Text

Pressurizer Relief Valve Discharge Piping Qualification, Rept on Task 05088
	ML20080N083
Person / Time
Site:	Calvert Cliffs
Issue date:	09/23/1983
From:	James Smith, Ventura J; BECHTEL GROUP, INC.
To:	;
Shared Package
ML20080N080	List: ML20080N077; ML20080N083; ML20080N084;
References
	NUDOCS 8310040355
	Download: ML20080N083 (154)
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CALVERT CLIFFS NUCLEAR POWER PLANT JOB NUMBER 11865

& c/062re l REPORT ON TASK 05088 PRESSURIZER RELIEF VALVE DISCHARGE PIPING QUALIFICATION FOR UNIT NO. 1 CALVERT CLIFFS NUCLEAR POWER PLANT JOB 11865 SEPTEMBER 23, 1983 (This report compliments the Class I Piping Stress Report)

Appr.oved: 3 4"

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CALVERT CLIFFS NtfCLEAR POWER PLANT JOB NUPUBER 11865 1.0 GENERAL This task was begun in response to NUREG 0578 Section 2.1.2, " Performance Testing on BWR and PWR Safety and Relief Valves", and the clarification supplied by NUREG 0737 Section II.D.I.

The task for the Calvert Cliffs Nuclear Plant was divided into two parts, namely, Assessment of Relief Valve Performance; and Qualification of Relief Valve Piping Due to Discharge Loading.

The assessment of the safety valves, SVs, and the power operated relief valves, PORVs, performance was undertaken by EPRI and a report was issued by that group. The research had shown significant valve / piping loading resulting from designs employing water seals upstream of the valves.

Bechtel was given the task of evaluating and qualifying the relief valve piping for Unit No. 1.

This plant does not have a water seal design.

1.1 DESIGN EVOLUTION The first effort to respond to this task was simply to qualify the piping by using the original class 1 analysis performed for Calvert Cliffs. Upon investigation into this area, that plan was dropped due to a lack of a plant specific dynamic forcing function from EPRI. This led to consideration of a new analysis using state of the art tools available today.

l After some study, and from a review of the research, the computer code RELAP 5/ MOD 1, which has been recommended by EPRI for this task, was chosen. An extensive computer model of the entire system was developed which included the pressurizer, all relief valve piping from the pressurizer down to and including the quench tank, as well as branch c'onnections to closed valves. The boundary conditions that were used were

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supplied by the NSSS vendor to EPRI in the form of a report.

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I CALVERT CLIFFS NUCLEAR POWER PLANT JOB NUMBER 11865 The original model included safety valves which behaved similarly to the safety valves (Dresser model No. 31739A) that were tested by EPRI. The valve model was bench marked to those test results. However, this valve model showed unsatisfactory behavior (chattering) in the Calvert Cliffs system. Subsequently, the NSSS vendor, Combustion Engineering, and the valve manufacturer, Dresser, collaborated on new ring settings to assure stable operation of the safety valves. This led to the present model which incorporates these changes to the safety valves as well as the latest boundary conditions reported by EPRI.

2.0 DESCRIPTION

OF ANALYTICAL METHODS 2.1 Forcing Function Determination i

.The RELAP 5/ MOD 1* code uses a full two fluid non-equilibrium treatment of the equations of continuity (mass, energy & momentum). The differential equations are solved in finite-difference form over a volume mesh' l

representing the piping system.

l The model of the pressurizer relief valve system (see Fig.1) is composed of 340 volumes tepresenting approximately 400 feet of piping. It includes all of the relief valves and branch lines between the pressurizer and the quench tank. The initial and transient conditions in the precsurizer for the two cases analyzed are presented in Table 1.

RELAPS/ MOD 1 hereafter is truncated to RELAP.

2

CALVERT CLIFFS NUCLEAR POWER PLA!Pr JOB NUMBER 11865 TABLE 1 PRESSURIZER TRANSIENT INITIAL CONDITIONS TRANSIENT VALVES IN MAX PRESSURE PRESSURE OPERATION (psia)

RAMP RATE (psia /sec)

Loss of Load PORV 2538.0 46.0 Loss of AC SV 2534.0 64.4 NOTE: During loss of load, the safety valves are assumed not to open and during loss of AC, the FORV's will not open. For the loss of load case the NSSS vendor states that if the PORVs open, the maximum pressure vill not be 2538 psia, but will stay below the safety valve set point. Therefore, the safety valves are assumed not to open but the maximum pressure used is 2538 psia for conservatism.

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CALVERT CLIFFS NUCLEAR POWER PLANT JOB NUMBER 11865 6

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TP3IT. ONE PRESSURIZER RELIEF FIPING ISOMETRIC I

SHOWING FORCING FUNCTION NODE W

W

. NUMBERS 86 a

y N

QUENCH TANK p

NOZZLE FIG. 1 4

CALVERT CLIFFS NUCLEAR POWER P,IANT j

JOB NUMBER 11865 The most important part of the system model is the safety valves. The valve models are valve components in RELAP 5.

This type of component acts as an orifice which opens at a set rate. The PORVs open when the pressurizer reaches the set pressure and they achieve full open in 0.13 seconds.

The safety valves open when the pipe directly upstream of the valve reaches the set pressere and they achieve full open in 0.012 seconds The valve opening timss are obtained from the EPRI Reports.

RELAP calculates all of the hydro-dynamic conditions in the piping for these transients and this information is translated to piping loadings by a post-processor code (REPIPE). These results are then used in the Bechtel stress code ME 101 which calculates hanger loads, forces and moments on connecting piping components, and pipe stresses.

2.2 Piping System Stress Analysis l

ME101 is a finite element computer program which performs linear elastic analysis of piping systems using standard beam theory techniques. The input data format is specifically designed for pipe stress engineering.

ME101 performs a thorough checking of the input prior to performing analysis. The program additionally modifies the geometry automatically to improve the finite element model.

ME101 performs static and dynamic load analysis of piping systems, effective weight calculations, and ASME Section III Nuclear Class 2 and ANSI B31.1 Code stress checks. The ME-101 output is then used for further analyses considering fatigue to develop a Class 1 report.

i Static analysis considers one or more of the following: thermal expansion, dead weight, uniformly distributed loads, and externally applied forces,

-moments, displacements and rotations, individual force loads, static seismic (uniform directional acceleration) loads, or seismic anchor movement analysis.

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CALVERT CLIFFS NUCLEAR POWER PIANT j

JOB NUMBER 11865 Dynamic Analysis is based upon the standard normal mode superposition techniques. The input excitation may be in the form of single or multiple seismic response spectra or time dependent loading functions such as was obtained from REPIPE. Various methods of eigenvalue solution are available. Determinant Search or Subspace Iteration considers all data points as mass points. Kinematic Reduction considers masses only at user specified data points in designated directions. In the time history analysis, the excitation may be in the form of arbitrary nodal forces, support displacements (or rotations) or support accelerations (or rotations) that are not necessarily in phase. The safety valve input (REPIPE) considered nodal forces.

The piping model includes the option of adding new PORV flanges in the future for maintenance purposes.

The resulting pipe stresses were. reviewed using the USAS B31.7, 1969 Code.

The piping system was modeled as three separate problems; two problems considered each SV/PORV network from the vessel nozzles to the common anchor, the third problem considered the piping from the anchor to the quench tank nozzle.

2.3 Pipe Supports Evaluation I

Supports were evaluated using classical beam-column linear analyses.

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Indeterminate structures were analyzed using ICES-STRUDL-II computer code.

1 Analytic procedures in ICES STRUDL-II apply to both franed structures and continuous mechanics problems. Framed structures are two or three dimensional structures composed of slender, linear members, which can be

-represented by properties along a centroidal axis. Such a structure is

- ' composed on joints, including support joints, and members connecting the joints. A variety of force conditions on member ends and at support joints j

may be specified implicitly by means of structural type and orientation ccamands or explicitly for a member or joint.

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CALVERT CLIFFS NUCLEAR POWER PLANT JOB NUMBER 11865 3.0 RESULTS 3.1 Forcing Functica The RELAP results are presented in the form of the force-time history plots for the nodes as shown in Figure 1.

(see Appendices A&B) These force-time histories were direct input to the stress code ME-101. The results of the stress analysis are presented in detail in the Class i stress report and are summarized in the following sections.

l 3.2 Stresses on Piping and Fittings A complete analysis of all design load cases resulted in pipe stresses I

which pass the ASME B31.7. 1969 Code.

The' flanges on the Class II piping at the Class I/II boundary have been reviewed in accordance with ANSI B31.7 and have been found to be-acceptable. The calculated and allowable stresses at the flanges are presented in Table 2.

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CALVERT CLIFFS NUCLEAR POWER PIANT JOB NUMBER 11865 TABLE 2 CLASS II FLANGE STRESSES AT SAFETY VALVE OUTLET LINE #

STRESS PROB STRESS IN STRESS (psi)

FLANGE CALCULATED / ALLOWABLE 5" GC-8-1007 P-1321 Rev.0 Longitudinal 19809

/ 30,000 Radial 15044

/ 30,000 Tangential 10068

/ 30,000 6" GC-8-1006 P1322 Rev.0 Longitudinal 19844

/ 30,000 Radial 15077

/ 30,000 Tangential 10090

/ 30,000 i

NOTE: All calculations are based on a back pressure of 670 psia at the flanges.

(The safety valve and flange evaluation is by others.)

Tables 3 and 4 present the loading on the safety valves due to the piping.

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NOTES:

1. Unite - Forces LBS Momente FT-LBS

2. h rmal Londe for 2 modes specified W rmal Mode la Both Valves - SRV 6 PORV Closed j

l h real Mode 2 FORV Open. SRV Closed i

l FORY toad Dynamic Imad due to FORV Opening (SRV Closed)

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Problem No. P-1321 Rev. O Data Pt. 10 Problem No. P-1321 Rev. O Data Pt. 12 Tast.

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NOTES:

1. Units - Forces LBS l

Moments: FT-LBS g

2. Thermal Loads for 2 modes specified Thermal Mode la Both Valves - SRV & PORY Closed Thermal Mode 2: PORV Open. SRV Closed PORV14aga Dynam{etoajjuetoSRV c laa ue to PORV Opening PORY C one))

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CALVERT CLIFFS NUCLEAR POWER PIANT L[/

JOB NUMBER 11865 3.3 Piping System Supports The support review for the new reactions is summarized below.

1.

Total number of existing supports - 84.

2.

Currently, modifications for a total of 10 supports are planned.

The new analysis requires upgrading of the supports to bring various members to within coda allowable stresses. Supports to be modified due to the new loads generated from this analysis are presented in Table 5.

TABLE 5 SUPPORTS REQUIRING MODIFICATION

+SK-19012

+SK-17521

+SK-25008

+SK-19022

+SK-33649 SK-19023

+SK-17500 SK-19031

+SK-17505 SK-40295

(+) are located within the Pressurizer Compartment.

3.

In addition 3 supports require field information. Analysis of these supports have been performed based on logical assumptions and they are found to be acceptable. A walkdown of these supports during the upcoming outage is planned for confirmatory checks.

l 4.

A fourth support (SK-40324) requires information in the form of bolt lengths for the base plates as indicated on the following sketches.

i (Figures 2 through 6)

(This information will be obtained by. field

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walkdown to complete the documentation / analysis of this hanger.)

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CALVERT CLIFFS NUCLEAR POWER PIRIT JOB Nt20BER 11865

4.0 CONCLUSION

In accordance with NUREG 0737 Section II.D.I, the analysis of the pressurizer relief valve piping has shown that piping system stresses due to discharge loading will be within code allowables. An analysis of the support system for this piping shows local yeilding of some support members. A non-linear analysis may show the supports to be adequate.

However, it is not recommended because of the expense and the possibility that modifications may still to a lesser extent be required.

Considering the stress margin (l) available for the piping system it is our judgement that even with support member deformation, the piping system will remain intact during relief valve operation coincident with an Operating Basis Earthquake (OBE). This condition is the limiting load case. In addition, it is also our judgement that the safety valves will remain operable as a result of the low valve end loadings shown in tables 3 and 4.

Based on the above it is our recommendation that the supports in question be re-worked in an orderly manner in lieu of further analysis.

l (1) a.' -The highest cumulative usage factor for class 1 jiping is less than

~~0.05 versus the allowable of 1.

b.

The highest combined stress for class 2 piping, for the OBE is 10948 psi compared to an allowable 1.2 Sh of 17558 psi.

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ML20080N083

Contents

Text

2.0 DESCRIPTION

4.0 CONCLUSION

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