NRC Generic Letter 1989-022: Potential for Increase Roof Loads and Plant Area Flood Runoff Depth at Licensed Nuclear Power Plants Due to Recent Change in Probable Max. Precipitation Criteria Developed by National Weather Service| ML031210438 |
| Person / Time |
|---|
| Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River |
|---|
| Issue date: |
10/19/1989 |
|---|
| From: |
Partlow J G
Office of Nuclear Reactor Regulation |
|---|
| To: |
|
|---|
| References |
|---|
| NUREG-0800 GL-89-022, NUDOCS 8910180273 |
| Download: ML031210438 (5) |
|
Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, 05000000, Zimmer, Fort Saint Vrain, Washington Public Power Supply System, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant, Clinch River |
|---|
Category:NRC Generic Letter
MONTHYEARML23200A1832023-08-0303 August 2023
Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML17067A2782017-04-18018 April 2017
Non-Power Reactor Closeout of Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools for the Armed Forces Radiobiology Research Institute, Docket No. 50-170 (CAC No. A11010)
ML17067A4042017-04-17017 April 2017
Washington State University GL 2016-01 Closeout Form Letter for Rtrs with No Credited NAM
NRC Generic Letter 2007-012007-02-0707 February 2007
NRC Generic Letter 2007-01: Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients
NRC Generic Letter 2006-012006-01-20020 January 2006
NRC Generic Letter 2006-01: Steam Generator Tube Integrity and Associated Technical Specifications
NRC Generic Letter 1999-021999-08-23023 August 1999
NRC Generic Letter 1999-002: (Errata): Laboratory Testing of Nuclear-Grade Activated Charcoal
NRC Generic Letter 1983-111999-06-24024 June 1999
NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis
ML0823509351999-06-0303 June 1999
Generic Ltr 99-02 to All Holders of OLs for Nuclear Power Reactors,Except Those Who Have Permanenetly Ceased Operations & Certified That Fuel Permanently Removed from Rv Re Laboratory Testing of nuclear-grade Activated Charcoal
ML0311101371999-06-0303 June 1999
Withdrawn NRC Administrative Letter 1999-002: Operating Reactor Licensing Action Estimates
NRC Generic Letter 1999-011999-05-0303 May 1999
NRC Generic Letter 1999-001: Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities
NRC Generic Letter 1998-011999-01-14014 January 1999
NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants
ML0311101601998-08-0303 August 1998
Withdrawn NRC Administrative Letter 1998-005: Availability of Summaries in Electronic Format of Technical Reports by Office for Analysis & Evaluation of Operational Data
NRC Generic Letter 1998-041998-07-14014 July 1998
NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i
NRC Generic Letter 1998-031998-06-22022 June 1998
NRC Generic Letter 1998-003; NMSS Licensees and Certificate Holders Year 2000 Readiness Programs
NRC Generic Letter 1998-021998-05-28028 May 1998
NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition
NRC Generic Letter 1997-061997-12-30030 December 1997
NRC Generic Letter 1997-006: Degradation of Steam Generator Internals
NRC Generic Letter 1997-051997-12-17017 December 1997
NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques
NRC Generic Letter 1996-061997-11-13013 November 1997
NRC Generic Letter 1996-006, Supplement 1: Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions
ML0312007011997-10-0808 October 1997
Withdrawn NRC Generic Letter 1991-018, Revision 1: Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions
NRC Generic Letter 1997-041997-09-30030 September 1997
NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules
NRC Generic Letter 1997-031997-07-0909 July 1997
NRC Generic Letter 1997-003: Annual Financial Surety Update Requirements for Uranium Recovery Licensees
NRC Generic Letter 1997-021997-05-15015 May 1997
NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report
NRC Generic Letter 1995-061997-01-31031 January 1997
NRC Generic Letter 1995-006: Changes in Operator Licensing Program
NRC Generic Letter 1996-081996-12-15015 December 1996
NRC Generic Letter 1996-008: Interim Guidance on Transportation of Steam Generators
NRC Generic Letter 1996-051996-09-18018 September 1996
NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
NRC Generic Letter 1996-041996-06-26026 June 1996
NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks
NRC Generic Letter 1995-091996-04-0505 April 1996
NRC Generic Letter 1995-009: Supplement 1: Monitoring and Training of Shippers and Carriers of Radioactive Materials
NRC Generic Letter 1996-021996-02-13013 February 1996
NRC Generic Letter 1996-002: Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat
NRC Generic Letter 1996-031996-01-31031 January 1996
NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits
NRC Generic Letter 1989-101996-01-24024 January 1996
NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors
NRC Generic Letter 1996-011996-01-10010 January 1996
NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits
NRC Generic Letter 1995-101995-12-15015 December 1995
NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation
ML0310701501995-10-31031 October 1995
Withdrawn - NRC Generic Letter 1995-008: 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval
NRC Generic Letter 1993-031995-10-20020 October 1995
NRC Generic Letter 1993-003: Verification of Plant Records
NRC Generic Letter 1995-071995-08-17017 August 1995
NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves
NRC Generic Letter 1995-041995-04-28028 April 1995
NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues
NRC Generic Letter 1995-031995-04-28028 April 1995
NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes
NRC Generic Letter 1995-021995-04-26026 April 1995
NRC Generic Letter 1995-002: Use of Numarc/Epri Report TR-102348, Guideline on Licensing Digital Upgrades, in Determining the Acceptability of Performing Analog-To-Digital Replacements Under 10CFR 50.59
NRC Generic Letter 1995-011995-01-26026 January 1995
NRC Generic Letter 1995-001: NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities
ML0312004431994-09-0202 September 1994
Withdrawn - NRC Generic Letter 1994-004: Voluntary Reporting of Additional Occupational Radiation Exposure Data
NRC Generic Letter 1994-031994-07-25025 July 1994
NRC Generic Letter 1994-003: Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors
NRC Generic Letter 1994-021994-07-11011 July 1994
NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors
NRC Generic Letter 1994-011994-05-31031 May 1994
NRC Generic Letter 1994-001: Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators
NRC Generic Letter 1993-081993-12-29029 December 1993
NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits
NRC Generic Letter 1993-071993-12-28028 December 1993
NRC Generic Letter 1993-007: Modification of Technical Specification Administrative Control Requirements for Emergency & Security Plans
NRC Generic Letter 1993-061993-10-25025 October 1993
NRC Generic Letter 1993-006: Research Results on Generic Safety Issue 106, Piping and the Use of Highly Combustible Gases in Vital Areas.
NRC Generic Letter 1993-051993-09-27027 September 1993
NRC Generic Letter 1993-005: Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation
NRC Generic Letter 1993-041993-06-21021 June 1993
NRC Generic Letter 1993-004: Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f)
NRC Generic Letter 1993-021993-03-23023 March 1993
NRC Generic Letter 1993-002: Public Workshop on Commercial Grade Procurement and Dedication
NRC Generic Letter 1993-011993-03-0303 March 1993
NRC Generic Letter 1993-001: Emergency Response Data System Test Program
2023-08-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Washington Public Power Supply System]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Clinch River]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Washington Public Power Supply System]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Clinch River]] </code>. |
UNITED STATESt BNUCLEAR REGULATORY COMMISSIONWASHINGTON, D. C. 20555October 19, 1989TO: ALL LICENSEES OF OPERATING REACTORS AND HOLDERS OF CONSTRUCTIONPERMITS*
SUBJECT: POTENTIAL FOR INCREASED ROOF LOADS AND PLANT AREA FLOOD RUNOFF DEPTHAT LICENSED NUCLEAR POWER PLANTS DUE TO RECENT CHANGE IN PROBABLEMAXIMUM PRECIPITATION CRITERIA DEVELOPED BY THE NATIONAL WEATHERSERVICE (GENERIC LETTER 89-22)This letter is to inform you that the NRC staff has adopted for future plantsthe latest probable maximum precipitation (PMP) criteria published by theNational Oceanic and Atmospheric Administration (NOAA), National WeatherService (NWS) to establish acceptable design configurations for safety-relatednuclear power plant facilities. The staff has been using the PMP concept inplant flood design for well over 15 years. The criteria appear in RegulatoryGuides, ANSI Standards, and Standard Review Plans (NUREG-0800) and were basedprimarily on procedures established in the 1940s and 1950s by the U.S. ArmyCorps of Engineers and National Weather Service (NWS).Since 1977, more recent PMP criteria have been published by the NationalOceanic and Atmospheric Administration (NOAA), National Weather Service.These criteria are to be used to evaluate the degree of licensee compliancewith the General Design Criterion 12 App A to 10 CFR Part 50. The newcriteria are contained in NOAA/NWS Hydrometerological Reports (HMR) No. 49(1977), No. 51 (1978), No. 52 (1982), No. 53 (1980) and No. 55 (1984). One ofthe more significant changes in the new HMRs is that they now provide PMPestimates for drainage areas as small as 1 square mile and for durations assmall as 5 minutes. The previous reports generally only provided PMP estimatesfor areas of 10 square miles or greater and durations of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or more.There were empirical methods to subdivide the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> duration to smallerincrements, but there was never any methodology to estimate PMP for areas lessthan 10 square miles. Thus, the 10 square mile PMP values were used for siteand roof drainage design. Current 1 square mile short duration PMP estimatesare larger than those previously used.Staff has revised (Revision 3) Sections 2.4.2, Floods,' and 2.4.2, 'ProbableMaximum Floods (PMF) on Streams and Rivers," of the Standard Review Plan(NUREG-0800) to formally incorporate the latest NWS reports into the licensing1* Five plants, Byron, Braidwood, Vogtle, South Texas, and River Bend, fullymeet the new PMP Criteria and the licensees for these five plants may dis-i letter.91 180273t C Generic Letter 89- 22 -2 -October 19, 1989review process. In general, the latest NWS criteria call for higher rainfallintensities over shorter time intervals and smaller areas than have beenpreviously considered. In some cases, such events could result in higher siteflooding levels and greater roof ponding loads than have been used in previousdesign studies.This information is provided for your review and determination of appropriateaction, if any. No submittal is required.
Sincerely,Jades G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor Regulation
Enclosure:
List of Most Recently IssuedGeneric Letters
Technical Contact:
_____ _ __ _S. Chan, ESGB/NRR492-0830 LIST OF RECENTLY ISSUED GENERIC LETTERS<_>GenericDate ofT 1 ciiand-Issued Toc.. I; , 4_.Letter NO. uu vLL ------ -89-2289-21POTENTIAL FOR INCREASED ROOF 10/19/89LOADS AND PLANT AREA FLOODRUNOFF DEPTH AT LICENSEDNUCLEAR POWER PLANTS DUE TORECENT CHANGE IN PROBABLEMAXIMUM PRECIPITATIONCRITERIA DEVELOPED BY THENATIONAL WEATHER SERVICE(GENERIC LETTER 89-22)REQUEST FOR INFORMATION 10/19/89CONCERNING STATUS OFIMPLEMENTATION OF UNRESOLVEDSAFETY ISSUE (USI) REQUIREMENTSPROTECTED AREA LONG-TERM 09/26/89HOUSEKEEPING89-2089-19ALL LICENSEES OFOPERATING REACTORS ANDHOLDERS OF CONSTRUCTIONPERMITS (EXCEPT BYRONBRAIDWOOD, VOGTLEOSOUTH TEXAS, AND RIVERBEND)ALL HOLDERS OFOPERATING LICENSESAND CONSTRUCTIONPERMITS FOR NUCLEARPOWER REACTORSALL FUEL CYCLEFACILITY LICENSEESWHO POSSESS, USE,OR PROCESS FORMULAQUANTITIES OFSTRATEGIC SPECIALNUCLEAR MATERIALALL LICENSEES OFOPERATING REACTORS,APPLICANTS FOROPERATING LICENSESAND HOLDERS OFCONSTRUCTION PERMITSFOR LIGHT WATERREACTOR NUCLEARPOWER PLANTSALL HOLDERS OFOPERATING LICENSESOR CONSTRUCTIONPERMITS FOR NUCLEARPOWER PLANTSREQUEST FOR ACTION RELATED TO 09/20/89RESOLUTION OF UNRESOLVEDSAFETY ISSUE A-47 "SAFETYIMPLICATION OF CONTROLSYSTEMS IN LWR NUCLEARPOWER PLANTS" PURSUANT TO10 CFR 50.54(f)89-18RESOLUTION OF UNRESOLVEDSAFETY ISSUE A-17, "SYSTEMSINTERACTIONS IN NUCLEARPOWER PLANTS09/06/89ACCESSION NUMBER IS 890907002989-17PLANNED ADMINISTRATIVECHANGES TO THE NRC OPERATORLICENSING WRITTEN EXAMINA-TION PROCESS -GENERICLETTER 89-1709/06/89ALL HOLDERS OFOPERATING LICENSESOR CONSTRUCTIONPERMITS FOR PWRSAND BWRS AND ALLLICENSED OPERATORS89-16INSTALLATIONWETWELL VENTLETTER 89-16)OF A HARDENED(GENERIC09/01/89ALL GE PLANTS Generic Letter 89- 22-2 -October 19, 1989review process. In general, the latest NWS criteria call for higher rainfallintensities over shorter time intervals and smaller areas than have beenpreviously considered. In some cases, such events could result in higher siteflooding levels and greater roof ponding loads than have been used in previousdesign studies.This informationaction, if any.is provided forNo submittal isyour review and determination of appropriaterequired.
Sincerely,ORIGINAL SIGNED BY JAMES G. PARTLOWJames G. PartlowAssociate Director for ProjectsOffice of Nuclear Reactor Regulation
Enclosure:
List of Most RecentlyGeneric Letters
Technical Contact:
S. Chan, ESGB/NRR492-0830DISTRIBUTION:Central FilesNRC PDR IPD4 ReadingP. O'ConnorF. HebdonG. HolahanF. MiragliaC. BerlingerJ. Partlow1K It1 VIaWY/ 14;~~IFTPD4JDRSP/PM :PD4/,DJS/ :A 4/UKIU+rA /U :AA UI r'qq, :A---___: ------- o---a-h---n-- -r a :C ___ inge :J) -----a_NAME :PO'Connor:bj:FHe n :G olahan olahan :' twDATE_ :--------- ---/---/8- _--/89 _______/89 -- _ _______ -__ _- : ---------DATE :1 /X7)/89 :/2L1/89 :lf /%V /89 V' A% /89 : 8al9 M /§/89 : l 5/89fOFFICIAL RECORD COPYDocument Name: GENERIC LETTER/PD4 DOCUMENT NAME:GENERIC LETTER/PD4ORIGINATOR NAME *:P. O'Connor x23026SECRETARY NAME:Beverly/Celeste x21340SUBJECT:GENERIC LETTER 89-XX RE: DESIGN FOR PROBATENAMEE MAXIMUMDATE_ -°\ lokh1°c\I I\F/Z/7 j1.2.3.4.5.7.7.P. O'ConnorF. HebdonG. HoIahan3tj-'CA2G. HolahanF. MiragliaC. BerlingerJ. PartlowSecretary -DispatchPLEASE DO NOT REMOVE THIS SHEET FROM PACKAGE* CAN THIS DOCUMENT BE DELETED FROM SYSTEM? YESSHOULD THIS DOCUMENT BE ARCHIVED? YES ---- NO_NO
Template:GL-Nav