ML20028E949

Forwards Reanalysis of Control Rod Drive Return Sys Piping Considering Axial U-Bolt Restraint & Site Specific Spectra, Per SEP Topic III-6, Seismic Design Considerations. Piping Stresses within Code Allowables

ML20028E949
Person / Time
Site:	Oyster Creek
Issue date:	01/20/1983
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
TASK-03-06, TASK-3-6, TASK-RR NUDOCS 8301280291
Download: ML20028E949 (14)

Text

O GPU Nuclear

... Q g7 P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number.

January 20, 1983 Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 SEP Topic III-6, Seismic Design Considerations Enclosed is a report entitled " Reanalysis of the Control Rod Drive Return System Piping Considering Axial U-Bolt Restraint and Site Specific Spectra".

This reanalysis demonstrates that the CRD return system piping stresses are within Code Allowables for the Oyster Creek Site specific seismic spectra. The analysis was requested by the NRC staf f during our meeting on September 1,1982.

Very truly yours, m_A>

a 1 Peter B. Fiedler Vice President and Director Oyster Creek PBF: lh Enclosure cc: Mr. Ronald C. Haynes, Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 I L i

8301280291 830120 PDR ADOCK 05000219 P PDR GPU Nuclear is a part of the General Public Utikties System j

OYSTER CREEK NUCLEAR GENERATING STATION -

Reanalysis of the Control Rod Drive Return System Piping Considering Axial U-Bolt Restraint and Site Specific Spectra

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Introduction A reana. lysis of the Oyster Creek control rod drive return (CRDR) system piping has been performed by.MPR to investi-gate the effect of system boundary conditions and the seis-mic excitation assumed for the analysis. Initial analyses of the CRDR system piping were conducted by EG&G for the NRC as part of the Systematic Evaluation Program (SEP) . The EG&G analyses indicated that stresses in four areas of a one inch recirculation line connected to the CRDR system were over allowable limits. Review of the EG&G analyses revealed two areas which could make the EG&G results conservatively high, as follows: (1) the analyses did not consider axial restraint at U-bolt supports due to friction effects, and j (2) the analyses seismic loads were based on scaled Reg.

l Guide 1.60 floor response spectra rather than the more l

l realistic floor response spectra developed for the Oyster Creek site specific spectra. The purpose of the reanalyses reported herein is to evaluate the effect of these 2.reas on l the reporteo stresses.

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d

' Summary of Results

. The nen reanalysis of the CRDR system piping was performed using a section of the EG&G finite element model. This model was provided to MPR by EG&G (Ms. V. Call) at the re--

quest of the NPC (Mr. T. Cheng). The details of the method and the results of the analysis are explained in the follow-ing sections of this report. 'A summary of the reduced stresses for the piping considering (1) axial O-bolt re-straint, (2) seismic loading due to site specific spectra, and (3) the r combination has been tabulated in Table 1.

The table indicates that use of site specific seismic load-ing alone reduces the highest stress locations given in the EG&G analyses below allowable limits. The addition of axial restraint at one U-bolt support further reduces the calculated stresses.

Method of Analysis The EG&G finite element model of the CRDR system piping is shown in Figure 1 attached to the report. This figure in-dicates geometry orientation and the location of the one inch recirculation piping found to be over allowable stress limits in the original EG&G analyses. The model was developed by EG&G from GPU Nuclear drawing SK-F-M-0020 for use with the finite clement code NUPIPE-II. This model has 2142 static degrees of freedom and 1035 dynamic degrees of freedom. Due to the high cost per run (in excess of I

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'S1,200), only a part of thm origincl EG&G piping model wns used in the MPR finite element analysis. The section of piping model that: was used in the analysis is shown in Figure 2 attached to this report. The geometry, anchor points, and node numbering are identical to that used by EG&G. This section of piping contains the locations of the highest stress areas identified in Figure 1 and a sufficient length of piping well away from these areas. Although the smaller model will not provide the identical results given in the EG&G analyses, it can be used to determine the amount of reduction or increase in stresses that can be expected for the above mentioned changes to the analytical model.

The original EG&G model was restrained at node #107 shown in Figure 2, which is the location of a U-bolt support. This difference in fixity, well away from the area of interest, should have minor affects on the end results, particularly since the displacements taken from the results of EG&G analyses for thir point are small.

The reanalysis consisted of three runs as follows:

1. Verification / Comparison Run An initial run was made of the shortened piping system using the EG&G boundary conditions and seismic input.

The run was used to compare with the EG&G analyses and i

as a base case to compare with todified support fixity and seismic input cases.

2. Axial Restraint Run The shortened system was then run with added axial restraint at the U-bolt support at node #1105 with the original EG&G seismic input based on Reg. Guide 1.60.

This run was used in comparison with the base case to find the reduction in the full model EG&G stresses due to axial U-bolt support.

3. Axial Restraint Plus Site Specific Spectra The final run with the shortened system piping included axial restraint at the U-bolt support at node #1105 and the seismic floot response spectra for the site speci-fic spectra. These floor. response spectra are developed in MPR-691, " Interim Floor Response Spectra for the Oyster Creek Reactor Building" dated October

.15 , 1981. The applicable site specific spectra are compared to spectra based on Reg. Guide 1.60 in Figures 3 and 4 attached to this report, for horizontal and vertical spectra, respectively. This run was used to determine the reductions in full model EG&G stresses due to the effect of using site specific spectra as well as the effect of using both site specific spectra and axial U-bolt restraint at node #1105.

Risults and Conclusions The results of run number 1, above, are comparable to the results obtained by EG&G. The shortened system predicts the same high and low stress points and demonstrates the same characteristic piping motions. Therefore, we believe that piping stresses resultine from modifications to the shortened system piping will represent linear-proportional changes'in the full EG&G model.

On this basis, the resulting stresses obtained from run number 2, above, were ratioed with the stresses obtained in run number 1. These ratios, along with the stresses from the EG&G analyses, were used to find reduced stresses for the case of axial U-bolt restraint due to friction effects.

The percent reduction due to the ratioed stresses, the original EG&G stresses, and the reduced stresses are shown

. in Table 1.

Similar ratio techniques were used with run number 3 and run number 1 to find the reduced stress levels in the full EG&G model due to axial restraint at U-bolt type supports and seismic loading for the site specific spectra. The percent reduction due to the ratioed stresses between run 3 and l run 1, the original EG&G stresses, and the reduced stresses are shown in Table 1.

~5- -

• Tha reduced strcsc:a fcr no exici rostraint or. U-bolt supports but with seismic loading from the site specific spectra is shown in Table 1 and was also obtained by ratioing.

The results presented in Table 1 indicate that the estimated reduced stresses for the control rod drive return system piping are within the allowable limit of 42 kui for the floor response spectra based on the Oyster Creek site speci-fic spectra. The stresses are further reduced when axial restraint in the U-bolt type supports is taken into account.

The assumption of axial restraint at the U-bolt support at node #1105 is considered reasonable since the calculated axial reaction laod for this relatively flexible small piping is only 81 lbs., as indicated in Table 1.

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TABLE 1 CRD PIPING STRESSES MPR ANALYSIS - ifR ANALYSIS -

EG8G STRESSES - SHORTENED PIPING SHORTENED PIPING ESTIMATED STRESSES ESTIMATED ESTIMATED W/0 AXIAL U-BOLT SYSTEM W/ AXIAL SYSTEM W/AX1AL IN EG8G MODEL STRESSES IN EG4G STRESSES IN EGSG SUPPORT AT NODE U-BOLT SUPPORT - SUPPORT AND SITE W/ AXIAL U-BOLT MODEL W/AX14L MDEL W/0 AXIAL

1. 1105 AND REG. 5 REDUCTION SPECIFIC SPECTRA -

HIGHEST STRESS SUPPORT AND REG. SUPPORT AND SITE SUPPORT BUT WITH GUIDE 1.60 SPECTRA IN STRESS 1 REDUCTION GUIDE 1.60 SPECTRA SPECIFIC SPECTRA SITE SPECIFIC LOCATIONS Note (1) Note (2) IN STRESS SPECTRA Node # 1310-Reducer 46174 4.16 18.49 44251 37638 1" Recirculation 39272 Line Node # 1380-Tee 52312 12.95 34.36 45536 34340 1" Recfrculation -

39449 L1ne

.. Node # 1455- .

Straight Run 54236 13.68 34.32 46814 35620-1" Recirculation 41265 Line Node # 1470-Reducer 43933 6.13 22.70 41239 33959 1" RecfrculatIon 36177 -

Line (Note 3)

Notes:

(1) Allowable Stress is 42000 psi (2) Reaction Load in axial direction at U-Bolt Support #1105 is 81 lbs.

(3) Stresses in 2" CRDR piping are within allowable lief ts for all analyses.

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