ML20127A561
| ML20127A561 | |
| Person / Time | |
|---|---|
| Site: | Perry, Clinton, 05000000 |
| Issue date: | 08/17/1982 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Booker J GULF STATES UTILITIES CO. |
| Shared Package | |
| ML20127A517 | List: |
| References | |
| 850817, NUDOCS 8506210176 | |
| Download: ML20127A561 (5) | |
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g UNITED STATES g
NUCLEAR REGULATORY COMMISSION 5
j WASHINGTON, D. C. 20555 O
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AUG 171982
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Mr. James E. Booker Gulf States Utilities P. O. Box 2951 Beaumont, Texas 77704
Dear Mr. Booker:
Subject:
Status of LRG II Issues Enclosed is a Licensing Review Group II (LRG II), report regarding the NRC review status of the'56 LRG II issues.
A total of 40 issues are resolved,11 remain unresolved and 5 have been determined to be non-generic and are being addressed on the individual plants. Additionally, a revised listing is provided of the section of the Perry Safety Evaluation Report (SER) identifying where the issue is addressed by the staff.
17, 1982, LRG II provided positions on t e last of the issues. We h
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On Mayplan to address these issues in a future supplement to the Perry SER.
Sincerely.
b Thomas M. Novak, Assistant Director for Licensing Division of Licensing
Enclosure:
As stated cc: See next page 0
8506210176 850619 PDR ADOCK 05000461 E
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Mr. James E. B2cker 2-gg77
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cc: w/ enclosure:
h Mr. Bill J. Reed Gulf States Utilities P. O. Box 2951 Beaumont, Texas 77704 Mr. Roger S. Boyd KMC 1747 Pennsylvania Avenue, N.W.
Washington, D. C.
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Compilation of LRG-II Generic Issues Perry Issue SER Issue No.
Title (TMI Action Plan Item)
Status
- Section 1-RSB Autorestart of HPCS After Manual Termination R
7.3.2.1 (II.K.3.21) 2-RSB Design Adequacy of RCIC (II.K.3.13)
R 5.4.1, 6.3.1.3 3-RSB Commitment To Participate in S/RV Surveillance R
5.2.3 Program 4-RSB
~ Operator Actions Required 10-20 Minutes R
6.3.3 Following a LOCA (II.K.3.18) 5-RSB Control of Post-LOCA Leakage To Protect R
6.3.1.3 ECCS and Preserve Suppression Pool Level 6-RSR Applicability of Liquid-Flow-Through-S/RV Test R
5.4.2 7'RSB Provisions To Preclude Vortex Formation R
Appendix C, A-43 8-RSB Long-Term Air Supply to ADS R
5.4.2 9-RSB Long-Term Operability to ECCS Pumps A
10-RSB.
LOCA Analysis With Subr.2quent Flow Control R
6.3.3 Valve Closure 11-RSB Use of Nonsafety-Grade Equipment in Shaft R
15.2 Seizure Event 12-RSB Classiff' cation of Transients:
Turbine Trip w/o R
' 15.1 Bypass an'd Generator Load Rejection y/o Bypass 1
13-RSB ECCS Valve High Pressure Interlock R
6.3.1.3 1
1-CPB Ballooning and Rupture of Cladding R
4.2.3.3 2-CPB Seismic and LOCA Loads on Fuel A
4.2.3.2 4.2.3.3 3-CPB Channel Box Deflection A
4.2.3.1 4-CPB High Burnup Fission Gas Release R
4.2.3.3 5-CPB Cladding Water-Side Corrosion R
4.2.3.1 6-CPB Inadequate Core Cooling (II.F.2)
A
'4.4.7.2 7-CPB Rod Withdrawal Transient Analysis R
15.4.2 1
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Perry Issue SER Issue No.
Title (TMI Action Plan Item)
Status
- Section 8-CPB Fuel Analyses for Mislocated or R
15.4.3 Misoriented Bundles 9-CPB Discrepancy in Void Coefficient Calcolation R
4.3.2.2 10-CPB Rod Worth:
Bounding Accident Analysis R
' 15.4.4 11-CPB Hydrodynamic Stability Analysis (license R**
4.4.4 condition) 1-CSB Pool Dynamic Loads R
6.2.1.8 2-CSB Hydrogen Generation and Control A
6.2.7 1-AEB MSLIV.8ypass Leakage Rate R
15.3.1 1-ASB BWR Scram Discharge Volume R
4.6 2-ASB '
Safe Shutdown for Fires NG 9.5.1 3-ASB Protection of Equipment in Main Steam R
3.6.1 Pipe Tunnel
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4-ASB De' sign Adequacy of RCIC Space Cooling R
9.4.5.3-n v
1-RAB Exposure Resulting From Actuation of S/RVs R
12.4 2-RAB Routine Exposures Inside Containment R
12.2.1 3-RAB,
Controlling Radioactivity During Steam Dryer R
12.2.1 and Steam Separator Refueling Transfer 4-RAB Shielding of Spent Fuel Transfer Tube NG 12.3.2 and Canal 1-ICSB -
Failure in Vessel Level Sensing Lines. Common A
7.7.2.3 to Control and Protection Systems 2-ICSB Interlocks Isolating High and Low Pressure R
7.6.2.1 Systems 3-ICSB Potential for Both Low-Low Setpoint R
7.6.2.2 Valves To Open
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4-ICSB Loss of Safety Function After Reset R***
7.3.2.5 5-ICSB Control Systems Failure NG 7.7.2.1 6-ICSB Procedures Following Bus Failure NG 7.5.2.4 7-ICSB Harsh Environment for Electric Equipment NG 7.7.2.1 Following High-Energy Line Breaks
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- Perry
-O Issue SER Issue No.
Title (TMI Action Plan Item)
Status
- Section 1-PSB Reliability of Diesel Generators R****
9.6.3 1-GIB InterimLicensingBasesPendingResoDtion R
. Appendix C 1-HFS Special Low-Power Testing Program (I.G.1)
R 2-HFS ATVS Emergency Operating Procedure A
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13.5.2.2 and GE Reactivity Control Guidelines 3-HFS Common Reference for Reactor Vessel Level A
18 Measurement 1-CHEB ReactdrCoolantSampling A
9.3.2 2-CHEB Suppression Pool Sampling A
9.3.2 3-CHElf Estimation of Fuel Damage From Coolant and A
9.3.2 Pool Sampling 1-MEB ~
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Use of SRSS for Mechanical Equipment R
3.9.3.1 2-MEB RPV Internals Vibration Assessment Program R
3.9.2.3 3-MEB OBE Stress Cycles Used for NSSS Mechanical R
3.9.1 Equipment Design 1-MTEB.
Inspectability of Welded, Flued lleads R
3.6.2 1-SEB Combination of Loads R
2-SEB Fluid / Structure Interaction R
- R - Resolved A - Unresolved NG - Determined to be non generic subsequent to compilation of issue list.
- Resolved through first cycle of operation
- Resolved for GE scope of design; unresolved for balance-of plant design aspec,ts
- Resolved; requires design modifications and procedural changes prior to first refueling e
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