ML20127A561

Forwards Licensing Review Group II Rept Re Review Status of 56 Issues.Forty Issues resolved,11 Unresolved & 5 Determined Nongeneric.Revised List,Identifying Where SER Issue Addressed Also Encl

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: ML20127A561 U-600065, Provides Info on Compliance W/Requirements of SER (NUREG-0853),dtd Feb 1982,re safety-relief Valve Surveillance Program,For Use by NRC to Close Issue. Procedures Instituted to Detect Valve Condition Listed
References
850817, NUDOCS 8506210176
Download: ML20127A561 (5)

Text

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[ */ g UNITED STATES

.!5 g NUCLEAR REGULATORY COMMISSION j WASHINGTON, D. C. 20555 O %,..... / AUG 171982

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Mr. James E. Booker Gulf States Utilities P. O. Box 2951 Beaumont, Texas 77704

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 ht e last of the issues. We On Mayplan to address these issues in a future supplement to the Perry SER.

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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 PDR p

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Mr. James E. B2cker gg77

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cc: w/ enclosure:

h Mr.GulfBillStates J. Reed Utilities P. O. Box 2951 Beaumont, Texas 77704 Mr. Roger S. Boyd KMC 1747 Pennsylvania Avenue, N.W.

Washington, D. C. 20006

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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 n

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• Perry

-O Issue No. Title (TMI Action Plan Item)

Issue SER 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 -

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2-HFS ATVS Emergency Operating Procedure A 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

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Use of SRSS for Mechanical Equipment 1-MEB ~ .

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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