NUREG-0519, Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves

Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves

ML20198D824
Person / Time
Site:	LaSalle
Issue date:	05/19/1986
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20198D816	List: NUREG-0519, Safety Evaluation of Final in-plant Safety/Relief Valve Test Evaluation Rept Per SER (NUREG-0519).Design Adequate to Accommodate Loads Associated W/Activation of One or More Safety Relief Valves
References
RTR-NUREG-0519, RTR-NUREG-519 NUDOCS 8605270072
Download: ML20198D824 (2)

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SAFETY EVALUATION RY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO IN-PLANT SRV TESTS COWONWEALTH EDISON COMPANY LA SALLE COUNTY STATION - UNIT 1 DOCKET NO. 50-373

1.0 INTRODUCTION

In our SER (Section 6.2.1.1 of NUREG-0519 I ), we identified the licensee commitment to perform comprehensive safety relief valve (SRV) in-plant testing. These test were performed at La Salle County Nuclear Power Statjon-Unit 1inDecgmber1982,inaccordancewithguidancginNUREG-0763 using a test plan that had been approved by the staff.

The SRV in-plant tests were performed to confirm the adequacy of the piping system desian to safely accommodate the hydrodynamic loads and thermal effects associated with SRV actuation. In addition, these tests were used to establish the difference between local and bulk pool temper-atures to demonstrate that a maximum local pool temperature specification of 200*F will not be exceeded. Our evaluation of the pool temoerature limit will be addressed in another SER.

2.0 EVALUATION The staff has reviewed the final report on the in-plant SRV test program which was completed on December 30, 1982, and submitted in September 1983.5 This program included 25 different discharge cases, with three or more trials performed for each test type, except for an extended blowdown test where two trails were obtained. Our evaluation of the licensee's SRV test results is that the licensee has met the goal of the plant specific test by confirming that the La Salle design is adequate to accommodate the dynamic loads associated with the actuation of the SRV(s). The test results indicated that none of the observed pressures exceeded the peak values used in the design of the structure. The goal of the test was confirmatory; that is, to verify the conservatism of a limited number of key features of generically established specifications. This was accomplished and the program is, therefore, acceptable.

3.0 CONCLUSION

S Basedonthestaffreviegofthecommitmentsmadebythelicensee,andof the licensee test report , we conclude that the licensee has sufficiently demonstrated the adequacy of the La Salle design to accommodate the loads associated with the activation of one or more SRVs and, therefore, has 5

fulfilled its commitment set forth in the SER r#2;=,gt q ga E

i. .*y 9 ,* e References

1. NUREG-0519, " Safety Evaluation Report related to the operatien of LaSalle County Station, Units 1 and 2," March 1981

2. NUREG-0763, " Guidelines for Confirmatory Inplant Tests of Safety-Relief Valve Discharges for BWR Plants" May 1981

3. Sargent and Lundy Engineers, "LaSalle County 1 In-Plant SRV Test Plan,"

Revision 4. October 27, 1980

4. Lin, C. C. et al., "BNL's Evaluation of LaSalle County In-Plant SRV Test

5. LaSalle County Station, Unit 1, "In-Plant SRV Test Final Evaluation Report," September 1983

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