ML20004D890
| ML20004D890 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/08/1981 |
| From: | Colbert W DETROIT EDISON CO. |
| To: | Kintner L Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM EF2-53491, NUDOCS 8106100269 | |
| Download: ML20004D890 (3) | |
Text
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Dear Mr. Kintner:
Ref erence:
Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341 Subj ect:
Amended FSAR Appendix H, Section H.II.D.1.3 Response, Safetv/ Relief Valve Test Requirements To comply with the Mechanical Engineering Branch position on NUREG -
0737, II.D.1 for SR/V test requirements, Edison has revised its position stated in Appendix H, Section H.II.D.1.3.
A draft of the revised FSAR section is included in the attachment to this letter.
Should you have any additional questions, please contact Mr. D. F. Lehnert (313-649-7583).
Sincerely, if W. I. Colbert Technical Director Fermi 2 Proj ect DFL/sim Attachment 1
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o ATTACMfENT FOR EF2-534 H H.II.D.l.3 Detroit Edison Position On September 17, 1980, the BWR Owners' Group submitted documents entitled NUREG - 0578 BWR Saf ety/ Relief Valve Test Description and Event Evaluation f or BWR Saf ety Relief Valve Testing Required by NUREG - 0578, 2.1.2 (Reference 1).
The test program description and basis described in this submittal is applicable to Fermi 2 and is endorsed by Detroit Edison.
The results of the BWR Owners' Group evaluation indicate that there is ona event and single-failure combination that would lead to the discharge of liquid from the safety / relief valves. This event and single-failure combination lead to the alternate shutdown mode of operation that uses the saf ety/ relief valves as a return flow path for low-pressure liquid to the suppression pool. The evaluation demonstrates that all other events postulated to produce liquid or two-phase saf ety/ relief valve flow, including events under high-pressure conditions, are either of suf ficiently low probability or that consequences are concluded to be acceptable. As such, no testing is needed for these events.
The BWR Owners' Group testing program includes the testing of ty-pical saf ety/ relief valves for BWR/2 through BWR/6 plants to demon-strate the ability to perform satisfactorily under the condition in which low-pressure (i.e., up to 250 t'20 psig) water passes'through the valve-instead of saturated steam. This corresponds,to condi-tions expected during the alternate shutdown cooling mode, that is, the mode in which low-pressure pumps are inj ecting cold water into the reactor vessel and this water is vented through the saf ety/ relief valves back to the suppression pool. A plant-specific evaluation of the test data correlated the generic program test conditions to the alternate shutdown cooling mode conditions for Fermi 2.
The preliminary saf ety/ relief valve (S/RV) operability test results demonstrating that the Fermi-2 S/RV satisfies the acceptance criteria for operability is to be submitted to the NRC by July 1,1981. The final test report is to be submitted to the NRC by October 1,1981.
The evaluation of the associated discharge piping is to be submitted by January 1, 1982. In addition, Edison will participate in develop-ment of any additional information applicable to the Fermi-2 docket with respect to S/RV operabLlity and system functionability on a sch-edule consistent with that agreed to between BWR Owners Group and the NRC staff.
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(with attacleents)
T. A. Alessi
-E. L. Alexanderson-R. M. Berg J. H. Casiglia --
W. J. Fahrner
- F. E. Gregor l
E. P. ' Grif f ing J...W. Honkala-W. H. Jens E. Lusis 1
-P. A. Marquardt L. E.'.Schuerman H., Tauber
.R. A. Vance-A. E. Wegela D. F. Lehnert J. W. Nunley
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