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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20057F2261993-09-30030 September 1993 Safety Evaluation Supporting Exemption Request from Requirements of 10CFR50.54(q) for License NPF-82 ML20056C7181993-07-14014 July 1993 SE Supporting Amend 10 to License NPF-82 ML20056A2001990-07-31031 July 1990 Safety Evaluation Supporting Amend 6 to License NPF-82 ML20055E3911990-06-25025 June 1990 Safety Evaluation Supporting Amend 5 to License NPF-82 ML20235M1941989-02-0808 February 1989 SER Accepting Util Response to NRC Bulletin 88-005 Re Identifying,Locating & Testing Nonconforming Flanges & Fittings Supplied by Piping Supplies,Inc,West Jersey Mfg Co & Chews Landing Mfgs ML20196E5961988-11-30030 November 1988 Safety Evaluation Supporting Amend 10 to License NPF-36 ML20196B6831988-11-30030 November 1988 Safety Evaluation Supporting Amend 9 to License NPF-36 ML20155F3531988-10-0606 October 1988 Safety Evaluation Supporting Util 870414 Request for Authorization to Increase Power to 25% of Full Rated Power W/Listed Conditions.Licensee Evaluation of Operation & Proposal for Inspecting Components Must Be Augmented ML20155F3431988-10-0606 October 1988 Safety Evaluation Supporting Util Request to Operate Facility at 25% Power Re Accident Evaluation ML20155F3381988-10-0606 October 1988 Safety Evaluation Supporting Util Request for Authorization to Operate Facility at 25% Power Re Sys & Procedures for Accident Mitigation ML20154K0101988-09-19019 September 1988 Safety Evaluation Supporting Util 840309,850621 & 860606 Responses to Generic Ltr 83-28, Required Actions Based on Generic Implication of Salem ATWS Events, Items 3.1.1, 3.1.2,3.2.1,3.2.2 & 4.5.1 ML20154F4031988-09-14014 September 1988 Safety Evaluation Supporting Request to Operate Facility at 25% Power Re Safety of Prolonged Operation at 25% Power ML20154F3951988-09-14014 September 1988 Safety Evaluation Supporting Request to Operate Facility at 25% Power Re Accident Evaluation ML20154F3921988-09-14014 September 1988 Safety Evaluation Supporting Request to Operate Facility at 25% Power Re Sys & Procedures for Accident Mitigation ML20154R9391988-05-31031 May 1988 Safety Evaluation Supporting Plant Primary Property Damage Insurance Exemption ML20236F7141987-10-19019 October 1987 Safety Evaluation Supporting Amend 8 to License NPF-36 ML20234B8201987-09-14014 September 1987 SER on Util 830414,851023 & 860227 Responses to Generic Ltr 82-33 Re post-accident Monitoring Instrumentation Meeting Requirements of Reg Guide 1.97 as Applied to Emergency Response Facility ML20237G4701987-08-14014 August 1987 Safety Evaluation Supporting Amend 7 to License NPF-36 ML20214K3961987-05-18018 May 1987 Safety Evaluation Supporting Amend 6 to License NPF-36 ML20215M4181987-05-0404 May 1987 Safety Evaluation Supporting Amend 5 to License NPF-36 ML20211N5921986-12-0909 December 1986 Safety Evaluation Supporting Amend 4 to License NPF-36 ML20213D5001986-11-0303 November 1986 Safety Evaluation Supporting Amend 3 to License NPF-36 ML20205E0601986-08-0101 August 1986 SER of Tdi Owners Group Program to Validate & Upgrade Quality of Tdi Diesel Generators for Nuclear Emergency Standby Svc.Technical Solution Available to Address Problem ML20154L9801986-03-0404 March 1986 Safety Evaluation Supporting Amend 2 to License NPF-36 ML20138N6701985-12-0606 December 1985 Safety Evaluation Supporting Amend 1 to License NPF-36 ML20058E1851982-07-15015 July 1982 Safety Evaluation Supporting Order Extending Const Completion Date to 830331 1993-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20135D8011996-11-26026 November 1996 Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced ML20080G4691995-01-26026 January 1995 Record of Telcon W/Nrc & Licensees 950126 to Clarify Position Re Dispositioning of Exempt Sources Listed in Section 6.3.3 of Shoreham Termination Survey Final Rept Dtd Oct 1994 05000322/LER-1994-001, :on 940121,determined That Violation of Tech Spec 6.7.3.c Occurred.Caused by Failure to Follow Administrative Procedure on Control of Station Procedures. Temporary Procedure Change Reviewed & Approved1994-02-14014 February 1994
- on 940121,determined That Violation of Tech Spec 6.7.3.c Occurred.Caused by Failure to Follow Administrative Procedure on Control of Station Procedures. Temporary Procedure Change Reviewed & Approved
05000322/LER-1993-002, :on 931228,fire in Primary Containment Occurred Which Required Evaluation & off-site Fire Department Assistance.Caused by Uncovered Opening in Bioshield Wall in Slag Path.Procedures Revised1994-01-25025 January 1994
- on 931228,fire in Primary Containment Occurred Which Required Evaluation & off-site Fire Department Assistance.Caused by Uncovered Opening in Bioshield Wall in Slag Path.Procedures Revised
ML20069F0001994-01-24024 January 1994 Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20057F2261993-09-30030 September 1993 Safety Evaluation Supporting Exemption Request from Requirements of 10CFR50.54(q) for License NPF-82 ML20056C7181993-07-14014 July 1993 SE Supporting Amend 10 to License NPF-82 ML20045B3551993-06-11011 June 1993 LER 93-001-00:on 930429,refueling Jib Crane Moved in Vicinity of Spent Fuel Pool Using vendor-supplied Lifting Eye in Violation of NUREG-0612.Caused by Failure to Identify Crane as Heavy Load.Meetings held.W/930611 Ltr ML20045C8881993-06-0808 June 1993 Vols 1 & 2 to Refueling Jib Crane 1T31-CRN-008A Incident Root Cause Analysis. W/One Oversize Encl ML20044C1181993-02-28028 February 1993 Shoreham Nuclear Power Station Updated Decommissioning Plan. ML20128P6451993-02-28028 February 1993 Snps Decommissioning Project Termination Survey Final Rept for Steam Turbine Sys (N31) ML20128P7431993-02-19019 February 1993 Rev 3 to 93X027, Nuclear QA Surveillance Rept ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20128B9641992-10-31031 October 1992 Rev 0 to Shoreham Decommissioning Project Termination Survey Plan ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20114B5401992-08-26026 August 1992 Rev 0 to Safety Evaluation. W/One Oversize Encl ML20099H5781992-07-31031 July 1992 Rev 4 to Shoreham Defueled Sar ML20114A6311992-07-28028 July 1992 Shoreham Decommissioning Plan ML20101K5791992-06-25025 June 1992 Long Island Power Authority Shoreham Decommissioning Project,Shoreham Nuclear Power Station,Technical Rept on Water Processing & Water Mgt Activities for Reactor Pressure Vessel & Wet Cutting Station ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20082M5081991-08-26026 August 1991 Rev 3 to Shoreham Defueled Sar PM-91-125, Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station1991-07-31031 July 1991 Monthly Operating Rept for Jul 1991 for Shoreham Nuclear Power Station PM-91-112, Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station1991-06-30030 June 1991 Monthly Operating Rept for Jun 1991 for Shoreham Nuclear Power Station PM-91-075, Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station1991-04-30030 April 1991 Monthly Operating Rept for Apr 1991 for Shoreham Nuclear Power Station ML20024G7171991-04-22022 April 1991 LER 91-001-00:on 910324,RB Normal Ventilation Sys (Rbnvs) Outboard Exhaust Valve Closed for No Apparent Reason.Cause Inconclusive.Sys Restored to Normal Lineup & Rbnvs Outboard Valve Will Be Stroked on Routine basis.W/910422 Ltr SNRC-1806, Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 19901991-04-15015 April 1991 Revised Pages 2 & 6 to Encl a of 10CFR50.59 Annual Rept for 1990 PM-91-058, Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station1991-03-31031 March 1991 Monthly Operating Rept for Mar 1991 for Shoreham Nuclear Power Station PM-91-037, Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station1991-02-28028 February 1991 Monthly Operating Rept for Feb 1991 for Shoreham Nuclear Power Station PM-91-016, Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station1991-01-31031 January 1991 Monthly Operating Rept for Jan 1991 for Shoreham Nuclear Power Station 05000322/LER-1990-010, :on 901213,unplanned ESF Actuation Occurred in Control Room Air Conditioning & RB Standby Ventilation Sys B.Caused by Procedural Deficiency.Procedure Revised,Incident Rept Issued & Policy Established1991-01-0909 January 1991
- on 901213,unplanned ESF Actuation Occurred in Control Room Air Conditioning & RB Standby Ventilation Sys B.Caused by Procedural Deficiency.Procedure Revised,Incident Rept Issued & Policy Established
SNRC-1799, Lilco 1990 Annual Rept1990-12-31031 December 1990 Lilco 1990 Annual Rept ML20069Q3901990-12-31031 December 1990 Shoreham Nuclear Power Station Decommissioning Plan. (Filed in Category P) SNRC-1797, 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 19901990-12-31031 December 1990 10CFR 50.59 Annual Rept of Facility Changes,Procedure Changes,Tests & Experiments for Jan-Dec 1990 SNRC-1794, Shoreham Nuclear Power Station Annual Operating Rept,19901990-12-31031 December 1990 Shoreham Nuclear Power Station Annual Operating Rept,1990 05000322/LER-1990-008, :on 900915,unplanned Actuation of ESF Sys Occurred Due to Lightning Strike.Damaged Remote Data Acquisition Unit Circuit Cards Replaced1990-10-0505 October 1990
- on 900915,unplanned Actuation of ESF Sys Occurred Due to Lightning Strike.Damaged Remote Data Acquisition Unit Circuit Cards Replaced
ML20028H0231990-09-28028 September 1990 LER 90-007-00:on 900907,unplanned Actuation of ESF Sys Occurred During I&C Surveillance Test.Caused by Inadequate procedure.SP44.650.16 Revised to Require That Leads Lifted & Individually separated.W/900928 Ltr 05000322/LER-1990-005, :on 900418,noted That on 791205,830808,851218, 861201,870703 & 890119 & 0510,conductor Failures Occurred. Caused by Loss or Reduction of Insulation Resistance or Loss of Continuity for Conductors in Assemblies1990-08-29029 August 1990
- on 900418,noted That on 791205,830808,851218, 861201,870703 & 890119 & 0510,conductor Failures Occurred. Caused by Loss or Reduction of Insulation Resistance or Loss of Continuity for Conductors in Assemblies
ML20056A2001990-07-31031 July 1990 Safety Evaluation Supporting Amend 6 to License NPF-82 PM-90-097, Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station1990-06-30030 June 1990 Monthly Operating Rept for June 1990 for Shoreham Nuclear Power Station ML20055E3911990-06-25025 June 1990 Safety Evaluation Supporting Amend 5 to License NPF-82 PM-90-083, Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station1990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Shoreham Nuclear Power Station 05000322/LER-1986-014, :on 860305,full Reactor Trip Occurred Due to Momentary False Low Vessel Level Signal,Causing Hydraulic Pressure Spike in Ref Leg A.Bourton Tube Type Pressure Transmitter Replaced W/Rosemount Model 11531990-05-16016 May 1990
- on 860305,full Reactor Trip Occurred Due to Momentary False Low Vessel Level Signal,Causing Hydraulic Pressure Spike in Ref Leg A.Bourton Tube Type Pressure Transmitter Replaced W/Rosemount Model 1153
05000322/LER-1986-039, :on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated1990-05-16016 May 1990
- on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated
05000322/LER-1988-015, :on 880916,seismic Monitoring Instrumentation, Including Peak Acceleration Recorders,Removed from Svc for More than 30 Days Due to Corrosion on Scratch Plates.Cover Gasket Replaced & Thermal Barrier Mount to Be Installed1990-05-16016 May 1990
- on 880916,seismic Monitoring Instrumentation, Including Peak Acceleration Recorders,Removed from Svc for More than 30 Days Due to Corrosion on Scratch Plates.Cover Gasket Replaced & Thermal Barrier Mount to Be Installed
05000322/LER-1987-035, :on 871221,880106 & 0330,high Energy Line Break Logic Isolations of RWCU & Main Steam Line Drain Valves Occurred.Caused by Problems W/Temp Monitoring Units. Grounding Scheme Changed & Transformers Rewired1990-05-16016 May 1990
- on 871221,880106 & 0330,high Energy Line Break Logic Isolations of RWCU & Main Steam Line Drain Valves Occurred.Caused by Problems W/Temp Monitoring Units. Grounding Scheme Changed & Transformers Rewired
1997-05-01
[Table view] |
Text
1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS SUPPORTING AN EXEMPTION FROM 10 CFR 50.54fo)
FACILITY LICENSE NO. NFP-82 SH0REHAM NUCLEAR POWER STATION. UNIT 1 (SNPS)
DOCKET NO. 50-322
1.0 INTRODUCTION
By letter dated January 26,1993, Long Island Power Authority (LIPA) requested an exemption from the requirements of 10 CFR 50.54(q) of the [ ode of Federal Reaulations. Section 50.54(q) of 10 CFR Part 50 requires a licensee authorized to possess a nuclear power reactor to follow and maintain in effect emergency plans that meet the standards of 10 CFR 50.47(b), and the requirements of Appendix E, to 10 CFR Part 50.
LIPA's request for this exemption was made pursuant to the provisions of 10 CFR 1
50.12, which, in part, state that the Commission may, upon application, grant exemptions from the requirements of the regulations of this part, which are:
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"(1) Authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security.
l (2) The Commission will not consider granting an exemption unless special circumstances are present.
Special circumstances are present whenever--
...(11) Application of the regulation in the particular circumstances would not serve the underlying purpose of the rule; or (iii) Compliance would result in undue hardship or other costs that are significantly in excess of those incurred by others similarly situated...."
2.0 BACKGROUND
SNPS is a boiling-water reactor located in the town of Brookhaven, Suffolk County, New York, about 50 miles east of New York City on the north shore of Long Island. The SNPS license was amended on July 19, 1991, to authorize possession-only, but not operation, of the reactor located at Wading River, New York. SNPS has been shut down since February 28, 1989, and only operated intermittently at low-power levels during the period July 1985 and June 1987. At the time of the plant's final shutdown, in June 1957, the average fuel burnup was calculated to be approximately two effective full-power days.
Fuel removal from the reactor was completed in August 1989, and all the fuel assemblies are currently stored i
in the Spent Fuel Storage Pool.
Because the fuel heat decay rate is low (220 watts), active cooling of the fuel is not required.
In addition, LIPA has I
entered into a contract with Philadelphia Electric Company to sell the fuel, and anticipates initial fuel transfer to begin in September 1993, and be completed by December 1994.
9310140311 930930 PDR ADDCK 05000322 le F
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.2 The Order Authorizing Decommissioning was issued June 11, 1992.
SNPS is currently in the process of-being decommissioned, and the decommissioning of SNPS is approximately 75 percent complete. LIPA estimates that the facility license will be terminated and the facility will be released for unrestricted use in 1995.
3.0 EVALUATION 3.1 The Exemption Is Authorized by law LIPA maintains that the exemption is fully authorized by law.
The NRC staff agrees with LIPA's contention and has determined that pursuant to 10 CFR 50.12, this exemption is authorized by law.
3.2 The Exemotion Would Present No Undue Risks to Public Health and Safety On July 31, 1990, LIPA was granted partial relief from the requirements of 10 CFR 50.54(q). The July 31, 1990, exemption granted LIPA relief from the requirements to maintain off-site emergency response capability, and the SNPS Defueled Emergency Preparedness Plan (DEPP) was implemented to address on-site emergency response.
LIPA is currently requesting an exemption from the DEPP. Granting an exemption to SNPS is a warranted case because: 1) SNPS is now permanently shut down; 2) the decommissioning of SNPS is now approximately 75 percent complete, and nearly all the radioactive material except for the fuel has been removed from the site; 3) SNPS is permanently defueled, and the fuel source term inventory and decay heat are even lower than the levels that existed in 1990 when relief from off-site emergency response was granted; 4) there is an insignificant radiological risk to offsite population from any credible accident scenario; and
- 5) SNPS has existing plant procedures to address any events that may require an emergency response.
Both the "Shoreham Nuclear Power Station Defueled Safety Analysis Report" (DSAR) and the approved "Shoreham Nuclear Power Station Decommissioning Plan" (DP) analyzed several accident scenarios. The worst-case accident scenario was the fuel damage accident analyzed in Chapter 15 of the DSAR. In summary, the worst-case fuel damage accident assumed all 560 fuel-element assemblies being damaged, and the release of all their fission gases, with no credit taken for containment isolation and filtration of fission products.
The assumption of a complete release of gaseous inventory is very conservative.
Regulatory Guide 1.25,
" Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the fuel Handling and Storage Facility for Boiling and Pressurized Water Reactors" recommends a 30 percent release fraction for a low burnup condition. Even with an extremely conservative analysis, the whole-body dose to an individual located at the exclusion area is 1.08 mrems.
This is considerably less than 1 percent of the U.S. Environmental Protection Agency's
" Protective Action Guidelines" dose of 1000 mrems requiring protective action.
For a defueled reactor such as SNPS, the underlying risks are small, compared with an operating reactor.
In addition, LIPA has developed and implemented emergency operating procedures and station procedures to respond to plant events. These procedures provide for appropriate notifications to, response actions by, and staff augmentations.
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Events covered include natural hazards, fuel handling accidents,
- fires, contaminated / injured individuals, and several other events. The staff agrees that t
the procedures address all credible events, and these procedures will remain in effect upon granting of the exemption.
Based on review of a LIPA analysis of possible events at SNPS, the staff concurs l
with LIPA's analysis and concludes that there is no credible accident at SNPS, l
in its present mode, that could result in the release of radioactive materials to the environment in quantities that would require protective actions for the public.
Because there is no credible accident at SNPS, in its present state, that could result in the release of radioactive materials to the environment in quantities that would require protective actions for the public, the staff concars with LIPA's contention that the continued implementation of the "Defueled Emergency Preparedness Plan," at an annual cost of $500,000, poses an undue hardship and is not necessary to achieve the underlying purpose of the rule.
3.3 The Exemption Would Be Consistent with Common Defense and Security LIPA believes and the staff concurs that the requested exemption is consistent with the common defense and security.
LIPA has proposed no changes, either to the SNPS physical security or fire protection programs, that could compromise the safeguarding of the remaining spent fuel.
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4.0 ENVIRONMENTAL CONSIDERATION
S i
Pursuant to 10 CFR 51.21, 51.32, and 51.35, an environmental assessment and i
finding of no significant impact has been prepared and published in the Federal i
Reaister, September 22, 1993, 58 FR 49332.
The NRC has determined that the
[
issuance of the exemption will not have a significant effect on the quality of the human environment.
5.0 AGENCIES AND PERSONS CONSULTED The State of New York was notified of the proposed issuance of the exemption.
7 The State Official stated that the State had no comments on the proposed exemption.
6.0 CONCLUSION
S i
The staff concludes that the special circumstances of both 10 CFR 50.12(a)(2)(ii) and (iii) exist. The staff further concludes, based on the considerations above, that: (1) the granting of an exemption is authorized by law, would not involve an increase in the probability or consequences of accidents previously evaluated, nor create the possibility of a new or different kind of accident from any accident previously evaluated, and does not result in any reduction in a margin r
of safety; (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (3) such activities will be conducted in compliance with the Commission's regulations; and (4) the issuance of the exemption will not be inimical to the common defense and l
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4 security, nor to the health and safety of the public..Thus the NRC finds LIPA's request for an exemption from the requirements of 10 CFR 50.54(q). should be granted.
Principal Contributor: Clayton L. Pittiglio, Jr.
Date:
SEE O O N3 TAC #50286
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Thus the staff finds LIPA's request for an exemption from the requirements of 10 CFR 50.54(q) should be granted.
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