ML030650804
| ML030650804 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/27/2003 |
| From: | Public Service Enterprise Group |
| To: | David Pinckney Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| SECG0101 | |
| Download: ML030650804 (26) | |
Text
Document Transmittal Form ID: SECGO101 TO : NRC CIO PINCKNEY, DAVID DOCUMENT CONTROL DESK WASHINGTON, DC 20555 Date : 2/27/03 with the following documents:
Please update your controlled set of documents Revision Status Quantity Format RecNo Document ID A H 160818 16 1 H 160856 PRCISECG-SECG-TOC-BASISl000 2 A PRClSECG.SECT.03.1 (BASIS)1000 to:
ALL PAGES of this acknowledgement receipt must be returned Document Management PSEG Nuclear PO Box 236 Hancocks Bridge, NJ 08038 MC N04 Your signature below verifies that:
documents have been removed and (1) the above documents have been filed and superseded destroyed or clearly marked as obsolete.
are correct or corrections have been (2) the mailing address and copyholder information identified on this transmittal.
n] Place checkmark here to be removed from controlled distribution Date:
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SALEM GENERATING STATION EVENT CLASSIFICATION GUIDE TECHNICAL BASIS February 27, 2003 CHANGE PAGES FOR REVISION #16 The Table of Contents forms a general guide to the current revision of each section and attachment of the Salem ECG Technical Basis. The changes that are made in this TOC Revision #16 are shown below.
- 1. Check that your revision packet is complete.
- 2. Add the revised documents.
- 3. Remove and recycle the outdated material listed below.
ADD REMOVE Pages Description Rev. Pacres Description Rev.
All TOC 16 All TOC 15 All Section 3.1 02 All Section 3. 01 iv a S-ECG 1 of 1
PSEG Internal Use Only SGS EAL Technical Basis PSE&G T.o.c.
Pg. I of 4 SALEM ECG TECHNICAL BASIS CONTROL TABLE OF CONTENTS/SIGNATURE PAM PY #.
ýa-6.)6)of SECTION TITLE REV # PAGES DATE T.O.C. Table of Contents/Signature Page 16 4 02/27/03 i Introduction and Usage 00 3 01/21/97 ii Glossary of Acronyms & Abbreviations 00 6 01/21/97 1.0 Fuel Clad Challenge 01 4 12/29/99 2.0 RCS Challenge 01 2 07/24/00 3.0 Fission Product Barriers (Table) 3.1 Fuel Clad Barrier 02 20 02/27/03 3.2 RCS Barrier 02 16 01/16/01 3.3 Containment Barrier 05 26 01/31/03 4.0 EC Discretion 00 8 01/21/97 5.0 Failure to Trip 03 9 12/18/01 6.0 Radiological Releases/Occurrences 6.1 Gaseous Effluent Release 00 42 01/21/97 6.2 Liquid Effluent Release 00 4 01/21/97 6.3 In - Plant Radiation Occurrences 00 6 01/21/97 6.4 Irradiated Fuel Event 00 10 01/21/97 7.0 Electrical Power 7.1 Loss of AC Power Capabilities 02 11 01/16/01 7.2 Loss of DC Power Capabilities 00 8 01/21/97 8.0 System Malfunctions 8.1 Loss of Heat Removal Capability 01 10 12/29/99 8.2 Loss of Overhead Annunciators 02 6 07/24/00 8.3 Loss of Communications Capability 00 4 01/21/97 8.4 Control Room Evacuation 01 4 12/18/01 8.5 Technical Specifications 00 2 01/21/97 9.0 Hazards - Internal/External 9.1 Security Threats 02 9 02/01/02 9.2 Fire 02 6 01/16/01 9.3 Explosion 02 5 01/16/01 9.4 Toxic/Flammable Gases 03 12 09/26/02 9.5 Seismic Event 02 4 09/26/02 9.6 High Winds 01 5 01/16/01 9.7 Flooding 02 5 01/16/01 9.8 Turbine Failure/Vehicle Crash/Missile Impact 02 7 01/16/01 9.9 River Level 01 4 01/16/01 SGS Rev. 16
PSEG Internal Use Only SGS EAL Technical Basis T.O.C.
Pg. 2 of 4 SALEM ECG TECHNICAL BASIS TABLE OF CONTENTS/SIGNATURE PAGE SECTION TITLE REV # PAGES DATE Reserved for future use Licensing is responsible for the Reportable Action Level (Section 11)
Reportable Action Levels (RALs) 11.1 Technical Specifications 01 9 01/23/01 11.2 Degraded or Unanalyzed Condition 02 4 01/23/01 11.3 System Actuation 04 7 04/19/02 11.4 Personnel Safety/Overexposure 01 7 01/23/01 11.5 Environmental/State Notifications 01 4 01/23/01 11.6 After-the-Fact 02 1 02/28/02 11.7 Security/Emergency Response 03 5 02/28/02 Capabilities 11.8 Public Interest 01 3 01/23/01 11.9 Accidental Criticality/ 02 8 01/23/01 Special Nuclear Material /
Rad Material Shipments - Releases 11.10 Voluntary Notifications 01 2 01/23/01 SGS Rev. 16
PSEG Internal Use Only SGS EAL Technical Basis T.O.C.
Pg. 3 of 4 REVISION
SUMMARY
Biennial Review Performed: Yes -No X Added EP03-001 reference under REFERENCES that address removal of the PASS system from the FSAR in EAL basis 3.1.2 and 3.1.5 SGS Rev. 16
PSEG Internal Use Only SGS EAL Technical Basis T.O.C.
Pg. 4 of 4 SIGNATURE PAGE Prepared By: William Detwiler 02/20/2003 Date Section/Attachments Revised: N/A N/A (List Non Editorial Only - Section/Attachments) Date Reviewed By: N/A N/A 10CFR50.54q Effectiveness Reviewer Date Reviewed By: N/A N/A Department Manager Date Reviewed By: N/A N/A Date Reviewed By:
Manager Date Reviewed By: NA N/A Manager - Quality Assurance Date (If Applicable)
SORC Review and Station Approvals NA N/A Mtg. No. Salem Chairman Vice President - Nuclear Operations N/A N/A Date Date Effective Date of this Revision: 02/27/03 Date SGS Rev. 16
SGS EAL/RALTechnical Basis 3.0 Fission Product Barriers PSE&G 3.1 Fuel Clad Barrier CONTROL 3.1.1 CRITICAL SAFETY STATUS COPY 3.1.1.a IC Potential Loss of Fuel Clad Barrier = 3 POINTS EAL MODE - 1, 2,3,4 BASIS Core Cooling PURPLE Path, as verified by EOP-CFST-l, indicates that subcooling has been lost and that some clad damage may occur.
Barrier Analysis Fuel Clad Barrier has been potentially lost.
ESCALATION CRITERIA This event will be classified and/or escalated based on the potential loss or loss of additional barriers per EAL Section 3.0.
DISCUSSION Symptom based criteria from the Emergency Operating Procedures Critical Safety Function Tree (CFST) Monitoring are integrated into this EAL. The CFSTs are contained as a tab to the ECG.
The intent of using confirmed CFST status in this EAL is to simplify the identification of the EAL threshold criteria monitored in the Control Room. CFST status will not be used for event classification until the Control Room Staff has implemented the CFSTs.
DEVIATION Salem Generating Station replaced the CFST "Orange Path" color designation with "Purple Path" due to the limitations imposed by the SPDS CRT's color gun configuration.
EAL - 3.1.L.a Rev. 02 Page 1 of 2
SGS EALIRALTechnical Basis REFERENCES NUMARC NESP-007, FC1 EOP-CFST-1 EOP-TRIP-1 EAL - 3.1.1.a Rev. 02 Page 2 of 2
SGS EAL/RALTechnical Basis 3.0 Fission Product Barriers 3.1 Fuel Clad Barrier 3.1.1 CRITICAL SAFETY FUNCTION STATUS 3.1.1.b IC Potential Loss of Fuel Clad Barrier =3 POINTS EAL MODE - 1,2,3,4 BASIS Heat Sink RED Path, as verified by EOP-CFST-1, indicates that Steam Generator dryout could occur. A loss of Heat Sink poses an extreme challenge to the Fuel Clad. A barrier loss classification should not be made if the Heat Sink RED Path is the result of procedurally required Auxiliary Feedwater flow control.
Barrier Analysis Fuel Clad and RCS Barriers have been potentially lost.
ESCALATION CRITERIA This event will be classified and/or escalated based on the potential loss or loss of additional barriers per EAL Section 3.0.
DISCUSSION Symptom based criteria from the Emergency Operating Procedures Critical Safety Function Tree (CFST) Monitoring are integrated into this EAL. The CFSTs are contained as a tab to the ECG.
The intent of using confirmed CFST status in this EAL is to simplify the identification of the EAL threshold criteria monitored in the Control Room. CFST status will not be used for event classification until the Control Room Staff has implemented the CFSTs.
EAL - 3.1.1.b Rev. 02 Page 1 of 2
SGS EAL/RALTechnical Basis DEVIATION None REFERENCES NUMARC NESP-007, FCI EOP-CFST-1 EOP-TRIP-1 FRHS-1 EAL - 3.1.1.b Rev. 02 Page 2 of 2
SGS EAL/RALTechnical Basis 3.0 Fission Product Barriers 3.1 Fuel Clad Barrier 3.1.1 CRITICAL SAFETY FUNCTION STATUS 3.1.1.c IC Loss of Fuel Clad Barrier =4 POINTS EAL MODE - 1,2,3,4 BASIS Core Cooling RED Path, as verified by EOP-CFST-1, is definitive indication that the heat transfer from the fuel to the coolant has degraded leading to a fuel clad heatup, significant superheating and core uncovery.
Barrier Analysis Fuel Clad Barrier has been lost and the Primary Containment Barrier has been potentially lost.
ESCALATION CRITERIA This event will be classified and/or escalated based on the potential loss or loss of additional barriers per EAL Section 3.0.
DISCUSSION Symptom based criteria from the Emergency Operating Procedures Critical Safety Function Tree (CFST) Monitoring are integrated into this EAL. The CFSTs are contained as a tab to the ECG.
The intent of using confirmed CFST status in this EAL is to simplify the identification of the EAL threshold criteria monitored in the Control Room. CFST status will not be used for event classification until the Control Room Staff has implemented the CFSTs.
EAL- 3.1.1.c Rev. 02 Page 1 of 2
SGS EAL/RALTechnical Basis DEVIATION None REFERENCES NUMARC NESP-007, FC1 EOP-CFST-1 EOP-TRIP-1 FRCC-1 EAL- 3.1.1.c Rev. 02 Page 2 of 2
SGS EAL/RALTechnical Basis 3.0 Fission Product Barriers 3.1 Fuel Clad Barrier 3.1.2 PRIMARY COOLANT IODINE CONCENTRATION IC Loss of Fuel Clad Barrier = 4 POINTS EAL MODE - 1, 2,3,4 BASIS A reactor coolant sample activity of greater than 300 pCi/gm Dose Equivalent Iodine-131 (DEI 131) was determined to indicate significant clad heating or mechanical stress and is indicative of the loss of the fuel clad barrier. This concentration is well above that expected for iodine spikes and corresponds to approximately 2.5% clad damage.
Barrier Analysis Fuel Clad Barrier has been lost.
ESCALATION CRITERIA This event will be classified and/or escalated based on the potential loss or loss of additional barriers per EAL Section 3.0.
DISCUSSION The actual value of 300 pCi/gm Dose Equivalent Iodine-131 (DEI-131) was determined based upon an engineering calculation which is not included with this EAL. This calculation was prepared by the Nuclear Fuels Group and is on file with Emergency Preparedness under file title DS 1.6-0098 "Verification of Emergency Action Levels for Event Classification" date 1/26/95.
DEVIATION None EAL - 3.1.2 Rev. 02 Page 1 of 2
SGS EAL/RALTechnical Basis REFERENCES NUMARC NESP-007, FC2 Reg. Guide 1.109, Table E-9 SGS-USFAR, Table 11.1-1 SGS-USFAR, Table 11.1-7 OP-AB.RC-0002(Q)
Calculation by Nuclear Fuels Group file title DS 1.6-0098 "Verification of Emergency Action Levels for Event Classification" date 1/26/95.
EP03-001 I EAL - 3.1.2 Rev. 02 Page 2 of 2
SGS EAL/RALTechnical Basis 3.0 Fission Product Barriers 3.1 Fuel Clad Barrier 3.13 CORE EXIT THERMOCOUPLES (CETS) 3.1.3.a IC Potential Loss of Fuel Clad Barrier = 3 POINTS EAL MODE - 1, 2,3,4, BASIS The threshold value chosen is from the EOP-CFST-l Core Cooling Status Tree and indicates a loss of core subcooling which could lead to clad damage.
Barrier Analysis Fuel Clad Barrier has been potentially lost.
ESCALATION CRITERIA This event will be classified and/or escalated based upon the potential loss or loss 3f additional barriers per EAL Section 3.0.
DISCUSSION Symptom based criteria from the EOP Critical Safety Function Tree (CFST) monitoring are integrated into this EAL. The CFSTs are contained as a tab to the ECG. Use of Core Exit Thermocouple (CET) temperature to indicate loss of subcooling is equivalent to the CFST Core Cooling status codes.
DEVIATION Salem Generating Station replaced the CFST "Orange Path" color designation wAth "Purple Path" due to the limitations imposed by the SPDS CRT's color gun configuration.
EAL - 3.1.3.a Rev. 02 Page 1 of 2
SGS EAL/RALTechnical Basis REFERENCES NUMARC NESP-007, FC3 EOP-CFST-1 EOP-TRIP-1 EOP-Setpoint Doe (G.03)
EAL - 3.1.3.a Rev. 02 Page 2 of 2
SGS EAL/RALTechnical Basis 3.0 Fission Product Barriers 3.1 Fuel Clad Barrier 3.1.3 CORE EXIT THERMOCOUPLES (CETS) 3.1.3.b IC Loss of Fuel Clad Barrier =4 POINTS EAL MODE - 1,2,3,4 BASIS Five Core Exit Thermocouple (CET) temperatures >1200 OF indicates a significant superheating of the reactor coolant.
Barrier Analysis Fuel Clad Barrier has been lost.
ESCALATION CRITERIA This event will be classified and/or escalated based on the potential loss or loss of additional barriers per EAL Section 3.0.
DISCUSSION Symptom based criteria from the Emergency Operating Procedures Critical Safety Function Tree (CFST) Monitoring are integrated into this EAL. The CFSTs are contained as a tab to the ECG.
The EAL threshold of >1200 OF is equivalent to CFST Core Cooling RED Path.
DEVIATION None EAL - 3.1.3.b Rev. 02 Page 1 of2
SGS EAL/RALTechnical Basis REFERENCES NUMARC NESP-007, FC3 EOP-CFST-1 EOP-TRIP-1 EOP-Setpoint Doc (G.04)
EAL - 3.1.3.b Rev. 02 Page 2 of 2
SGS EAL/RALTechnical Basis 3.0 Fission Product Barriers 3.1 Fuel Clad Barrier 3.1.4 RX VESSEL LEVEL INDICATION SYSTEM (RVLIS) 3.1.4.a IC Potential Loss of Fuel Clad Barrier = 3 POINTS EAL MODE - 1, 2,3,4 BASIS The threshold value of RVLIS Full Range < 39% is chosen from the EOP-CFST-1 Core Cooling Status Tree. This value approximates the "Top of Active Fuel" which is a water level at which clad damage may be expected to occur.
Barrier Analysis Fuel Clad Barrier has been potentially lost.
ESCALATION CRITERIA This event will be classified and/or escalated based upon the potential loss or loss of additional barriers per EAL Section 3.0.
DISCUSSION Symptom based criteria from the EOP Critical Safety Function Tree (CSFT) monitoring are integrated into this EAL. The CFSTs are contained as a tab to the ECG. Use of RVLIS to indicate reactor vessel water level is more specific than the CFST Core Cooling status codes.
Full Range RVLIS indicates reactor vessel water level with no RCPs running. The intent of this EAL is to provide a RVLIS level which approximates core uncovery. The actual RVLIS level which indicates "Top of Active Fuel" is somewhat higher than 39%; however, 39% was adopted to be consistent with the CFST value.
EAL - 3.1.4.a Rev. 02 Page 1 of 2
SGS EAL/RALTechnical Basis DEVIATION Salem Generating Station replaced the CFST "Orange Path" color designation with "Purple Path" due to the limitations imposed by the SPDS CRT's color gun configuration.
REFERENCES NUMARC NESP-007, FC4 EOP-CFST-1 EOP-TRIP-1 EOP-Setpoint Doc (G.03)
EAL - 3.1.4.a Rev. 02 Page 2 of 2
SGS EAL/RALTechnical Basis 3.0 Fission Product Barriers 3.1 Fuel Clad Barrier 3.1.4 RX VESSEL LEVEL INDICATION SYSTEM (RVLIS) 3.1.4.b IC Potential Loss of Fuel Clad Barrier = 3 POINTS EAL RVLIS Dynamic Range Indicates ANY one of the following:
- 4 RCPs I/S <44%
- 3 RCPs I/S <30%
- 2 RCPs I/S <20%
- 1 RCP I/S<13%
MODE - 1, 2,3,4 BASIS The threshold values for RVLIS Dynamic Range levels with various combinations of RCPs is chosen from the EOP-CFST-1 Core Cooling Status Tree. These values correspond to a 50%
void fraction which may result in clad damage.
Barrier Analysis Fuel Clad Barrier has been potentially lost.
ESCALATION CRITERIA This event will be classified and/or escalated based upon the potential loss or loss of additional barriers per EAL Section 3.0.
DISCUSSION /
Symptom based criteria from the EOP Critical Safety Function Tree (CSFT) monitoring are integrated into this EAL. The CFSTs are contained as a tab to the ECG. Use of RVLIS to indicate reactor vessel water level is more specific than the CFST Core Cooling Purple Path EAL - 3.1.4.b Rev. 02 Page 1 of2
SGS EAL/RALTechnical Basis status codes. Dynamic Range RVLIS indicates reactor vessel water level when at least I RCP is running. The intent of this EAL is to provide a RVLIS level which approximates a 50 % RCS void fraction. With this void fraction, a loss of all operating RCPs could lead to core uncovery.
DEVIATION Salem Generating Station replaced the CFST "Orange Path" color designation with "Purple Path" due to the limitations imposed by the SPDS CRT's color gun configuration.
REFERENCES NUMARC NESP-007, FC4 EOP-CFST-1 EOP-TRIP-1 EOP-Setpoint Doc (L.01)
K-;
EAL- 3.1.4.b Rev. 02 Page 2 of 2
SGS EAL/RALTechnical Basis 3.0 Fission Product Barriers 3.1 Fuel Clad Barrier 3.1.5 CONTAINMENT RADIATION LEVELS IC Loss of Fuel Clad Barrier = 4 POINTS EAL MODE - 1, 2,3,4 BASIS The reading of 300 R/hr on the containment high range monitor (R44A or R44B) indicates the loss of the Fuel Clad fission product barrier. The reading was calculated assuming an instantaneous release of the Reactor Coolant volume into the Primary Containment at an RCS Activity of 300 pCi/gm Dose Equivalent Iodine 131. This value is much larger than Technical Specification allowed Iodine spikes and corresponds to fuel clad damage of approximately 2.5%.
Barrier Analysis Fuel Clad and RCS Barriers have been lost.
ESCALATION CRITERIA This event will be classified and/or escalated based upon the loss or potential loss of the Primary Containment barrier per EAL Section 3.0 DISCUSSION This calculation is based upon a concentration of 300 pCi/gm Dose Equivalent Iodine 131 as it relates to R44 measured Dose Rate values. This calculation was prepared by the Nuclear Fuels Group and is on file with Emergency Preparedness under file title DS 1.6-0098 "Verification of Emergency Action Levels for Event Classification" date 1/26/95.
EAL - 3.1.5 Rev. 02 Page 1 of 2
SGS EAL/RALTechnical Basis DEVIATION None REFERENCES NUMARC NESP-007, FC5 Calculation by Nuclear Fuels file title DS 1.6-0098 "Verification of Emergency Action Levels for Event Classification EP03-001 EAL- 3.1.5 Rev. 02 Page 2 of 2
SGS EAL/RALTechnical Basis 3.0 Fission Product Barriers 3.1 Fuel Clad Barrier 3.1.6 EMERGENCY COORDINATOR JUDGMENT 3.1.6.a/ 3.1.6.b IC Potential Loss (= 3 POINTS) or Loss of Fuel Clad Barrier (= 4 POINTS)
EAL ANY condition, in the opinion of the EC, that indicates EITHER a Potential Loss OR Loss of the Fuel Clad Barrier MODE - 1, 2,3,4 BASIS This EAL allows the Emergency Coordinator (EC) to address any factor not otherwise covered in the Fission Product Barrier Table to determine that the Fuel Clad barrier has been lost or K_ potentially lost. A complete loss in the ability to monitor the Fuel Clad barrier should be considered a "Potential Loss" of that barrier.
Barrier Analysis The Fuel Clad Barrier has been lost or potentially lost.
ESCALATION CRITERIA This event will be classified and/or escalated based on the loss or potential loss of additional barriers per EAL section 3.0.
DISCUSSION None DEVIATION None EAL - 3.1.6.af 3.1.6.b Rev. 02 Page 1 of 2
SGS EAL/RALTechnical Basis REFERENCES NUMARC NESP-007, FC7 EAL - 3.1.6.a/3.1.6.b Rev. 02 Page 2 of 2