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In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Unit 1 and Unit 2 Reactor Buildings. This updated analysis has identified circuit configurations in four Fire Areas where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. These are Category 1 barrier impairments. In the Unit 1 Safe Shutdown Analysis, RCIC (1E51C001) (Path 1) components are impacted by a fire in Fire Area 1203. The postulated failure described above impacts HPCI (1E41C001) (Path 2) operation. Therefore, in the updated analysis there is no safe shutdown method for high pressure injection that remains free of fire damage for an Appendix R postulated fire in Fire Area 1203. While this represents an unanalyzed condition for Appendix R, the described scenario is only possible given a fire has occurred in Fire Area 1203. In the Unit 1 Safe Shutdown Analysis, Path 2 components are impacted by a fire in Fire Area 1205. The postulated failure described above impacts the 1E 4160 Kv (1R22S005) emergency bus power to Path 1 components. Therefore, in the updated analysis there is no safe shutdown method that remains available for an Appendix R postulated fire in Fire Area 1205. While this represents an unanalyzed condition for Appendix R, the described scenario is only possible given a fire has occurred in Fire Area 1205. In the Unit 2 Safe Shutdown Analysis, Path 2 components are impacted by a fire in Fire Area 2205. The postulated failure described above impacts the 2E 4160 Kv (2R22S005) emergency bus power to Path 1 components. Therefore, in the updated analysis there is no safe shutdown method that remains available for an Appendix R postulated fire in Fire Area 2205. While this represents an unanalyzed condition for Appendix R, the described scenario is only possible given a fire has occurred in Fire Area 2205. In the updated post-fire safe shutdown model, both safe shutdown paths include the same three options for Torus Water Temperature indication (1T48R072, 1T47R611 or 1T47R612). Only one of these three components is required to succeed, however, all are impacted by the postulated fire. Thus, there is no Unit 1 Torus Water Temperature Indication available for a fire in Fire Area 1205. While this represents an unanalyzed condition for Appendix R, the described scenario is only possible given a fire has occurred in Fire Area 1205. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. CR 10079009, 10079019, 10079022, 10079025 The licensee has notified the NRC Resident Inspector.

• * * UPDATE FROM STANLEY STONE TO DONALD NORWOOD AT 1634 EDT ON 6/17/2015 * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Unit 1 and Unit 2 Turbine Building. This updated analysis has identified circuit configurations in two Fire Areas where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. These are Category 1 barrier impairments. 1) In the Unit 1 Safe Shutdown Analysis, Path 1 RCIC components are impacted by a fire in Fire Area 1105. The postulated failure would impact Path 2 (HPCI) operation. Therefore, in the current analysis for the credited safe shutdown method for high pressure injection may be affected for an Appendix R postulated fire in Fire Area 1105. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1105. 2) In the updated post-fire safe shutdown model, both safe shutdown paths include the same two options for Torus Water Level Indication: 2T48-R622A and 2T48-R622B. Only one of these two components is required to succeed, however both would be impacted by a postulated fire in Fire Area 2104. Consequently, both credited paths of Unit 2 Torus Water Level Indication could potentially be affected due to a fire in Fire Area 2104. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2104. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. The analysis associated with the transition of the Plant Hatch Fire Protection Licensing Basis from Appendix R to NFPA 805 is continuing, and this and any subsequent similar conditions that meet reporting requirements will be in included in an ENS Update Report. CR 10084753, CR 10084757. The licensee notified the NRC Resident Inspector. Notified R2DO (HAAG).

• * * UPDATE FROM SCOTT BRITT TO VINCE KLCO ON 6/24/15 AT 2114 EDT * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Diesel Generator Building. This updated analysis has identified circuit configurations in five Fire Areas where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. These are Category 1 barrier impairments. 1) An Appendix R postulated fire in Fire Area 1404 is assessed to impact a cable required for RHR Inboard Injection Valve A, 1E11-F015A, to open. This cable was not identified in the current Safe Shutdown Analysis Report (SSAR) for this component. This valve is normally closed and is required to open to support the operation of RHR Loop A in LPCI mode, which is the credited Low Pressure Injection system for Unit 1 in support of Inventory Control to the RPV for a fire in Fire Area 1404. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1404. RHR Loop B is not available in this fire area due to fire impacts. 2) An Appendix R postulated fire in Fire Area 1408 is assessed to impact cables required for RHR Inboard Injection Valve B, 1E11-F015B, to open. These cables were not identified in the current Safe Shutdown Analysis Report (SSAR) for this component. This valve is normally closed and is required to open to support the operation of RHR Loop B in LPCI mode, which is the credited Low Pressure Injection system for Unit 1 in support of Inventory Control to the RPV for a fire in Fire Area 1408. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1408. RHR Loop A is not available in this fire area due to fire impacts. 3) An Appendix R postulated fire in Fire Area 1412 is assessed to impact a cable required for RHR Inboard Injection Valve B, 1E11-F015B, to open. This cable was not identified in the current Safe Shutdown Analysis Report (SSAR) for this component. This valve is normally closed and is required to open to support the operation of RHR Loop B in LPCI mode, which is the credited Low Pressure Injection system for Unit 1 in support of Inventory Control to the RPV for a fire in Fire Area 1412. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1412. RHR Loop A is not available in this fire area due to fire impacts. 4) An Appendix R postulated fire in Fire Area 2404 is assessed to impact a cable required for RHR Inboard Injection Valve B, 2E11-F015B, to open. This cable was not identified in the current Safe Shutdown Analysis Report (SSAR) for this component. This valve is normally closed and is required to open to support the operation of RHR Loop B in LPCI mode, which is the credited Low Pressure Injection system for Unit 2 in support of Inventory Control to the RPV for a fire in Fire Area 2404. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2404. RHR Loop A is not available in this fire area due to fire impacts. 5) An Appendix R postulated fire in Fire Area 2408 is assessed to impact cables required for RHR Inboard Injection Valve B, 2E11-F015B, to open. These cables were not identified in the current Safe Shutdown Analysis Report (SSAR) for this component. This valve is normally closed and is required to open to support the operation of RHR Loop B in LPCI mode, which is the credited Low Pressure Injection system for Unit 2 in support of Inventory Control to the RPV for a fire in Fire Area 2408. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2408. RHR Loop A is not available in this fire area due to fire impacts. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. The analysis associated with the transition of the Plant Hatch Fire Protection Licensing Basis from Appendix R to NFPA 805 is continuing, and this and any subsequent similar conditions that meet reporting requirements will be in included in an ENS Update Report. CR 10088142 The licensee will notify the NRC Resident Inspector. Notified the R2DO (O'Donohue).

• * * UPDATE AT 1739 EDT ON 08/13/15 FROM PAUL UNDERWOOD TO JEFF HERRERA * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Control Building. This updated analysis has identified circuit configurations in a Fire Area where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. This is a Category 1 barrier impairment. 1) An Appendix R postulated fire in Fire Area 0014 is assessed to impact a cable that is required for Diesel Building MCC 1C, 1R24-S027, to remain energized. Further analysis has shown that an inter-cable hot short between two conductors could cause the feeder breaker to this MCC to trip. This MCC is required to support the operation of Diesel Generator 1C, which is a credited power source in the Safe Shutdown analysis for both Unit 1 and Unit 2 in the event of a fire in this area. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0014. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. CR 10108999. The licensee notified the NRC Resident Inspector. Notified the R2DO (Nease).

• * * UPDATE AT 1331 EDT ON 08/25/15 FROM JOHN MITCHELL TO JEFF HERRERA * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48c (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Diesel Building. This updated analysis has identified circuit configurations in a Fire Area where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. This is Category 1 barrier impairment. 1) An Appendix R postulated fire in Fire Area 1408 is assessed to impact a cable that is required for Station Battery Chargers 1D, 1E, and 1F to remain energized. These chargers support 125V DC Switchgear 1B which is the credited DC Switchgear for Unit 1 Path 2 Safe Shutdown in the event of a fire in this area. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1408. 2) An Appendix R postulated fire in Fire Area 2408 is assessed to impact a cable that is required for Station Battery Chargers 2D, 2E, and 2F to remain energized. These chargers support 125V DC Switchgear 2B which is the credited DC Switchgear for Unit 2 Path 2 Safe Shutdown in the event of a fire in this area. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2408. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. The analysis associated with the transition of the Plant Hatch Fire Protection Licensing Basis from Appendix R to NFPA 805 is continuing, and this and any subsequent similar conditions that meet reporting requirements will be in included in an ENS Update Report.

CR 10113740, CR 10113745 The Licensee notified the NRC Resident Inspector. Notified the R2DO (Rose).

• * * UPDATE FROM KENNY HUNTER TO DONALD NORWOOD AT 1717 EDT ON 8/28/2015 * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Turbine Building. This updated analysis has identified circuit configurations in a Fire Area where an Appendix R postulated fire could impact the ability to achieve safe shutdown (SSD) conditions. This is a Category 1 barrier impairment. 1) An Appendix R postulated fire in Fire Area 1105 is assessed to impact cables which are required for HPCI Steam Supply Isolation MOV, 1E41-F002, to remain open. This valve is required open in support of HPCI (SSD Path 2), which is the credited form of high pressure injection in this fire area. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1105. 2) An Appendix R postulated fire in Fire Area 1104 is assessed to impact a cable required for the RCIC Vacuum Breaker Isolation MOV, 1E51-F105, to remain open. This valve is required open to ensure operability of the RCIC turbine if RCIC is required to stop and restart. Failure of this valve to remain open could cause a siphon that would impact the operability of RCIC, and thus disable Safe Shutdown Path 1 High Pressure Injection. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1104. In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10 CFR 50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Reactor Building. This updated analysis has identified circuit configurations in a Fire Area where an Appendix R postulated fire could impact the ability to achieve safe shutdown conditions. This is a Category 1 barrier impairment. 1) An Appendix R postulated fire in Fire Area 1203 is assessed to impact a cable required for HPCI Steam Supply Isolation MOV, 1E41-F002, to remain open. This valve is required open to ensure steam flow to the HPCI turbine. Failure of this valve to remain open would isolate steam to the HPCI turbine, which would disable HPCI, and thus disable Safe Shutdown Path 2 High Pressure Injection. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 1203. 2) An Appendix R postulated fire in Fire Area 2203 is assessed to impact cables required for RHR Outboard Injection Valve B, 2E11-F017B, to remain open. This valve is required open to support RHR Loop B in LPCI mode, which is the credited lineup for Path 2 Safe Shutdown Decay Heat Removal. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2203. 3) An Appendix R postulated fire in Fire Area 2203 is assessed to impact cables required for HPCI Vacuum Breaker Isolation Valve, 2E41-F104, to remain open. This valve is required open in support of Safe Shutdown Path 2 High Pressure Injection. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2203. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. The analysis associated with the transition of the Plant Hatch Fire Protection Licensing Basis from Appendix R to NFPA 805 is continuing, and this and any subsequent similar conditions that meet reporting requirements will be in included in an ENS Update Report. CR 10115432, CR10115473, CR10115436, CR10115446, CR10115444 The licensee will notify the NRC Resident Inspector. Notified R2DO (Rose).

• * * UPDATE PROVIDED BY GUY GRIFFIS TO JEFF ROTTON AT 1815 EDT ON 09/04/2015 * * *

In preparation for transitioning the Plant Hatch Fire Protection Licensing Basis from 10 CFR 50.48(b) (Appendix R) to 10CFR50.48(c) (NFPA 805), an update to the Plant Hatch Appendix R Safe Shutdown Analysis has been performed for the Control Building and Reactor Building. This updated analysis has identified circuit configurations in Fire Area's where an Appendix R postulated fire could impact the ability to achieve safe shutdown (SSD) conditions. These are Category 1 barrier impairments. 1) An Appendix R postulated fire in Fire Area 0024 is assessed to impact a cable that is required for Torus Suction Valve, 1E11-F065B to remain open. This valve is required to remain open in support of LPCI train B which is credited for Unit 1 Safe Shutdown in the event that the RPV has spuriously depressurized and low pressure inventory control is performed from the remote shutdown panel. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0024. 2) An Appendix R postulated fire in Fire Area 0024 is assessed to impact a cable required for Torus Suction Valve, 2E11-F065B to remain open. This valve is required to remain open in support of LPCI train B which is credited for Unit 2 Safe Shutdown in the event that the RPV has spuriously depressurized and low pressure inventory control is performed from the remote shutdown panel. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0024. 3) An Appendix R postulated fire in Fire Area 0014 is assessed to impact all three Air Handling Units; 1Z41-B003A, 1Z41-B003B, and 1Z41-B003C. The fire impacts a cable required for MCC 1C, 1R23-S003 to remain energized. This MCC supports the operation of Air Handling Unit B, 1Z41-B003B which is required in support of Main Control Room HVAC. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0014. 4) An Appendix R postulated fire in Fire Area 0031 is assessed to impact all three Air Handling Units; 1Z41-B003A, 1Z41-B003B, and 1Z41-B003C. These AHUs are required in support of MCR HVAC. MCR HVAC was not required in the current Safe Shutdown Analysis Report, and thus these failures were not evaluated in this fire area. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0031. 5) An Appendix R postulated fire in Fire Area 2014 is assessed to impact a cable required for Station Battery Chargers 2A (2R42-S026) 2B (2R42-S027) and 2C (2R42-S028) to remain energized. These chargers support 125 VDC Switchgear 2A (2R22-S016), which is the credited DC Switchgear for Path 1 Safe Shutdown. Path 2 Safe Shutdown is not available in this fire area due to fire impacts. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2014. 6) An Appendix R postulated fire in Fire Area 2014 is assessed to impact a cable required for 125 VDC Switchgear 2A (2R22-S016) to remain energized. This is the credited DC Switchgear for Path 1 Safe Shutdown. Path 2 Safe Shutdown is not available in this fire area due to fire impacts. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 2014. 7) An Appendix R postulated fire in Fire Area 0014 is assessed to impact cables required for Station Battery Chargers 1D (1R42-S029), 1E (1R42-S030), and 1F (1R42-S031) to remain energized. These chargers support 125VDC Switchgear 1B (1R22-S017) which is the credited DC Switchgear for Path 2 Safe Shutdown. Path 1 Safe Shutdown is not available in this fire area due to fire impacts. While this represents an unanalyzed condition for Appendix R, the described scenario presumes a fire has occurred in Fire Area 0014. Based on the updated Plant Hatch Appendix R Safe Shutdown analysis recommendations and the plant's Fire Hazard Analysis (FHA), compensatory measures have been taken and will remain in place until the conditions are resolved. The presence of the compensatory measures, in addition to portable fire protection equipment and installed fire protection and detection equipment, ensures the safe shutdown paths are preserved until the conditions are resolved. The analysis associated with the transition of the Plant Hatch Fire Protection Licensing Basis from Appendix R to NFPA 805 is continuing, and this and any subsequent similar conditions that meet reporting requirements will be in included in an ENS Update Report. CR 10118312, CR 10118328, CR10118333, CR10118338, CR10118345 The licensee will notify the NRC Resident Inspector. Notified R2DO (Seymour)

This is a non-emergency Event Notification made in accordance with 10 CFR 20.2201(a)(1)(ii) to inform the NRC of a nuclear material accountability discrepancy amounting to, in the aggregate, a portion of a spent fuel rod used at Plant Hatch (HNP). In the process of reviewing records and physically verifying the contents of the spent fuel pool (SFP) as a part of activities associated with SNC's (Southern Nuclear Company) response to Bulletin 2005-01, SNC has identified discrepancies between fuel segments located in the SFP and segments indicated in plant records. The segments originated in the early 1980s during fuel reconstitution and inspection activities. The discrepancies call into question the location of segments of single spent fuel rods in each of three bundles. Characterization of three segments located in the SFP provided rod serial numbers which, in turn, were used to determine the bundles from which these segments originated. These bundles were then inspected, and the length of fuel in the location corresponding to each rod segment's intended location was determined. The aggregate in-bundle length found in these rod locations was combined with the lengths of the segments located in the SFP and compared to the design active fuel length of the three rods. This comparison results in a material discrepancy of approximately 55 inches, based on the length measurements. In addition to this discrepancy, historical records indicate two segments (totaling 13 inches of fuel length), which may not be within the inventory of segments identified to date in the SFP. When this amount is added to the length associated with the three rod locations, a discrepancy of approximately 68 inches results. When the planned supplemental inspection of select bundles and SFP locations is completed and photographs are evaluated to aid in the determination of special nuclear material present, this 68 inch estimate may increase or decrease. On June 16, 2005 SNC formed a team to identify and characterize material in the SFPs at Hatch in order to account for special nuclear material (SNM) at the level of detail requested by Bulletin 2005-01. A work scope was established and specialized resources were contracted to support the work activities. During the performance of these work activities, a number of items of interest were characterized as being either SNM or non-SNM items. On October 28, 2005, SNC submitted the interim status report to NRC. On November 4, 2005 the Hatch Plant Review Board (PRB) reviewed the SNM Issue Resolution Team's assessment of data produced by the records searches and physical cataloging of SNM in the SFPs. Based on that review, the PRB concurred that a discrepancy exists in material accounting for a portion of a spent fuel rod in each of three bundles and records, as noted above, which in the aggregate approximates 68 inches of fuel rod length. This length is equivalent to about 45% of the length of one intact fuel rod. Further physical examination of the SFP will include additional examination of SFP floor areas that have not been examined to date and selected fuel bundle inspections. The SFP floor areas are limited to a small number of locations that are under equipment or objects stored on the SFP floor. This expanded work scope is expected to be completed by December 15, 2005. Based on the nature of the fuel rod segments and radiation monitoring, a high degree of confidence exists that the segments are in a restricted area of the plant or otherwise under the control of a licensed facility such that the public health and safety has not been adversely affected. In addition, there is no evidence of theft or diversion. This notification satisfies the 30-day notification requirement of 10 CFR 20.2201(a)(1)(ii). A subsequent written report will be made in accordance with 10 CFR 20.2201(b). The licensee has informed the NRC Resident Inspector regarding the discrepancies. SNC will be making a press release describing the current status of this issue. Accordingly, this notification also satisfies the 4-hour notification requirement of 10 CFR 50.72(b)(2)(xi) with respect to issuance of the press release associated with this issue.

• * * UPDATE AT 15:48 ON 8/21/2006 FROM FRANK GORLEY TO ABRAMOVITZ * * *

This is an update of non-emergency Event Notification 42135 that was previously made on November 10, 2005, in accordance with 10CFR 20.2201. This non-emergency Event Notification is made in accordance with 10 CFR 74.11 and informs the NRC of the loss of special nuclear material (SNM) from the historic breakage of several fuel rods used at Plant Hatch (HNP) in the early 1980s amounting to, in the aggregate, approximately 18 inches of a spent fuel rod. This amount is based on the available information, potentially affected by incomplete historic documentation. While reviewing records and physically verifying the contents of the spent fuel pool (SFP) in 2005 and 2006 associated with its response to Bulletin 2005-01, SNC identified discrepancies between fuel rod segments located in the SFP and segments indicated in plant records. This discrepancy was the subject of Event Notification 42135 and LER 2005-003 transmitted by letter NL-05-2262 dated 12/09/2005, including Rev. 1 of the LER, dated 04/14/2006 (transmitted by letter NL-06-0689). Additional locations in and around the fuel racks and additional fuel bundles were inspected between November 11, 2005, and July 21, 2006. Fuel vendor disorientation and plant SNM offsite shipping records reviews and quantity reconciliations were also recently completed. Based an the results of this expanded work scope, SNC concluded that some SNM material has been lost. This material either resides in some unidentified location in the SFP, resides in the bottom of the SFP as particles or small pieces, or was inadvertently shipped to a licensed low level waste processing facility. One SNM fragment, referred to as Item 30, was dropped during the physical activities in the pools and has not yet been recovered. This 4-1/2-inch fuel segment had been characterized and quantified and was dropped in the SFP during handling. A search was performed to look for item 30, but the intact segment was not found. During this search, a cladding segment with no appreciable SNM inside was located and identified as Item 32. It may be a portion of Item 30. Item 30's fuel length of 4-1/2 inches is included in the total characterized as lost. Based on the nature of the fuel rod segments, fragments, pellets, pellet chips, and small particles, and the barrier provided by in-plant radiation monitoring Instrumentation, a high degree of confidence exists that the lost SNM is either still in the SFP or was inadvertently shipped offsite to a licensed low level waste processing facility. Throughout its investigation and review, SNC has identified no evidence to indicate the possibility of theft or diversion of the missing quantity of SNM material. This notification satisfies the one-hour notification requirement of 10 CFR 74.11 (b). A subsequent written report will be made in accordance with 10CFR74.11(c). The licensee has informed the NRC Resident Inspector regarding the discrepancies and the conclusion regarding the lost material. SNC will be making a press release describing the current status of this issue. Accordingly, this notification also satisfies the 4-hour notification requirement of 10 CFR 50.72(b)(2)(xi) with respect to issuance of the press release associated with this issue. Notified the R2DO (Lesser), PAO (Brenner), and NRR EO (Jung).