ML20028F999

Forwards Response to SER Confirmatory Issue 21 Re Suppression Pool Temp Limits.Response Addresses plant- Specific Info & Assumptions Used in Analyses to Meet NUREG-0783 Requirements & Criteria

ML20028F999
Person / Time
Site:	Perry
Issue date:	01/31/1983
From:	Edelman M CLEVELAND ELECTRIC ILLUMINATING CO.
To:	Youngblood B Office of Nuclear Reactor Regulation
References
RTR-NUREG-0783, RTR-NUREG-783 PY-CEI-NRR-0009, PY-CEI-NRR-9, NUDOCS 8302070301
Download: ML20028F999 (16)

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s P O DOx 5000 - CLEVELAND, OHlo 44101 TELEPttONE (216) 622-9800 ILLUMINATING DLDG - SS PUDLICSoVAHE Somng The Cost location in the Nation MURRAY R. EDELMAN VICE PRf SIDE NT NUCLE A R

.h January 31, 198f PY-CEI/NRR-0009 L Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555  ;

1 Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Confirmatory Issue No. 21 Suppression Pool Temperature Limits

Dear Mr. Youngblood:

This letter and the attached report are provided in response to the Perry IJuclear Power Plant (PNPP) SER Confirmatory Issue No. 21 regarding suppression pool temperature limits. The attached report addresses the PNPP plant-specific information, analysen, and assumptions used in the analyses, to meet the requirement,s and criteria given in NUREG-0783. All analyses in the attached report,were performed by General Electric.

The result.s can be summarized as follows:

a. The SRV discharge events of Paragraph 5.6 of NUREG-0783 were analyzed with the conservative assumptions fiven in Paragraph 5.7 of NUREG-0783.

b. The highest computed bulk pool temperature for the events mentioned in a. above is 1,81 F with SRV operation at steam discharge condition below 25 lbm/ft.'/sec. This means that the local pool temperature will remain below 200 F. NUREG-0783 criteria requires that the local pool temperature not exceed 210 F for low mass flux conditions.

These analyses with NtlREG-0783 assumptions are quite conservative. The actual maximum bulk pool temperature from such an event is expected to be substantially below 180 F using more realist.ic assumptions. Thus, the pool will be stable even beyond 220 F for such low mass flux rates with Perry's X quenchers design.

9302070301 830131 ph PDR ADOCK 05000440 PDR E

Mr. B. J. Youngblood January 31, 1983 These analyses are being provided in support of the PNPP's Technical Spec- ,

fications. Therefore, the information contained in the attached report l will not be incorporated into the PNPP FSAR. j We believe that this letter and the attached report should resolve this confirmatory issue in the next Supplementary Safety Evaluation Report.

Very truly yours, Murray R. Edelman Vice President Nuclear Group MRE:mb cc: Jay Silberg, Esq.

John Stefano Max Gildner John Kudrick Enclosure

Attachment to Letter PY-CEI/NRR-0009 L PERRY NUCLEAR POWER PLANT SUPPRESSION POOL TEMPERATURE ANALYSES REPORT I

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PNPP NUREG-0783 SUPPRESSION i

l p001. TEMPERATURE ANALYSES INTRODUCTION &

SUMMARY

This report addresses the Mark III porry plant sup ess'.on pool temperature limits during safety relief valvo discharge events based on the assumptions and transients described in NUREG-0783. No transient was found to exceed the acceptance critoria described in NUREG-0783 Scution 5.1. The analytical model used for the pool temperature calcu-lation is described in NRC approved NEDO-20533, "The GE Mark III pressure Suppression Containment System Analytical Modol." The model is used to analyze the thermodynamic responso of a pressure suppression containment to various transients. It calculates a peak bulk tempor-ature for the suppression pool. The local temperature can be computed by adding to the bulk temperature an increment determined by existing applicable plant data; in this case 14 degrees from Kuosheng test data.

The 1imit for this temperature, as stated in NUREG-0783, is 200 F for quencher mass flux greater than 94 lbm/ f t* sec. For quencher mass flux less than 42 lbm/ft' sec., local temperaturo must be 20*F subcooled; considering the submergence depth of the quenchor for this plant that value is 210 F. Local temperature limits in between these two values are linearly interpolated.

All assumptions for these analyses are in accordance with NUREG-0783, Section 5.7.1 and other major assumptions are listed in Table 1. The transients analyzed are those described in Section 5.7.2. They are of throo main types; Stuck Open Relief Valves, Isolation / Scram, and Small Bruak Accidents. Details of these transients are in Tablo 2. The tabu-lated results for bulk temperatures are listed in Table 3. The highest bulk temperature calculated was 181 F for the isolation caso. The

addition of local to bulk temperature of 14*F determined by Kuosheng test data gives a local temperature of 195*F which is within the cri-terion described earlier. Perry has the same GE's X-shaped quenchers used in Kuosheng. The analyses and results are summarized in the following tables:

Table 1 Major Assumptions and Initial Conditions Table 2 SRV Transient Cases Table 3 Peak Suppression Pool Bulk Temperatures The Perry suppression pool temperature monitoring system meets the general design requirements of Section 5.8 of NUREG-0783.

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TAllLE 1 ASSUMPTIONS AND INITIAL CONDITIONS

1. Initial conditions for Perry are those specified in the Perry FSAR with the exception that the wat.or within the woir wall is not used as a heat sink.

2. Suppression pool temperature at the normal power operation Toch-nical Specification limit (95 F).

3. Foodwater pumps are operating and trip on an automatic signal.

4. In the event of a loss of off-sito power in conjunction with the loss of any one cmorgency bus, it is assumed that the available RilR loop can be '. witched from the pool cooling modo to the reactor shutdown cooling modo.

5. 10 minuto operator action to initiate RIIR pool cooling modo.

6. A switchover time of 16 minutos is allowed to switch from the pool cooling modo to the shutdown cooling modo.

7. When bot.h RilR loops are operating and shutdown cooling is avail-ablo, one RIIR loop is lett aligned in the pool cooling mode while the other is diverted to shutdown cooling.

8. Drywell fan coolers are initially available in SORV ovents and isolation events, lloweve r , it is assumed that the coolers will not operat.o to koop the drywell pressure below the high drywell pressure trip set point (~2 psig) af t.or RPV lower water level 2 is reached. Consequently, under appropriato initial conditions, I

TABLE 1 (Continued) the Rl!R will automatically switcli out of the pool cooling modo and line up in the low pressure coolant injection (LPCI) modo.

The RIIR system will have to be manually switched back into the pool cooling modo. Ten minutes are allowed for this action. Each caso is considered individually to see if this is applicable. For the small break cases which scram on high drywell pressure, this is assumed to occur at scram.

NOTE: The assump' ions in Section 5.7.1 of NUREG-0783 woro all used in this report.

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TABLE 2 DESCRIPTION OF SRV TRANSIENTS CASE 1A - STUCE OPEN SRV DURING POWER WITl! 1 RilR LOOP AVAILABLE.

. Event initiated by SORV occurring when pool temperature is at TS 1 (95*F).

. Operator initiates RilR in pool cooling mode.

. HilR operating 10 minutes later.

. At pool temperature of 110 F operator manually scrams reactor.

. The main condenser is available for approximately 20 seconds as a heat sink and can be reinstated at 1200 seconds at 30% steam-line flow if vessel pressure is above 125 psia.

. At pool temperature of 120*F, 3 additional SRV's are available to further depressurize the vessel at a cool down rate of 100 F/hr. ,

if necessary.

. When vessel pressure reaches the RIIR shutdown cooling permissive pressure of 134.7 psia, operator starts change over from.RllR pool cooling modo to vessel shutdown cooling mode. This action is assumed to take 16 minutes. There is no RllR on during this time.

Vessel pressure is maintained with SRV's if necessary.

. Transient ends shortly after shutdown cooling starts as decay heat is being removed by this method and no more energy is being added to the pool.

TABLE 2 (Continued)

CASE IB - SORV WITII HSIV CLOSURE WITl! 2 RllR LOOPS AVAILABLE.

. Similiar to Case 1A with these exceptions; 1) spurious MSIV closure disallows use of main condenser as heat sink and 2) given MSIV closure as second failure, no RilR's are assumed to fail.

4 CASE 2A - SRV DISCifARGE FOLLOWING ISOLATION / SCRAM Wi t li 1 RIIR LOOP AVAI LAB LE.

. Event is initiated by scram.

. MSIV closes 3.5 secoi.ds after scram.

. RIIR in pool cooling mode 10 minutes after scram.

. At pool temperature of 120*F, 3 additional SRV's are manuali; actuated to depressurize the vessel at a cooldown rate of 100 F/hr. or higher if necessary to keep pool temperatures within design limits.

When vessel pressure reaches the RIIR shutdown cooling permissive pressure of 134.7 psia, operator starts changeover of RllR loop to vessel shutdown cooling mode.

. During the assumed 16 minutes changeover time, vessel pressure is maintained by manual SRV control.

. At onset of shutdown cooling modo, pool no longer receives energy from vessel and transient is over. l l

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TABLE 2 (Continued)

CASE 3A - SRV DISCllARGE FOLLOWING SMALL BREAK ACCIDENT - 1 RilR AVAI LABLE .

. Event is initiated by small break in steamline.

. Scram occurs on high drywell pressure.

. Rapid vessel depressurization.

. Rest of the transient as described in Case 2A.

CASE 3B - SRV DISCIIARGE FOLLOWING SMALL BREAK ACCIDENT - 2 RIIR AVAILABLE LOSS OF Sl!UTDOWN COOLING MODE.

Similar to Case 3A with this exception; both RIIR loops are in the pool cooling mode 10 minutes after scram and stay in that modo throughout the transient.

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TABLE 3 PEAK SUPPRESSION POOL BULK TEMPERATURE PERRY NUREG ANALYSIS EVENT TEMPERATURE la. SORV at Power + 1 RHR and Condenser 154'F lb. SORV with MSIV Closure + 2 RHR 158'F 2a. Isolation / SCRAM + 1 RHR 181'F 3a. SBA + 1 RHR 176*F i

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j 3b. SBA + 2 RHR; Shutdown Cooling i

Mode Failure 151'F 1

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Cases la, Ib, 2a Vessel Normal Cooldown Rate.

Cases 3a and 3b, Vessel Rapid Cooldown~ Rate.

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