
-  :  :  : 200 9722  :
:  :  : 20E 7339  :
:  :  : 210 10270  :
==============:==============:============== ==============:

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. .i FIGURE

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