ML19282A426
Text
{{#Wiki_filter:, c, 8 "" 4 UNITED STATES ~ p y S NUCLEAR REGULATORY COMMisslON WASHINGTON, D. C. 20555 E ~s / JAN 19 B19 Docket Nos. 50-329/330 MEMORANDUM FOR: Darl Hood, Project Manger, LWR-4, DPM FROM: Gerald R. Mazetis, Section Leader, RSB, DSS
SUBJECT:
RSB OPEN ITEMS ON MIDLAND 1 AND 2 Your note of January 9,1979 requests that we prepare a list of all significant open items from our review of Midland. We continue to point out (see also our 12/27/78 memo from R. Tedesco to D. Vassallo) that an inordinate number of open items exist in the RSB areas. Late or incomplete responses have yet to be reviewed, several even from the Round One stage. To expedite transmittal of this list to your office, we have provided only a brief statement of the item since significant time would be required to provide the information you have requested in all areas. The open items are categorized into 4 groups: I. Items addressed in second round of questions (memo Tedesco to Vassallo dated Dec. 27, 1978) for which no responses have been received. II. Round One Questions which the applicant has not yet responded to, but has comitted to do so. III. 7tems for which we have recently received a Round One response, but have not completed the review. IV. Generic issues. Our list of RSB open items is attached as Enclosure 1. / Gerald R. Ma etis, Section Leader Reactor Systems Branch Division of Systems Safety [ (fy & nclosure: E As Stated cc: T. Novak k[.4 G. Mazetis r S. Newberry
Contact:
Scott Newberry, NRR 49-27341
~ .~ Midland 1 & 2 RSB Open Items Group I 1. Overpressure Protection (211.176) 2. Post LOCA Passive Failures (211.177) 3. BWSTVent(211.178) 4. Boron Dilution Dump to Sump Indication (211.179) 5. Containment Sump Level Indication (211.180) 6. DHR Pump Low Flow (211.181) 7. Check Valve Leak Testing (211.182) 8. Baron Dilution Events (211.183) 9. Auxiliary Feedwater Water Level Control (211.184)
- 10. Mai'i Steam Line Break (Single Failure, Process Steam) (211.185)
- 11. Process Steam Operating Modes - Chap.15 Analyses (211.186)
- 12. Cold Shutdown Requirements (211.35) (211.187)
Group II 13.
- siles Inside Containment (211.95)
- 14. Reactor Coolant Pump Mounting (211.100)
- 15. Pressurizer Safety Valves (211.104)
- 16. Appendix G Overpressure Protection (211.105) (211.110)
- 17. Pressurizer Heaters (211.112)
- 18. HPI Line Break Analysis (211.117)
- 19. BPRA and ORA Modifications (211.138)
- 20. FeedwaterLineBreak(211.153)
- 21. Main Steam Line Isolation Valve Closure Analysis (211.164) 2
- 22. Main Steam Line Break (211.166-211.175)
- 23. Overpressure Protection - BAW 10043 (9.11.147)
- 24. Small Break Fix/ Analysis (211.116)
- 25. Long Term Cooling After Main Steam Line Break (211.163)
~ O ~ Group III 26. LOCA Calculation - Reactor Coolant Flow Assumption (211.119)
- 27. Locked Rotor - Percent Fuel Pin Failure (211.149)
- 28. Loss of Flow Transiant Analysis (1 RCP.) (all.150)
Main Steam Line Break Operator Actions f 211.161) 29. 30. DHR and HPI Pump Trips (211.113) (211.115) 31. NPSH Calculation (211.118) 32. ECCS Sump Test 33. Partial Loop Operation (211.139)
- 34. Rod Worth Assumptions in Chaps.er 15(211.140)
- 35. Frequency Decay to Reactor Coolant Pumps (211.116) 36.
ECCS Shift to Recirculation (211.122) Group IV
- 37. ATWS 38.
Reactor Coolant Pump Overspeed q e =}}