ML20196F541

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Forwards List of Items Deleted from SEP Comprehensive List of Technical Issues & Reasons for Deletions.Requests Comments by 770427
ML20196F541
Person / Time
Issue date: 04/19/1977
From: Ziemann D
Office of Nuclear Reactor Regulation
To: Baer R, Butler W, Grimes B
Office of Nuclear Reactor Regulation
Shared Package
ML20196F442 List:
References
FOIA-87-854 NUDOCS 8803040106
Download: ML20196F541 (9)
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MP 191377 MEMORANDUM FOR:

Robert Baer, Chief, Reactor Safety Branch. OT/00R Walter Butler, Chief, Plant Systems Branch OT/ DOR '

Brian Grimes Chief. Environmental Evaluation Branch OT/00R Lawrence Shao, Chief. Engineering Branch OT/ DOR Darrell Eisenhut, Assistant Director for Operational THRU:

Technology, 00R l

Dennis L. Ziemann, Group Leader, Systematic Evaluation FROM:

Progran Review Group, OT/00R

SUBJECT:

SYSTEMATIC EVALUATION PROGRAM (SEP) FOR OPERATING NUCLEAR POWER PLANTS .

l By memorandua dated April 14, 1977, you received a first draft of aIn comprehensive list of topics for consideration in the SEP review.

generating that list the SEP Group eliminated only those items which j a consensus of the roup agreed were clearly not appropriate for The j

' inclusion in the SEP comprehensive list of technical issues. f  ;

items we deleted and the reasons for the deletions are given in the attactrient, e f

" J Please review the attached list to determine if you believe any of these l items should be included in the conprehensive list of topics for SEP

' consideration. Indicate your reasons for including any of these itens e in the comprehensive list by brief narginal coment. Again, please l ensure that the views of all technical reviewers in your Branch have been properly taken into consideration and please provide your Branch cor.itents to the SEP Group by COB April 27, 1977, -

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Oiche<cc2 O'(Tennis OA. L.A Ziemann, Group LeMe i Systematic Evaluation Progran Review Group .

Division of Operatinj Reactors attackent:

Initial neletions froo 5!'P Cm crehensive List cc w/attactrient:

See next paty 8803040106 080229 PDR FOIA PDR CONNOR87-654 4

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(I' CATEGORICAL CRITERIA FOR INITIAL DELETION OF TOPICS FROM SEP COMPREHENSIVE LIST CATEGORY a: NotwithinthescopeofreviewforSEP(i.e., topics not relating to operating reactors)

CATEGORY 6: Research and Development (i.e., includes topics currently under review but staff position not formulated) ,

CATEGORY Y: Refinement (includes methodology, evaluation techniques, and data collection to enhance staff capabilities)

CATEGORY 6: Non-technical, non-safety, duplications, generalizations EXAMPLE:

CATEGORY a: HTGR Sourci Term Parameters (Encl. B-263)

CATEGORY B: Calculatior of Constant Axial Offset Transients-BNL (Encl. B-110)

CATEGORY Y: Review of F, eign Reactor Operating Experience (Encl. B-324)

CATEGORY 6: Seismology ( ~L-ll8-20)

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c CATEGORY a

1. HTGR Source Term Parameters (Encl. B-263)
2. LMFBR Source Terms (Encl. B-267)
3. Steam /0xygen, Graphite / Fuel Reactions (Encl. B-124)
4. Fission Product Release and Transport (HTGR) (Encl. B-125) (TSAR-74)
5. Graphite Properties and Thermal / Irradiation Perfonnance (Encl. B-126)
6. HTGR Fuels Thermal Analysis Procedures (Encl. B-127)
7. Pressure Equalization System - GCFR (Encl. B-128)
8. LMFBR Fuel System Thermal Design Limits (Encl. B-129) -
9. LMFBR Fuel System Mechanical Design & Limits (Encl. B-130)
10. HTGR Fission Product Release Model (Encl. B-169)
11. Combustible Gas Control in HTGR Containments (Encl. B-247)
12. LMFBR Steady-State Thermal-Hydraulic Analysis (TSAR-83)
13. HTGR Accident Analysis (T3AR-99)
14. LMFBR Containment Structural Integrity (TSAR-122)
15. Design Criteria for HTGR Graphite Components (TSAR-130)
16. (TSAR-131)
17. HTGR StructuralAnalysis HTGR Containment Technology (TSAR-221)
18. Combustible Gas Control in HTGR's (TSAR-222)
19. LMFBR Fuel Cladding Design Limits (TSAR-36)
20. LMFBR Fuel Rod Performance Evaluation (TSAR-55)
21. LMFBR Cladding Chemical Compatibility (TSAR-66)
22. HTGR Performance & Reliability of Fuel Particles (TSAR-75)
23. Prototype Identification According to R. G. 1.20(102 List-24A) i 24. Personnel Exposure Due to Pressure Relief Valve Venting in BWR-6 Containment Structures (Encl. B-212) 4 S

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CATEGORY S

! 1. International Safety Criteria Review (including Germany) (Encl. B-322)

2. Design Guidance for Radwaste Systems for Offshore Nuclear Power Plants (Encl. B-269)
3. Intra-cycle Core Physics (Encl. B-101)
4. Calculation of Load Following - BNL (Encl. B-102)
5. Analysis and Reduction of Incore Measurements (Encl. B-107)
6. Calculation of Rod Insertion Limits - BNL (Encl. B-109)
7. Calculation of Constant Axial Offset Transients - BNL (Encl. B-11,0)
8. Vendor Transient Analysis Codes (Encl. B-112)
9. Vendor Models for Plutonium Recycle Fuel (Encl. B-119)
10. Hybrid Reactor Protection System (Encl. B-79
11. Short Distance Diffusion Model (Encl. B-202)) (TSAR-244)
12. Earthquake Fault Age Studies (Encl. B-190)
13. Hurricane Data Collection (Encl. B-198)
14. Effect of Building Wakes on Plumes from Vents (Encl. B-206)
15. Waterspout Climatology (Encl. B-207)
15. Laboratory soil Testing (Encl. B-188)
17. Containment Code Development (TSAR-79)
18. Compare Code Development (TSAR-196)
19. Marviken Test Data Evaluation (TSAR-199)
20. GESMO: Behavior of Mixed Oxide fuel (TSAR-34) 21.
22. Qualification of New for Fixed Incore Detectors Fuel DesignsPWR's High-Power (TSAR-35) (Encl. B-96)
23. Development of In-House BWR and PWR Physics Calculation Capability (Encl. B-104) (Encl. B-98) (TSAR-38) ~
24. Required Physics Test (Encl. B-99)
25. Development of In-House Reactor Kinetics Calculation Capability M (Encl. B-105) (TSAR-39)
26. Completeness of the Review of Plants Referencing RESAR-3 (Encl. B-56)
27. Peridoic Comprehensive 10-Year Review of Operating Power Reactors (Encl. B-78)
28. Occupational Radiation Dose Assessment Methods for Nuclear Facilities (Design Stage) (Encl. B-216)
29. Revise Appendix K (TSAR-94)
30. Contempt Code Modification (TSAR-207) 31: Two-PhaseFlowImprovmentsinTWIGL(TSAR-28)
32. Two-Phase Instrumentation Review (TSAR-102) 33.
34. Development of Advanced Evaluation of Adequacy of ASMEFracture Section XIMechanics Methods (Encl. B-298)(En Code NDE Requirements
35. Fracture Toughness Testing (TSAR-179)
36. Strain Aging of Reactor Vessel Steels (TSAR-185) '
37. Stress Relief Cracking of RV Steels (TSAR-186)
38. Reliability of Ultrasonic Testing for Austenitic Weldments (TSAR-166)
39. Fracture Mechanics of High Temperature Materials (TSAR-177)
40. Effects of Accelerated Irradiation on RV Materials (TSAR-178)
41.Section III, Stainless Steel Design Fatigue Basis (102 List - 24F)
42. Radiation Damage Technology Improvements (Encl. B-296)
43. Failure Modes for Stainless Steel Components (Encl. B-300)
44. Pipe Break Probability Study (Encl. B-282-)
45. Evaluation of Acoustic Emission and Other Advanced NDE Techniques (Encl. B-279)

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CATEGORY a (CONTINUE 0)

46. Evaluation of Plugging Criteria (Encl. B-150)
47. Failure Probabilities ofSteamGeneratorTubes(TFL118-97)(Encl.B-159)

(Encl. B-306) ,

48. Vendor Pump and Valve Operability Programs (TSAR-146)
49. Evaluation of Test Results of Tangential Shear in Concrete (TSdR-104)
50. Ductility of Two-Way Slabs and Shells (TSAR-107)
51. Buckling Behavior of Steel Containments (TSAR-109)
52. Adequacy of Threaded Rebar Couplers (TSAR-ll7)
53. Development of Generalized Distantly Generated Tsunami Parameters (Encl. B-199)
54. Development of Generalized Locally Generated Tsunami Parameters (Encl. B-200)
55. Advisability of Seismic Scram (Encl. B-71) (TSAR-116)
56. Subsurface Exploration Methodology (Encl. B-187)
57. Seismic Probabilities (Encl. B-191)
58. Effect of Burnup on Thermal Conductivity (TSAR-56)
59. LWR Fuel Thermal Expansion Models (TSAR-59).
60. Behavior of Water Logged Fuel (TSAR-65)
61. Acoustic and Neutronic Noise Monitoring (102 List - 47)
62. Noise Analysis (Encl. B-100)
63. Acoustic Emission (TSAR-180)
64. Use of ASME BPV Code Section III Subsection NF (TSAR-155)
65. Revise ASME BPV Code Section III Appendix F (TSAR-157)
66. ECCS Capability for Future Plants (Encl. B-72)
67. ECCS Evaluation Model Development (TSAR-76) g 68.

69.

Upper Head Injection Model (TSAR-82)

70. VendorProtection Computer ECCS Evaluation Model (TSAR-98))

System (Encl. B-51

71. Testing of Reactor Trip System and Engineered Safety Features (TFL 118-42)
72. Shared Safety and Service Systems for Multiple Unit Facilities (TFL 118-44)
73. Effects of Failure in Non-Safety Related Systems Curing Design Basis Events (TFL 118-56) ,
74. Core Protection Calculator (TSAR-87) i
75. Review of New Infonnation for Air Cleanup Systems (Encl. B-264) i
76. Review of Naval Research Laboratory Charcoal Adsorber Test Results 1 (Encl. B-271)
77. Review of Reg. Guide 1.11 (TSAR-217)
78. Subcompartment Standard Problem (TSAR-197)(Encl. B-226)
79. Revision of Proposed Regulatory Guide 1.BB and 1.CC (Enclx B-260)
80. Low lodine Concentration Adsorption Efficiency Test Evaluation (Encl. B-265)
81. Preparation of Proposed Regulatory Guide on Effluent and Process  !

Monitoring Instrumentation (Encl. B-262)

82. System Reliability Studies (Encl. B-258) (TSAR-234)
83. NRC Small Break Evaluation Model (Encl. B-ll4)
84. Vendor Small Break ECCS - ME (Encl. B-ll5)
85. NRC Large Break Evaluation Model (Encl. B-ll6)
86. Improved Reliability of Target Rock Relief Valves (Encl. B-152)
87. Enhanced Fission Gas Release at High Burnup (Encl. B-302)
88. GE ECCS Model Errors (Encl. B-303)  ;
89. Event Categorization (TSAR-3) l l

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90. Decontamination of Decomissioning of Reactors (Encl. B-85)
91. Effects on Utility Transmission Systems of the Explosion of ,

a Large Nuclear Weapon (Encl. B-63) . l

92. Establish an Acceptable PWR And BWR Main Steam Line Valves Design Basis (Functional) (Encl. B-253)

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93. Standard Nuclear Data for Dose Calculations (Encl. B-183)
94. Containment Purging During Norical Plant Operations Study (Encl. B-228) i
95. Aircraf t Crash Statistics (Encl. B-176) 1 l

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C CATEGORY Y

1. Standard Plant Interface Format (Encl. B-257)
2. Standardization and Com Writeups (Encl. B-268) puterization of PWR and BWR DES and SER
3. ReviewofForeignReactorOperatingExperience(Encl.B-324)
4. Guide for Reload Application', (Encl. B-97)
5. Standard Review Plan and MM,agement Guide for Core Reload Application Reviews (Encl. B-106)
6. NRC Transient Analysis Code (Encl. B-111)
7. Statistical Assessment of LOCA (Encl. B-117)
8. Updating Regulatory Guide 1.59 (Encl. B-194)
9. Cooling Tower Plume Model Assessment (Encl. B-211)
10. Proposed ANSI-N45.4, Reactor Containment Leak Testing (Encl. B-236) 11.
12. AAB Computer Code Development and Maintenance (Encl. B-184)(TSAR-Identify)SRP's to be(TSAR-247)

(TSAR-37 (TSAR-229) Revised(TSAR-262)

(TSAR-92) (TSAR-110) (TSAR-6)

13. Verification of Structural Engineering Computer Codes (TSAR-121)
14. Comparison of Linear and Non-Linear Time History Methods of Dynamic Analysis (TSAR-129)
15. Mark III Test Program (TSAR-198)
16. Containment Component Demonstration Tests (TSAR-208)
17. Reference Safety Evaluation Report (TSAR-216)
18. Containment Analysis Guidelines (TSAR-218)
19. Event Categorization (TSAR-3)
20. ECCS Outage Requirements (TSAR-17)
21. MCPR/DNBR Calculation Capability (TSAR-29)
22. Decay Heat Update (TSAR-46)
23. LOCA Heat Sources (TSAR-47)
24. Standard Tech Spec Coordination (TSAR-50)

E 25. B&W Standard Tech Specs (TSAR-51)

26. BbH Standard Tech Specs (TSAR-52)
27. Westinghouse STOL Tech Specs (TSAR-53)
28. Tech Specs - Concepts and Principles (TSAR-67) -
29. B&W, GE, CE. Topical Reports (Planning) (TSAR-70) (TSAR-71)(TSAR-72)
30. Study (TSAR-73)
31. LhR FuelProblem Standard Local Uncertainty Analysis (TSAR-85)
32. Semiscale Test Results (TSAR-90)
33. Equal Risk Assessment Methodology for Dispersion Conditions During Accidents (Encl. B-204)
34. Non-Linear Seismic Analysis (TSAR-108)
35. Analysis Techniques (102 List - 388)
36. Fuel Operating Experience (Encl. B-274 (TSAR-60) ,

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CATEGORY 6

1. Seismic Re-evaluation of Operating Plants (Encl. B-284)
2. Seismology (TFL118-20)
3. Definition of Seismotectonic Province in Eastern U. S. (Encl. B-189)
4. Geology (TFL 118-19)
5. Foundation (TFL 118-21)
6. Analysis of the Interaction of Structions and the Supporting Soil (Encl. B-55)
7. Evaluation of Soil-Structure Interaction During Earthquake (TSAR-106)
8. Repair Programs (102 List - 23G)
9. Pressure Vessel Integrity (TSAR-161)
10. Austenitic Stainless Steel Piping (TFL 118 - 80)
11. Bimetallic Welds (TFL 118 - 80)
12. Feedwater System Pipe Breaks (TFL 118 - 101)
13. Piping Pre-Operational Test Program (TSAR-136)
14. Pipic.9 Benchmark Problems (TSAR-138)
15. Hic,n Energy Line Break (Encl. B-19)
16. Pro?.ection Against Postulated Piping Failures in Fluid Systems Outside Concainment(TSAR-232)
17. Snubber Design Requirements (TSAR-148)
18. Bundle Replacement Technique and Logics (Encl. B-292)
19. Design Codes (102 List - 30A)
20. Design Criteria (102 List - 308)
21. Design Codes (102 List - 310) (Encl. B-243) (TFL 118 - 83)
22. Design Criteria (102 List - 31E) (TFL 118 - 83)
23. Inservice Inspection of Prestressed Concrete Containments with Either Grouted or Ungrouted Tendons (TFL 118 - 84) (TSAR-127)
24. Updating of Hurricane Design Parameters (Encl. B-197)
25. Marine Shipping Accident Statistics (Encl. B-177) g 26. Structural Response from Turbine Missile Criteria for Spent Fuel Pools (TSAR-ll3)
27. Pool Swell (102 List - 36A)
28. MSRV (Encl. B-240)
29. Mark 1 Containment STP Technical Specification (Encl. B-25)

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30. Mark I Containment Evaluation STP, LTP (Encl. B-24) (Encl. B-25)
31. Mark I Safety Relief Valve Line Restraints in the Torus (Encl. B-26)
32. Mark 1 Torus Capability - Temperature Limits (Encl. B-27)
33. Determination of LOCA Dynamic Loads for BWR Containment (TSAR-192)
34. Operability of Rotating Machinery Following a Seismic Event (TSAR-16) (Encl. B-307)
35. Qualification of Steam S/V for Dynamic Loads (TSAR-147)
36. Safety / Relief Valve Requirements (TSAR-lS8)
37. Functional Design of Reactivity Control System (Operating. Shutdown, and Refueling Modes) (102 List - 48)
38. Protection Against Single Failures in Rear tivity Control Systems (Encl. B-44) (TSAR-245)
39. Improvement of BWR Shutdown Reactivit
40. Boron Addition Systems (TFL 118 - 22)y Performance (Encl. B-62)
41. Requirements for Isolation of high and Low Pressure Systems (TSAR-9)
42. ECCS Re-evaluation (Encl. B-7)
43. Pressure in Containment Following LOCA (Encl. B-73) (TSAR-190)

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CATEGORY 6 (CONTINUED)~

44. Containment Post-LOCA Temperature (Encl. B-277)
45. Improving the Availability of Offsite Power (Encl. B-60) (TSAR-260)
46. PostAccidentInstrumentation(TSAR-7)
47. Fire Protection Systems (TSAR-224)
48. SpentFuelPoolRequirenents(TSAR-23)
49. Cooling Water System Makeup Water Requirements (For Safety Systems).

(Encl. B-256) -

50. Adequacy of Provisions to Provide Physical Separation of Component Cooling Water Systems Which are Vital to the Performance of Engineered ,

Safety System Components (Encl. B-312 (TSAR-227) (TSAR-16)

51. Auxiliary FeedwaterSSystem (PWR) - Functional Performance (TSAR-228)

(Encl. B-249)

52. Appendix I - ALARA (TFL 118 -10)
53. Water Hamer - PWR and BWR (Encl. B-86) (TSAR-5)
54. Mass and Energy Release to Containment (Encl. B-118)

.. 55. Behavior of Mark III Containment (Encl. B-81)

56. Seismic Category I Requirements for Radioactive Gas Systems (Encl. B-185)
57. Multiplexing - Use in Control and Safety-Related Systems (Encl. B-139)
58. Solid Fission Product Release Model (Encl. B-170)
59. Minimum Containment Pre-sure (TSAR-214)
60. Requirements for Power Operated Relief Valves in Secondary Systems (TSAR-235)
61. Circulating Water System Barrier Failure Protection (TSAR-238)
62. Ovepressurization During Startup and Shutdown of PWR's (TSAR-1)
63. Manual Valve Position Requirements (TSAR-18)
64. Reactor Coolant Break Accident Analysis (TFL 118-112)
65. RHR System Oveprotection (TFL 118 - 61)
66. Chemical Decontamination (TFL 118 - 82) ggy 67. Nuclear Plant Personnel Qualification (TFL 118 - 8) e t

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