ML20005B277
| ML20005B277 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/17/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Gary R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| NUDOCS 8107070055 | |
| Download: ML20005B277 (7) | |
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JLNI 1 7 1981 "LB#1 Rdg^ - ' TERA DEisenhut PDR JYoungblood LPDR SBurwell NSIC Docket Nos.: ISO MC MRushbrook TIC SHanauer ACRS (16) and 50-446 RVollmer TMurley a
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Mr. R. J. Gary Q
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RHartfield c/ N[(,ijd q-Executive Vice President OELD and General Manager 0IE (3)
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Texas Utilities Generating Company
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Dallas, Texas 75201
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Dear !!r. Gary:
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S"bject: Open Itens in Safety Review of Ceeanche Peak Stean Electric Units 1 and 2 As a result of the staff review of the Final Safety Analysis Report completed to date we have identified a list o-? open itens (see the enclosure) for which we require additional information.
In view of the large amount of additional information required at this tire, we do not believe that we will be able to issue the Safety Evaluation Report (SER) for Comanche Peak on the current schedule of June 11, 1981.
We have been working closely with your staff in an effort to resolve the identified open issues as rapidly as possible. We understand that your staff has initiated a crash program to subnit information on the bulk of the open issues by June 12, 1981. He will evaluate the situation early in the following week and advise you of our schedule for issuing the SER.
If you require any clarification on the list of open issues, please contact the NRC project nanager, S. B. Burwell.
Sir :erely, Original signed byf' Darrell G. Eisenhut, Director Division of Licensing Office of Huclear Reactor Regulation
Enclosure:
As stated cc: See next page 8107070055 81061 PDR ADOCK 05000 h
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81 sac ronw ais ne sm uncu ene OFFICIAL RECORD COPY
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Mr. R. J. Gary Executive Vice President and General Manager Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 cc:
Nicholas S. Reynolds, Esq.
Mr. Richard L. Fouke Debevoise & Liberman Citizens for Fair Utility Regulation 1200 Seventeenth Street 1668-B Carter Drive Washington, D. C.
20036 Arlington, Texas 76010 Spencer C. Relyea, Esq.
Resident Inspector / Comanche Peak Worsham, Forsythe & Sampels Nuclear Power Station 2001 Bryan Tower c/o U. S. Nuclear Regulatory Commission Dallas, Texas 75201 P. O. Box 38 Glen Rose, Texas 76043 Mr. Homer C. Schmidt Manager - Nuclear Services Texas Utilities Services, Inc.
2001 Bryan Tower Dallas, Texas 75201 Mr. H. R. Rock
_Gibbs and Hill, Inc.
393 Seventh Avenue New York, New York 10001 l
Mr. A. T. Parker Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230 David J. Preister Assistant Attorney General Environmental Protection Division P. O. Box 12546, Capitol Station Austin, Texas 78711 Mrs. Juanita Ellis, President Citizens Association for Sound Energy 1426 South Polk
)allas, Texas 75224 Dwiht H. Moore, Esq.
West Texas Legal Services 100 Main Street (Lawyers Bidg.)
l Fort Worth, Texas 76102 l
m.,
r COMANCHE PEAK OPEN ISSUES 1.
Stress limits for Class 7 and 3 piping bends and elbows.
2.
Inservice testing program for pumps and valves.
3.
Confirmation of analysis for asymmetric LOCA loads.
4.
Tornado missile protection for tops of outdoor tanks.
5.
Masonry walls inside seismic Category 1 s:ructures.
6.
Design basis groundwater level.
7.
Design of rip-rap on the SSI dam.
8.
Heave of claystone under seismic Category 1 buried piping.
9.
Reactor coolant pump flywheel inspection program.
- 10. Conformance of Unit 2 to 10 CFR Part 50, Appendices G and H.
- 11. Preservice inspection program, 10 CFR $50.55a(g).
- 12. Steam generator water chemistry program.
- 13. Turbine missile analysis assumptions.
- 14. Organic materials inside the containment building.
- 15. Spent fuel pool cleanup system.
- 16. Process sampling system.
17.
Post accident sampling; NUREG-0737, Item II.B.3.
- 18. Valve operability program for containment 18-inch vent valve; NUREG-0737, Item II.E.4.2.
- 19. Completeness of the FSAR Section 17 list of items under the control of the quality assurance program.
- 20. Emergency plans; NUREG-0654, Revision 1.
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- 21. - Emergency facilities; NUREG-0737, Item TII. A.1.2.
- 22. Direct indication of PORV and safety valve position; NUREG-0737, Item II.D.3.
23.
Instrumentation for detection of inadequate core cooling; NUREG-0737, Item II.F.2.
. 24.
Installation and testing of automatic PORY isolation system; NUREG-0737, Item II.K.3.1.
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- 25. N-16 power measurement system.
- 26. Loss of safety function after reset.
- 27. Level measurement errors due to environmental temperature effects on level reference legs.
- 28. Boron dilution control design modification.
- 29. Failure modes and effects analysis interface requirements.
- 30. Containment purge and fuel building isolation valves control.
- 31. Auxiliary feedwater system control.
- 32. Post accident monitoring; Regulatory Guide 1.97, Revision 2.
- 33. Bypass and inoperable status indication for safety related systems.
- 34. Loss of Non-Class IE instrumentation and control power system bus during operation; IE Bulletin 79-27.
- 35. RCS pressure control during low temperature operation.
- 36. Common electrical power sources or sensor malfunctions causing multiple control system failures.
- 37. Environmental qualification of control systems.
- 38. Locked rotor accident without offsite power.
39.
Isolation of CVCS pipe break outside containment.
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- 40. Temperature assumption in the upper head region for the LOCA analysis.
- 41. Manual reset of SIS in 2 minutes versus 10 minutes.
- 42. Low temperature overpressure protection with a failed DC bus.
- 43. Seismic qualification of the pressurizer PORV operator.
. 44. Seismic qualification of the steam PORY operators.
- 45. RHR system test and procedures for natural circulation per Branch Technical Position RSB 5-1.
- 46. Time to reach RHR system cut-in per Branch Technical Positior: RSB 5-1.
- 47. Boration to shutdown without CVCS.
50. Flooding of safety related equipment in the electrical and control building from breaks in the circulating water system.
51.
Internally generated missiles in the safety chilled water system area.
- 52. Flooding from a break in the condensate storage tank line or pipe tunnel.
- 53. Environmental qualification of the steam generator PORVs.
54.
Exclusion zone pipe break analysis.
- 55. Pipe break analysis for all safety related compartments.
- 56. Pipe break analysis for jet impingement.
- 57. Seismic design of spent fuel pool gates.
- 58. Movement of heavy loads by cranes; NUREG-0612.
- 59. Reactor coolant pump cooling on loss of component cooling water supply.
- 60. Radioactive release to evaporation pond through drains originating in auxiliary building.
- 61. Backflow flooding through drain system.
- 62. Fuel building ventilation system supply and exhaust.
- 63. Plant ventilation system exhaust line blockage.
- 64. Safety-grade controls for tne steam generator PORVs.
- 65. Waterhammer in the feedwater line to the steam generator.
- 66. Operation of the turbine driven auxiliary feedwater pump without ventilation.
.. 67. Waterhamner in the auxiliary feedwater system.
- 68. Auxiliary feedwater system availability, alarm on low water in the condensate storage water tank, and 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> test.
- 69. Tornado missile entry through building openings.
- 70. Control room ventilation system in isolation mode.
- 71. Automatic initiation and continuous operation of containment spray system.
- 72. The space for preshipment storage of solid radwaste is inadequate.
- 73. The solid radwaste system requires process control procedures.
- 74. The health physicist and radiological chemist should be organizational 1y separated.
- 75. Plant shielding for postaccident operations; NUREG-0737,~ Item II.B.2.
- 76. Containment high-range radiation monitor; NUREG-0737, Item II.F.1.3.
77.
Inplant radiation monitoring of radioiodine; NUREG-0737, Item III.D.3.3.
- 78. The 18-inch containment vent line requires a screen.
- 79. The setpoint pressure for containment isolation system actuation is not resolved.
- 80. Containment post-accident monitors for pressure, water level, and hydrogen; NUREG-0737, Item II.F.1.4,.5, 8.6.
- 81. The use of hafnium control rods.
82.
I ecorpc ation of rod bow penalty in operating limits.
- 83. Provision for management control and technical support of the plant by combined TUGC0 and TUSI organizational structure.
- 84. Size and qualifications of the corporate staff available to support the plant.
- 85. Health physicist access to plant manager.
- 86. Numbers of personnel on the plant staff by section and group.
- 87. Training program for non-licensed plant personnel.
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.. 88. Supplementing CPSES operating staff during startup and early operation.
- 89. The nunt>ers of cold license operator candidates.
- 90. Training of non-operating supervisors in operating procedures.
- 91. Staff training during low power testing; NUREG-0737, Item I.G.I.
- 93. Environmental qualification of safety-related electrical equipment, NUREG-0588.
- 94. Equipment qualification for seismic loads.
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