ML20077J031

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Assessment Against RHR Safety/Relief Valve Discharge Steam Condensation Loads
ML20077J031
Person / Time
Site: LaSalle  Constellation icon.png
Issue date: 07/29/1983
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20077J019 List:
References
NUDOCS 8308120190
Download: ML20077J031 (20)


Text

. LaSalle County Station Project No.: 6728,30 Date: July 29, 1983 i

, Page: 1 ASSESSMENT AGAINST RHR SAFETY / RELIEF VALVE DISCHARGE STEAM CONDENSATION LOADS

1.0 INTRODUCTION

The Residual Heat Removal (RHR) system can be operated in the non-safety-related steam condensing mode, thus providing a back-up capability for the decay heat removal when the decay heat removal function is not available via the main condenser or through the main steam safety relief. valves. The operation of the RHR system in this mode can be initiated manually only.

With the RHR system in the steam condensing mode reactor steam is released through the pressure-reducin'g control valve (200 psig) to the heat exchanger. The heat exchanger is protected with a safety relief valve (SRV) set'at 500 psig.

The discharge through this RHR SRV is routed through a ramshead discharge device into'the suppression pool. The steam discharge into the pool can occur only if the pressure-reducing control valve fails open or if the RHR SRV inadvertently opens and

, fails to reclose.

If the pressure-reducing control valve fails open the down-stream piping pressurizes quickly to the pressure relief .

setpoint causing the SRV to open. Since the capacity of the SRV is larger than that of the pressure-reducing control valve the system depressurizes and the SRV reseats. The vacuum breake*r valve on the SRV discharge line opens to allow air into the discharge line. This event repeats itself until the operator isolates the steam condensing mode. -

If the RHR SRV inadvertently opens and fails to reclose the controller would try to maintain the downstream system pressure at 200 psig by opening the pressure-reducing control valve to its limits. The steam discharge through the failed RHR SRV into the suppression pool continues until the operator isolates

  • l the steam condensing mode.

8308120190 830005 PDR ADOCK 05000373 P pm ,

. . LaSalle County Station

. Project No.: 6728-30 Date: July 29, 1983 Page: 2 Steam discharge through the RHR SRV into the suppression pool produces the usual hydrodynamic loads. Here, however, only steam condensation loads associated with this discharge through the RHR SRV are discussed.

2.0 RHR SRV DISCHARGE STEM 1 CONDENSATION LOAD DEFINITION The RHR SRV discharge line (8") ends 10 feet below the pool water surface with a ramshead discharge device. A'similar discharge device was also used on the main steam SRV discharge lines for Mark I power plants, and data- for continuous steam a

condensation through this ramshead discharge device wcs collected during the SRV discharge test at the Monticello l,

( Re f . 1) and Quad Cities (Ref. 2) power plants. These data

were used to develop the RHR SRV discharge steam condensation load definition for the LaSalle County Station.

2.1 Load Definition -

The RHR SRV discharge steam condensation load is defined as a sinusoidal load with amplitude of 10 psi over a frequency range from 50 to 200 Hz. The load magnitude varies over the suppression pool boundaries as shown on Figures 1, 2 and 3.

2.2 Method of Load Development i The load definition was developed in the following manner.

. The Sargent & Lundy computer code IMAGES, which is based on potential flow theory and the method of images, has the capability of modeling the Mark I and Mark II suppression pool geometries. IMAGES was used to infer

the steam bubble source strength from the' maximum wall.

pressures observed during the Monticello and Quad Cities tests on a sensor near the discharge device. The larger source strength (7.65 psid for the Monticello test 15, sensor P14) was then' arbitrarily increased (to 10 psid) l for conservatism and used as input to IMAGES with the i

LaSalle suppression pool configuration, and the boundary pressure distribution was calculated. The frequency

  • LaSalle County Station

. Project No.: 6728-30 Date: July 29, 1983 Page: 3 range for the load definition was based on the observa-tion given in the Monticello test report (Ref. 1), where it is said that the measured frequencies ranged from 80 to 125 Hz. Again, for conservatism, the f'equency r range was enlarged to 50 to 200 Hz. It should be noted that the upper limit agrees with the observations provided in the DFFR (Ref. 3) for the condensation regime of the Monticello test.

2.3 Discussion of the Data Base .

The Monticello test data form a conservative data base for use in derivation of the load definition for the RHR SRV discharge steam condensation. The steam condensation regime is a function of two parameters: steam mass flux and pool temperature. The comparison of the Monticello SRV steam mass flux (200 lb/ft 2-sec) and the LaSalle RHR SRV steam mass flux (75 lb/ft2 0sec) shows that the test data were obtained for a steam mass flux about 2.7 times higher than the case of interest. Since, in general, the boundary load increases with steam mass flux (Ref. 3) ,

the selected data base is conservative for the derived load definition. For Test 15, the data base used, the initial pool temperature'was 78*F. However, the . test report (Ref. 1) concludes that "no apparent trend in the peak load magnitude values with time, during the steam discharge transient, was observed. The longest steam discharge was 27.5 seconds." On the other hand, since the RHR is used in the pool cooling mode whenever the suppression pool exceeds 100*F, it is expected that the system will be used in the steam condensing mode for pool temperatures below 100*F only. This discussion, coupled with the steam condensation information provided in the DFFR (Ref. 3), suggests that the steam condensation loads on the pool boundary will change very little, if

l

, . LaSalle County Stationi

. Project No.: 6728-30 '

Date: July 29, 198 Page: 4 at all, within the temperature range from 78* to 100*F.

It can therefore be concluded that the Monticello test data is a conservative data base for a description of the RHR SRV discharge steam condensation load.

3.0 STRUCTURAL EVALUATION The containment and the internal concrete structures were evaluated to include the effects due to the steam condensation loads defined in Section 2. The load combinations considered and details of analysis and evaluation are summarized below.

3.1 Load Combination The containment and the internal concrete structures were evaluated for the applicable load combinations contained in Table 4.1-1 of the LaSalle County Station Design Assessment Report (LSCS DAR) which includes the following load categories: .

a. Normal loads,
b. Normal loads with severe environmental loads, and
c. Normal loads with extreme environmental loads.

In the above load combinations, the KWU (quencher) SRV loads are replaced by the RHR SRV steam condensation loads. .

3.2 Analysis An axisymmetric finite element model similar to that described in Subsection 5.1.1 of the LSCS DAR vas used in the analysis.

The steam condensation loads were applied'on the suppression pool wetted boundary as a series of FOURIER Cosine harmonics which, when added, adequately represent the distribution of the loads around the circumference of the wetted pool boundary.

A dynamic analysis was performed in the frequency domain using the FAST FOURIER Transform method. A band-limited

"

  • LaSalle County Station Project No.: 6728-30 Date: July 29, 1983 Page: 5 white-noise time history, the FOURIER transform of which has a constant magnitude at all the frequencies of interest in the frequency range defined for the load,'was used for the analysis. Responses to the applied load are then computed from the transfer functions obtained from the resulting response time histories using the~Sargent & Lundy FAST computer program.

Acceleration response spectra were generated at selected node locations using the RSG computer program, for the equipment / subsystem assessment.

3.3 Containment Evaluation Forces at critical containment locations resulting from the analysis for the RHR SRV steam condensation loads are combined by the absolute sum (AB'S) method with other appropriate loads' as per.the load combinations discussed in Subsection 3.1. The acceptance criteria are the same as described in Section 4.1 of the LSCS DAR.

The results confirm that the effects due to the steam condensation loads attenuate rapidly and are smaller in magnitude compared to the design basis KWU SRV loads.

Therefore, plant design safety margin factors established '

in Section 5.1 of the LSCS DAR for the applicable load combinations are not affected.

3.4 Conclusion The LaSalle containment design can safely accommodate the effects due to the RHR SRV steam condensation loads. No additional analysis or design work is required to establish the plant adequacy.

4.0 EVALUATION OF PIPING Piping in the wetwell and containment areas was assessed for the RHR safety relief valve loading. Response spectra for i

the RHR loading was generated at specified locations on the l

i l

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1 LaSalle County Station '

Project No.: 6728-30 '

Date: July 29, 198'3 '

Page: 6 containment wall and slab (see Fig. 4). For this assessment the RHR SRV loading was considered to act simultaneously with the SSE (Safe Shutdown Earthquake) loading. The RHR SRV combined loading was then compared to the applicable LaSalle design basis curve (Figures H.4-2 through H.4-34) (Ref. 4).

This comparison confirmed that the RHR SRV combined loading was bounded by the original LaSalle Design Basis.

~

4.1 Load Combinations

~

The RHR SRV load was combined to act simultaneously with the seismic loading SSE (Safe Shutdown Earthquake 2%

damping). The two independent dynamic loadings were combined using the SRSS method (square root of the sum of the squares).

4.2 Analysis At selected locations within the reactor building, the RHR SRV combined loading was compared to the LaSalle i

design basis. The model and locations used for the RHR SRV assessment is shown in Fig. 4 (NP.227, 245 and 273).

The RHR SRV load generated (described in Section 3.2) was defined in two directions: One horizontal and one vertical. Since the SSE response spectra was defined in two horizontal directions (NS and EW) and one vertical direction, horizontal'RHR SRV was combined with NS and EW l spectra separately. For NP. 227 elevation 698'6" (containment wall), enveloped response spectra at elevations 673'4" and 735'0" were used. For NP. 273 elevation-743'6" (contaimment wall), enveloped response spectra at elevations 735'0" and 786'6" were used.

4.3 Response Spectra Comparison ,

The RHR 'SRV loading was defined in the frequency range between 50 and 200 Hz. Seismic SSE loading is primarily j in the low frequency range (< 33 Hz). SSE response spectra-  !

l in the frequency range between 50~and 200.Hz is represented I l i

l l'. . .. _ . . - _ - _ . - . - - .

LaSalle County Station

, Project No.: 6728-30 Date: July 29, 1983 Page: 7 l

by the ZPA value (Zero period acceleration) . Therefore, in all cases, the RHR SRV loading was essentially combined with the ZPA for each specified location and direction.

The comparison between the SRSS combination response spectra (RIIR SRV and SSE) and the LaSalle Design Spectra indicated that the original Design Basis can adequately bound the RHR SRV combination. Results of the response spectra comparisons are shown in Fig. 5-13.

4.4 Conclusion -

The results of this assessment clearly show that the RHR SRV load combination was bounded by the original LaSalle Design Basis. At each of the representative locations and frequencies the' combination was less than the design basis. This result confirms that the original LaSalle Design Basis can, accommodate the additional RHR SRV loading.

5.0 REFERENCES

1. Final Report In-plant Safety / Relief Valve Discharge Load Test - Monticello Plant", General Electric Co., {

NEDO-21581-P, Class III, August 1977. l

. 2. " Steam Vent Clearing Phenomena And Structural Response of the BWR Torus (Mark I Containment) ",

General Electric Co., NEDO-10859, Class I, April 1973.

3. " Mark II Containment Dynamic Forcing Functions Information Report", General Electric Co. and Sargent & Lundy, NEDO-21061, Class I, September 1975.
4. LaSalle County Station - Mark II DAR, Appendix H.

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sercrea vem 88 - .

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, vennsceret Project No.: 6728-30' C "'C ^

  • 5:!stv-RetztM l r:en-1.f,w r. Date: July 29, 1983 Page: 19 Clket P.,ws i by -

l'roject F.r&xd by Dste Proi. No. Ecolo. Ils. /.osieved by Dat

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