ML20037D163
| ML20037D163 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/15/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Aswell D LOUISIANA POWER & LIGHT CO. |
| References | |
| NUDOCS 8105220085 | |
| Download: ML20037D163 (7) | |
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.....*#p WAY 15 1981 Docket Nos.: 50-382 Mr. D. L. Aswell Vice President - Power Production Louisiana Power and Light Company 142 Delaronde Street New Orleans, Louisiana 70174
Dear Mr. Aswell:
SUBJECT:
OPEN ITEMS - WATERFORD 3 As a result of the staff review completed to date, the enclosed list of items identi-(1(s areas for which we require additional infomation. We will forward an updated list w you by May 18, 1981 which will include those areas of review which we expect to complete by May 15, 1981.
In view of the large amount of additional infomation required at this time, we do not believe that we will be able to issue the Waterford 3 SER on the current schedule of i9y 30,1981.
We request that you review the enclosed list and provide us with your schedule for providing the requested infomation. Your response should address all items individually and should be provided by May 20, 1981. Based on your response, we will then determine an issuance date for the Waterford 3 SER.
If you require any clarification, please contact the staff's assigned project manager.
Sincerely, I
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Darrell G.
senht.t Director i
Division of Licensing Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: See next page.
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Mr. D. L. Aswell Vice President, Power Production Louisiana Power & Light Comps::y 142 Delaronde~ Street N;w Orleans, Louisiana 70174 cc:
W. Malcolm Stevenson, Esq.
Monrne & Lemann 1424 Whitney Building New Orleans, Louisiana 70130 Mr. E. Blake Shaw, Pittman, Potts and Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 Mr. D. B. Lester Production Engineet Louisiana Power & Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Lyman L. Jones, Jr., Esq.
Gillespie & Jor.es P. O. Box 9216 Metairie,_ Louisiana 70005 Luk.e Fontana, Esq.
Gillespie & Jones 824 Esplanade Avenue New Orleans, Louisiana 70116 i
Stephen M. Irving, Esq.
One American Place, Suite 1601 Baton Rouge, Louisiana 70825 Resident Inspector /Waterford NPS P. O. Box 822 Killona, Louisiana 70066 l
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Open Items as of 5/13/81 (Including SER Section Number) 1.
Flood protection of safety related components in the cooling tower area (2.4.2.3) 2.
Fire Protection (8,3.3, 9.5.2, and 9.5.3) 3.
Diesel Engine Piping (9.5.4.2, 9.5.5, 9.5.6, and 9.5.7) 4.
Turbine Missiles (3.5.1.3 and 3.5.3) 5.
Qualification of in containment instrument cabinet heaters and associated controls (7.2, 7.3) 6.
Containment Isolation Actuation Signal diversity using low primary pressure (7.3) 7.
Emergency Feedwater Isolation on Main Steam Isolation Signal (7.3) 8.
Emergency Feedwater Control (7.3) 9.
Confonnance with R.G.1.47, Bypass and Inoperable Status Indication (7.5) 10.
IE Bulletin No. 79-21 (steam generator level measurement accuracy) (7.2, 7.3,7.5) l 11.
IE Bulletin No. 79-27 (safe shutdown following loss of an instrument bus)
(7.4,7.5,7.7)
- 12. Transfer to Spare ESF ' Pomp (7.1, 7.3)
I 13.
IE Bulletiri No. 80-06 (reset and override of engineered safety features)
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(7.3) 1
- 14. Monitoring Safe Shutdown (7.4)
- 15. RCP Shaft Break (modification of reactor protection system) (7.1, 7.2, i
l 7.3, 7.5) l
- 16. Containment Vacuum Relief System (7.6)
- 17. Single failure of Control System Study (7.7)
- 18. Operatica of Reactor Protective System with One Channel in Bypass (7.2)
- 19. Buffer Qualification (7.1, 7.2, 7.3)
- 20. Confonnance with R.G.1.118... Periodic Testing... (7.1, 7.2, 7.3)
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2-21. Core Protection Calculators (7.1, 7.2)
- 22. TMI Open Items - need design details (22)
- 23. Management Capabilities and Staffing (13.1 and 22)
- 24. Training - qualification of personnel and program (13.2)
- 25. Review and audit (of the three review groups) (13.4)
- 26. Shift Technical Advisor (22)
- 27. Shift Manning (22)
- 28. Post-Accident Sampling and Analysis Arta-Shielding (22)
- 29. Control of Heavy Loads (9.1.4)
- 30. Health Physics Instrumentation (12.5.2)
- 31. Performance of PWR Relief and Safety Valves (22)
- 32. Revised analysis of shield building is required (6.2.1)
- 33. Containment Pressure Monitors (6.2.1)
- 34. Reactor Vessel Support loads (6.2.1)
- 35. Analysis,of Secondary Containment (6.2.3)
- 36. Bypass leakage paths not treated by CVAS (6.2.3)
- 37. Classification af Containment Isolation System Yacuum Relief Lines (6.4.4) 38.
Isolation of Steam Generator Nitrogen Blanket Lines (6.4.4)
- 39. CVCS Charging line should not be locked open and should fail "as is."
l (6.4.4) l l
40.
Isolation provisions of the monitoring instrument lines of the vacuum relief sys tem.
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. 41. CCW Inlet and Outlet valves for RCP's and CEDM should fail "as is." (6.4.4)
- 42. Containment Leakage Testing (6.2.6)
- 43. Control Room (22)
- 44. Preservice Inspection Program (RCP Boundary, Reactor Vessel, and Class 2 and 3) (5.2.4 and 6.6)
- 45. Turbine disc inspection intervals (10.2.3)
- 46. Reactor Yessel Materials - Compliance with Appendices G and H (5.3.1)
- 47. Pressure-Temperature Limits (5.3.2)
- 48. Reanalysis of Category I structures (3.7.3)
- 49. Reevaluate foundation mat for changes in the value of the subgrade modulus (3.8.5)
- 50. Clad swelling and rupture analysis (ECCS and NUREG-0630) (4.2.2) 51. Rod Bow Penalty (4.2.2 and 4.4.1)
- 53. Fuel assembly post-irradiation surveillance program is deficient (4.2.3)
- 54. Reevaluate DNBR limit'(4.4.1)
- 55. CPC system commitments needed (4.4.1)
- 56. Emergency Planning (13.3)
- 57. Organic Materials - review total amount of unqualified protective coatings and organic materials used inside containment (6.1.2)
- 58. Post-Accident Sampling (22)
- 59. Exclusion area control (2.1.2)
- 60. Security plan (13.6) i
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- 61. Fire Protection (9.5.1)
- 62. Equipment Qualification (3.11) i
- 63. Seismic Qualification (3.10) 64.
Inservice inspection of pumps and valves (3.9.6)
- 65. Site hazards (2.2) t 1
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