|
---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20069F0001994-01-24024 January 1994 Vols 1-4 to Shoreham Decommissioning Project Termination Survey Final Rept ML20045C8881993-06-0808 June 1993 Vols 1 & 2 to Refueling Jib Crane 1T31-CRN-008A Incident Root Cause Analysis. W/One Oversize Encl 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 ML20099H5781992-07-31031 July 1992 Rev 4 to Shoreham Defueled Sar 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 ML20082M5081991-08-26026 August 1991 Rev 3 to Shoreham Defueled Sar ML20005F2511990-01-0505 January 1990 Shoreham Nuclear Power Station Defueled Sar. ML19332G1991989-09-18018 September 1989 Rev 0 to Radiological Safety Analysis for Spent Fuel Storage & Handling. ML20245E0181989-06-19019 June 1989 QC 1989 Staffing Rept ML20153G8941988-08-31031 August 1988 Rev 1 to Shoreham Nuclear Power Station Prompt Notification Sys Rept ML20196K6311988-06-29029 June 1988 QC Div 1988 Staffing Rept ML20148A4851988-02-29029 February 1988 Shoreham Nuclear Power Station PRA W/Supplemental Containment Sys ML20214U2021987-01-31031 January 1987 Technical Rept 86.2SH Verification of IPE for Shoreham. W/ 870313 Release Memo ML20210M6001986-12-31031 December 1986 Emergency Planning Federal Involvement in Preparedness Exercise at Shoreham Nuclear Plant. Related Correspondence ML20214T6021986-12-31031 December 1986 Rev 6 to Plant Design Assessment Rept for Safety/Relief Valves & LOCA Loads, Vols 1 & 2.Proprietary Suppl Withheld (Ref 10CFR2.790) ML20210K2961986-12-31031 December 1986 Nuclear Regulation,Unique Features of Shoreham Nuclear Plant Emergency Planning. Related Correspondence ML20214U3641986-10-31031 October 1986 Shoreham Startup & Low Power Testing Operations,Special Rept:Lilco QA Audit on Training & Qualifications ML20237H6381986-07-31031 July 1986 Compliance W/10CFR50,App I ML20211P6851986-06-30030 June 1986 Implications of Chernobyl-4 Accident for Nuclear Emergency Planning for State of Ny ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications SNRC-1207, Vols 1 & 2 of Colt Emergency Diesel Generator Info to Be Incorporated in Fsar. W/11 Oversize Drawings1985-11-30030 November 1985 Vols 1 & 2 of Colt Emergency Diesel Generator Info to Be Incorporated in Fsar. W/11 Oversize Drawings ML20128N9651985-05-31031 May 1985 New York Power Pool,1985 Summer Operating Reserve, Projection & Analysis ML20111C0961984-11-20020 November 1984 Rev 1 to Long Island Lighting Co,Shoreham Nuclear Power Station,Prompt Notification Sys Design Rept ML20091Q8851984-06-30030 June 1984 Colt Diesel Generator Summary for Shoreham Nuclear Power Station - Unit 1 ML20092N6631984-06-12012 June 1984 Seismic Survivability Study for MP-45 Diesel Generators ML20091M5451984-05-31031 May 1984 Design Review of Connecting Rods for Tdi DSRV-4 Series Diesel Generators, Final Rept Prepared for Tdi Diesel Generator Owners Group ML20091M5511984-05-23023 May 1984 Investigation of Types AF & Ae Piston Skirts, Final Rept Prepared for Tdi Diesel Generator Owners Group ML20091M5201984-05-22022 May 1984 Draft Final Rept, Evaluation of Emergency Diesel Generator Crankshafts at Shoreham & Grand Gulf, Prepared for Tdi Diesel Generator Owners Group ML20084E5421984-04-30030 April 1984 Emergency Diesel Generator Engine & Auxiliary Module Wiring & Termination Qualification to IEEE-383-1974 ML20087L3511984-03-31031 March 1984 Emergency Diesel Generator Air Start Valve Capscrew Dimension & Stress Analysis, Prepared for Transamerica Delaval,Inc (Tdi) Diesel Generator Owners Group ML20081C4721984-03-12012 March 1984 Design Review of Connecting Rod Bearing Shells for Transamerica Delaval Enterprise Engines ML20087L2851984-02-27027 February 1984 Control Bldg Category I Equipment Balance-of-Plant Qualification Level, Monthly Status Rept ML20086S2221984-02-27027 February 1984 Investigation of Types AF & Ae Piston Skirts ML20080U3971984-02-10010 February 1984 Rept on Special Lifting Devices ML20083F6511983-12-15015 December 1983 Analysis of Replacement Connecting Rod Bearings Emergency Diesel Generators,Fatigue Life Prediction,Shoreham Nuclear Power Station ML20083C6681983-12-0808 December 1983 Metallurgical Analysis of Cracked Piston Skirts from Emergency Diesel Generators,Shoreham Nuclear Power Station ML20081C1571983-10-20020 October 1983 Diesel Generator Status Rept ML20112J2501983-08-31031 August 1983 Critique of Hudson Inst/Lilco Defense of Shoreham Economics. Related Info Encl ML20082D8831983-08-30030 August 1983 Suppression Pool Local-to-Bulk Temp Difference,Shoreham Nuclear Power Station - Unit 1 ML20112J2981983-08-30030 August 1983 Lilco/Hudson Inst Rept on Shoreham:Analysis of Errors Re Property Taxes & Employment. Related Info Encl ML20081L6891983-08-29029 August 1983 Excerpt from Draft FSAR Section 5.2.8, Inservice Insp Program, & Section 5.2.8.1 Provisions for Access to Rcpb ML20085D8921983-07-26026 July 1983 Books 1-3 of Independent Design Review for Shoreham Nuclear Power Station, Final Technical Rept ML20072J9521983-06-30030 June 1983 Independent Design Review for Shoreham Nuclear Power Station, Executive Summary of Final Rept ML20058N6071983-06-30030 June 1983 Environ Qualification Rept for Class 1E Equipment for Shoreham Nuclear Power Station Unit 1 Lilco ML20072K0141983-06-27027 June 1983 Rev 1 to Independent Design Review,Shoreham Nuclear Power Plant ML20076M0861983-06-27027 June 1983 Rev 5 to Environ Qualification Rept for Class IE Equipment for Shoreham Nuclear Power Station Unit 1 ML20072F2401983-06-22022 June 1983 Element-By-Element Review of Lilco Transition Module of Shoreham Nuclear Power Station Offsite Radiological Emergency Response Plan ML20079R7351983-05-31031 May 1983 Shoreham Common Sensors Failures Evaluation Rept ML20073L5911983-04-30030 April 1983 Cable Separation Analysis Rept 1994-01-24
[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 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 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 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 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) 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 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-1988-0151990-05-16016 May 1990 LER 88-015-02: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-1986-0391990-05-16016 May 1990 LER 86-039-01: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-1986-0321990-05-16016 May 1990 LER 86-032-01:on 860728,RWCU Isolated on High Differential Flow Sensed by Steam Leak Detection Sys While Placing Filter Demineralizers in Operation.Cause Not Determined. Operating Procedures Revised to Monitor RWCU Sys 05000322/LER-1987-0091990-05-16016 May 1990 LER 87-009-01:on 870203,full Reactor Trip Occurred Due to Perturbation in Ref Leg.Caused by Spurious Low Level Reactor Pressure Vessel Water Level Signal.Existing Level & Pressure Transmitters Replaced W/Newer Models 05000322/LER-1987-0221990-05-16016 May 1990 LER 87-022-01:on 870604,HPCI Test Valve to Condensate Storage Tank,Globe Valve & Hpci/Rcic Test Valve to Condensate Storage Tank Failed to Close Against Sys Operating Pressure.Disc of motor-operated Valve 37 Modified 05000322/LER-1989-0051990-05-16016 May 1990 LER 89-005-01:on 890321,results of Local Leak Rate Test of Core Spray Suction Valve a Determined That Leakage,When Combined W/All Type B & C Penetration Leakages,Exceeded Tech Spec Limit.Caused by Normal Valve Degradation 05000322/LER-1989-0031990-05-16016 May 1990 LER 89-003-01:on 890310,emergency Diesel Generator (EDG) 102 Manually Shutdown During 18-month Surveillance Test Due to Failure of EDG Output Breaker.Cause Not Determined. Replacement Breaker Installed in Cubicle 102-8 05000322/LER-1985-0591990-05-16016 May 1990 LER 85-059-01:on 851219,half Reactor Trip,Full NSSS Shutoff Sys Isolation & Reactor Bldg Standby Ventilation Sys Initiation Occurred Due to Loss of Power to Reactor Protection Sys Bus B.Assembly Breaker Reset 05000322/LER-1987-0351990-05-16016 May 1990 LER 87-035-02: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 05000322/LER-1988-0031990-05-16016 May 1990 LER 88-003-01:on 880322,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation Sys Side a Occurred During Deenergization of Relay.Caused by Close Placement of Relay Terminals.Wiring Inside Electrical Panels Reworked 1997-05-01
[Table view] |
Text
t. ,
e;+i; e,f , ; .
i .p . ..- .
r-SE-90-023, Rev. 1-Attacinant B
?
g , -
- Page 2 of 12-c :...
~
Revision 1 - January 1982 Revision 2 - May 1982 Revision 3 - August:1982 Revision 4 - October 1982-6 Revision 5 - June 1983 4
4 i
h
} -;g f ..
a u
- 1
z i
', EVIPCtNENTAL CGLTFICATION REFORT -
FOR CIASS'IE EQUIPMENT
- i. g-SHORDIAM NUCLEAR POLER STATION - LHIT lt 14NG ISLAND LIGHTING COMPANY s.
M ,
T 4
l ,
.\'
1 1 J
1
';l3 '
t p .. t 9008140240 900810 J o PDR ADOCK 05000322 P PDC 7 ,
d,. ,
.4 1- . , ,
f
-A 4 .
- r. .
. g 4
- c;-;
i
- ' 'O j '$t<) ,,
4>
SE-90-023,.Revo :1-
- Attachment B.
Page-3 of 12 s
ggpg.g g ,
7JST OF APFETED PAGES
. REVISION.
PAGE, TABLE, OR FIGURE NLNBL,.
n ar . s11- 6-
,;t e 'li-1 6
, 21 6 Ji-1 6 4
41 1- .- 6 I
51-1 6 n'
- Di C >-
~g-lss' '
, s Ei-1 6 l cFi-1 6 e
-3p 4
L 1
-^ t 4
4 b
')\ \
, s.
.t 'l h
~t. {
[- '.
H
,ei 7 .
.. . 4 ; . 4:.
g . ,
SE-90-023,:Rev. 1-n ;- ' Attachment B.
Page 4 of 12-SNPS-1 EQR. -
SGNUE
.'Ihis report is produced. for NFC review of the modified Enviseddal Qualification Program which is applicable to the Shoreham Nuclear Power Station-
, (STS)' defueled condition.
-;Should the plant status change in the future, a reconsideration of this report
, will precede this. change.
't
1
}'
,[ :.
4 3 I
S f
Si-1 a;
i'
.p. ,
("
b
+ J;p g.
.. ' ' ,=
- ' ~
. -SE-90-023, Rev. 1 "O - Attachnent B F -
Page 5 of 12
>t. , SNPS-1 EQR .
SEcrIm 1 Ih e m 1
- 1. 0 -- MJDITIED ENVIRJtNENTAL QUALIFICATIm PHOGRAM Based on the plant defueled condition, the possibility.of producing a'-
- harsh environnent is eliminated (Safety Evaluation 90-023)'. 'Iherefore ,-
all electrical equipnent (Safety Related Class 1E equipnent and equipment required by Regulatory Guide 1.97) are located in a mild envirorsnent and the environmental qualification of such equipnent isi not included within the scope of 10 CFR 50.49.
Should the plant status change in the future, a reconsideration of the basis for qulification must precede the plant's upgrade to operable :
status.
If-1 11-1
}; .
.p. ,(, . ,r .y. -.
3 ,.
.SE-90-023, Rev. 1' l a" '
Attachment B '! '
Page 6 of.12 Al-
, SNPS-1,.EQR .
s SECTION 2
- m. 4
[
t c2.0~ }ODIFIED DEFINITION OF SAFTTY-PETATED ELTTRICAL
. FUJIPferr i
+
.j The definition of " Electrical equipment important to safety," as.
defined-in 10 CPR 50.49- (b) (1) through (3), does apply to safety related equipaent at SNPS . However, the plant will not rely upon any' ,
electrical epipnent to remain functional during- and following design !
basis events to'perfom functions I(i) through (iii) of Section (1)'of
- 10 CPR 50.49 due to the SNPS present defueled condition.-
s 1
o i
5
').
l :.
l1
-t 1
21-1 l
t a.-
+< ' 6 ::; < .
..a'*-- "
j.[ *
. < SE-90-023, Rev. 1 Lig' -Attachment B
.Page 7 of 12-SNPS-1 EQR ,
+
3.0. EDITIED DNIRONMENTAL 00NDfrICNS With the plant in its defueled condition the only applicable postulated accidents fran Chapter 15.of the USAR are:
Tuel Handling Accident IMIM Radwaste Tank Rupture The results of analysis determined chat the Total Integrated Dose (TID) on the refueling level for six fronth post accident duration is 32 rads, Gartra and Beta.
.The temperature and pressure conditions in the' plant are at ambient and'
- will not change due to any one of the accidents-postulated above.:
Therefore, the envirorrnents where safety related equipment is installed-will not be> significantly rnore-severe than normal envirorsnents- and can be considered a mild envirornnent.
3 I
31-1
'i
a
.jf g 1
')
~
SE-90-023,Rev.ll-Attaclitent B -
3 :' - Page 8 of 12 ci SNPS-1 ECR SICTION 4 ;
4.0- MODIFIED QUALIFICATIN STAMIS With the plant in the defueled condition, there is no EQ equiptent that : ;
is relied upon to remain functional during and following design basis
. events. Therefore, operab'.lity codes' assigned to EQ equipnent par.
NUR E 0588 Appendix E ar< not applicable.
, t
.6 I,
r L
IJ i
4 , !
e I'- y
\
i 41-1 y
k
& (
go;- ot- o ;.
SE-90-023, Rev. 1
- Attachment B Page 9 of 12
,V SNPS-1 EQR ,
SECTION 5 SURVEIMANCE AND MAINTDENCE The Shorehan surveillance and maintenance progrm will continue as is. However,
- the Environmental Qualification related maintenance, to maintain the equiptent
_ qualification status, will be inactivated as follows:
Engineering will halt the transnitting of the EQ related maintenance requirements to plant maintenance.
- - Installation of non-qualified replacement parts will be allowed in qualified equipment.
' - No EQ related surveillances will be performed.
- - All normal maintenarce required to maintain the equipment or systen functional will be performed.
e 51-1
+ff[cQ ah-v[f3 _.
1 ..
- SE-90-023, Rev._1 w-
Page 10 of 12 SNPS-1-ECR' .
'"3 APPDOIX D -
1:
}ODIFIED RADIATION, Tl!2tPERA'IURE AND PRESSURE EATA Based on the plant present defueled condition the plant normal and-accident
' conditions are:
RE2ATIVE Temperature (F) Radiation (RADS) PRESSURE; !!LMIDITE Normal- 79 III Insignificant (2) Atmospheric Not-Controlled 3
Accident 79 32(3) Atmospheric L Not-Controlled
.(1)~ LIIf0 Calculation No. CCI-036590 Revision O.
-(21 -The estimated 2 days full power operation in ecnparison to 40 years-operation results in insignificant backgrcund radiation.
~-(311 Calculation No. C-RPD-529 Revision O.
r Di-1
Rya _e , , ~ * -
p .. - ,.
Attachment B
'bc .
Page 11 of 12'
' 1 ,
SNPS-1 EQR ,
APPDOIX E
^
E.0 , The analyses foming the basis for the Envirornental Qualification
+ ' Program;(EQP) modification are:
- 1. NED 4170024 Revision 0 " Radiological Safety Analysis"
- 1. Calculation No. C-RPD-529 Revision 0 "Offsite and Onsite Reactor
+> Building. Dose Rates Due.to FHA with Core Inventories as of June 15,.1989" t
r Ei-1 i
. v.
' wi -};ff j 1 ,. ,
SE-90-023, Rev. 1
-!!l Attachment B-Page 12 of 12 i/
SNPS-1 EQR ,
.. i APPENDIX F ENVIRONMENTAL QUALIFICATION STATUS REPORP !
4 1
I w :-'!his caponent of the EnvircrYnental Qualification Progran (EOP) will be
' deactivated as the result of EQP nodification. Should the plant status change ]
in the future, a reconsideration of the EQP nodification will pid this change.. l 1
a l
l Fi-1 I
i.
I