LR-N10-0355, Salem, EAL Technical Bases Supporting Documents
| ML110060239 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 10/14/2010 |
| From: | Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| LR-N10-0355 | |
| Download: ML110060239 (15) | |
Text
Attachment 8 SGS EAL Technical Bases Supporting Documents (CD with paper index)
Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Number(s)Collected (Y/N)4 ______________________________________________________ EOP-CFST-1 Critical Safety Function Status Trees SGI.1 SA3.1 SS3.1 SG3.1 FB 1 -P FB2-P FB3-P FB4-P FB 1 -L FB2-L RB1-P RB2-P RB2-L CB 1-P CB2-P CB3-P CB4-P CB6-P CG3.2 Y 1- -I-1-EOP-FRCC-I Response to Inadequate Core Cooling CB3-P CB4-P CB7-P CG3.2 Y 1-EOP-FRHS-1 Response to Loss of Secondary Heat Sink FB2-P Y RB2-P 1-EOP-FRSM-1 Response to Nuclear Power Generation SA3.1 Y SS3.1 SG3.1 I -EOP-LOCA-6 LOCA Outside Containment CB5-L Y Page 1 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Collected (Y/N)Number s)1-EOP-LOPA-1 Loss of all AC Power SU1.1 Y SAI.1 SSI.1 SGI.1 CU1.1 CAl.1 1-EOP-LOSC-1 Loss of Secondary Coolant CBI-L Y 1-EOP-SGTR-1 Steam Generator Tube Rupture RB3-P Y RB3-L CB3-L 1-EOP-SGTR-3 SGTR with LOCA -Subcooled Recovery CB3-L Y 1-EOP-TRIP-1 Reactor Trip or Safety Injection SU1.1 Y SAI.1 SSI.L SGI.1 SA3.1 SS3.1 SG3.1 RB3-P RB3-L CB I -P CB2-P CB8-P CB5-L CUi.1 CAlI.1 Page 2 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 EALColce(YN Procedure Number Procedure Nomenclature Number Collected (Y/N)2-EOP-CFST-1 Critical Safety Function Status Trees SG1.I Y SA3.1 SS3.1 SG3.1 FBI-P FB2-P FB3-P FB4-P FBI -L FB2-L RB 1-P RB2-P RB2-L CBI-P CB2-P CB3-P CB4-P CB6-P CG3.2 2-EOP-FRCC-1 Response to Inadequate Core Cooling CB3-P Y CB4-P CB7-P CG3.2 2-EOP-FRHS-1 Response to Loss of Secondary Heat Sink RB2-P Y 2-EOP-FRSM-1 Response to Nuclear Power Generation SA3.1 SS3.1 SG3.1 2-EOP-LOCA-6 LOCA Outside Containment CB5-L Y 2-EOP-LOPA-I Loss of all AC Power SUI.1 Y SAI.1 SSI.SGI.1 CU 1.1 CA1.1 2-EOP-LOSC-1 Loss of Secondary Coolant CB 1 -L Y Page 3 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Collected (Y/N)Number s)2-EOP-SGTR-1 Steam Generator Tube Rupture RB3-P Y RB3-L CB3-L 2-EOP-SGTR-3 SGTR with LOCA -Subcooled Recovery CB3-L Y 2-EOP-TRIP-1 Reactor Trip or Safety Injection SU1.1 Y SAL.I SS1.1 SGL.l SA3.1 SS3.1 SG3.1 RB3-P RB3-L CB 1-P CB2-P CB8-P CB5-L CU1.1 CA1.1 DOT (ERG2008)
DOT Emergency Response Guide -Link No -Available online at: HU3.2 lihttp://plmisa.dot.gov/staticf' les/l1l I MSA/DownloadableFiles/Files/erg22 008 eng.pdf Verification of Emergency Action Levels for Event FB3-L No -Copy could not meet PDF DS 1.6-0098 Classification Guide FB4-L requirements for NRC electronic RB1-L submittal CB5-P Units l&2 Reactor Containment Drain Trench El 81' & 78'- CU3.2 No -Copy could not meet PDF DWG 208915-A-8823 Sump Pit El 54'-6" & 72'-7" requirements for NRC electronic submittal Emergency Plan Section 7, Communications SU6.1 Y CU5.l ES-45.003 Station Blackout Duration Calc SGI.1 Y Page 4 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 EAL Procedure Number Procedure Nomenclature Number(s)
Collected (Y/N)HOLTEC Hi-Stormn 100 FSAR No -See ADAMS Accession Numbers TOC ML101090396 listed under Procedure Chapter 1: General Description ML101090397 Nomenclature:
Chapter 2: Principal Design Criteria.
ML101090398 Chapter 3: Structural Evaluation.
ML101110022 Chapter 4: Thermal Evaluation.
...Chapter 5: Shielding Evaluation.
ML101110021 EU 1.1 Chapter 6: Criticality Evaluation.
ML1 01110036 Chapter 7: Confinement.
ML101110037 Chapter 8: Operating Procedures.
ML101110038 Chapter 9: Acceptance Criteria and Maint ML1 01110039 Chapter 10: Radiation Protection.
ML101110042 Chapter 11: Accident Analysis.
ML1 01110043 Chapter 12: Operating Controls and Limits. ML101110044 Chapter 13: Quality Assurance.
ML101110045 HOLTEC (Spent Fuel Certificate of Compliance, Docket # 72-1014 No -Storage Cask) C of See ADAMS Accession listed below: Numbers C = ADAMS Accession EU 1.1 No. ML082030158, App A = ADAMS Accession No.ML082030221.
App B = ADAMS Accession No.ML082030231 NC.CH-SH.MET-1206
-Meteorological Monitoring System Calibration and HU.2Y Replaced by: Maintenance HA 1.2 CY-AA-1 70-500 ODCM -Figure 5. 1-3 Area Plot Plan of Site RS1.3 Y RG 1.3 ODCM -Section 3.11.1 Liquid Effluents RU 1.3 Y RA 1.3 ODCM -Section 3.11.2 Gaseous Effluents RU 1.3 Y ODCM -Section 3.3.8 Radioactive Liquid Effluent Monitoring Instrumentation RU 1.2 Y RA1.2 Page 5 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Collected (YIN)Number(s)OE-25324 Alert Declared Due to CO 2 Fire Extinguisher Discharge HU3.1 No -INPO Confidential HA3.1 OP-AA- 108-111 -1001 Severe Weather and Natural Disaster Guidelines HU 1.2 Y HU 1.5 HA1.2 OU-AA-103 Shutdown Safety Management Program CG3.2 Y CA4.1 PSBP 315733 Radiation Monitoring System Manual, Salem Unit No 1 RULI.1 No -Copy could not meet PDF RU1.2 requirements for NRC electronic RA1.1 submittal RA1.2 RS 1.1 RGI.1 SUT7.1 PSBP 315734 Radiation Monitoring System Manual, Salem Unit No 2 RUI.1 No -Copy could not meet PDF RU1.2 requirements for NRC electronic RAI .1 submittal RA1.2 RSI.1 RG1.L SU7.1 S 1.IC-CC.RCP-0070 IPT-403 Reactor Coolant System Hot Leg Pressure Chan II CA4.1 Y S1.OP-AB.4KV-0001 Loss of 1A 4KV Vital Bus SU1.1 Y SAL.1 SSI.1 SGI.1 CU1.1 CA1.1 S1.OP-AB.4KV-0002 Loss of lB 4KV Vital Bus SUI.1 Y SAl.1 SSI.1 SGlI.1 CUI.1 CA1.1 Page 6 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Collected (YIN)Number(s)S1I.OP-AB.4KV-0003 Loss of IC 4KV Vital Bus SUI.I Y SA1.1 SSI.1 SG1.1 CU1.1 CAL.1 S1.OP-AB.ANN-0001 Loss of Overhead Annunciator System SU5.1 Y SA5.1 SS5.1 S I.OP-AB.CONT-000 1 Containment Closure CG3.2 Y CA4.1 SL.OP-AB.CR-0001 Control Room Evacuation HA5.1 Y HS5.1 Control Room Evacuation Due to Fire in the Control Room, HA5.1 Y Relay Room, 460/230V Switchgear Room or 4kV Swgr Rm HS5.1 SL.OP-AB.CW-0001 Circulating Water System Malfunction HU1.5 Y S 1.OP-AB.FUEL-000 1 Fuel Handling Incident RU2.1 Y RA2.l S1.OP-AB.FUEL-0002 Loss of Refueling Cavity or Spent Fuel Pool Level RU2.1 Y RA2.1 S 1.OP-AB.LOOP-0001 Loss of Off-Site Power SU1.1 Y SA1.1 SSI.l SGLI.1 CU1.1 CAL.I SL .OP-AB.RAD-0001 Abnormal Radiation RU2.1 Y RA2.1 RA3.1 Page 7 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Collected (Y/N)Number(s)SI .OP-AB.RC-0001 Reactor Coolant System Leak SUs.1 Y RB3-P CU3.2 CA3.1 CA3.2 CS3.2 CG3.2 S 1.OP-AB.RC-0002 High Activity in Reactor Coolant System SU7.1 Y SU7.2 FB4-L S 1.OP-AB.RHR-0001 Loss of RHR CU4.1 Y CU4.2 CA4.1 S1.OP-AB.RHR-0002 Loss of RHR at Reduced Inventory CU3.2 Y CA3.1 CA3.2 CU4.1 CU4.2 CA4.1 S 1.OP-AB.ZZ-0002 Flooding HU 1.4 Y HUI.5 S1I.OP-AR.ZZ-000 I Overhead Annunciators Window A HU1.1 Y HA1.L S1.OP-AR.ZZ-0003 Overhead Annunciators Window C RU2.1 Y CB7-P CB2-L CB5-L CG3.2 S 1.OP-AR.ZZ-0005 Overhead Annunciators Window E RB3-P Y CU3.1 Si .OP-IO.ZZ-0006 Hot Standby to Cold Shutdown CU3.1 Y SI .OP-IO.ZZ-0007 Cold Shutdown to Refueling CU3.1 Y S1.OP-SO.125-0005 IA 125VDC Bus Operation SS2.1 Y______________________________________________
CU2.1 Page 8 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Number(s)Collected (Y/N)S O.0P-SO. 125-0006 I B 125VDC Bus Operation IC 125VDC Bus Operation SS2.1 CU2.1 SI .OP-SO. 125-0007 SS2.1 ( )2. I RB3-P Si .OP-SO.CVC-0002 Charging Purnm Operation 4 .-, .-, 4 I SI .OP-SO.RC-0004 Identifying and Measuring Leakage Sus.1+ -.- 4 S I.OP-SO.RC-0005 Draining the Reactor Coolant System to > 101 Foot Elevation CU3.1 CU3.2 CU3.3 CA3.1 CA3.2 CS3.2 CG3.2 CU4.2 CA4.1 Y Y Y Y SI .OP-SO.RC-0006 Draining the Reactor Coolant System to < 101 Foot Elevation with Fuel in the Vessel CU3.1 S1 .OP-SO.RVL-0001 Reactor Vessel Level Instrumentation System CU3.2 Y CU3.3 CA3.2 CU4.2 CA4.1 S 1.OP-ST.CAN-0007 Refueling Operations
-Containment Closure CA4.1 Y S 1.OP-ST.RC-0008 Reactor Coolant System Water Inventory Balance SU8.1 Y S2.IC-CC.RCP-0070 2PT-403 Reactor Coolant System Hot Leg Pressure Chan II CA4.1 Y S2.OP-AB.4KV-0001 Loss of 2A 4KV Vital Bus SU1.1 SAL.l SSI.1 SGIA.CUI.1 CAL.1 Y Page 9 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Number(s)Collected (Y/N)S2.OP-AB.4KV-0002 Loss of 2B 4KV Vital Bus SUl.] Y SA1.1 SSLI.SGL.l CUl.1 CAl.I S2.OP-AB.4KV-0003 Loss of 2C 4KV Vital Bus SUL.1 Y SAI.1 SSI.1 SGI.1 CUI1.1 CAL.1 S2.OP-AB.ANN-0001 Loss of Overhead Annunciator System SU5.1 Y SA5.1 SS5.1 S2.OP-AB.CONT-0001 Containment Closure CG3.2 Y CA4.1 S2.OP-AB .CR-0001 Control Room Evacuation HA5.1 Y HS5.1 Control Room Evacuation Due to Fire in the Control Room, HA5.1 Y Relay Room, 460/230V Switchgear Room or 4kV Swgr Rm HS5.1 S2.OP-AB.CW-0001 Circulating Water System Malfunction HU1.5 Y S2.OP-AB.FUEL-000l Fuel Handling Incident RU2.1 Y RA2.1 S2.OP-AB.FUEL-0002 Loss of Refueling Cavity or Spent Fuel Pool Level RU2.1 Y RA2.1 S2.OP-AB.LOOP-0001 Loss of Off-Site Power SUI.1 SALI1 SSI.1 SGLI.1 CU1.I CAl1.1 Y Page 10 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Collected (Y/N)________________________________________Number s)S2.OP-AB.RAD-0001 Abnormal Radiation RU2.1 Y RA2.1 RA3.1 S2.OP-AB.RC-000 1 Reactor Coolant System Leak SU8.1 Y RB3-P CU3.2 CA3.1 CA3.2 CS3.2 CG3.2 S2.OP-AB.RC-0002 High Activity in Reactor Coolant System SU7.1 Y SU7.2 FB4-L S2.OP-AB.RJ-IR-0001 Loss of RHR CU4.1 Y CU4.2 CA4.1 S2.OP-AB.RHR-0002 Loss of RHR at Reduced Inventory CU3.2 Y CA3.1 CA3.2 CU4.1 CU4.2 CA4.1 S2.OP-AB.ZZ-0002 Flooding HU 1.4 Y HU1.5 S2.OP-AR.ZZ-0003 Overhead Annunciators Window C RU2.1 Y CB7-P CB2-L C135-L CG3.2 S2.OP-AR.ZZ-0005 Overhead Annunciators Window E RB3-P Y CU3.1 S2.OP-lO.ZZ-0006 Hot Standby to Cold Shutdown CU3.1 Y S2.OP-IO.ZZ-0007 Cold Shutdown to Refueling CU3.1 Y Page I Iof14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Collected (Y/N)Number(s)S2.OP-SO.125-0005 2A 125VDC Bus Operation SS2.1 Y CU2.1 S2.OP-SO.125-0006 2B 125VDC Bus Operation SS2.1 Y CU2.1 S2.OP-SO.125-0007 2C 125VDC Bus Operation SS2.1 Y CU2.1 S2.OP-SO.CVC-0002 Charging Pump Operation RB3-P Y S2.OP-SO.RC-0004 Identifying and Measuring Leakage SU8.1 Y S2.OP-SO.RC-0005 Draining the Reactor Coolant System to > 101 Foot Elevation CU3.1 Y CU3.2 CU3.3 CA3.t CA3.2 CS3.2 CG3.2 CU4.2 CA4.1 Draining the Reactor Coolant System to < 101 Foot Elevation Y with Fuel in the Vessel S2.OP-SO.RVL-0001 Reactor Vessel Level Instrumentation System CU3.2 Y CU3.3 CA3.2 CU4.2 CA4.1 S2.OP-ST.CAN-0007 Refueling Operations
-Containment Closure CA4.1 Y S2.OP-ST.RC-0008 Reactor Coolant System Water Inventory Balance SU8.I Y EAL Dose Rates to Radiation Detectors Following Loss of CS3.2 No -Copy could not meet PDF S-C-ZZ-MDC-2280 RPV Water Level During Refueling Operations CG3.2 requirements for NRC electronic submittal SC.IC-CC.NIS-001 1 N31 Source Range SU3.1 Y CS3.2 CG3.2 CU6.1 Page 12 of 14 Salem NEI 99-01, Rev. 05, EAL Submittal Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Collected (Y/N)Number(s)SC.JC-CC.NIS-0012 N32 Source Range SU3.1 Y CS3.2 CG3.2 CU6.1 SC.MD-ST.125-0004 125 Volt Station Batteries 18 Month Service Test and SS2.1 Y Associated Surveillance Testing Using BCT-2000 CU2.1 SC.MD-ST.28D-0004 28 Volt Station Batteries 18 Month Service Test and SS2.1 Y Associated Surveillance Using BCT-2000 CU2.1 SC.OP-AB.CR-0003 Control Room Habitability HA5.1 Y HS5.1 SC.OP-AB.CR-0004 Security Event HU4.1 No -Security Sensitive Procedure
-HA4.1 not included in submittal package HS4.1 HG4.1 SC.OP-AB.CR-0005 Airborne Threat HU4.1 No -Security Sensitive Procedure
-HA4.1 not included in submittal package HS4.1 HG4.1 SC.OP-AB.ZZ-0001 Adverse Environmental Conditions HUI.2 Y HA1.2 HA1.4 HAI.4 SC.OP-AB.ZZ-0004 Earthquake HUI.] Y HA1.1 SC.OP-DL.ZZ-001 I Reactor Coolant System Heatup/Cooldown Log CU4.1 Y CU4.2 CA4.1 SC.RA-AP.ZZ-0051 Leakage Monitoring and Reduction Program SU8.1 Y SCP Salem-Hope Creek Security Contingency Plan HU4.1 No -Safeguards Document -not HA4.1 included in submittal package HS4.1 SY-AA-101-132 Threat Assessment HU4.1 Y Page 13 of 14 Salem NEI 99-01, Rev. 05, EAL Submittaf Reference Material Checklist Rev. 01 Procedure Number Procedure Nomenclature EAL Number(s)Tech Specs and FSAR Reference Materials not included on Supporting Document CD All Tech Specs and FSAR Reference Materials Multiple EALs Collected
(\/N)No -Tech Specs and ISAR Reference Materials not included oni Supporting Document CD as NRC maintains current copies Vendor Doc # 320832 Emergency Operating Procedure Setpoint Document Salem SGI .1 No -Copy could not meet PDF Units 1 & 2 SG3.1 requirements for NRC electronic CB6-P submittal CB7-P CG3.2 Page 14 of 14