ML032890431
| ML032890431 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/08/2003 |
| From: | Banner C Public Service Enterprise Group |
| To: | David Pinckney Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| Download: ML032890431 (16) | |
Text
Document Transmittal Form TO
- NRCC/O PINCKNEY, DAVID DOCUMENT CONTROL DESK ID: SECGO101 WASHINGTON, DC 20555 Date:
10/8/03 Please update your controlled set of documents with the following documents:
Document ID PRCISECG-SECG-TOCBASIS1000 PRCISECG-SECT.06.4 (BASIS)1000 Revision Status 18 A
I A
Quantity Format RecNo I
I H
177791 H
177829 ALL PAGES of this acknowledgement receipt must be returned to:
Document Management PSEG Nuclear PO Box 236 Hancocks Bridge, NJ 08038 MC N04 Your signature below verifies that:
(1) the above documents have been filed and superseded documents have been removed and destroyed or clearly marked as obsolete.
(2) the mailing address and copyholder information are correct or corrections have been identified on this transmittal.
[] Place checkmark here to be removed from controlled distribution Signature:
Date:
JNOLV5
SALEM GENERATING STATION EVENT CLASSIFICATION GUIDE TECHNICAL BASIS October 08, 2003 CHANGE PAGES FOR REVISION #18 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 #18 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 Remove and recycle the outdated material listed below.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 Pares Description Rev.
Pages Description TOC Rev.
All TOC 18 All 17 All Section 6.4 01 All Section 6.4 00 S-ECG 1 of 1
PSEG Internal Use Only SGS EAL Technical Basis T.O.C.
Pg. 1 of 4 SALEM ECG TECHNICAL 3ASIS TABLE OF CONTENTS/SIGNATURE PAGE SECTION TITLE REV #
PAGES DATE T.O.C.
i ii 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 Table of Contents/Signature Page Introduction and Usage Glossary of Acronyms & Abbreviations Fuel Clad Challenge RCS Challenge Fission Product Barriers (Table) 3.1 Fuel Clad Barrier 3.2 RCS Barrier 3.3 Containment Barrier EC Discretion Failure to Trip Radiological Releases/Occurrences 6.1 Gaseous Effluent Release 6.2 Liquid Effluent Release 6.3 In - Plant Radiation Occurrences 6.4 Irradiated Fuel Event Electrical Power 7.1 Loss of AC Power Capabilities 7.2 Loss of DC Power Capabilities System Malfunctions 8.1 Loss of Heat Removal Capability 8.2 Loss of Overhead Annunciators 8.3 Loss of Communications Capability 8.4 Control Room Evacuation 8.5 Technical Specifications Hazards - Internal/External 9.1 Security Threats 9.2 Fire 9.3 Explosion 9.4 Toxic/Flammable Gases 9.5 Seismic Event 9.6 High Winds 9.7 Flooding 9.8 Turbine Failure/Vehicle Crash/Missile Impact 9.9 River Level 18 00 00 01 01 4
10/08/03 3
01/21/97 6
01/21/97 4
12/29/99 2
07/24/00 02 02 05 00 03 20 02/27/03 16 01/16/01 26 01/31/03 8
01/21/97 9
12/18/01 00 00 00 01 42 4
6 10 01/21/97 01/21/97 01/21/97 10/08/03 02 00 11 01/16/01 8
01/21/97 01 02 00 01 00 10 12/29/99 6
07/24/00 4
01/21/97 4
12/18/01 2
01/21/97 02 02 02 03 02 01 02 02 01 9
02/01/02 6
01/16/01 5
01/16/01 12 09/26/02 4
09/26/02 5
01116/01 5
01/16/01 7
01/16/01 4
01/16/01 PSE&G x i >
CONTROL 1-SGS COPY #SFUC&,)01 Rev. 18
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 10.0 Reserved for future use Licensing is responsible for the Reportable Action Level (Section 11)
Reportable Action Levels (RALs) 11.1 Technical Specifications 11.2 Degraded or Unanalyzed Condition 11.3 System Actuation 11.4 Personnel Safety/Overexposure 11.5 Environmental/State Notifications 11.6 After-the-Fact 11.7 Security/Emergency Response Capabilities 11.8 Public Interest 11.9 Accidental Criticality/
Rad Material Shipments - Releases 11.10 Voluntary Notifications 01 02 04 01 02 02 03 01 02 01 9
01/23/01 4
01/23/01 7
04/19/02 7
01/23/01 4
10/01/03 1
02/28/02 5
02/28/02 3
01/23/01 8
01/23/01 2
01/23/01 SGS Rev. 18
PSEG Internal Use Only SGS EAL Technical Basis T.O.C.
Pg. 3 of 4 REVISION
SUMMARY
Biennial Review Perforned: Yes__
No X Updated EAL Basis for 6.4.2.a and 6.4.2.b to correct reference to EALs for other conditions.
SGS Rev. 18
PSEG Internal Use Only SGS EAL Technical Basis T.O.C.
Pg. 4 of 4 SIGNATURE PAGE Prepared By:
Craig Banner 09/17/03 Date Section/Attachments Revised:
N/A (List Non Editorial Only - Section/Attachments)
N/A Date Reviewed By:
Reviewed By:
N/A 10CFR50.54q Effectiveness Reviewer N/A Date N/A Date N/A Department Manager Reviewed By:
N/A Manager - Licensing N/A Date Reviewed By:
EP Managei ate Reviewed By:
NA Manager - Quality Assurance (If Applicable)
N/A Date SORC Review and Station Approvals Mtg. No.
NA Salem Chairman N/A Vice President - Nuclear Operations N/A Date N/A Date Effective Date of this Revision:
Date Rev. +- /6 SGS
SGS EAL/RALTechnical Basis 6.0 Radiological Releases/Occurrences 6.4 Irradiated Fuel Event UNUSUAL EVENT - 6.4.1.a IC Unplanned increase in Plant Radiation EAL PSE&G
- t..-
CONTROL by I-Vs COPY #Quito I An uncontrolled level drop in the Refueling Cavity as indicated by EITHER one of the following:
- Visual observation RVLIS - Refueling Mode MODE - 6 BASIS This EAL condition indicates a possible failure of the Refueling Cavity Seal or RHR System that results in inventory loss from the Refueling Cavity when flooded. Coverage of these events is appropriate due to the potential for higher doses to plant staff. These events have a long lead time relative to potential for radiological release outside the site boundary, thus the impact to public health and safety is very low. Classification as an Unusual Event is warranted as a precursor to a more serious event. Uncontrolled means that the level drop cannot be terminated, or level cannot be maintained by operator action.
Barrier Analysis N/A ESCALATION CRITERIA This event will be escalated to an Alert as a result of uncovery of a fuel assembly and/or indication of high radiation levels on the refueling floor.
DISCUSSION Design of the Refueling Cavity is such that a liner failure in these volumes is unlikely; however, should such a failure occur, it would come under this EAL. If uncovery of fuel elements occur or EAL - 6.4.L.a Rev. 01 Page 1 of 2
SGS EAL/RALTechnical Basis if there is indication of high radiation levels on the refuel floor then the event will be classified as an Alert.
During refueling operations the Reactor Vessel and Refuel Cavity are flooded. During fuel handling operations, the Fuel Transfer Tube will connect the Reactor Cavity and the Spent Fuel Pool. An unexplained lowering of Refuel Cavity level or Spent Fuel Pool level can be an indication that these volumes are draining. A drop in Reactor Cavity and Spent Fuel Pool level may result in a Spent Fuel Pool low level alarm. This alarm would be validated by visual observation of lowering level in the Refuel Cavity/Spent Fuel Pool.
DEVIATION NUMARC states that this EAL will be applicable in all modes of operation. In modes other than Mode 6 the Reactor Vessel head will be fully tensioned and there will be no interconnection between the Refueling Cavity and the Spent Fuel Pool. In other modes, a loss of Reactor Vessel inventory is addressed in Section 3. Uncontrolled loss of water level in the Spent Fuel Pool, however, is classified under EAL 6.4.1.b in all modes of operation.
REFERENCES NUMARC NESP-007, AU2.1 OP-ARZZ-0003(Q) OHA-C35 OP-AB.FUEL-0002(Q)
EAL - 6.4.1.a Rev. 01 Page 2 of 2
SGS EAL/RALTechnical Basis 6.0 Radiological Releases/Occurrences 6.4 Irradiated Fuel Event UNUSUAL EVENT - 6.4.1.b IC Unplanned increase in Plant Radiation EAL Valid SFP Low Level alarm - OHA C-35 AND Visual observation of an uncontrolled level drop in the Spent Fuel Pool MODE - All BASIS These EAL conditions indicate a possible failure of the Spent Fuel Pool Cooling System that results in inventory loss from the Spent Fuel Pool. This EAL also works in conjunction with the loss of Refueling Cavity EAL for Mode 6 operations, with the Spent Fuel Pool and Refueling Cavity connected via the Fuel Transfer Canal.
Coverage of this event is appropriate due to the potential for higher doses to plant staff. This event has a long lead time relative to potential for radiological release outside the site boundary, thus the impact to public health and safety is very low. Classification as an Unusual Event is warranted as a precursor to a more serious event. Uncontrolled means that the level drop cannot be terminated, or level cannot be maintained by operator action.
Barrier Analysis N/A ESCALATION CRITERIA Emergency Classification will escalate to an Alert as a result of uncovery of a irradiated fuel as indicated by high radiation levels in the Fuel Handling Building.
EAL - 6.4.L.b Rev. 01 Page 1 of 2
SGS EAL/RALTechnical Basis DISCUSSION Design of the Spent Fuel Pool (SFP) is such that a liner failure in this volume is unlikely; however, should such a failure occur, it would be classified under this EAL. Lowering of water level in the SFP to below the level of the spent fuel bundles may result in a rise in the airborne contamination level in the Fuel Handling Building. If uncovery of fuel elements occurs or if there is indication of high radiation levels in the Fuel Handling Building, then the event will be classified as an Alert.
This alarm would be validated by visual observation of lowering level in the Spent Fuel Pool.
The added requirement for an uncontrolled drop in SFP level with a low level alarm is included to allow normal makeup to recover level for minor level deviations due to evaporation losses, etc.
DEVIATION None REFERENCES NUMARC NESP-007, AU2.2 OP-AR.ZZ-0003(Q) OHA-C35 OP-AB.FUEL-0002(Q)
EAL - 6.4.L.b Rev. 01 Page 2 of 2
SGS EAL/RALTechnical Basis 6.0 Radiological Releases/Occurrences 6.4 Irradiated Fuel Event ALERT - 6.4.2.a IC Major Damage to Irradiated Fuel or Loss of Water Level that has or will result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel EAL Major Damage to Irradiated Fuel reported in the Fuel Handling Bldg.
AND Valid High Alarm is received on EITHER one of the following RMS channels:
R5 R32A AND Valid High Alarm received from EITHER one of the following RMS channels:
R41 R45 MODE - All BASIS Major Damage to an irradiated fuel bundle that results in a High Fuel Handling Building Radiation Monitor alarm coincident with a Plant Vent Effluent Process Radiation Monitor alarm warrants declaration of an Alert, due to the potential for an offsite release exceeding the Technical Specification limit. The intent of this EAL is to classify those events that result in the actual release of fission products from an irradiated Fuel Bundle, due to physical damage. Events that result in higher radiation levels due to shine, as a result of lowered shielding, but do not involve a release of fission products should not be classified under this EAL, but should be classified EAL 6.4.2.c, when those conditions exist.
Major Damage is defined as physical damage to an Irradiated Fuel Bundle that results from either dropping or physical contact with other components, such that the magnitude of the EAL - 6.4.2.a Rev. 01 Page 1 of 2 I1-
SGS EAL/RALTechnical Basis damage specifically results in actuation of an Area Radiation Alarm. Valid is defined as the High alarm occurring as a result of the damage to the irradiated fuel bundle.
Barrier Analysis N/A ESCALATION CRITERIA Emergency Classification will escalate to a Site Area Emergency when loss of control of radioactive materials causes significant offsite doses.
DISCUSSION The Fuel Handling Building Area Monitors provide an early warning of developing problems which may be related to a damaged fuel bundle. The Plant Vent Exhaust Rad Monitors are Process Monitors and are designed to detect a release of Fission Products. Hence, they are included as part of the EAL threshold, to confirm the magnitude of damage to an irradiated fuel bundle.
DEVIATION None REFERENCES NUMARC NESP-007, AA2.1 OP-AR.ZZ-0003(Q) OHA-C35 OP-AB.FUEL-0002(Q)
NUREG/CR-4982 NRC Information Notice no. 90-08 10CFR50 EAL - 6.4.2.a Rev. 01 Page 2 of 2
SGS EAL/RALTechnical Basis 6.0 Radiological Releases/Occurrences 6.4 Irradiated Fuel Event ALERT - 6.4.2.b IC Major Damage to Irradiated Fuel or Loss of Water Level that has or will result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel EAL Major Damage to Irradiated Fuel reported in the Containment AND Valid High Alarm received on ANY one of the following RMS channels:
R2 R1OA
- ROB AND Valid High Alarm received from ANY one of the following RMS channels:
- RlA R12A R12B MODE - All BASIS Major Damage to an irradiated fuel bundle that result in a High Containment Area Radiation Monitor alarm coincident with a Containment Process Radiation Monitors alarm warrants declaration of an Alert, due to the potential for an offsite release exceeding the Technical Specification limit. The intent of this EAL is to classify those events that result in the potential release of fission products from an irradiated Fuel Bundle, due to physical damage. Events that result in higher radiation levels due to shine, as a result of lowered shielding, but do not involve a release of fission products should not be classified under this EAL, but should be classified EAL 6.4.2.c, when those conditions exist.
I EAL - 6.4.2.b Rev. 01 Page 1 of 2
SGS EAL/RALTechnical Basis Major Damage is defined as physical damage to an Irradiated Fuel Bundle that results from either dropping or physical contact with other components, such that the magnitude of the damage specifically results in actuation of an Area Radiation Alarm. Valid is defined as the High alarm occurring as a result bf the damage to the irradiated fuel bundle.
Barrier Analysis N/A ESCALATION CRITERIA Emergency Classification will escalate to a Site Area Emergency when loss of control of radioactive materials causes significant offsite doses.
DISCUSSION The Containment Area Monitors provide an early warning of developing problems which may be related to a damaged fuel bundle. The Containment Rad Monitors are Process Monitors and are designed to detect a release of Fission Products. Hence, they are included as part of the EAL threshold, to confirm the magnitude of damage to an irradiated fuel bundle.
DEVIATION None REFERENCES NUMARC NESP-007, AA2.1 OP-AR.ZZ-0003(Q) OHA-C35 OP-AB.FUEL-0002(Q)
NUREG/CR-4982 NRC Information Notice no. 90-08 EPA 400-R-92-00 1, Manual of Protective Action Guide and Protective Actions for Nuclear Incidents EAL - 6.4.2.b Rev. 01 Page 2 of 2
SGS EAL/RALTechnical Basis 6.0 Radiological Releases/Occurrences 6.4 Irradiated Fuel Event ALERT - 6.4.2.c/6.4.2.d IC Major Damage to Irradiated Fuel or Loss of Water Level that has or will result in the Uncovering of Irradiated Fuel Outside the Reactor Vessel EAL EITHER one of the following:
- Unplanned rise on ANY one of the following Area Rad Monitors or by general area rad survey indicates > 2000 mRem/hr R2 R5 R9 R32A
- Visual observation of Irradiated Fuel uncovered MODE - All BASIS This EAL indicates a possible failure of the Refueling Cavity Seal, RHR System, or Spent Fuel Pool Cooling System that results in inventory loss from the Refueling Cavity when flooded or the Spent Fuel Pool. Design of the Refueling Cavity and Spent Fuel Pool is such that a liner failure in these volumes is unlikely; however, should such a failure occur, it would come under this EAL. Lowering of water level in the Spent Fuel Pool to such a value as to cause Dose Rates to increase to this value will result in evacuation of the local areas. Uncovery of irradiated fuel elements can lead to their fuel clad failure due to loss of cooling.
The term "unplanned" is defined as those events which are not associated with a pre-planned evolutions such that radiation levels are increasing for reasons which cannot be immediately explained. The EAL addresses radiation levels which would impede operation of systems required to continue efforts to stop the loss of Refueling water level. Radiation levels could be indicated by ARM or radiological survey. The Dose Rate of 2000 mRem/hr was chosen as a threshold based upon NAP-24 Administrative Dose Limits and Extension criteria which has Senior Radiation Protection Supervisor approval required prior to exceeding 2000 mRem/yr.
EAL - 6.4.2.c/ 6.4.2.d Rev. 01 Page 1 of 2
SGS EAL/RALTechnical Basis This value is low enough to ensure classification of an Alert before personnel access is severely hampered and high enough to allow any unplanned rise in normal radiation level, by a factor of 1000, to be classified as an Unusual Event per EAL 6.3.1.
Visual observation of irradiated fuel uncovered will result in onsite dose levels changing significantly.
The Area Radiation Monitors included in this EAL are:
- R2 Containment, General Area Low R5 Fuel Handling Building Area Fuel Pool R9 Fuel Handling Building Fuel Storage Area R32A Spent Fuel Handling Crane, Area Monitor Barrier Analysis N/A ESCALATION CRITERIA This event will be escalated to a Site Area Emergency when loss of control of radioactive materials causes significant offsite doses.
DISCUSSION It is understood that a drop in Refueling Cavity water level will cause Dose Rates to rise due to the uncovery of irradiated Reactor components other than a spent fuel assembly. However, Dose Rates in excess of 2 Rem/hr indicate a loss of level such that recovery options may be limited and thus an Alert declaration is warranted.
DEVIATION None REFERENCES NUMARC NESP-007, AA2.3 and AA2.4 OP-AR.ZZ-0003(Q) OHA-C35 OP-AB.FUEL-0002(Q)
NUREG/CR-4982 NRC Information Notice no. 90-08 EAL - 6.4.2.c/ 6.4.2.d Rev. 01 Page 2 of 2