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| B009260 MEMBER MIODLE SOUTH UT1UTIES SYSTEM | | B009260 MEMBER MIODLE SOUTH UT1UTIES SYSTEM |
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| i As discussed in our letter to you dated September 11, 1980, each CCU is required to have a flow rate of 1250 gpm to obtain maximum performance capability. This, of course, requires a flow rate of 2500 gpm through any Group (containing 2 CCUs) to obtain 1250 gpm through each CCU. Due to the pressure drop across the group and the partially restricted flow, we cannot obtain a flow rate of 2500 gpm through either Group. We can, however, obtain 1250 gpm through a single CCU if the other CCU in the group is isolated. | | i As discussed in our letter to you dated September 11, 1980, each CCU is required to have a flow rate of 1250 gpm to obtain maximum performance capability. This, of course, requires a flow rate of 2500 gpm through any Group (containing 2 CCUs) to obtain 1250 gpm through each CCU. Due to the pressure drop across the group and the partially restricted flow, we cannot obtain a flow rate of 2500 gpm through either Group. We can, however, obtain 1250 gpm through a single CCU if the other CCU in the group is isolated. |
| There is no cleaning procedure known to us that will remove the re-maining clams without jeopardizing the integrity of the tube materials. | | There is no cleaning procedure known to us that will remove the re-maining clams without jeopardizing the integrity of the tube materials. |
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| Therefore, we desire to continue operation with less than maximum flow until our refueling outage early next year. | | Therefore, we desire to continue operation with less than maximum flow until our refueling outage early next year. |
| We have studied the safety implications of continued operation with reduced flow carefully and believe that the public health and safety will not be endangered by such. Attachment 3 is a safety e"sluation addressing this issue. | | We have studied the safety implications of continued operation with reduced flow carefully and believe that the public health and safety will not be endangered by such. Attachment 3 is a safety e"sluation addressing this issue. |
| To allow continued operation, we propose modifications to the ANO-2 Technical Specifications and to the surveillance requirements. Figure 1 is i simplified drawing of the CCUs, service water inlet and outlet and | | To allow continued operation, we propose modifications to the ANO-2 Technical Specifications and to the surveillance requirements. Figure 1 is i simplified drawing of the CCUs, service water inlet and outlet and required flow rates. A more detailed P&ID is shown on ANO-2 FSAR Fig-ure 9.2-1 Sht. 2 of 4. |
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| required flow rates. A more detailed P&ID is shown on ANO-2 FSAR Fig-ure 9.2-1 Sht. 2 of 4. | |
| The attached Technical Specification Change Request modifies ANO-2 Technical Specification 3.6.2.3 to allow operation with a minimum of one CCU OPERABLE in each Group and modifies Specification 4.6.2.3.a.3 to. | | The attached Technical Specification Change Request modifies ANO-2 Technical Specification 3.6.2.3 to allow operation with a minimum of one CCU OPERABLE in each Group and modifies Specification 4.6.2.3.a.3 to. |
| specify a surveillance flow requirement of 1250 gpm to each OPERABLE Group. | | specify a surveillance flow requirement of 1250 gpm to each OPERABLE Group. |
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| Ve y truly yours William Ca augh, III WC:JTE:nak Attachments | | Ve y truly yours William Ca augh, III WC:JTE:nak Attachments |
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| STATE OF ARKANSAS ) | | STATE OF ARKANSAS ) |
| ) SS COUNTY OF PULASKI ) | | ) SS COUNTY OF PULASKI ) |
| Willam Cavanaugh, III, being duly sworn, states that he is Vice President, Generation & Construction, for Arkansas Power & Light Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this Supplementary Information; that he has reviewed or caused to have reviewed all of the statements contained in such information, and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief. | | Willam Cavanaugh, III, being duly sworn, states that he is Vice President, Generation & Construction, for Arkansas Power & Light Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this Supplementary Information; that he has reviewed or caused to have reviewed all of the statements contained in such information, and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief. |
| " William Cav ,III | | " William Cav ,III SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State above named, this day of -y W/ , 1980. |
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| SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State above named, this day of -y W/ , 1980. | |
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| LJEth f - f/Eu/ | | LJEth f - f/Eu/ |
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| Mg Commission Dpires 9/1/81 | | Mg Commission Dpires 9/1/81 |
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| n ATTACHMENT 1 ASIAN CLAMS Asian clams, Corbicula Fluminea, are common mollusks found abundantly in the warm freshwaters of the United States. Adult clams, approximately 1-1 1/2 inches in diameter, reproduce prolifically during the year when water temperatures range from 62 to 75F. Larvae discharged from the adults are about 1/50 of an inch in diameter and are passively carried by water movements. Stagnant, or low flow areas, provide suitable conditions for the larvae to quickly grow into adults. | | n ATTACHMENT 1 ASIAN CLAMS Asian clams, Corbicula Fluminea, are common mollusks found abundantly in the warm freshwaters of the United States. Adult clams, approximately 1-1 1/2 inches in diameter, reproduce prolifically during the year when water temperatures range from 62 to 75F. Larvae discharged from the adults are about 1/50 of an inch in diameter and are passively carried by water movements. Stagnant, or low flow areas, provide suitable conditions for the larvae to quickly grow into adults. |
| At ANO-2, service water saction is taken from Lake Dardanelle and is strained before entering the plant. DP measurement is checked on the screens once per shift to prevent buildup of adult clams. | | At ANO-2, service water saction is taken from Lake Dardanelle and is strained before entering the plant. DP measurement is checked on the screens once per shift to prevent buildup of adult clams. |
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| | s ATTACHMENT 2 CONTAINMENT COOLING UNIT CI.EANING OPERATIONS Following the shutdown of ANO-2, several attempts at removing the block-age (clams) from the coolees were made. These efforts, although not completely successful, did substantially reduce the blockage and thus increase flow. |
| s ATTACHMENT 2 CONTAINMENT COOLING UNIT CI.EANING OPERATIONS Following the shutdown of ANO-2, several attempts at removing the block-age (clams) from the coolees were made. These efforts, although not | |
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| completely successful, did substantially reduce the blockage and thus increase flow. | |
| Operations performed included: | | Operations performed included: |
| : 1) Backflushing through the cooler tubes. | | : 1) Backflushing through the cooler tubes. |
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| i ATTACHMENT 3 SAFETY EVALUATION Currently, ANO-2 is allowed to operate with three Containment Cooling Units (CCUs) OPERABLE. CCUs provide (along with Containment Sprays - | | i ATTACHMENT 3 SAFETY EVALUATION Currently, ANO-2 is allowed to operate with three Containment Cooling Units (CCUs) OPERABLE. CCUs provide (along with Containment Sprays - |
| CS) an essential safety function by removing heat, and thus reducing pressure in the Containment following a PBA LOCA or MSLB. Pressure in the Containment is important and significant for two distinct reasons: | | CS) an essential safety function by removing heat, and thus reducing pressure in the Containment following a PBA LOCA or MSLB. Pressure in the Containment is important and significant for two distinct reasons: |
| : 1) Containment design pressure must not be exceeded to assure Con- | | : 1) Containment design pressure must not be exceeded to assure Con-(ainment integrity is maintained and the accident is contained within at least the third fission product barrier, and 2) Pressure needs to be reduced to as near atmospheric as possible following the accident to minimize leakage through the Containment and thus minimize exposure off-site. Each of these two areas are addressed below. |
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| (ainment integrity is maintained and the accident is contained within at least the third fission product barrier, and 2) Pressure needs to be reduced to as near atmospheric as possible following the accident to minimize leakage through the Containment and thus minimize exposure off-site. Each of these two areas are addressed below. | |
| : 1. Peak Containment Pressure a) Current Technical Specification The current ANO-2 Technical Specification requires two Containment Spray Systems (CSS) OPERABLE and two Con-tainment Cooling Groups with two CCUs in one group sud one CCU in the second group OPERABLE. Assuming a most limiting single failure of a diesel generator, equipment remaining in service would be one CSS and one CCU. Our letter of September 11, 1980 provided you the results of the most recent peak containment pressure calculation in this configuration. The peak pressure is calculated o be 52.8 psig vs a containment design pressure of 54 psig and is thus acceptable. | | : 1. Peak Containment Pressure a) Current Technical Specification The current ANO-2 Technical Specification requires two Containment Spray Systems (CSS) OPERABLE and two Con-tainment Cooling Groups with two CCUs in one group sud one CCU in the second group OPERABLE. Assuming a most limiting single failure of a diesel generator, equipment remaining in service would be one CSS and one CCU. Our letter of September 11, 1980 provided you the results of the most recent peak containment pressure calculation in this configuration. The peak pressure is calculated o be 52.8 psig vs a containment design pressure of 54 psig and is thus acceptable. |
| b) Proposed Technical Specification The proposed Technical Specification Change would allow ANO-2 operation with 2 CSS OPERABLE and 2 Con *.ainment Cooling Groups OPERABLE with at least one CCd in each group. Again assuming the most limiting eingle failure of a Diesel Generator, equipment remaining in service would be one CSS and one CCU or identigal to the above case for the existing Technical Specificacion. Thus Containment Peak resign Pressure would not be exceeded nor would the calculated peak pressure increase above the current calculation. | | b) Proposed Technical Specification The proposed Technical Specification Change would allow ANO-2 operation with 2 CSS OPERABLE and 2 Con *.ainment Cooling Groups OPERABLE with at least one CCd in each group. Again assuming the most limiting eingle failure of a Diesel Generator, equipment remaining in service would be one CSS and one CCU or identigal to the above case for the existing Technical Specificacion. Thus Containment Peak resign Pressure would not be exceeded nor would the calculated peak pressure increase above the current calculation. |
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| i This information is summarized in the following Table. i Single , ,, | | i This information is summarized in the following Table. i Single , ,, |
| CCU CS Failure CCU CS SI Peak Pressure Current T.S. 3 2 DG 1 1 2 52.8 psig Proposed T.S. 2 2 DG 1 1 2 52,8 psig | | CCU CS Failure CCU CS SI Peak Pressure Current T.S. 3 2 DG 1 1 2 52.8 psig Proposed T.S. 2 2 DG 1 1 2 52,8 psig Assuming full Safety Injection Flow (2 trains of SI) is incon-sistent with the failure of a Diesel Generator and is thus con-se rva tive. |
| * Assuming full Safety Injection Flow (2 trains of SI) is incon-sistent with the failure of a Diesel Generator and is thus con-se rva tive.
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| Bases and code description provided in our letter of September 11, 1980. | | Bases and code description provided in our letter of September 11, 1980. |
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| : 2. Reduction of Pressure Post DBA The rate of cooldown of the containment atmosphere following a DBA affects the rate of pressure decrease inside the con-tainment and thus affects off-site dose due to containment leakage. | | : 2. Reduction of Pressure Post DBA The rate of cooldown of the containment atmosphere following a DBA affects the rate of pressure decrease inside the con-tainment and thus affects off-site dose due to containment leakage. |
| In the most limiting case above (failure of a Diesel Gen-erator) containment cooldown rate with the Proposed Technical Specification would be identical to the containment cooldown rate with the current Technical Specification as the same equipment would be operable (i.e., 1 CCU and 1 CSS). | | In the most limiting case above (failure of a Diesel Gen-erator) containment cooldown rate with the Proposed Technical Specification would be identical to the containment cooldown rate with the current Technical Specification as the same equipment would be operable (i.e., 1 CCU and 1 CSS). |
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| This conclusion is not unexpected as the most limiting con-dition (failure of a Diesel Generator) with the Proposed Technical Specification is identical to the most limiting condition with the existing Technical Specification. | | This conclusion is not unexpected as the most limiting con-dition (failure of a Diesel Generator) with the Proposed Technical Specification is identical to the most limiting condition with the existing Technical Specification. |
| In addition to the change described above, we also desire to modify Surveillance Requirement 4.6.2.3.a. This specification, approved by your letter of Oeptember 12, 1980, requires a service water flow of 2500 gpm to each Group containing two operational cooling units and 1250 gpm to each Group containing one operational cooling unit. The proposed change requires a service water flow of 1250 gpm to each Group regardless of the number of operational CCUs in each Group. | | In addition to the change described above, we also desire to modify Surveillance Requirement 4.6.2.3.a. This specification, approved by your letter of Oeptember 12, 1980, requires a service water flow of 2500 gpm to each Group containing two operational cooling units and 1250 gpm to each Group containing one operational cooling unit. The proposed change requires a service water flow of 1250 gpm to each Group regardless of the number of operational CCUs in each Group. |
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| This change is requested for two reasons. First, the analysis discussed above shows that one CCU per Group with a flow rate of 1250 gpm is adequate to mitigate the consequences of a postulated DBA. When two CCUs in a Group are operating, a total service water flow of 253250 gpm will provide essen-tially equivalent heat removal capability as compared to 1250 gpm through one cooler. Second, this change will prevent unnecessarily removing one of two operating CCUs from service when service water flow to a Group is between 1250 and 2500 gpm. | | This change is requested for two reasons. First, the analysis discussed above shows that one CCU per Group with a flow rate of 1250 gpm is adequate to mitigate the consequences of a postulated DBA. When two CCUs in a Group are operating, a total service water flow of 253250 gpm will provide essen-tially equivalent heat removal capability as compared to 1250 gpm through one cooler. Second, this change will prevent unnecessarily removing one of two operating CCUs from service when service water flow to a Group is between 1250 and 2500 gpm. |
| Conclusion As demonstrated above, the Proposed Technical Specification will not jeopardize containment integrity by exceeding the containment design pressure nor will it increase the calculated post DBA Peak Containment Pressure in the most limiting case. Off-site dose consequences as a result of containment leakage post DBA will not exceed the dose pro-jections of the original design basis calculations for ANO-2 and will be identical to projected doses using the existing Technical Specification in the most limiting case. | | Conclusion As demonstrated above, the Proposed Technical Specification will not jeopardize containment integrity by exceeding the containment design pressure nor will it increase the calculated post DBA Peak Containment Pressure in the most limiting case. Off-site dose consequences as a result of containment leakage post DBA will not exceed the dose pro-jections of the original design basis calculations for ANO-2 and will be identical to projected doses using the existing Technical Specification in the most limiting case. |
| Thus, the Proposed Technical Specification does not constitute a sig-nificant hazard to the health and safety of the public; in the most limiting case, the margin of safety is not reduced; and, a reasonable degree of assurance of safety is maintained. | | Thus, the Proposed Technical Specification does not constitute a sig-nificant hazard to the health and safety of the public; in the most limiting case, the margin of safety is not reduced; and, a reasonable degree of assurance of safety is maintained. |
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| FIGURE 1 | | FIGURE 1 2VCC2A SW 1250 gpm > > |
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| 2VCC2C SW 1250 gpm y .. | | 2VCC2C SW 1250 gpm y .. |
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEAR1CAN099904, Application for Amend to License DPR-51,changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16,for Suppl Use of OTSG Repair Roll Technology1999-09-19019 September 1999 Application for Amend to License DPR-51,changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16,for Suppl Use of OTSG Repair Roll Technology 0CAN099903, Application for Amends to Licenses DPR-51 & NPF-6,changing Heavy Load Handling Requirements & Transportation Provisions to Permit Movement of Original & Replacement SGs Through Containment Opening During SG Replacement Outage1999-09-17017 September 1999 Application for Amends to Licenses DPR-51 & NPF-6,changing Heavy Load Handling Requirements & Transportation Provisions to Permit Movement of Original & Replacement SGs Through Containment Opening During SG Replacement Outage 0CAN099901, Application for Amends to Licenses DPR-51 & NF-6,changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks1999-09-17017 September 1999 Application for Amends to Licenses DPR-51 & NF-6,changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks 1CAN089903, Application for Amend to License DPR-51,revising ESAS Low RCS Pressure Setpoint,To Ensure That TS Adequately Bounds Safety Analysis1999-08-18018 August 1999 Application for Amend to License DPR-51,revising ESAS Low RCS Pressure Setpoint,To Ensure That TS Adequately Bounds Safety Analysis 2CAN089905, Application for Amend to License NPF-6,revising TS to Remove Requirements for Tube Repair (Sleeving) & Clarify Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs1999-08-18018 August 1999 Application for Amend to License NPF-6,revising TS to Remove Requirements for Tube Repair (Sleeving) & Clarify Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs 2CAN079903, Application for Amend to License NPF-6,revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage1999-07-29029 July 1999 Application for Amend to License NPF-6,revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage 1CAN079904, Suppl to Util 990409 Proposed TS Changes to Revise Requirements Associated with Station Batteries & Dc Sources to 125 Volt Dc Switchyard Distribution Sys1999-07-29029 July 1999 Suppl to Util 990409 Proposed TS Changes to Revise Requirements Associated with Station Batteries & Dc Sources to 125 Volt Dc Switchyard Distribution Sys 0CAN079901, Application for Amends to Licenses DPR-51 & NPF-6 to Change TS & Subsequent Relief Request from Post Accident Sampling Requirements of NUREG-0737.TS Administrative Control requirements,NUREG-0737 & RG 1.97,rev 3,affected1999-07-14014 July 1999 Application for Amends to Licenses DPR-51 & NPF-6 to Change TS & Subsequent Relief Request from Post Accident Sampling Requirements of NUREG-0737.TS Administrative Control requirements,NUREG-0737 & RG 1.97,rev 3,affected 1CAN069902, Application for Amend to License DPR-51,revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-06-0101 June 1999 Application for Amend to License DPR-51,revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks 1CAN059901, Application for Amend to License DPR-51,revising TS SRs & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG Tubes Encompassed by Upper Tube Sheet. Proprietary Rept Encl.Rept Withheld,Per 10CFR2.790(b)(4)1999-05-14014 May 1999 Application for Amend to License DPR-51,revising TS SRs & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG Tubes Encompassed by Upper Tube Sheet. Proprietary Rept Encl.Rept Withheld,Per 10CFR2.790(b)(4) 2CAN049902, Application for Amend to License NPF-6,adding TS 3.0.6 & Associated Bases to ANO-2 Ts.Proposed Specification Is Identical to Specification 3.0.5 of NUREG-1432, Improved STS CE Plants, Rev 11999-04-0909 April 1999 Application for Amend to License NPF-6,adding TS 3.0.6 & Associated Bases to ANO-2 Ts.Proposed Specification Is Identical to Specification 3.0.5 of NUREG-1432, Improved STS CE Plants, Rev 1 1CAN049901, Application for Amend to License DPR-51,revising Requirements Associated with ANO 1 Provisions for RB Testing & Insp1999-04-0909 April 1999 Application for Amend to License DPR-51,revising Requirements Associated with ANO 1 Provisions for RB Testing & Insp 1CAN049902, Application for Amend to License DPR-51,revising Requirements Associated with ANO-1 Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys1999-04-0909 April 1999 Application for Amend to License DPR-51,revising Requirements Associated with ANO-1 Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys 2CAN029913, Application for Amend to License NPF-6,adding Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable.Action 2 Is Associated with TS Table 3.3-1, Reactor Protective Instrumentation1999-02-25025 February 1999 Application for Amend to License NPF-6,adding Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable.Action 2 Is Associated with TS Table 3.3-1, Reactor Protective Instrumentation 0CAN119801, Application for Amends to Licenses DPR-51 & NPF-6, Implementing Consolidated EOI QA Plan Manual Submitted on 980430 & Approved by NRC in 981106 Se.Changes Also Clarify Responsibilities on STA Position on Shift1998-11-24024 November 1998 Application for Amends to Licenses DPR-51 & NPF-6, Implementing Consolidated EOI QA Plan Manual Submitted on 980430 & Approved by NRC in 981106 Se.Changes Also Clarify Responsibilities on STA Position on Shift 2CAN099805, Application for Amend to License NPF-6,modifying Notes in Table Associated with Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint1998-09-17017 September 1998 Application for Amend to License NPF-6,modifying Notes in Table Associated with Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint 1CAN089801, Application for Amend to License DPR-51,revising TS 3.3.4.B Requirements for Sodium Hydroxide Tank Concentration1998-08-0606 August 1998 Application for Amend to License DPR-51,revising TS 3.3.4.B Requirements for Sodium Hydroxide Tank Concentration 2CAN089802, Application for Amend to License NPF-6,revising TS 3.1.3.2 Action Requirements for CEA Position Indicator Channels1998-08-0606 August 1998 Application for Amend to License NPF-6,revising TS 3.1.3.2 Action Requirements for CEA Position Indicator Channels 2CAN069801, Application for Amend to License NPF-6,revising Portion of Plant Protection Sys Design to Ensure That ESFAS Meets Its Applicable Design Requirements.Rev 1 to Engineering Rept 97-R-2015-01 Encl1998-06-30030 June 1998 Application for Amend to License NPF-6,revising Portion of Plant Protection Sys Design to Ensure That ESFAS Meets Its Applicable Design Requirements.Rev 1 to Engineering Rept 97-R-2015-01 Encl 2CAN069805, Application for Amend to License NPF-6,providing Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values, to Be Consistent W/Requirements Set Forth in NUREG-1432,rev 11998-06-29029 June 1998 Application for Amend to License NPF-6,providing Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values, to Be Consistent W/Requirements Set Forth in NUREG-1432,rev 1 2CAN069807, Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys & to Reflect Installation of New Inverters During Next Scheduled Refueling Outage1998-06-29029 June 1998 Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys & to Reflect Installation of New Inverters During Next Scheduled Refueling Outage 2CAN069806, Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.121998-06-29029 June 1998 Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.12 2CAN069804, Application for Amend to License NPF-6,increasing Allowable as-found Lift Setting Tolerances on MSSVs & Pressurizer Safety Valves1998-06-29029 June 1998 Application for Amend to License NPF-6,increasing Allowable as-found Lift Setting Tolerances on MSSVs & Pressurizer Safety Valves 2CAN049802, Application for Amend to License NPF-6,revising Value of Single Largest post-accident Load Capable of Being Supplied by DGs & Relocates Value to Associated Bases1998-04-30030 April 1998 Application for Amend to License NPF-6,revising Value of Single Largest post-accident Load Capable of Being Supplied by DGs & Relocates Value to Associated Bases 1CAN049802, Application for Amend to License DPR-51,revising TS 1.6.1 Re Qpt Definition.Amend Allows Use of Either Incore Detectors or Excore Detectors for Determining Qpt1998-04-30030 April 1998 Application for Amend to License DPR-51,revising TS 1.6.1 Re Qpt Definition.Amend Allows Use of Either Incore Detectors or Excore Detectors for Determining Qpt 1CAN049806, Application for Amend to License DPR-51,changing Order of Channel Rotation During Outage for Scheduling Flexibility, While Still Requiring Rotation Schedule to Be Established for Operating Cycle1998-04-28028 April 1998 Application for Amend to License DPR-51,changing Order of Channel Rotation During Outage for Scheduling Flexibility, While Still Requiring Rotation Schedule to Be Established for Operating Cycle 1CAN049803, Application for Amend to License DPR-51,allowing Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15,as Discussed W/Nrc on 980318 & 261998-04-0101 April 1998 Application for Amend to License DPR-51,allowing Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15,as Discussed W/Nrc on 980318 & 26 1CAN029803, Application for Amend to License DPR-51,revising TS to Allow Use of Repair Roll Technology (Reroll) for Upper Tubesheet of Sgs.Revised TS Pages,Proprietary Rev 0 to Topical Rept BAW-10232P Included.Proprietary Encl Withheld1998-02-0909 February 1998 Application for Amend to License DPR-51,revising TS to Allow Use of Repair Roll Technology (Reroll) for Upper Tubesheet of Sgs.Revised TS Pages,Proprietary Rev 0 to Topical Rept BAW-10232P Included.Proprietary Encl Withheld 1CAN129702, Application for Amend to License DPR-51,establishing Alternate Repair Criteria for Upper Tubesheet Region of ANO-1 Sgs.Proprietary Topical Rept BAW-10226P Encl.Rept Withheld (Ref 10CFR2.790(b)(4))1997-12-12012 December 1997 Application for Amend to License DPR-51,establishing Alternate Repair Criteria for Upper Tubesheet Region of ANO-1 Sgs.Proprietary Topical Rept BAW-10226P Encl.Rept Withheld (Ref 10CFR2.790(b)(4)) 2CAN099701, Application for Amend to License NPF-6,reducing Min Required Reactor Coolant Sys Flow Rate Requirements Listed in 3.2.5 Until ANO-2 SGs Are Replaced1997-09-23023 September 1997 Application for Amend to License NPF-6,reducing Min Required Reactor Coolant Sys Flow Rate Requirements Listed in 3.2.5 Until ANO-2 SGs Are Replaced 2CAN099703, Application for Amend to License NPF-6,modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure1997-09-23023 September 1997 Application for Amend to License NPF-6,modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure 2CAN079702, Application for Amend to License NPF-6,modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation1997-07-28028 July 1997 Application for Amend to License NPF-6,modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation 2CAN079703, Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Facility EFW Sys as Specified in TS 4.7.1.2.Requests That Effective Date for Change Be within 30 Days of Issuance1997-07-21021 July 1997 Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Facility EFW Sys as Specified in TS 4.7.1.2.Requests That Effective Date for Change Be within 30 Days of Issuance 1CAN059702, Application for Amend to License DPR-51,allowing Sufficient Time for Submittal & NRC Review & Approval of Exigent TS Change Request for one-time Exception to Requirements of Section 4.18.5.b Re SG Tube Insp Surveillance Requirements1997-05-0202 May 1997 Application for Amend to License DPR-51,allowing Sufficient Time for Submittal & NRC Review & Approval of Exigent TS Change Request for one-time Exception to Requirements of Section 4.18.5.b Re SG Tube Insp Surveillance Requirements 2CAN049703, Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves1997-04-24024 April 1997 Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves 2CAN049702, Application for Amend to License NPF-6,permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-991997-04-18018 April 1997 Application for Amend to License NPF-6,permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-99 1CAN049703, Application for Amend to License DPR-51,requesting Exigent TS Change Re Steam Generator Tube Insp Surveillance Requirements1997-04-11011 April 1997 Application for Amend to License DPR-51,requesting Exigent TS Change Re Steam Generator Tube Insp Surveillance Requirements ML20133A6801996-12-23023 December 1996 Application for Amend to License NPF-6,revising TS 3/4.7.8 Which Will Enable on-line Testing of Selected Snubbers by Clarifying Intent of TS 2CAN129603, Application for Amend to License NPF-6,requesting Change to Power Calibr Requirements1996-12-19019 December 1996 Application for Amend to License NPF-6,requesting Change to Power Calibr Requirements 2CAN129604, Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.21996-12-19019 December 1996 Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.2 2CAN129611, Application for Amend to License NPF-6,requesting to Provide Addl NRC-approved Methodology in List of References in TS 6.9.51996-12-19019 December 1996 Application for Amend to License NPF-6,requesting to Provide Addl NRC-approved Methodology in List of References in TS 6.9.5 2CAN119609, Application for Amend to License NPF-6,revising Surveillance Requirements for Unit 2 Re SG Tubing,Ts 4.4.5.CEN-630-NP & CEN-630-P Repts encl.CEN-630-P Rept Withheld,Per 10CFR2.790(b)(4)1996-11-26026 November 1996 Application for Amend to License NPF-6,revising Surveillance Requirements for Unit 2 Re SG Tubing,Ts 4.4.5.CEN-630-NP & CEN-630-P Repts encl.CEN-630-P Rept Withheld,Per 10CFR2.790(b)(4) 2CAN119610, Application for Amend to License NPF-6,adding Suppl 1-P & Approval Ltr to Section 6.9.5.1 in Support of Increased SG Tube Plugging Limit Beyond 10% Ref to Small Break LOCA Methodology CENPD-1371996-11-24024 November 1996 Application for Amend to License NPF-6,adding Suppl 1-P & Approval Ltr to Section 6.9.5.1 in Support of Increased SG Tube Plugging Limit Beyond 10% Ref to Small Break LOCA Methodology CENPD-137 2CAN109603, Application for Amend to License NPF-6,changing Channel Functional Testing Frequency for Most of Reactor Protection Sys (RPS) & ESFAS Instrumentation from Monthly to Every Four Months1996-10-0707 October 1996 Application for Amend to License NPF-6,changing Channel Functional Testing Frequency for Most of Reactor Protection Sys (RPS) & ESFAS Instrumentation from Monthly to Every Four Months 0CAN109603, Application for Amend to Licenses DPR-51 & NPF-6 Re Relocation of RETS Per GL 89-011996-10-0202 October 1996 Application for Amend to Licenses DPR-51 & NPF-6 Re Relocation of RETS Per GL 89-01 0CAN109602, Application for Amends to Licenses DPR-51 & NPF-6,reducing Costs for Licensees by Allowing Change to Requirements W/O Necessarily Requiring License Amend,Per GL 95-101996-10-0202 October 1996 Application for Amends to Licenses DPR-51 & NPF-6,reducing Costs for Licensees by Allowing Change to Requirements W/O Necessarily Requiring License Amend,Per GL 95-10 2CAN089601, Application for Amend to License NPF-6,relocating RCS Flow Rate Limit from TS & to Colr,Iaw/Gl 88-16, Removal of Cycle-Specific Parameter Limits from Ts1996-08-23023 August 1996 Application for Amend to License NPF-6,relocating RCS Flow Rate Limit from TS & to Colr,Iaw/Gl 88-16, Removal of Cycle-Specific Parameter Limits from Ts 0CAN089606, Application for Amends to Licenses DPR-51 & NPF-6,allowing Implementation of Approved Option B to 10CFR50,App J1996-08-23023 August 1996 Application for Amends to Licenses DPR-51 & NPF-6,allowing Implementation of Approved Option B to 10CFR50,App J 2CAN089609, Application for Amend to License NPF-6,revising Section 5.0, Design Features & Would for Most Part,Adopt NUREG-1432 Rev 1,improved, Std Tech Specs for C-E Plants, for Section of TS1996-08-23023 August 1996 Application for Amend to License NPF-6,revising Section 5.0, Design Features & Would for Most Part,Adopt NUREG-1432 Rev 1,improved, Std Tech Specs for C-E Plants, for Section of TS 0CAN069601, Application for Amends to Licenses DPR-51 & NPF-6,allowing Reactor Containment Bldg Equipment Hatch Doors to Remain Open During Fuel Handling & Core Alterations1996-06-28028 June 1996 Application for Amends to Licenses DPR-51 & NPF-6,allowing Reactor Containment Bldg Equipment Hatch Doors to Remain Open During Fuel Handling & Core Alterations 1999-09-19
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEAR1CAN099904, Application for Amend to License DPR-51,changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16,for Suppl Use of OTSG Repair Roll Technology1999-09-19019 September 1999 Application for Amend to License DPR-51,changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16,for Suppl Use of OTSG Repair Roll Technology 0CAN099901, Application for Amends to Licenses DPR-51 & NF-6,changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks1999-09-17017 September 1999 Application for Amends to Licenses DPR-51 & NF-6,changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks 0CAN099903, Application for Amends to Licenses DPR-51 & NPF-6,changing Heavy Load Handling Requirements & Transportation Provisions to Permit Movement of Original & Replacement SGs Through Containment Opening During SG Replacement Outage1999-09-17017 September 1999 Application for Amends to Licenses DPR-51 & NPF-6,changing Heavy Load Handling Requirements & Transportation Provisions to Permit Movement of Original & Replacement SGs Through Containment Opening During SG Replacement Outage 2CAN089905, Application for Amend to License NPF-6,revising TS to Remove Requirements for Tube Repair (Sleeving) & Clarify Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs1999-08-18018 August 1999 Application for Amend to License NPF-6,revising TS to Remove Requirements for Tube Repair (Sleeving) & Clarify Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs 1CAN089903, Application for Amend to License DPR-51,revising ESAS Low RCS Pressure Setpoint,To Ensure That TS Adequately Bounds Safety Analysis1999-08-18018 August 1999 Application for Amend to License DPR-51,revising ESAS Low RCS Pressure Setpoint,To Ensure That TS Adequately Bounds Safety Analysis 1CAN079904, Suppl to Util 990409 Proposed TS Changes to Revise Requirements Associated with Station Batteries & Dc Sources to 125 Volt Dc Switchyard Distribution Sys1999-07-29029 July 1999 Suppl to Util 990409 Proposed TS Changes to Revise Requirements Associated with Station Batteries & Dc Sources to 125 Volt Dc Switchyard Distribution Sys 2CAN079903, Application for Amend to License NPF-6,revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage1999-07-29029 July 1999 Application for Amend to License NPF-6,revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage 0CAN079901, Application for Amends to Licenses DPR-51 & NPF-6 to Change TS & Subsequent Relief Request from Post Accident Sampling Requirements of NUREG-0737.TS Administrative Control requirements,NUREG-0737 & RG 1.97,rev 3,affected1999-07-14014 July 1999 Application for Amends to Licenses DPR-51 & NPF-6 to Change TS & Subsequent Relief Request from Post Accident Sampling Requirements of NUREG-0737.TS Administrative Control requirements,NUREG-0737 & RG 1.97,rev 3,affected 1CAN069902, Application for Amend to License DPR-51,revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks1999-06-0101 June 1999 Application for Amend to License DPR-51,revising SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Tube End Cracks 1CAN059901, Application for Amend to License DPR-51,revising TS SRs & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG Tubes Encompassed by Upper Tube Sheet. Proprietary Rept Encl.Rept Withheld,Per 10CFR2.790(b)(4)1999-05-14014 May 1999 Application for Amend to License DPR-51,revising TS SRs & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG Tubes Encompassed by Upper Tube Sheet. Proprietary Rept Encl.Rept Withheld,Per 10CFR2.790(b)(4) 2CAN049902, Application for Amend to License NPF-6,adding TS 3.0.6 & Associated Bases to ANO-2 Ts.Proposed Specification Is Identical to Specification 3.0.5 of NUREG-1432, Improved STS CE Plants, Rev 11999-04-0909 April 1999 Application for Amend to License NPF-6,adding TS 3.0.6 & Associated Bases to ANO-2 Ts.Proposed Specification Is Identical to Specification 3.0.5 of NUREG-1432, Improved STS CE Plants, Rev 1 1CAN049901, Application for Amend to License DPR-51,revising Requirements Associated with ANO 1 Provisions for RB Testing & Insp1999-04-0909 April 1999 Application for Amend to License DPR-51,revising Requirements Associated with ANO 1 Provisions for RB Testing & Insp 1CAN049902, Application for Amend to License DPR-51,revising Requirements Associated with ANO-1 Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys1999-04-0909 April 1999 Application for Amend to License DPR-51,revising Requirements Associated with ANO-1 Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys 2CAN029913, Application for Amend to License NPF-6,adding Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable.Action 2 Is Associated with TS Table 3.3-1, Reactor Protective Instrumentation1999-02-25025 February 1999 Application for Amend to License NPF-6,adding Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable.Action 2 Is Associated with TS Table 3.3-1, Reactor Protective Instrumentation 0CAN119801, Application for Amends to Licenses DPR-51 & NPF-6, Implementing Consolidated EOI QA Plan Manual Submitted on 980430 & Approved by NRC in 981106 Se.Changes Also Clarify Responsibilities on STA Position on Shift1998-11-24024 November 1998 Application for Amends to Licenses DPR-51 & NPF-6, Implementing Consolidated EOI QA Plan Manual Submitted on 980430 & Approved by NRC in 981106 Se.Changes Also Clarify Responsibilities on STA Position on Shift 2CAN099805, Application for Amend to License NPF-6,modifying Notes in Table Associated with Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint1998-09-17017 September 1998 Application for Amend to License NPF-6,modifying Notes in Table Associated with Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint 2CAN089802, Application for Amend to License NPF-6,revising TS 3.1.3.2 Action Requirements for CEA Position Indicator Channels1998-08-0606 August 1998 Application for Amend to License NPF-6,revising TS 3.1.3.2 Action Requirements for CEA Position Indicator Channels 1CAN089801, Application for Amend to License DPR-51,revising TS 3.3.4.B Requirements for Sodium Hydroxide Tank Concentration1998-08-0606 August 1998 Application for Amend to License DPR-51,revising TS 3.3.4.B Requirements for Sodium Hydroxide Tank Concentration 2CAN069801, Application for Amend to License NPF-6,revising Portion of Plant Protection Sys Design to Ensure That ESFAS Meets Its Applicable Design Requirements.Rev 1 to Engineering Rept 97-R-2015-01 Encl1998-06-30030 June 1998 Application for Amend to License NPF-6,revising Portion of Plant Protection Sys Design to Ensure That ESFAS Meets Its Applicable Design Requirements.Rev 1 to Engineering Rept 97-R-2015-01 Encl 2CAN069804, Application for Amend to License NPF-6,increasing Allowable as-found Lift Setting Tolerances on MSSVs & Pressurizer Safety Valves1998-06-29029 June 1998 Application for Amend to License NPF-6,increasing Allowable as-found Lift Setting Tolerances on MSSVs & Pressurizer Safety Valves 2CAN069806, Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.121998-06-29029 June 1998 Application for Amend to License NPF-6,modifying Requirements for Pressurizer Code Safety Valve Requirements Specified by TS 3.4.2 & Safety Tank Isolation Requirements Specified in TS 3.4.12 2CAN069807, Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys & to Reflect Installation of New Inverters During Next Scheduled Refueling Outage1998-06-29029 June 1998 Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys & to Reflect Installation of New Inverters During Next Scheduled Refueling Outage 2CAN069805, Application for Amend to License NPF-6,providing Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values, to Be Consistent W/Requirements Set Forth in NUREG-1432,rev 11998-06-29029 June 1998 Application for Amend to License NPF-6,providing Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values, to Be Consistent W/Requirements Set Forth in NUREG-1432,rev 1 2CAN049802, Application for Amend to License NPF-6,revising Value of Single Largest post-accident Load Capable of Being Supplied by DGs & Relocates Value to Associated Bases1998-04-30030 April 1998 Application for Amend to License NPF-6,revising Value of Single Largest post-accident Load Capable of Being Supplied by DGs & Relocates Value to Associated Bases 1CAN049802, Application for Amend to License DPR-51,revising TS 1.6.1 Re Qpt Definition.Amend Allows Use of Either Incore Detectors or Excore Detectors for Determining Qpt1998-04-30030 April 1998 Application for Amend to License DPR-51,revising TS 1.6.1 Re Qpt Definition.Amend Allows Use of Either Incore Detectors or Excore Detectors for Determining Qpt 1CAN049806, Application for Amend to License DPR-51,changing Order of Channel Rotation During Outage for Scheduling Flexibility, While Still Requiring Rotation Schedule to Be Established for Operating Cycle1998-04-28028 April 1998 Application for Amend to License DPR-51,changing Order of Channel Rotation During Outage for Scheduling Flexibility, While Still Requiring Rotation Schedule to Be Established for Operating Cycle 1CAN049803, Application for Amend to License DPR-51,allowing Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15,as Discussed W/Nrc on 980318 & 261998-04-0101 April 1998 Application for Amend to License DPR-51,allowing Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15,as Discussed W/Nrc on 980318 & 26 1CAN029803, Application for Amend to License DPR-51,revising TS to Allow Use of Repair Roll Technology (Reroll) for Upper Tubesheet of Sgs.Revised TS Pages,Proprietary Rev 0 to Topical Rept BAW-10232P Included.Proprietary Encl Withheld1998-02-0909 February 1998 Application for Amend to License DPR-51,revising TS to Allow Use of Repair Roll Technology (Reroll) for Upper Tubesheet of Sgs.Revised TS Pages,Proprietary Rev 0 to Topical Rept BAW-10232P Included.Proprietary Encl Withheld 1CAN129702, Application for Amend to License DPR-51,establishing Alternate Repair Criteria for Upper Tubesheet Region of ANO-1 Sgs.Proprietary Topical Rept BAW-10226P Encl.Rept Withheld (Ref 10CFR2.790(b)(4))1997-12-12012 December 1997 Application for Amend to License DPR-51,establishing Alternate Repair Criteria for Upper Tubesheet Region of ANO-1 Sgs.Proprietary Topical Rept BAW-10226P Encl.Rept Withheld (Ref 10CFR2.790(b)(4)) 2CAN099703, Application for Amend to License NPF-6,modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure1997-09-23023 September 1997 Application for Amend to License NPF-6,modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure 2CAN099701, Application for Amend to License NPF-6,reducing Min Required Reactor Coolant Sys Flow Rate Requirements Listed in 3.2.5 Until ANO-2 SGs Are Replaced1997-09-23023 September 1997 Application for Amend to License NPF-6,reducing Min Required Reactor Coolant Sys Flow Rate Requirements Listed in 3.2.5 Until ANO-2 SGs Are Replaced 2CAN079702, Application for Amend to License NPF-6,modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation1997-07-28028 July 1997 Application for Amend to License NPF-6,modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation 2CAN079703, Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Facility EFW Sys as Specified in TS 4.7.1.2.Requests That Effective Date for Change Be within 30 Days of Issuance1997-07-21021 July 1997 Application for Amend to License NPF-6,revising Surveillance Testing Requirements for Facility EFW Sys as Specified in TS 4.7.1.2.Requests That Effective Date for Change Be within 30 Days of Issuance 1CAN059702, Application for Amend to License DPR-51,allowing Sufficient Time for Submittal & NRC Review & Approval of Exigent TS Change Request for one-time Exception to Requirements of Section 4.18.5.b Re SG Tube Insp Surveillance Requirements1997-05-0202 May 1997 Application for Amend to License DPR-51,allowing Sufficient Time for Submittal & NRC Review & Approval of Exigent TS Change Request for one-time Exception to Requirements of Section 4.18.5.b Re SG Tube Insp Surveillance Requirements 2CAN049703, Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves1997-04-24024 April 1997 Application for Amend to License NPF-6,revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp Steam Generator Tube Sleeves 2CAN049702, Application for Amend to License NPF-6,permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-991997-04-18018 April 1997 Application for Amend to License NPF-6,permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-99 1CAN049703, Application for Amend to License DPR-51,requesting Exigent TS Change Re Steam Generator Tube Insp Surveillance Requirements1997-04-11011 April 1997 Application for Amend to License DPR-51,requesting Exigent TS Change Re Steam Generator Tube Insp Surveillance Requirements ML20133A6801996-12-23023 December 1996 Application for Amend to License NPF-6,revising TS 3/4.7.8 Which Will Enable on-line Testing of Selected Snubbers by Clarifying Intent of TS 2CAN129603, Application for Amend to License NPF-6,requesting Change to Power Calibr Requirements1996-12-19019 December 1996 Application for Amend to License NPF-6,requesting Change to Power Calibr Requirements 2CAN129611, Application for Amend to License NPF-6,requesting to Provide Addl NRC-approved Methodology in List of References in TS 6.9.51996-12-19019 December 1996 Application for Amend to License NPF-6,requesting to Provide Addl NRC-approved Methodology in List of References in TS 6.9.5 2CAN129604, Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.21996-12-19019 December 1996 Application for Amend to License NPF-6,requesting Deletion of Specific Value for Total Reactor Coolant Sys Volume in TS 5.4.2 2CAN119609, Application for Amend to License NPF-6,revising Surveillance Requirements for Unit 2 Re SG Tubing,Ts 4.4.5.CEN-630-NP & CEN-630-P Repts encl.CEN-630-P Rept Withheld,Per 10CFR2.790(b)(4)1996-11-26026 November 1996 Application for Amend to License NPF-6,revising Surveillance Requirements for Unit 2 Re SG Tubing,Ts 4.4.5.CEN-630-NP & CEN-630-P Repts encl.CEN-630-P Rept Withheld,Per 10CFR2.790(b)(4) 2CAN119610, Application for Amend to License NPF-6,adding Suppl 1-P & Approval Ltr to Section 6.9.5.1 in Support of Increased SG Tube Plugging Limit Beyond 10% Ref to Small Break LOCA Methodology CENPD-1371996-11-24024 November 1996 Application for Amend to License NPF-6,adding Suppl 1-P & Approval Ltr to Section 6.9.5.1 in Support of Increased SG Tube Plugging Limit Beyond 10% Ref to Small Break LOCA Methodology CENPD-137 2CAN109603, Application for Amend to License NPF-6,changing Channel Functional Testing Frequency for Most of Reactor Protection Sys (RPS) & ESFAS Instrumentation from Monthly to Every Four Months1996-10-0707 October 1996 Application for Amend to License NPF-6,changing Channel Functional Testing Frequency for Most of Reactor Protection Sys (RPS) & ESFAS Instrumentation from Monthly to Every Four Months 0CAN109602, Application for Amends to Licenses DPR-51 & NPF-6,reducing Costs for Licensees by Allowing Change to Requirements W/O Necessarily Requiring License Amend,Per GL 95-101996-10-0202 October 1996 Application for Amends to Licenses DPR-51 & NPF-6,reducing Costs for Licensees by Allowing Change to Requirements W/O Necessarily Requiring License Amend,Per GL 95-10 0CAN109603, Application for Amend to Licenses DPR-51 & NPF-6 Re Relocation of RETS Per GL 89-011996-10-0202 October 1996 Application for Amend to Licenses DPR-51 & NPF-6 Re Relocation of RETS Per GL 89-01 0CAN089606, Application for Amends to Licenses DPR-51 & NPF-6,allowing Implementation of Approved Option B to 10CFR50,App J1996-08-23023 August 1996 Application for Amends to Licenses DPR-51 & NPF-6,allowing Implementation of Approved Option B to 10CFR50,App J 2CAN089601, Application for Amend to License NPF-6,relocating RCS Flow Rate Limit from TS & to Colr,Iaw/Gl 88-16, Removal of Cycle-Specific Parameter Limits from Ts1996-08-23023 August 1996 Application for Amend to License NPF-6,relocating RCS Flow Rate Limit from TS & to Colr,Iaw/Gl 88-16, Removal of Cycle-Specific Parameter Limits from Ts 2CAN089609, Application for Amend to License NPF-6,revising Section 5.0, Design Features & Would for Most Part,Adopt NUREG-1432 Rev 1,improved, Std Tech Specs for C-E Plants, for Section of TS1996-08-23023 August 1996 Application for Amend to License NPF-6,revising Section 5.0, Design Features & Would for Most Part,Adopt NUREG-1432 Rev 1,improved, Std Tech Specs for C-E Plants, for Section of TS 0CAN069601, Application for Amends to Licenses DPR-51 & NPF-6,allowing Reactor Containment Bldg Equipment Hatch Doors to Remain Open During Fuel Handling & Core Alterations1996-06-28028 June 1996 Application for Amends to Licenses DPR-51 & NPF-6,allowing Reactor Containment Bldg Equipment Hatch Doors to Remain Open During Fuel Handling & Core Alterations 1999-09-19
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k ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLEROCK. ARKANSAS 72203 (501)371-4422 WILLIAM CAVANAUGH lll Vee Pmsidet September 16, 1980 Generation & Constructon 2-090-20 Director of Nuclear Reactor Regulation ATTN: Mr. Robert A. Clark, Chief Operating Reactors Branch #3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Subject:
Arkansas Nuclear One-Unit 2 Docket No. 50-368 License No. NPF-6 Technical Specification Change Request-Containment Coolers 2-80A-10 (File: 2-151.2)
Gentlemen:
On September 3, 1980, Arkansas Nuclear One -Unit 2 (ANO-2) was shutdown due to inadequate service water flow to the containment cooling units.
Flow requirements are shown in ANO-2 Technical Specification 4.6.2.3.a.3.
The containment cooling units (CCU) are required to be demonstrated operable every 31 days. These units had successfully passed all sur-veillance tests prior to the test which demonstrated inadequate flow and resulted in the recent plant shutdown. The cause of the inadequate flow was subsequently determined to be the result of an intrusion of Asian Clams into the CCUs. These clams grew rather quickly inside the heat exchanger tubes, afixing themselves to the tube walls, thus blocking flow. A* tachment 1 is a discussion of the Asian Clams growth cycle and the actions we are taking to prevent further growth and/or intrusion.
Significant effort has been expended in cleaning of the CCUs. This effort, however, has been only partially successful. Flow rates have been increased significantly but not yet to the 2500 gpm limit required by Technical Specification 4.6.2.3.a.3. (Note: The CCUs are arranged in two Groups with two CCUs per Group. Each Group is powered by a different safety grade electrical pow (" source.) Some flow blockage still exists as a result of remaining clams which our efforts have been unsuccessful in removing. Attachment 2 is a discussion of the cleaning efforts that have been undertaken.
B009260 MEMBER MIODLE SOUTH UT1UTIES SYSTEM
i As discussed in our letter to you dated September 11, 1980, each CCU is required to have a flow rate of 1250 gpm to obtain maximum performance capability. This, of course, requires a flow rate of 2500 gpm through any Group (containing 2 CCUs) to obtain 1250 gpm through each CCU. Due to the pressure drop across the group and the partially restricted flow, we cannot obtain a flow rate of 2500 gpm through either Group. We can, however, obtain 1250 gpm through a single CCU if the other CCU in the group is isolated.
There is no cleaning procedure known to us that will remove the re-maining clams without jeopardizing the integrity of the tube materials.
In our opinion, it is necessary to completely disassemble the CCUs for such removal. This activity is projected to take 6 to 8 weeks to com-plete. Given the unseasonably hot weather we are now experiencing, power generation from ANO-2 is essential to meet our customers needs.
Therefore, we desire to continue operation with less than maximum flow until our refueling outage early next year.
We have studied the safety implications of continued operation with reduced flow carefully and believe that the public health and safety will not be endangered by such. Attachment 3 is a safety e"sluation addressing this issue.
To allow continued operation, we propose modifications to the ANO-2 Technical Specifications and to the surveillance requirements. Figure 1 is i simplified drawing of the CCUs, service water inlet and outlet and required flow rates. A more detailed P&ID is shown on ANO-2 FSAR Fig-ure 9.2-1 Sht. 2 of 4.
The attached Technical Specification Change Request modifies ANO-2 Technical Specification 3.6.2.3 to allow operation with a minimum of one CCU OPERABLE in each Group and modifies Specification 4.6.2.3.a.3 to.
specify a surveillance flow requirement of 1250 gpm to each OPERABLE Group.
We request your review and approval of the attached Technical Specifi-cation Change Request. As this issue is critical path to start-up of ANO-2 and given our current need for generated power, your most expe-dited review will be sincerely appreciated.
Pursuant to 10 CFR 170.22, we have determined this to be a Class III amendment. Accordingly, attached is a check in the amount of $4,000.00.
Ve y truly yours William Ca augh, III WC:JTE:nak Attachments
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STATE OF ARKANSAS )
) SS COUNTY OF PULASKI )
Willam Cavanaugh, III, being duly sworn, states that he is Vice President, Generation & Construction, for Arkansas Power & Light Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this Supplementary Information; that he has reviewed or caused to have reviewed all of the statements contained in such information, and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information and belief.
" William Cav ,III SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State above named, this day of -y W/ , 1980.
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4 otary Public My Commission Expires:
Mg Commission Dpires 9/1/81
n ATTACHMENT 1 ASIAN CLAMS Asian clams, Corbicula Fluminea, are common mollusks found abundantly in the warm freshwaters of the United States. Adult clams, approximately 1-1 1/2 inches in diameter, reproduce prolifically during the year when water temperatures range from 62 to 75F. Larvae discharged from the adults are about 1/50 of an inch in diameter and are passively carried by water movements. Stagnant, or low flow areas, provide suitable conditions for the larvae to quickly grow into adults.
At ANO-2, service water saction is taken from Lake Dardanelle and is strained before entering the plant. DP measurement is checked on the screens once per shift to prevent buildup of adult clams.
Apparently, during a previous surveillance test of the Containment Cooling Units, Asian clam larvae were present in the service water and were pumped with the water into the Containment Coolers. Upon comple-tion of the Surveillance test, some service water was left stagnent in the coolers. The larvae present apparently found the growth conditions inside the cooling coils quite agreeable and grew very rapidly. This resulted in the reduced flow (flow blockage) evidenced during the last surveillance test.
To preclude future events such as this, we will be taking the following corrective measures:
- 1) Surveillance testing of the Containment Cooling Units will be increased to a frequency of once per 14 days.
- 2) During periods of the year when service water temperature is conducive to the production of larvae, (62-75F) we will chlor-inate the service water intake and the entire service water loop before performing a surveillance test on the Containment l Cooling Units. Chlotination has Ivoved very effective in killing the larvae and is believed oppropriate in this case.
To assure chlorine is used during the period of larvae pro-duction, we will conservatively chlorinate when service water l temperature is between 60 and 80F. !
We believe the above measures provide adequate assurance this problem either will not reoccur or will be identified rapidly if it should. )
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s ATTACHMENT 2 CONTAINMENT COOLING UNIT CI.EANING OPERATIONS Following the shutdown of ANO-2, several attempts at removing the block-age (clams) from the coolees were made. These efforts, although not completely successful, did substantially reduce the blockage and thus increase flow.
Operations performed included:
- 1) Backflushing through the cooler tubes.
- 2) High velocity flushes using compressed air.
- 3) In accessable portions of the tubes (the tubes make six U bends) wires, etc., were used to remove clams.
- 4) Chlorine was introduced for several hours followed by more flushing.
- 5) Chemical cleaning was investigated but was determined to be unacceptable due to possible effects on tube integrity.
The results of these operations substantially reduced blockage and increased flow. Visual examinations of the cooling tube surfaces in-dicated them to be as clean as new condition. The conclusion of this visual inspection was that no significant heat transfer degradation exists. The effect of the remaining clams in the system is basically one of flow blockage.
Complete removal of the clams will involve complete disassembly of the coolers by cutting the tubes, physically removing the clams and re-welding the tubes. Such an operation would take an estimated 6 to 8 weeks and in addition, problems might be encountered in re-validating the N stamp on the coolers.
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i ATTACHMENT 3 SAFETY EVALUATION Currently, ANO-2 is allowed to operate with three Containment Cooling Units (CCUs) OPERABLE. CCUs provide (along with Containment Sprays -
CS) an essential safety function by removing heat, and thus reducing pressure in the Containment following a PBA LOCA or MSLB. Pressure in the Containment is important and significant for two distinct reasons:
- 1) Containment design pressure must not be exceeded to assure Con-(ainment integrity is maintained and the accident is contained within at least the third fission product barrier, and 2) Pressure needs to be reduced to as near atmospheric as possible following the accident to minimize leakage through the Containment and thus minimize exposure off-site. Each of these two areas are addressed below.
- 1. Peak Containment Pressure a) Current Technical Specification The current ANO-2 Technical Specification requires two Containment Spray Systems (CSS) OPERABLE and two Con-tainment Cooling Groups with two CCUs in one group sud one CCU in the second group OPERABLE. Assuming a most limiting single failure of a diesel generator, equipment remaining in service would be one CSS and one CCU. Our letter of September 11, 1980 provided you the results of the most recent peak containment pressure calculation in this configuration. The peak pressure is calculated o be 52.8 psig vs a containment design pressure of 54 psig and is thus acceptable.
b) Proposed Technical Specification The proposed Technical Specification Change would allow ANO-2 operation with 2 CSS OPERABLE and 2 Con *.ainment Cooling Groups OPERABLE with at least one CCd in each group. Again assuming the most limiting eingle failure of a Diesel Generator, equipment remaining in service would be one CSS and one CCU or identigal to the above case for the existing Technical Specificacion. Thus Containment Peak resign Pressure would not be exceeded nor would the calculated peak pressure increase above the current calculation.
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i This information is summarized in the following Table. i Single , ,,
CCU CS Failure CCU CS SI Peak Pressure Current T.S. 3 2 DG 1 1 2 52.8 psig Proposed T.S. 2 2 DG 1 1 2 52,8 psig Assuming full Safety Injection Flow (2 trains of SI) is incon-sistent with the failure of a Diesel Generator and is thus con-se rva tive.
Bases and code description provided in our letter of September 11, 1980.
- 2. Reduction of Pressure Post DBA The rate of cooldown of the containment atmosphere following a DBA affects the rate of pressure decrease inside the con-tainment and thus affects off-site dose due to containment leakage.
In the most limiting case above (failure of a Diesel Gen-erator) containment cooldown rate with the Proposed Technical Specification would be identical to the containment cooldown rate with the current Technical Specification as the same equipment would be operable (i.e., 1 CCU and 1 CSS).
Calculations of off-site dose from containment leakage fol-lowing a DBA were performed in accordance with Regulatory Guide 1.4 Revision 2. (See ANO-2 FSAR Section 15.1.13-2)
This Regulatory Guide requires using the leakage associated with the peak Containment Pressure, as shown in the Technical
! Specifications, for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following the DBA and one-half that leakage for the remaining time until the ac-cident is terminated. We have reviewed calculations using the limits in the Proposed Technical Specification and have concluded that containment leakage and, thus, off-site dose is at all times less than the original dose calculations performed in accordance with Regulatory Guide 1.4.
This conclusion is not unexpected as the most limiting con-dition (failure of a Diesel Generator) with the Proposed Technical Specification is identical to the most limiting condition with the existing Technical Specification.
In addition to the change described above, we also desire to modify Surveillance Requirement 4.6.2.3.a. This specification, approved by your letter of Oeptember 12, 1980, requires a service water flow of 2500 gpm to each Group containing two operational cooling units and 1250 gpm to each Group containing one operational cooling unit. The proposed change requires a service water flow of 1250 gpm to each Group regardless of the number of operational CCUs in each Group.
This change is requested for two reasons. First, the analysis discussed above shows that one CCU per Group with a flow rate of 1250 gpm is adequate to mitigate the consequences of a postulated DBA. When two CCUs in a Group are operating, a total service water flow of 253250 gpm will provide essen-tially equivalent heat removal capability as compared to 1250 gpm through one cooler. Second, this change will prevent unnecessarily removing one of two operating CCUs from service when service water flow to a Group is between 1250 and 2500 gpm.
Conclusion As demonstrated above, the Proposed Technical Specification will not jeopardize containment integrity by exceeding the containment design pressure nor will it increase the calculated post DBA Peak Containment Pressure in the most limiting case. Off-site dose consequences as a result of containment leakage post DBA will not exceed the dose pro-jections of the original design basis calculations for ANO-2 and will be identical to projected doses using the existing Technical Specification in the most limiting case.
Thus, the Proposed Technical Specification does not constitute a sig-nificant hazard to the health and safety of the public; in the most limiting case, the margin of safety is not reduced; and, a reasonable degree of assurance of safety is maintained.
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FIGURE 1 2VCC2A SW 1250 gpm > >
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2VCC2C SW 1250 gpm y ..
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