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| , Alabama Power Company 40 inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Telephone 205 868-5581 W. G. Hairston, til Senior Vice President h
| | , Alabama Power Company 40 inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Telephone 205 868-5581 W. G. Hairston, til h |
| Nuclear Operations M8ballla Power the southem electnc system March 23,1989 Docket Nos. 50-348 50-364 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Vashington, D.C. 20555 Gentlemen Joseph M. Parley Muclear Plant - Units 1 and 2 ; | | Senior Vice President Nuclear Operations M8ballla Power the southem electnc system March 23,1989 Docket Nos. 50-348 50-364 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Vashington, D.C. |
| Miniflov Evaluation - NRC Bulletin No. 88-04 By letter of November 30, 1988, Alabama Power Company provided additional I information as committed in its July 8, 1988 response to NRC Bulletin No. | | 20555 Gentlemen Joseph M. Parley Muclear Plant - Units 1 and 2 Miniflov Evaluation - NRC Bulletin No. 88-04 By letter of November 30, 1988, Alabama Power Company provided additional I |
| 88-04. This letter which provided an update on Alabama Power Company's response to the bulletin was not submitted under " oath or affirmation". At the verbal request of the Farley NRC Project Manager, however, the {{letter dated|date=November 30, 1988|text=November 30, 1988 letter}} is being resubmitted under " oath or affirmation". | | information as committed in its July 8, 1988 response to NRC Bulletin No. |
| NRC Bulletin No. 88-04, " Potential Safety Related Pump Loss," requires ; | | 88-04. |
| Alabama Power Company to investigate and correct, if applicable, two j miniflow design concerns. l The Bulletin requires that each safety-related system be evaluated for pump-to-pump interaction during miniflov operation. If pump-to-pump i interaction is possible, the system is required to be evaluated from a flow division standpoint. The Bulletin further requires an evaluation to address the adequacy of the minimum flow bypass lines for safety-related centrifugal pumps with respect to damage resulting from operation and testing. | | This letter which provided an update on Alabama Power Company's response to the bulletin was not submitted under " oath or affirmation". |
| | At the verbal request of the Farley NRC Project Manager, however, the {{letter dated|date=November 30, 1988|text=November 30, 1988 letter}} is being resubmitted under " oath or affirmation". |
| | NRC Bulletin No. 88-04, " Potential Safety Related Pump Loss," requires Alabama Power Company to investigate and correct, if applicable, two j |
| | miniflow design concerns. |
| | l The Bulletin requires that each safety-related system be evaluated for pump-to-pump interaction during miniflov operation. |
| | If pump-to-pump i |
| | interaction is possible, the system is required to be evaluated from a flow division standpoint. The Bulletin further requires an evaluation to address the adequacy of the minimum flow bypass lines for safety-related centrifugal pumps with respect to damage resulting from operation and testing. |
| The Bulletin reporting requirements include submittal of a short-term (60 day) report which (a) summarizes the problems and the systems affected, (b) identifies the short-term and long-term modifications to plant operating procedures or hardware that have been or are being implemented to ensure safe plant operations, (c) identifies an appropriate schedule for long-term resolution of this and/or other significant problems that are identified as a result of this bulletin, and (d) provides justification for continued operation particularly with regard to General Design Criterion 35 of Appendix A to Title 10 of the Code of Federal Regulations (10 CFR 50), | | The Bulletin reporting requirements include submittal of a short-term (60 day) report which (a) summarizes the problems and the systems affected, (b) identifies the short-term and long-term modifications to plant operating procedures or hardware that have been or are being implemented to ensure safe plant operations, (c) identifies an appropriate schedule for long-term resolution of this and/or other significant problems that are identified as a result of this bulletin, and (d) provides justification for continued operation particularly with regard to General Design Criterion 35 of Appendix A to Title 10 of the Code of Federal Regulations (10 CFR 50), |
| " Emergency Core Cooling" and 10 CFP. 50.46, " Acceptance Criteria for Emergency Core Cooling Systehi for Light Water Nuclear Power Reactors."
| | " Emergency Core Cooling" and 10 CFP. 50.46, " Acceptance Criteria for Emergency Core Cooling Systehi for Light Water Nuclear Power Reactors." |
| Additionally, a long-term resolution report is required to be submitted within 30 days of the completion of the long-term resolution actions. | | Additionally, a long-term resolution report is required to be submitted within 30 days of the completion of the long-term resolution actions. |
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| 8903300096 890323 1 PDR ADOCK 05000348 I 0 PDC g | | 8903300096 890323 1 |
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| 'U. S. Nuclear Regulatory Commission March 23, 1989 Page 2 By {{letter dated|date=July 8, 1988|text=letter dated July 8, 1988}}, Alabama Power Company provided a partial response to the Bulletin and committed to provide a status of evaluation efforts by November 30, 1988. The results of evaluations on safety-related pumps are outlined in Attachment 1. All evaluations are complete with the exception of the evaluation required for the auxiliary feedvater (AFV)-
| | 'U. S. Nuclear Regulatory Commission March 23, 1989 Page 2 By {{letter dated|date=July 8, 1988|text=letter dated July 8, 1988}}, Alabama Power Company provided a partial response to the Bulletin and committed to provide a status of evaluation efforts by November 30, 1988. The results of evaluations on safety-related pumps are outlined in Attachment 1. |
| pumps. Due to the increased work load placed on the pump vendor by the Bulletin, a final evaluation of the AFV pumps is scheduled to be completed in May, 1989. Alabama Power Company vill provide the results of the AFV pump evaluation and a long-term action schedule within 60 days of evaluation completion. Continued operation of the AFV pumps until completion of the evaluation is justified in Attachment 1. For all other i | | All evaluations are complete with the exception of the evaluation required for the auxiliary feedvater (AFV)- |
| | pumps. Due to the increased work load placed on the pump vendor by the Bulletin, a final evaluation of the AFV pumps is scheduled to be completed in May, 1989. Alabama Power Company vill provide the results of the AFV pump evaluation and a long-term action schedule within 60 days of evaluation completion. Continued operation of the AFV pumps until completion of the evaluation is justified in Attachment 1. |
| | For all other i |
| pumps evaluated, evaluations have shown that there is no significant pump-to-pump interaction and the current minimum flow lines are adequate. | | pumps evaluated, evaluations have shown that there is no significant pump-to-pump interaction and the current minimum flow lines are adequate. |
| If there are any questions, please advise. | | If there are any questions, please advise. |
| Respectfully submitted, A1.ABAMA POVER COMPANY lb. . ha $ | | Respectfully submitted, A1.ABAMA POVER COMPANY lb. |
| V. G. Hairston, III VGH,III/ REM:pr-5.16 Attachment cc: Mr. S. D. Ebnetter Mr. E. A. Reeves Mr. G. F. Maxwell SVORN TO AND SUBSCRIBED BEFORE ME THIS J3 d DAY of %m[ , 1989 dluna(] Notary lhdf}L-}</rf/] Public My Commission Expires DEEN | | . ha V. G. Hairston, III VGH,III/ REM:pr-5.16 Attachment cc: |
| | Mr. S. D. Ebnetter Mr. E. A. Reeves Mr. G. F. Maxwell SVORN TO AND SUBSCRIBED BEFORE ME |
| | %m[ |
| | , 1989 THIS J3 d DAY of dluna lhdf}L-}</rf/] |
| | (] Notary Public DEEN My Commission Expires |
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| ATTACHMENT 1 SYSTEM DESCRIPTION AND EVALUATION System: High Head Safety Injection / Charging Pumps: 3 Charging pumps (HHSI) per unit Miniflow | | ATTACHMENT 1 SYSTEM DESCRIPTION AND EVALUATION System: |
| | High Head Safety Injection / Charging Pumps: |
| | 3 Charging pumps (HHSI) per unit Miniflow |
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| == Description:== | | == Description:== |
| A miniflow line from each HHSI pump discharges into a common miniflow header. | | A miniflow line from each HHSI pump discharges into a common miniflow header. |
| Pump-to-Pump Interaction: Pump-to-pump interaction is precluded by the use of a 60 GPM high resistance minimum flow orifice in the miniflow line from each HHSI l pump. The individual miniflow lines combine l into a low resistance common header. | | Pump-to-Pump Interaction: |
| Adequacy of Miniflow: The HHSI pump miniflow lines have a greater capacity than originally required by the pump vendor. The system designer, in conjunction with the pump vendor, has evaluated the adequacy of the minimum flow lines. The required thermal minimum flow is substantially below the expected pump flow for all operating modes. The required mechanical minimum flow to prevent hydraulic instability and mechanical damage is lower than the expected minimum flow which results from cach mode of operation. | | Pump-to-pump interaction is precluded by the use of a 60 GPM high resistance minimum flow orifice in the miniflow line from each HHSI l |
| System: Lov Head Safety Injection / Residual Heat Removal (RHR) | | pump. The individual miniflow lines combine l |
| Pumps: 2 RHR pumps per unit Miniflow | | into a low resistance common header. |
| | Adequacy of Miniflow: |
| | The HHSI pump miniflow lines have a greater capacity than originally required by the pump vendor. The system designer, in conjunction with the pump vendor, has evaluated the adequacy of the minimum flow lines. The required thermal minimum flow is substantially below the expected pump flow for all operating modes. The required mechanical minimum flow to prevent hydraulic instability and mechanical damage is lower than the expected minimum flow which results from cach mode of operation. |
| | System: |
| | Lov Head Safety Injection / Residual Heat Removal (RHR) |
| | Pumps: |
| | 2 RHR pumps per unit Miniflow |
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| == Description:== | | == Description:== |
| Each RHR pump has an independent miniflow line. | | Each RHR pump has an independent miniflow line. |
| Pump-to-Pump Interaction: Pump-to-pump interaction is precluded by use f of independent miniflov lines. ! | | Pump-to-Pump Interaction: |
| Adequacy of Miniflow: The RHR pump miniflow lines have a greater { | | Pump-to-pump interaction is precluded by use f |
| capacity than originally required by the pump i j vendor. The system designer, in conjunction i with thin pump vendor, has evaluated the < | | of independent miniflov lines. |
| adequacy of the minimum flow lines. The ' | | Adequacy of Miniflow: |
| requireo thermal minimum flow is substantially . | | The RHR pump miniflow lines have a greater |
| below the expected pump flow for all operating l modas. The required mechanical minimum flov s to prevent hydraulic instability and i mechanical damage is lover than the expected . | | { |
| minimum flow which results from each mode of operation. | | capacity than originally required by the pump i |
| i System: Containment Spray (CS) l Pumps: 2 CS pumps per unit l | | j vendor. The system designer, in conjunction i |
| | with thin pump vendor, has evaluated the adequacy of the minimum flow lines. The requireo thermal minimum flow is substantially below the expected pump flow for all operating l |
| | modas. The required mechanical minimum flov s |
| | to prevent hydraulic instability and i |
| | mechanical damage is lover than the expected minimum flow which results from each mode of operation. |
| | i System: |
| | Containment Spray (CS) l Pumps: |
| | 2 CS pumps per unit l |
| l | | l |
| _ _ _ _j | | _ _ _ _j |
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| Attechment.l' Syst03 Deacriptiens cnd Evaluations | | Attechment.l' Syst03 Deacriptiens cnd Evaluations |
| 'P g2 2 Miniflow
| | 'P g2 2 Miniflow |
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| == Description:== | | == Description:== |
| Each CS pump has a recirculation line which-joins to form a common return header to the Refueling Vater Storage Tank (RWST). Normally locked closed valves are provided in the recirculation' lines and in the common header for isolation. This piping arrangement is utilized as a means to test the spray pumps without spraying into containment. In addition, each pump has a spray eductor recirculation line. | | Each CS pump has a recirculation line which-joins to form a common return header to the Refueling Vater Storage Tank (RWST). Normally locked closed valves are provided in the recirculation' lines and in the common header for isolation. This piping arrangement is utilized as a means to test the spray pumps without spraying into containment. In addition, each pump has a spray eductor recirculation line. |
| Pump-to-Pump Interaction: During accident situations, and all surveillance testing except for the " Spray and Phase B Actuation Test", the operation of the two trains is completely independent, with the exception of a common portion of the suction line from the RWST. The pumps can develop sufficient discharge pressure to exceed the containment design pressure such-that there is no possibility of deadheading a pump during spray actuation. During individual pump surveillance testing (Spray Pump Honthly, Quarterly and Annual Testing) the spray header is isolated, however, each pump's miniflow path to the RVST is available to prevent deadheading. During the " Spray and Phase B l Actuation Surveillance Test" the discharge headers are isolated, and the two pumps are ! | | Pump-to-Pump Interaction: |
| l run simultaneously in parallel with flov directed to the common miniflow line. The
| | During accident situations, and all surveillance testing except for the " Spray and Phase B Actuation Test", the operation of the two trains is completely independent, with the exception of a common portion of the suction line from the RWST. The pumps can develop sufficient discharge pressure to exceed the containment design pressure such-that there is no possibility of deadheading a pump during spray actuation. During individual pump surveillance testing (Spray Pump Honthly, Quarterly and Annual Testing) the spray header is isolated, however, each pump's miniflow path to the RVST is available to prevent deadheading. |
| , surveillance procedure requires that the time i the spray pumps are run in parallel be held to a maximum of 1 minute. .The resistance-in the common miniflow path is high relative to that in the individual ~line. Hence, given a mismatch between the pump ~ developed heads, it is possible for the pressure at the junction point (where the discharge heads combine) to be high enough to prevent one pump from recirculating to the RVST. This condition is considered acceptable because (1) the pumps only run for one minute maximum and (2) the spray eductor recirculation line in essence provides an individual and independent minimum flow path.
| | During the " Spray and Phase B l |
| Adequacy of Miniflow: The system der.igner, in conjunction with the I pump vendor, has evaluated the adequacy of the l minimum flov lines. The required thermal I minimum flow is substantially below the expected pump flow for all operating modes. | | Actuation Surveillance Test" the discharge headers are isolated, and the two pumps are l |
| The required mechanical minimum flow to prevent hydraulic instability and mechanical j damage is lower than the expected minimum flov ' | | run simultaneously in parallel with flov directed to the common miniflow line. The surveillance procedure requires that the time i |
| l vhich results from each mode of operation. ;
| | the spray pumps are run in parallel be held to a maximum of 1 minute..The resistance-in the common miniflow path is high relative to that in the individual ~line. Hence, given a mismatch between the pump ~ developed heads, it is possible for the pressure at the junction point (where the discharge heads combine) to be high enough to prevent one pump from recirculating to the RVST. This condition is considered acceptable because (1) the pumps only run for one minute maximum and (2) the spray eductor recirculation line in essence provides an individual and independent minimum flow path. |
| | Adequacy of Miniflow: |
| | The system der.igner, in conjunction with the I |
| | pump vendor, has evaluated the adequacy of the l |
| | minimum flov lines. The required thermal I |
| | minimum flow is substantially below the expected pump flow for all operating modes. |
| | The required mechanical minimum flow to prevent hydraulic instability and mechanical j |
| | damage is lower than the expected minimum flov l |
| | vhich results from each mode of operation. |
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| Attach::nt 1 | | Attach::nt 1 |
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| | .Systs2 D2scriptions and Evaluations |
| .Systs2 D2scriptions and Evaluations
| | ~ |
| *Psg2 3 Systems Auxiliary Feedvater_ (AFW) i Pumps: 2 motor driven AFV pumps per unit i 1 turbine driven AFV pump per unit .!
| | *Psg2 3 Systems Auxiliary Feedvater_ (AFW) i Pumps: |
| Miniflow | | 2 motor driven AFV pumps per unit i |
| | 1 turbine driven AFV pump per unit Miniflow |
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| == Description:== | | == Description:== |
| A continuously open miniflow line from each AFV pump discharges into a common miniflow header. | | A continuously open miniflow line from each AFV pump discharges into a common miniflow header. |
| Pump-to-Pump Interaction: Pump-to-pump interaction is precluded by the use of a high resistance minimum flow orifice and check valve in the miniflov line from each AFV pump. The miniflow orifice was supplied " | | Pump-to-Pump Interaction: |
| by the pump vendor and installed following the vcndor's technical manual. | | Pump-to-pump interaction is precluded by the use of a high resistance minimum flow orifice and check valve in the miniflov line from each AFV pump. The miniflow orifice was supplied by the pump vendor and installed following the vcndor's technical manual. |
| Adequacy of Miniflow: The use of the vendor supplied miniflow orifice, installed following the vendor's technical manual, has resulted in a miniflow capacity which meets original requirements. | | Adequacy of Miniflow: |
| The pump vendor, in conjunction with the . | | The use of the vendor supplied miniflow orifice, installed following the vendor's technical manual, has resulted in a miniflow capacity which meets original requirements. |
| | The pump vendor, in conjunction with the. |
| system designer, is evaluating the adequacy of the miniflov line for long-term operation. | | system designer, is evaluating the adequacy of the miniflov line for long-term operation. |
| Due to the pump vendor's workload.and engineering staff size, the evaluation is not expected to be completed until early 1989. | | Due to the pump vendor's workload.and engineering staff size, the evaluation is not expected to be completed until early 1989. |
| Continued operation of the MDAFV and TDAFV pumps is justified for the near term based on l the following considerations: | | Continued operation of the MDAFV and TDAFV pumps is justified for the near term based on l |
| | the following considerations: |
| (a) Damage of the pumps due to internal recirculation has not been experienced to date, nor is the manufacturer aware of minimum flow problems with similar type pumps in other plants. | | (a) Damage of the pumps due to internal recirculation has not been experienced to date, nor is the manufacturer aware of minimum flow problems with similar type pumps in other plants. |
| (b) The minimum flow rates are not affected because of interaction during parallel operation. This is a result of the high flow resistances of the individual j minimum flow orifices. | | (b) The minimum flow rates are not affected because of interaction during parallel operation. This is a result of the high flow resistances of the individual j |
| ]
| | minimum flow orifices. |
| (c) The degradation due to operation with low minimum flow rates is gradual. Because , | | ] |
| of this and because the pumps operate I infrequently at minimum. flow, life of the i pump would not be degraded with less than l desirable miniflow. I i | | (c) The degradation due to operation with low minimum flow rates is gradual. |
| Furthermore, required routine i maintenance, inspections and surveillance testing are expected to detect any l excessive wear or damage well before system performance is degraded. 1 | | Because of this and because the pumps operate I |
| )
| | infrequently at minimum. flow, life of the i |
| | pump would not be degraded with less than l |
| | desirable miniflow. |
| | I i |
| | Furthermore, required routine i |
| | maintenance, inspections and surveillance l |
| | testing are expected to detect any excessive wear or damage well before system performance is degraded. |
| | 1 |
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| I 1 | | I 1 |
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| Attechment 1 l Systc3 Descriptions cnd Evaluations i | | Attechment 1 l |
| *P ga 4 l Systems Component Cooling Vater (CCV) ,
| | Systc3 Descriptions cnd Evaluations i |
| i )
| | *P ga 4 l |
| Pumps: 3 CCV pumps per unit Miniflow | | Systems Component Cooling Vater (CCV) i |
| | ) |
| | Pumps: |
| | 3 CCV pumps per unit Miniflow |
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| == Description:== | | == Description:== |
| A separate recirculation line from the CCV pump discharge to the CCV pump suction is provided for each pump. The recirculation line contains a minimum flow orifice provided by the pump manufacturer. A check valve is located in the discharge line dovnstream of the recirculation line connection for each pump. | | A separate recirculation line from the CCV pump discharge to the CCV pump suction is provided for each pump. The recirculation line contains a minimum flow orifice provided by the pump manufacturer. |
| Pump-to-Pump Interaction: Pump-to-pump interaction is precluded by providing a separate recirculation line for each pump. | | A check valve is located in the discharge line dovnstream of the recirculation line connection for each pump. |
| Adequacy of Miniflow: During normal operation, the miniflow line is isolated and the system designer has determined that the system flovrate is adequate to prevent pump degradation. The Unit 2 Inservice Testing Program contains the only known requirement to run the CCV pumps solely on miniflow. The Unit 2 Inservice Testing Program is expected to be revised as part of the second ten year update (spring 1989 outage) to eliminate the requirement. | | Pump-to-Pump Interaction: |
| | Pump-to-pump interaction is precluded by providing a separate recirculation line for each pump. |
| | Adequacy of Miniflow: |
| | During normal operation, the miniflow line is isolated and the system designer has determined that the system flovrate is adequate to prevent pump degradation. The Unit 2 Inservice Testing Program contains the only known requirement to run the CCV pumps solely on miniflow. The Unit 2 Inservice Testing Program is expected to be revised as part of the second ten year update (spring 1989 outage) to eliminate the requirement. |
| The Unit 1 Inservice Testing Program has already been revised te eliminate the requirement. The system designer, in conjunction with the pump vendor, has determined that the miniflow line is adequate provided that the duration of operation is minimized. | | The Unit 1 Inservice Testing Program has already been revised te eliminate the requirement. The system designer, in conjunction with the pump vendor, has determined that the miniflow line is adequate provided that the duration of operation is minimized. |
| System: Service Water (aV) | | System: |
| Pumps: 5 SV pumps per unit Miniflow | | Service Water (aV) |
| | Pumps: |
| | 5 SV pumps per unit Miniflow |
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| == Description:== | | == Description:== |
| The 5 SV pumps are divided as illustrated in Pigure 1. SV pumps A and B are A train pumps. | | The 5 SV pumps are divided as illustrated in Pigure 1. |
| SV pumps D and E are B train pumps. SV pump C is a sving pump which may be aligned to the A or B train. A common miniflow is provided for pumps A and B. A common miniflow is provided for pumps D and E. Pump C is provided with 1 its own miniflow line. The control valves for all of the miniflow lines are set to open at 130 psig. Additionally the SV system contains a 24 inch dilution bypass line which { | | SV pumps A and B are A train pumps. |
| ultimately discharges to the rive *. The dilution bypass line control va7ve opens at 100 psig. | | SV pumps D and E are B train pumps. |
| | SV pump C is a sving pump which may be aligned to the A or B train. A common miniflow is provided for pumps A and B. |
| | A common miniflow is provided for pumps D and E. |
| | Pump C is provided with 1 |
| | its own miniflow line. The control valves for all of the miniflow lines are set to open at 130 psig. |
| | Additionally the SV system contains |
| | { |
| | a 24 inch dilution bypass line which ultimately discharges to the rive *. The dilution bypass line control va7ve opens at 100 psig. |
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| Attschment 1 Systea Descriptions cnd Evoluttions P ga 5 l 1 | | Attschment 1 Systea Descriptions cnd Evoluttions P ga 5 l |
| Pump-to-Pump Interaction: The SV system is not designed to preclude ) | | 1 Pump-to-Pump Interaction: |
| pump-to-pump interaction while on miniflow. { | | The SV system is not designed to preclude |
| Operation of pumps A and B or pumps D and E, ; | | ) |
| in conjunction with pump C, could result in ) | | pump-to-pump interaction while on miniflow. |
| multiple pumps discharging to a common header ! | | { |
| with miniflow protection. Plant operators are ! | | Operation of pumps A and B or pumps D and E, in conjunction with pump C, could result in |
| procedurally directed to start and secure SV-pumps in order to maintain SV header pressure between'70 to 100 psig.. With'the procedural j guidance.that is available to operators, I pump-to-pump interaction in the SV header is j precluded. I Adequacy of Miniflow: The pump vendor has stated that "we do not-recommend the minimum continuous throttled flow to be less than thirty-five percent (35%) | | ) |
| of the pump capacity at Best Efficiency Point-(BEP). This calculates to approximately 3150 , | | multiple pumps discharging to a common header with miniflow protection. |
| GPM..." The SV pump miniflow lines are sized ; | | Plant operators are procedurally directed to start and secure SV-pumps in order to maintain SV header pressure between'70 to 100 psig.. With'the procedural j |
| to handle 3150 GPM/ pump. Additionally, the ( | | guidance.that is available to operators, I |
| I dilution bypass line, which opens before the J l SV pump miniflov line, provides additional protection for SV pumps during operation. The l system designer, in conjunction with the pump l vendor,.has determined that there are no l circumstances under which the SW pumps vill operate at flow rates lov enough to adversely affect the pumps. | | pump-to-pump interaction in the SV header is j |
| System Diesel Generator (DG) Fuel Oil (FO) | | I precluded. |
| Pumps: 5 manual FO transfer pumps 5 automatic F0 transfer pumps Miniflow | | Adequacy of Miniflow: |
| | The pump vendor has stated that "we do not-recommend the minimum continuous throttled flow to be less than thirty-five percent (35%) |
| | of the pump capacity at Best Efficiency Point-(BEP). This calculates to approximately 3150 GPM..." |
| | The SV pump miniflow lines are sized to handle 3150 GPM/ pump. Additionally, the |
| | ( |
| | I dilution bypass line, which opens before the J |
| | l SV pump miniflov line, provides additional protection for SV pumps during operation. The l |
| | system designer, in conjunction with the pump l |
| | vendor,.has determined that there are no l |
| | circumstances under which the SW pumps vill operate at flow rates lov enough to adversely affect the pumps. |
| | System Diesel Generator (DG) Fuel Oil (FO) |
| | Pumps: |
| | 5 manual FO transfer pumps 5 automatic F0 transfer pumps Miniflow |
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| == Description:== | | == Description:== |
| The DG F0 system has no miniflow lines. The F0 transfer pumps take a. suction on the F0 storage tanks and discharge to the day tanks or other F0 storage tanks. | | The DG F0 system has no miniflow lines. The F0 transfer pumps take a. suction on the F0 storage tanks and discharge to the day tanks or other F0 storage tanks. |
| 1 l | | 1 l |
| Pamp-to-Pump Interaction: If the F0 transfer pumps are operated in parallel, possible dead heading of a pump ]- | | Pamp-to-Pump Interaction: |
| could occur. Procedures do not provide for operating pumps in parallel. A precaution against parallel operation has been added to the operating procedure. Therefore, j pump-to-pump interaction is preclude / | | If the F0 transfer pumps are operated in |
| System: Boric Acid Transfer (BAT) System ! | | ] |
| Pumps: 2 Boric Acid Transfer Pumps per unit | | parallel, possible dead heading of a pump could occur. |
| )
| | Procedures do not provide for operating pumps in parallel. |
| | A precaution against parallel operation has been added to the operating procedure. Therefore, j |
| | pump-to-pump interaction is preclude / |
| | System: |
| | Boric Acid Transfer (BAT) System Pumps: |
| | 2 Boric Acid Transfer Pumps per unit |
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| l Attach: nt I Systcm Descriptions end Ev21untiens , | | l Attach: nt I Systcm Descriptions end Ev21untiens |
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| ," 'P gs 6 l
| | 'P gs 6 l |
| l Miniflow | | l l |
| | Miniflow |
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| == Description:== | | == Description:== |
| Each BAT pump has an independent miniflow line l which recirculates to the boric acid tanks. - | | Each BAT pump has an independent miniflow line which recirculates to the boric acid tanks. |
| However, the system may be physically aligned such that both pumps discharge to the same i miniflow line. | | However, the system may be physically aligned such that both pumps discharge to the same i |
| l Pump-to-Pump Interaction: Pun:p-to-pump interaction is precluded through the use of procedures which prevent the operator from starting both pumps and operating them through the same miniflow line. | | miniflow line. |
| Adequacy of Miniflow: The system designer, in conjunction with the pump vendor, has evaluated the adequacy of the minimum flov line. The required thermal minimum flov is substantially below the expected pump flow for all operating modes. | | l Pump-to-Pump Interaction: |
| The required mechanical minimum flow to prevent hydraulic instability and mechanical damage is lover than the expected minimum flov l vhich results from each mode of operation. | | Pun:p-to-pump interaction is precluded through the use of procedures which prevent the operator from starting both pumps and operating them through the same miniflow line. |
| System: Spent Fuel Pool Cooling Pumps: 2 Spent Fuel Pit Pumps per unit Miniflow | | Adequacy of Miniflow: |
| | The system designer, in conjunction with the pump vendor, has evaluated the adequacy of the minimum flov line. The required thermal minimum flov is substantially below the expected pump flow for all operating modes. |
| | The required mechanical minimum flow to prevent hydraulic instability and mechanical damage is lover than the expected minimum flov l |
| | vhich results from each mode of operation. |
| | System: |
| | Spent Fuel Pool Cooling Pumps: |
| | 2 Spent Fuel Pit Pumps per unit Miniflow |
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| |
|
| == Description:== | | == Description:== |
| The Spent Fuel Pit system does not include a miniflow provision for these pumps. | | The Spent Fuel Pit system does not include a miniflow provision for these pumps. |
| Pump-to-Pump Interaction: Operating procedures provide for only one spent fuel pool cooling loop on service at a time. Therefore, pump-to-pump interaction is precluded by operating only one pump at a i time. | | Pump-to-Pump Interaction: |
| Adequacy of Miniflow: Normal operation of the Spent Fuel Pool Cooling system is to throttle flow across the pump to 54 psid. This operational philosophy results in system pumps operating in the vicinity of the best efficiency point. Since these pumps are not operated at flows that would require miniflow, no additional action is required. | | Operating procedures provide for only one spent fuel pool cooling loop on service at a time. Therefore, pump-to-pump interaction is precluded by operating only one pump at a i |
| | time. |
| | Adequacy of Miniflow: |
| | Normal operation of the Spent Fuel Pool Cooling system is to throttle flow across the pump to 54 psid. This operational philosophy results in system pumps operating in the vicinity of the best efficiency point. |
| | Since these pumps are not operated at flows that would require miniflow, no additional action is required. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217G0801999-10-0707 October 1999 Informs That on 990930,staff Conducted mid-cycle PPR of Farley & Did Not Identify Any Areas in Which Performance Warranted More than Core Insp Program.Nrc Will Conduct Regional Insps Associated with SG Removal & Installation ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212J8391999-09-30030 September 1999 Forwards RAI Re Request for Amends to Ts.Addl Info Needed to Complete Review to Verify That Proposed TS Are Consistent with & Validate Design Basis Analysis.Request Discussed with H Mahan on 990930.Info Needed within 10 Days of This Ltr ML20212J8801999-09-30030 September 1999 Discusses GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps. Util 980731,990607 & 03 Ltrs Provided Requested Info in Subj Gl.Nrc Considers Subj GL to Be Closed for Unit 1 ML20212E7031999-09-23023 September 1999 Responds to GL 98-01, Year 2000 Readiness of Computer Sys at Npps. Util Requested to Submit Plans & Schedules for Resolving Y2K-related Issues ML20212F1111999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20212D4581999-09-10010 September 1999 Responds to to D Rathbun,Requesting Review of J Sherman Expressing Concerns That Plant & Other Nuclear Plants Not Yet Y2K Compliant ML20212C8041999-09-10010 September 1999 Responds to to D Rathbun Requesting Review of J Sherman Re Y2K Compliance.Latest NRC Status Rept on Y2K Activities Encl ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211N8041999-09-0808 September 1999 Informs That on 990930 NRC Issued GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Condition, to Holders of Nuclear Plant Operating Licenses ML20212C0071999-09-0202 September 1999 Forwards Insp Repts 50-348/99-05 & 50-364/99-05 on 990627- 0807.No Violations Noted.Licensee Conduct of Activities at Farley Plant Facilities Generally Characterized by safety-conscious Operations & Sound Engineering ML20211Q4801999-09-0101 September 1999 Informs That on 990812-13,Region II Hosted Training Managers Conference on Recent Changes to Operator Licensing Program. List of Attendees,Copy of Slide Presentations & List of Questions Received from Participants Encl ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC ML20211G6851999-08-26026 August 1999 Informs That During Insp,Technical Issues Associated with Design,Installation & fire-resistive Performance of Kaowool Raceway fire-barriers Installed at Farley Nuclear Plant Were Identified ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210T2021999-08-0606 August 1999 Forwards Draft SE Accepting Licensee Proposed Conversion of Plant,Units 1 & 2 Current TSs to Its.Its Based on Listed Documents ML20210Q4641999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr to La Reyes,As Listed,With List of Individuals to Take exam,30 Days Before Exam Date ML20210J8341999-07-30030 July 1999 Forwards Second Request for Addl Info Re Util 990430 Amend Request to Allow Util to Operate Unit 1,for Cycle 16 Based on risk-informed Probability of SG Tube Rupture & Nominal accident-induced primary-to-second Leakage ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines ML20210G8181999-07-26026 July 1999 Forwards Insp Repts 50-348/99-04 & 50-364/99-04 on 990516- 0626.One Violation Identified & Being Treated as Noncited Violation ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-027, Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines1999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed ML20196J6571999-07-0202 July 1999 Discusses Closure to TAC MA0543 & MA0544 Re GL 92-01 Rev 1, Suppl 1,RV Structural Integrity.Nrc Has Revised Rvid & Releasing It as Rvid,Version 2 as Result of Review of Responses ML20196J7471999-07-0202 July 1999 Forwards RAI Re Cycle 16 Extension Request.Response Requested within 30 Days of Date of Ltr ML20196J5781999-07-0202 July 1999 Forwards RAI Re 981201 & s Requesting Amend to TS Associated with Replacing Existing Westinghouse Model 51 SG with Westinghouse Model 54F Generators.Respond within 30 Days of Ltr Date ML20196J6191999-07-0202 July 1999 Forwards Final Dam Audit Rept of 981008 of Category 1 Cooling Water Storage Pond Dam.Requests Response within 120 Days of Date of Ltr L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA ML20196J3591999-06-30030 June 1999 Forwards SE of TR WCAP-14750, RCS Flow Verification Using Elbow Taps at Westinghouse 3-Loop Pwrs L-99-024, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA ML20196D1931999-06-22022 June 1999 Discusses Requesting Approval & Issuance of Plant Units 1 & 2 ITS by 990930.New Target Date Agrees with Requested Date ML20196A3401999-06-10010 June 1999 Forwards Insp Repts 50-348/99-03 & 50-364/99-03 on 990404-0515.No Violations Noted ML20196H9801999-06-10010 June 1999 Submits Two RAI Re ITS Section 4.0 That Were Never Sent. Reply to RAI Via e-mail ML20195F1731999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARL-99-035, Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld1999-10-18018 October 1999 Forwards non-proprietary & Proprietary Versions of Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs, Used to Support SG Replacement Project.Proprietary Encl Withheld ML20217P0661999-10-0606 October 1999 Requests Withholding of Proprietary Rept NSD-SAE-ESI-99-389, Farley Units 1 & 2 LBB Calculation Results Due to SG Replacement & SG Snubber Elimination Programs ML20217B1891999-10-0404 October 1999 Submits Clarification Re Development of Basis for Determining Limiting Internal Pressure Loads Re Review of NRC SE for Cycle 16 Extension Request.Util Intends to Use Guidelines When Evaluating SG Tube Structural Integrity ML20212C2351999-09-16016 September 1999 Submits Corrected Info Concerning Snoc Response to NRC GL 99-02, Lab Testing of Nuclear-Grade Activated Charcoal L-99-031, Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams1999-09-13013 September 1999 Forwards Info Requested in Administrative Ltr 99-03, Preparation & Scheduling of Operator Licensing Exams ML20211K4101999-08-31031 August 1999 Resubmits Relief Requests Q1P16-RR-V-5 & Q2P16-RR-V-5 That Seek to Group V661 Valves from Each Unit Into Sample Disassembly & Insp Group,Per 990525 Telcon with NRC ML20211K2131999-08-31031 August 1999 Informs That Snoc Has Conducted Review of Reactor Vessel Integrity Database,Version 2 (RVID2) & Conclude That Latest Data Submitted for Farley Units Has Not Been Incorporated Into RVID2 ML20211B9431999-08-17017 August 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 990101-990630,IAW 10CFR26.71(d).Rept Covers Employees at Jm Farley Nuclear Plant & Southern Nuclear Corporate Headquarters ML20211B9211999-08-17017 August 1999 Responds to NRC Re Violations Noted in Insp Rept 50-348/99-09 & 50-364/99-09.Corrective Actions:Security Response Plan Was Revised to Address Vulnerabilities Identified During NRC Insp ML20210R5101999-08-12012 August 1999 Forwards Revised Page 6 to 990430 LAR to Operate Farley Nuclear Plant,Unit 1,for Cycle 16 Only,Based on risk- Informed Approach for Evaluation of SG Tube Structural Integrity,As Result of Staff Comments ML20212C8141999-08-0909 August 1999 Forwards Correspondence Received from Jm Sherman.Requests Review of Info Re Established Policies & Procedures ML20210G4901999-07-30030 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, Issued 990603.Ltr Contains NRC License Commitment to Utilize ASTM D3803-1989 with Efficiency Acceptance Criteria Utilizing Safety Factor of 2 L-99-028, Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines1999-07-30030 July 1999 Responds to NRC 990730 RAI Re 990423 OL Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described by NEI 97-06, SG Program Guidelines ML20210E4071999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-027, Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines1999-07-22022 July 1999 Responds to NRC 990702 RAI Re Change Request to Allow for Risk Informed Approach for Evaluation of SG Tube Structural Integrity as Described in NEI 97-06, SG Program Guidelines L-99-026, Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments1999-07-19019 July 1999 Forwards Response to NRC 990702 RAI Re SG Replacement Related TS Change Request Submitted 981201.Ltr Contains No New Commitments L-99-264, Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 20011999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 ML20209H4721999-07-13013 July 1999 Responds to NRC 990603 Administrative Ltr 99-02, Operating Licensing Action Estimates, for Fy 2000 & 2001 05000364/LER-1999-001, Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed1999-07-0202 July 1999 Forwards LER 99-001-00 Re Reactor Trip Due to Loss of Condenser Vacuum Steam Dump Drain Line Failure.Commitments Made by Licensee,Listed L-99-249, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA ML20196J8631999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-024, Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA1999-06-30030 June 1999 Submits Correction to Errors Contained in to NRC Re TS Changes Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation.Errors Do Not Require Rev of SA L-99-025, Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.211999-06-30030 June 1999 Forwards Rev 2 to Jfnp Security plan,FNP-0-M-99,IAW 10CFR50.4(b)(4).Attachment 1 Contains Summary of Changes & Amended Security Plan Pages.Encl Withheld from Public Disclosure Per 10CFR73.21 L-99-224, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments L-99-217, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-225, Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants1999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195F0621999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments ML20195E9581999-06-0707 June 1999 Responds to GL 98-01, Yr 2000 Readiness of Computer Sys at Nuclear Power Plants ML20195F1731999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-022, Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments1999-06-0707 June 1999 Submits Rev to Unit 2 SG Tube voltage-based Repair Criteria Data Rept.Ltr Contains No Commitments L-99-021, Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld1999-06-0707 June 1999 Forwards Proprietary & non-proprietary Responses to NRC RAIs Re W TR WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs. W Proprietary Notice,Affidavit & Copyright Notice,Encl.Proprietary Info Withheld L-99-203, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program ML20195C6941999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program L-99-020, Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program1999-05-28028 May 1999 Forwards Response to NRC RAI Re GL 96-05 for Farley Nuclear Plant.Farley Is Committing to Implement Phase 3 of JOG Program ML20195F2101999-05-24024 May 1999 Requests That Farley Nuclear Plant Proprietary Responses to NRC RAI Re W WCAP-14750, RCS Flow Verification Using Elbow Taps at W 3-Loop Pwrs, Be Withheld from Public Disclosure Per 10CFR2.790 L-99-180, Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI1999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI ML20206F4321999-04-30030 April 1999 Forwards Responses to NRC RAI Questions for Chapter 3.8 of Ts.Proposed Revs to TS Previously Submitted with LAR Related to RAI ML20206C8021999-04-26026 April 1999 Forwards 1998 Annual Rept, for Alabama Power Co.Encls Contain Financial Statements for 1998,unaudited Financial Statements for Quarter Ending 990331 & Cash Flow Projections for 990101-991231 ML20205S9501999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 L-99-172, Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.21999-04-21021 April 1999 Forwards FNP Annual Radioactive Effluent Release Rept for 1998, IAW TSs Sections 6.9.1.8 & 6.9.1.9.Changes to ODCM Revs 16,17 & 18 Are Encl,Iaw TS Section 6.14.2 L-99-153, Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error1999-04-13013 April 1999 Forwards Correction to 960212 GL 95-07 180 Day Response. Level 3 Evaluation for Pressure Locking Utilized Analytical Models.Encl Page Has Been Amended to Correct Error L-99-125, Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z1999-03-19019 March 1999 Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z ML20205A2871999-03-19019 March 1999 Forwards Rev 0 to W Rept WCAP-15171, Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program, Presenting Surveillance Capsule Test Results from Capsule Z ML20205A1531999-03-19019 March 1999 Forwards Corrected Typed & marked-up Current TS Pages for Replacing Previous Pages Submitted on 990222,re CR, Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation L-99-012, Forwards 10CFR50.46 Annual Rept for 1998,re Effects of ECCS Evaluation Model Mod on Peak Cladding Temp Results Since 1997 Annual Rept & Most Recent PCT Error Rept Submitted 9809101999-03-19019 March 1999 Forwards 10CFR50.46 Annual Rept for 1998,re Effects of ECCS Evaluation Model Mod on Peak Cladding Temp Results Since 1997 Annual Rept & Most Recent PCT Error Rept Submitted 980910 L-99-010, Forwards ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jfnp,Unit 1, & Vols 1 & 2 to ISI Refueling 15,Interval 3, Period 1,Outage 1 for Jfnp,Unit 1. Summary of Results May Be Found in Tab B of Encl 21999-03-18018 March 1999 Forwards ISI Refueling 15,Interval 2,Period 3,Outage 3 for Jfnp,Unit 1, & Vols 1 & 2 to ISI Refueling 15,Interval 3, Period 1,Outage 1 for Jfnp,Unit 1. Summary of Results May Be Found in Tab B of Encl 2 ML20205A7611999-03-18018 March 1999 Forwards Annual DG Reliability Data Rept for 1998,per Plant TS 6.9.1.12 & 10CFR50.36.Rept Provides Number of Tests (Valid or Invalid) & Number of Failures for DGs at Jm Farley Nuclear Plant.Ltr Contains No New Commitments ML20205H2741999-03-18018 March 1999 Forwards Info on Status of Decommissioning Funding for Jm Farley Nuclear Plant,Units 1 & 2,IAW 10CFR50.75(f)(i) ML20204D4281999-03-16016 March 1999 Forwards SG-99-03-001, Farley Unit-1 1999 Voltage-Based Repair Criteria 90-Day Rept, Per GL 95-05.Required Rept for Fall 1998 SG Insp Is Included in Rept ML20204E5841999-03-15015 March 1999 Submits Info on Current Levels & Sources of Insurance on Jm Farley Nuclear Plant,Units 1 & 2 1999-09-16
[Table view] Category:UTILITY TO NRC
MONTHYEARML20064A7131990-09-17017 September 1990 Advises That Due to Reassignment,Jj Clark No Longer Needs to Maintain Senior Reactor Operator Licenses ML20059J2811990-09-14014 September 1990 Forwards List of Key Radiation Monitors Which Will Be Used as Inputs to Top Level Radioactivity Status Bar Re Spds.List Identifies Monitors Which Would Provide Concise & Meaningful Info About Radioactivity During Accidents ML20065D5961990-09-13013 September 1990 Responds to Violations Noted in Insp Repts 50-348/90-19 & 50-364/90-19.Response Withheld ML20059J1661990-09-13013 September 1990 Forwards Monthly Operating Rept for Aug 1990 for Jm Farley Nuclear Plant & Rev 10 to ODCM ML20059L0751990-09-12012 September 1990 Forwards Revised Pages to Rev 3 to, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20059J2911990-09-12012 September 1990 Forwards Operator Licensing Natl Exam Schedules for FY91 Through FY94,per Generic Ltr 90-07.Requalification Schedules & Estimated Number of Candidates Expected to Participate in Generic Fundamental Exam,Also Encl ML20064A7111990-09-12012 September 1990 Forwards Rev 1 to Relief Request RR-1, Second 10-Yr Interval Inservice Insp Program for ASME Code Class 1,2 & 3 Components ML20059J2891990-09-12012 September 1990 Confirms Rescheduling of Response to Fitness for Duty Program Notice of Violation 90-18-02,per 900907 Telcon ML20065D6621990-09-12012 September 1990 Forwards NPDES Permit AL0024619 Effective 900901.Limits for Temp & Residual Chlorine Appealed & Stayed ML20064A3431990-08-28028 August 1990 Forwards Corrected Insertion Instructions to Rev 8 to Updated FSAR for Jm Farley Nuclear Plant ML20059D4711990-08-22022 August 1990 Forwards Fitness for Duty Performance Data for Jan-June 1990 ML20059B5101990-08-22022 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990.No Changes to Process Control Program for First Semiannual Period of 1990 Exists ML20056B2751990-08-20020 August 1990 Forwards Relief Requests from Second 10-yr Interval Inservice Testing Program for Class 1,2 & 3 Pumps & Valves. Request Incorporates Commitments in 891222 Response to Notice of Violation ML20056B2741990-08-20020 August 1990 Forwards Rev 2 to Unit Inservice Testing Program,For Review & Approval.Rev Incorporates Commitments Addressed in Util 891222 Response to Notice of Violation & Other Editorial & Technical Changes ML20058Q1481990-08-15015 August 1990 Forwards Rev 3 to FNP-1-M-043, Jm Farley Nuclear Plant Unit 1 Second 10-Yr Inservice Insp Program,Asme Code Class 1,2 & 3 Components ML20058P6201990-08-15015 August 1990 Forwards Rev 1 to FNP-2-M-068, Ten-Yr Inservice Insp Program for ASME Code Class 1,2 & 3 Components, Per 891207 & 900412 Responses to NRC Request for Addl Info ML20055G7701990-07-18018 July 1990 Updates 900713 Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20055F7411990-07-11011 July 1990 Forwards Monthly Operating Rept for June 1990 & Corrected Monthly Operating Repts for Nov 1989 Through May 1990.Repts Revised to Correct Typo on Value of Cumulative Number of Hours Reactor Critical ML20055F3781990-07-10010 July 1990 Submits Final Response to Generic Ltr 83-28,Items 4.2.3 & 4.2.4.Util Position That Procedures Currently Utilized by Plant Constitute Acceptable Ongoing Life Testing Program for Reactor Trip Breakers & Components ML20055D4861990-07-0202 July 1990 Requests Authorization to Use Encl ASME Boiler & Pressure Vessel Code Case N-395 Re Laser Welding for Sleeving Process Described by Oct 1990,per 10CFR50.55a,footnote 6 ML20055D1001990-06-26026 June 1990 Responds to Violations Noted in Insp Repts 50-348/90-12 & 50-364/90-12 on 900411-0510.Corrective Actions:Electrolyte Level Raised in Lights Identified by Inspector to Have Low Electrolyte Level ML20044A6191990-06-26026 June 1990 Suppls 900530 Ltr Containing Results of SPDS Audit,Per Suppl 1 to NUREG-0737.One SPDS Console,Located in Control Room,Will Be Modified So That Only SPDS Info Can Be Displayed by Monitor.Console Will Be Reconfigured ML20043G4741990-06-11011 June 1990 Submits Addl Info Re 900219 Worker Respiratory Protection Apparatus Exemption Rev Request.Proposed Exemption Rev Involves Features Located Entirely within Restricted Area as Defined in 10CFR20 ML20043C1851990-05-29029 May 1990 Forwards Proposed Schedules for Submission & Requested Approval of Licensing Items ML20043B5941990-05-25025 May 1990 Provides Rept of Unsatisfactory Performance Testing,Per 10CFR26,App A.Error Caused by Olympus Analyzer Which Allowed Same Barcode to Be Assigned to Two Different Samples. Smithkline Taken Action to Prevent Recurrence of Scan Error ML20042G7461990-05-10010 May 1990 Certifies That Plant Licensed Operator Requalification Program Accredited & Based Upon Sys Approach to Training,Per Generic Ltr 87-07.Program in Effect Since 890109 ML20042F0831990-05-0101 May 1990 Forwards Rev 18 to Security Plan.Rev Withheld ML20042G3081990-04-25025 April 1990 Forwards Alabama Power Co Annual Rept 1989, Unaudited Financial Statements for Quarter Ending 900331 & Cash Flow Projections for 1990 ML20042E4121990-04-12012 April 1990 Provides Addl Info Re Review of Second 10-yr Inservice Insp Program,Per NRC 890803 Request.Relief Request RR-30 Requested Reduced Holding Time for Hydrostatically Testing Steam Generator Secondary Side ML20012E9571990-03-27027 March 1990 Forwards Annual Diesel Generator Reliability Data Rept,Per Tech Spec 6.9.1.12.Rept Provides Number of Tests (Valid or Invalid),Number of Failures for Each Diesel Generator at Plant for 1989 & Info Identified in Reg Guide 1.108 ML20012D9661990-03-22022 March 1990 Forwards Annual ECCS Evaluation Model Changes Rept,Per Revised 10CFR50.46.Info Includes Effect of ECCS Evaluation Model Mods on Peak Cladding Temp Results & Summary of Plant Change Safety Evaluations ML20012D8901990-03-20020 March 1990 Clarifies 891130 Response to Generic Ltr 83-28,Item 2.2.1 Re Use of Q-List at Plant,Per NRC Request.Fnpims Data Base Utilized as Aid for Procurement,Maint,Operations & Daily Planning ML20012C4701990-03-15015 March 1990 Responds to NRC 900201 Ltr Re Emergency Planning Weaknesses Identified in Insp Repts 50-348/89-32 & 50-364/89-21. Corrective Actions:Cited Procedures Revised.Direct Line Network Notification to State Agencies Being Implemented ML20012C6241990-03-14014 March 1990 Informs of Resolution of USI A-47,per Generic Ltr 89-19 ML20012C4651990-03-13013 March 1990 Provides Verification of Nuclear Insurance Reporting Requirements Specified in 10CFR50.54 w(2) ML20012C2051990-03-0505 March 1990 Forwards SPDS Critical Function Status Trees,Per G West Request During 900206 SPDS Audit at Plant.W/O Encl ML20012A1621990-03-0202 March 1990 Forwards Addl Info Inadvertently Omitted from Jul-Dec 1989 Semiannual Radioactive Effluent Release Rept,Including Changes to Process Control Program ML20012A1301990-03-0101 March 1990 Responds to Generic Ltr 90-01 Re Request for Voluntary Participation in NRC Regulatory Impact Survey.Completed Questionnaire Encl ML20043A7481990-02-0202 February 1990 Forwards Util Exam Rept for Licensed Operator Requalification Written Exams on 900131 ML20006D2311990-01-31031 January 1990 Responds to NRC Bulletin 89-003 Re Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures Will Be Revised to Incorporate Guidance That Will Preclude Inadvertent Loss of Shutdown ML20006A9091990-01-23023 January 1990 Forwards Response to Generic Ltr 89-13 Re Svc Water Sys Problems Affecting safety-related Equipment.Util Has Program to Perform Visual Insps & Cleanings of Plant Svc Water Intake Structure by Means of Scuba Divers ML20005E4931989-12-28028 December 1989 Provides Certification That fitness-for-duty Program Meets 10CFR26 Requirements.Testing Panel & cut-off Levels in Program Listed in Encl ML20005E3681989-12-28028 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-28 & 50-364/89-28 on 891002-06.Corrective Actions:All Piping Preparation for Inservice Insp Work in Containment Stopped & All Participants Assembled to Gather Facts on Incident ML20005E1971989-12-27027 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22 on 890911-1010.Corrective Actions:Steam Generator Atmospheric Relief Valve Closed & Core Operations Suspended.Shift Supervisor Involved in Event Counseled ML20011D5041989-12-22022 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-26 & 50-364/89-26.Corrective Actions:Personnel Involved in Preparation of Inservice Test Procedures Counseled. Violation B Re Opening of Pressurizer PORV Denied ML19332F2111989-12-0707 December 1989 Forwards Final Response to NRC 890803 Request for Addl Info Re Review of Updated Inservice Insp Program,Summarizing Results of Addl Reviews & Providing Exam Listing Info ML19332F0791989-12-0707 December 1989 Responds to Violations Noted in Insp Repts 50-348/89-22 & 50-364/89-22.Corrective Actions:All Managers Retrained on Intent of Overtime Procedures & Sys Established to Provide Independent Check of All Time Sheets Each Pay Period ML19332F1141989-12-0707 December 1989 Forwards Description of Instrumentation Sys Selected in Response to Generic Ltr 88-17, Loss of DHR, Per Licensee 890127 Commitment.Hardware Changes Will Be Implemented During Unit 1 Tenth & Unit 2 Seventh Refueling Outages ML19332F1241989-12-0707 December 1989 Forwards Response to NRC 890803 Request for Addl Info Re Review of Second 10-yr Inservice Insp Program,Per 891005 Ltr ML19353B0071989-12-0606 December 1989 Forwards Rev 1 to Safeguards Security Contingency Plan.Rev Withheld 1990-09-17
[Table view] |
Text
v
, Alabama Power Company 40 inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Telephone 205 868-5581 W. G. Hairston, til h
Senior Vice President Nuclear Operations M8ballla Power the southem electnc system March 23,1989 Docket Nos. 50-348 50-364 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Vashington, D.C.
20555 Gentlemen Joseph M. Parley Muclear Plant - Units 1 and 2 Miniflov Evaluation - NRC Bulletin No. 88-04 By letter of November 30, 1988, Alabama Power Company provided additional I
information as committed in its July 8, 1988 response to NRC Bulletin No.
88-04.
This letter which provided an update on Alabama Power Company's response to the bulletin was not submitted under " oath or affirmation".
At the verbal request of the Farley NRC Project Manager, however, the November 30, 1988 letter is being resubmitted under " oath or affirmation".
NRC Bulletin No. 88-04, " Potential Safety Related Pump Loss," requires Alabama Power Company to investigate and correct, if applicable, two j
miniflow design concerns.
l The Bulletin requires that each safety-related system be evaluated for pump-to-pump interaction during miniflov operation.
If pump-to-pump i
interaction is possible, the system is required to be evaluated from a flow division standpoint. The Bulletin further requires an evaluation to address the adequacy of the minimum flow bypass lines for safety-related centrifugal pumps with respect to damage resulting from operation and testing.
The Bulletin reporting requirements include submittal of a short-term (60 day) report which (a) summarizes the problems and the systems affected, (b) identifies the short-term and long-term modifications to plant operating procedures or hardware that have been or are being implemented to ensure safe plant operations, (c) identifies an appropriate schedule for long-term resolution of this and/or other significant problems that are identified as a result of this bulletin, and (d) provides justification for continued operation particularly with regard to General Design Criterion 35 of Appendix A to Title 10 of the Code of Federal Regulations (10 CFR 50),
" Emergency Core Cooling" and 10 CFP. 50.46, " Acceptance Criteria for Emergency Core Cooling Systehi for Light Water Nuclear Power Reactors."
Additionally, a long-term resolution report is required to be submitted within 30 days of the completion of the long-term resolution actions.
40 7
8903300096 890323 1
PDR ADOCK 05000348 I
0 PDC g
'U. S. Nuclear Regulatory Commission March 23, 1989 Page 2 By letter dated July 8, 1988, Alabama Power Company provided a partial response to the Bulletin and committed to provide a status of evaluation efforts by November 30, 1988. The results of evaluations on safety-related pumps are outlined in Attachment 1.
All evaluations are complete with the exception of the evaluation required for the auxiliary feedvater (AFV)-
pumps. Due to the increased work load placed on the pump vendor by the Bulletin, a final evaluation of the AFV pumps is scheduled to be completed in May, 1989. Alabama Power Company vill provide the results of the AFV pump evaluation and a long-term action schedule within 60 days of evaluation completion. Continued operation of the AFV pumps until completion of the evaluation is justified in Attachment 1.
For all other i
pumps evaluated, evaluations have shown that there is no significant pump-to-pump interaction and the current minimum flow lines are adequate.
If there are any questions, please advise.
Respectfully submitted, A1.ABAMA POVER COMPANY lb.
. ha V. G. Hairston, III VGH,III/ REM:pr-5.16 Attachment cc:
Mr. S. D. Ebnetter Mr. E. A. Reeves Mr. G. F. Maxwell SVORN TO AND SUBSCRIBED BEFORE ME
%m[
, 1989 THIS J3 d DAY of dluna lhdf}L-}</rf/]
(] Notary Public DEEN My Commission Expires
~
ATTACHMENT 1 SYSTEM DESCRIPTION AND EVALUATION System:
High Head Safety Injection / Charging Pumps:
3 Charging pumps (HHSI) per unit Miniflow
Description:
A miniflow line from each HHSI pump discharges into a common miniflow header.
Pump-to-Pump Interaction:
Pump-to-pump interaction is precluded by the use of a 60 GPM high resistance minimum flow orifice in the miniflow line from each HHSI l
pump. The individual miniflow lines combine l
into a low resistance common header.
Adequacy of Miniflow:
The HHSI pump miniflow lines have a greater capacity than originally required by the pump vendor. The system designer, in conjunction with the pump vendor, has evaluated the adequacy of the minimum flow lines. The required thermal minimum flow is substantially below the expected pump flow for all operating modes. The required mechanical minimum flow to prevent hydraulic instability and mechanical damage is lower than the expected minimum flow which results from cach mode of operation.
System:
Lov Head Safety Injection / Residual Heat Removal (RHR)
Pumps:
2 RHR pumps per unit Miniflow
Description:
Each RHR pump has an independent miniflow line.
Pump-to-Pump Interaction:
Pump-to-pump interaction is precluded by use f
of independent miniflov lines.
Adequacy of Miniflow:
The RHR pump miniflow lines have a greater
{
capacity than originally required by the pump i
j vendor. The system designer, in conjunction i
with thin pump vendor, has evaluated the adequacy of the minimum flow lines. The requireo thermal minimum flow is substantially below the expected pump flow for all operating l
modas. The required mechanical minimum flov s
to prevent hydraulic instability and i
mechanical damage is lover than the expected minimum flow which results from each mode of operation.
i System:
Containment Spray (CS) l Pumps:
2 CS pumps per unit l
l
_ _ _ _j
Attechment.l' Syst03 Deacriptiens cnd Evaluations
'P g2 2 Miniflow
Description:
Each CS pump has a recirculation line which-joins to form a common return header to the Refueling Vater Storage Tank (RWST). Normally locked closed valves are provided in the recirculation' lines and in the common header for isolation. This piping arrangement is utilized as a means to test the spray pumps without spraying into containment. In addition, each pump has a spray eductor recirculation line.
Pump-to-Pump Interaction:
During accident situations, and all surveillance testing except for the " Spray and Phase B Actuation Test", the operation of the two trains is completely independent, with the exception of a common portion of the suction line from the RWST. The pumps can develop sufficient discharge pressure to exceed the containment design pressure such-that there is no possibility of deadheading a pump during spray actuation. During individual pump surveillance testing (Spray Pump Honthly, Quarterly and Annual Testing) the spray header is isolated, however, each pump's miniflow path to the RVST is available to prevent deadheading.
During the " Spray and Phase B l
Actuation Surveillance Test" the discharge headers are isolated, and the two pumps are l
run simultaneously in parallel with flov directed to the common miniflow line. The surveillance procedure requires that the time i
the spray pumps are run in parallel be held to a maximum of 1 minute..The resistance-in the common miniflow path is high relative to that in the individual ~line. Hence, given a mismatch between the pump ~ developed heads, it is possible for the pressure at the junction point (where the discharge heads combine) to be high enough to prevent one pump from recirculating to the RVST. This condition is considered acceptable because (1) the pumps only run for one minute maximum and (2) the spray eductor recirculation line in essence provides an individual and independent minimum flow path.
Adequacy of Miniflow:
The system der.igner, in conjunction with the I
pump vendor, has evaluated the adequacy of the l
minimum flov lines. The required thermal I
minimum flow is substantially below the expected pump flow for all operating modes.
The required mechanical minimum flow to prevent hydraulic instability and mechanical j
damage is lower than the expected minimum flov l
vhich results from each mode of operation.
Attach::nt 1
.Systs2 D2scriptions and Evaluations
~
- Psg2 3 Systems Auxiliary Feedvater_ (AFW) i Pumps:
2 motor driven AFV pumps per unit i
1 turbine driven AFV pump per unit Miniflow
Description:
A continuously open miniflow line from each AFV pump discharges into a common miniflow header.
Pump-to-Pump Interaction:
Pump-to-pump interaction is precluded by the use of a high resistance minimum flow orifice and check valve in the miniflov line from each AFV pump. The miniflow orifice was supplied by the pump vendor and installed following the vcndor's technical manual.
Adequacy of Miniflow:
The use of the vendor supplied miniflow orifice, installed following the vendor's technical manual, has resulted in a miniflow capacity which meets original requirements.
The pump vendor, in conjunction with the.
system designer, is evaluating the adequacy of the miniflov line for long-term operation.
Due to the pump vendor's workload.and engineering staff size, the evaluation is not expected to be completed until early 1989.
Continued operation of the MDAFV and TDAFV pumps is justified for the near term based on l
the following considerations:
(a) Damage of the pumps due to internal recirculation has not been experienced to date, nor is the manufacturer aware of minimum flow problems with similar type pumps in other plants.
(b) The minimum flow rates are not affected because of interaction during parallel operation. This is a result of the high flow resistances of the individual j
minimum flow orifices.
]
(c) The degradation due to operation with low minimum flow rates is gradual.
Because of this and because the pumps operate I
infrequently at minimum. flow, life of the i
pump would not be degraded with less than l
desirable miniflow.
I i
Furthermore, required routine i
maintenance, inspections and surveillance l
testing are expected to detect any excessive wear or damage well before system performance is degraded.
1
)
I 1
Attechment 1 l
Systc3 Descriptions cnd Evaluations i
Systems Component Cooling Vater (CCV) i
)
Pumps:
3 CCV pumps per unit Miniflow
Description:
A separate recirculation line from the CCV pump discharge to the CCV pump suction is provided for each pump. The recirculation line contains a minimum flow orifice provided by the pump manufacturer.
A check valve is located in the discharge line dovnstream of the recirculation line connection for each pump.
Pump-to-Pump Interaction:
Pump-to-pump interaction is precluded by providing a separate recirculation line for each pump.
Adequacy of Miniflow:
During normal operation, the miniflow line is isolated and the system designer has determined that the system flovrate is adequate to prevent pump degradation. The Unit 2 Inservice Testing Program contains the only known requirement to run the CCV pumps solely on miniflow. The Unit 2 Inservice Testing Program is expected to be revised as part of the second ten year update (spring 1989 outage) to eliminate the requirement.
The Unit 1 Inservice Testing Program has already been revised te eliminate the requirement. The system designer, in conjunction with the pump vendor, has determined that the miniflow line is adequate provided that the duration of operation is minimized.
System:
Service Water (aV)
Pumps:
5 SV pumps per unit Miniflow
Description:
The 5 SV pumps are divided as illustrated in Pigure 1.
SV pumps A and B are A train pumps.
SV pumps D and E are B train pumps.
SV pump C is a sving pump which may be aligned to the A or B train. A common miniflow is provided for pumps A and B.
A common miniflow is provided for pumps D and E.
Pump C is provided with 1
its own miniflow line. The control valves for all of the miniflow lines are set to open at 130 psig.
Additionally the SV system contains
{
a 24 inch dilution bypass line which ultimately discharges to the rive *. The dilution bypass line control va7ve opens at 100 psig.
I l
Attschment 1 Systea Descriptions cnd Evoluttions P ga 5 l
1 Pump-to-Pump Interaction:
The SV system is not designed to preclude
)
pump-to-pump interaction while on miniflow.
{
Operation of pumps A and B or pumps D and E, in conjunction with pump C, could result in
)
multiple pumps discharging to a common header with miniflow protection.
Plant operators are procedurally directed to start and secure SV-pumps in order to maintain SV header pressure between'70 to 100 psig.. With'the procedural j
guidance.that is available to operators, I
pump-to-pump interaction in the SV header is j
I precluded.
Adequacy of Miniflow:
The pump vendor has stated that "we do not-recommend the minimum continuous throttled flow to be less than thirty-five percent (35%)
of the pump capacity at Best Efficiency Point-(BEP). This calculates to approximately 3150 GPM..."
The SV pump miniflow lines are sized to handle 3150 GPM/ pump. Additionally, the
(
I dilution bypass line, which opens before the J
l SV pump miniflov line, provides additional protection for SV pumps during operation. The l
system designer, in conjunction with the pump l
vendor,.has determined that there are no l
circumstances under which the SW pumps vill operate at flow rates lov enough to adversely affect the pumps.
System Diesel Generator (DG) Fuel Oil (FO)
Pumps:
5 manual FO transfer pumps 5 automatic F0 transfer pumps Miniflow
Description:
The DG F0 system has no miniflow lines. The F0 transfer pumps take a. suction on the F0 storage tanks and discharge to the day tanks or other F0 storage tanks.
1 l
Pamp-to-Pump Interaction:
If the F0 transfer pumps are operated in
]
parallel, possible dead heading of a pump could occur.
Procedures do not provide for operating pumps in parallel.
A precaution against parallel operation has been added to the operating procedure. Therefore, j
pump-to-pump interaction is preclude /
System:
Boric Acid Transfer (BAT) System Pumps:
2 Boric Acid Transfer Pumps per unit
)
l Attach: nt I Systcm Descriptions end Ev21untiens
~
i
'P gs 6 l
l l
Miniflow
Description:
Each BAT pump has an independent miniflow line which recirculates to the boric acid tanks.
However, the system may be physically aligned such that both pumps discharge to the same i
miniflow line.
l Pump-to-Pump Interaction:
Pun:p-to-pump interaction is precluded through the use of procedures which prevent the operator from starting both pumps and operating them through the same miniflow line.
Adequacy of Miniflow:
The system designer, in conjunction with the pump vendor, has evaluated the adequacy of the minimum flov line. The required thermal minimum flov is substantially below the expected pump flow for all operating modes.
The required mechanical minimum flow to prevent hydraulic instability and mechanical damage is lover than the expected minimum flov l
vhich results from each mode of operation.
System:
Spent Fuel Pool Cooling Pumps:
2 Spent Fuel Pit Pumps per unit Miniflow
Description:
The Spent Fuel Pit system does not include a miniflow provision for these pumps.
Pump-to-Pump Interaction:
Operating procedures provide for only one spent fuel pool cooling loop on service at a time. Therefore, pump-to-pump interaction is precluded by operating only one pump at a i
time.
Adequacy of Miniflow:
Normal operation of the Spent Fuel Pool Cooling system is to throttle flow across the pump to 54 psid. This operational philosophy results in system pumps operating in the vicinity of the best efficiency point.
Since these pumps are not operated at flows that would require miniflow, no additional action is required.
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