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| {{#Wiki_filter:Entergy Operations, Inc.1448 SR, 333 Russellville. | | {{#Wiki_filter:Entergy Operations, Inc. |
| AR 72802 Tel 479-858-3110 Timothy G. Mitchell Vice President, Operalions Arkansas Nuclear One 2CAN030802 March 13, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 | | 1448 SR, 333 Russellville. AR 72802 Tel 479-858-3110 Timothy G. Mitchell Vice President, Operalions Arkansas Nuclear One 2CAN030802 March 13, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| License Amendment Request Technical Specification Changes To Relocate RCS Chemistry Requirements to TRM Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6 | | License Amendment Request Technical Specification Changes To Relocate RCS Chemistry Requirements to TRM Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6 |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) hereby requests the following amendment for Arkansas Nuclear One, Unit 2 (ANO-2). The proposed change will relocate the Technical Specification (TS) 3.4.7, Reactor Coolant System Chemistry, to the Technical Requirements Manual (TRM). This change is consistent with the Improved Standard Technical Specifications for Combustion Engineering Plants of NUREG 1432.The requirements for monitoring and maintaining Reactor Coolant System (RCS) chemistry limits do not meet the criteria of 10 CFR 50.36 and, therefore, are proposed for relocation to the station TRM. Changes to the TRM are controlled in accordance with the requirements of 10 CFR 50.59. The associated TS Bases, controlled in accordance with the TS Bases Control Program of TS 6.5.14, will also be relocated to the TRM. The relocation of the TS Bases is part of the ANO TS change implementation process; therefore, a markup of the TS Bases is not provided in this submittal. | | |
| The proposed change has been evaluated in accordance with 10 CFR 50.91 (a)(1) using criteria in 10 CFR 50.92(c) and it has been determined that the changes involve no significant hazards consideration. | | Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) hereby requests the following amendment for Arkansas Nuclear One, Unit 2 (ANO-2). The proposed change will relocate the Technical Specification (TS) 3.4.7, Reactor Coolant System Chemistry, to the Technical Requirements Manual (TRM). This change is consistent with the Improved Standard Technical Specifications for Combustion Engineering Plants of NUREG 1432. |
| The bases for these determinations are included in the attached submittal. | | The requirements for monitoring and maintaining Reactor Coolant System (RCS) chemistry limits do not meet the criteria of 10 CFR 50.36 and, therefore, are proposed for relocation to the station TRM. Changes to the TRM are controlled in accordance with the requirements of 10 CFR 50.59. The associated TS Bases, controlled in accordance with the TS Bases Control Program of TS 6.5.14, will also be relocated to the TRM. The relocation of the TS Bases is part of the ANO TS change implementation process; therefore, a markup of the TS Bases is not provided in this submittal. |
| | The proposed change has been evaluated in accordance with 10 CFR 50.91 (a)(1) using criteria in 10 CFR 50.92(c) and it has been determined that the changes involve no significant hazards consideration. The bases for these determinations are included in the attached submittal. |
| The proposed change does not include any new commitments. | | The proposed change does not include any new commitments. |
| Entergy requests approval of the proposed amendment by April 1, 2009. Once approved, the amendment shall be implemented within 90 days.A oo/ | | Entergy requests approval of the proposed amendment by April 1, 2009. Once approved, the amendment shall be implemented within 90 days. |
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| 2CAN030802 Page 2 of 2 If you have any questions or require additional information, please contact David Bice at 479-858-5338. | | 2CAN030802 Page 2 of 2 If you have any questions or require additional information, please contact David Bice at 479-858-5338. |
| I declare under penalty of perjury that the foregoing is true and correct. Executed on March 13, 2008.Sincerely~,Q Attachments: | | I declare under penalty of perjury that the foregoing is true and correct. Executed on March 13, 2008. |
| : 1. Analysis of Proposed Technical Specification Change 2. Proposed Technical Specification Changes (mark-up)cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P. 0. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS 0-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437 Attachment 1 2CAN030802 Analysis of Proposed Technical Specification Change Attachment to 2CAN030802 Page 1 of 4 | | Sincerely~,Q Attachments: |
| | : 1. Analysis of Proposed Technical Specification Change |
| | : 2. Proposed Technical Specification Changes (mark-up) cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P. 0. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS 0-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437 |
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| ==1.0 DESCRIPTION==
| | Attachment 1 2CAN030802 Analysis of Proposed Technical Specification Change |
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| This letter is a request to amend Operating License NPF-6 for Arkansas Nuclear One, Unit 2 (ANO-2).The proposed change will relocate Technical Specification (TS) 3.4.7, Reactor Coolant System Chemistry, to the ANO-2 Technical Requirements Manual (TRM). Changes to the TRM are controlled in accordance with 10 CFR 50.59. The change is consistent with NUREG 1430, Improved Standard Technical Specifications for Combustion Engineering Plants, heretofore referred to as ITS.Note that plant-specific TSs relating to Reactor Coolant System (RCS) chemistry were not included in the original version of NUREG 1432 because this TS did not meet the TS inclusion requirements of 10 CFR 50.36.
| | Attachment to 2CAN030802 Page 1 of 4 |
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| ==2.0 PROPOSED CHANGE== | | ==1.0 DESCRIPTION== |
| ANO-2 TS 3.4.7, Reactor Coolant System Chemistry, is proposed for relocation to the ANO-2 TRM. During relocation, the current TS Actions may be modified.
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| Such modification, if performed, will be in accordance with the requirements of 10 CFR 50.59.Note that the proposed location results in several TS pages being deleted. Therefore, a change to TS page 3/4 4-14 is included in the attached markups to state that the "next page is..." This supporting change is administrative in nature and is not discussed further in this submittal.
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| ==3.0 BACKGROUND==
| | This letter is a request to amend Operating License NPF-6 for Arkansas Nuclear One, Unit 2 (ANO-2). |
| | The proposed change will relocate Technical Specification (TS) 3.4.7, Reactor Coolant System Chemistry, to the ANO-2 Technical Requirements Manual (TRM). Changes to the TRM are controlled in accordance with 10 CFR 50.59. The change is consistent with NUREG 1430, Improved Standard Technical Specifications for Combustion Engineering Plants, heretofore referred to as ITS. |
| | Note that plant-specific TSs relating to Reactor Coolant System (RCS) chemistry were not included in the original version of NUREG 1432 because this TS did not meet the TS inclusion requirements of 10 CFR 50.36. |
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| TS 3.4.7 provides limits on the oxygen, chloride, and fluoride content in the RCS to minimize corrosion. | | ==2.0 PROPOSED CHANGE== |
| Per the TS Bases, RCS chemistry parameters ensure that corrosion of RCS components is minimized, thus reducing the potential for RCS leakage or failure due to corrosion-based mechanisms.
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| Maintaining' the chemistry within limits provides adequate corrosion protection to ensure the structural integrity of the RCS over the life of the plant.4.0 TECHNICAL ANALYSIS RCS corrosion is a slow process which can be detected by in-service inspections or other means before significant degradation occurs. RCS chemistry is controlled to minimize corrosion over the long term. Although it is important to monitor and control RCS chemistry, limits and surveillance requirements do not meet the criteria of 10 CFR 50.36 for inclusion in the TSs. An assessment of the current RCS chemistry TS requirements against the 10 CFR 50.36 criteria is provided below.
| | ANO-2 TS 3.4.7, Reactor Coolant System Chemistry, is proposed for relocation to the ANO-2 TRM. During relocation, the current TS Actions may be modified. Such modification, if performed, will be in accordance with the requirements of 10 CFR 50.59. |
| Attachment to 2CAN030802 Page 2 of 4 1. The RCS chemistry limits are not installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
| | Note that the proposed location results in several TS pages being deleted. Therefore, a change to TS page 3/4 4-14 is included in the attached markups to state that the "next page is..." This supporting change is administrative in nature and is not discussed further in this submittal. |
| The RCS chemistry limits do not satisfy Criterion 1.2. The RCS chemistry limits are not a process variable, design feature, or operating restriction that is an initial condition of a DBA or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The RCS chemistry limits do not satisfy Criterion 2.3. The RCS chemistry limits are not a structure, system or component that is part of the primary success path and which functions or actuates to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The RCS chemistry limits do not satisfy Criterion 3.4. The RCS chemistry limits are not a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. As discussed in Section 4.0, (Appendix A, page A-40) of topical report WCAP- 11618 (Reference 1), the RCS chemistry limits were found to be a non-significant risk contributor to core damage frequency and offsite releases (WCAP-1 1618,"Criteria Application," evaluated Limiting Conditions for Operation (LCOs) contained in TSs for Westinghouse pressurized water reactors with respect to the criteria of 10 CFR 50.36 to determine which LCOs satisfied any of the criteria).
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| In addition to the above, the RCS chemistry limits are not importantfor any scenarios modeled in the ANO-2 safety analyses.
| | ==3.0 BACKGROUND== |
| Therefore, the RCS chemistry limits do not meet Criterion 4.Since the 10 CFR 50.36 criteria have not been met, the RCS chemistry limits LCO and associated Applicability, Actions, and Surveillances may be relocated out of the TSs. The RCS chemistry specification will be relocated to the TRM. Changes to the TRM will be controlled under the provisions of 10 CFR 50.59.5.0 REGULATORY ANALYSIS 5.3 Applicable Regulatory Requirements/Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met.There are no specific General Design Criteria (GDC) associated with RCS chemistry.
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| RCS sampling and chemistry limits are discussed in various documents, such as NUREG 0737 and Regulatory Guide 1.97. However, the proposed change does not eliminate monitoring and maintaining RCS chemistry, but only acts to relocate the requirements from the TSs to the TRM. Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will continue to be conducted in accordance with the site licensing basis, and (3) the approval of the proposed change will not be inimical to the common defense and security or to the health and safety of the public.-I Attachment to 2CAN030802 Page 3 of 4 In conclusion, Entergy has determined that the proposed change does not require any exemptions or relief from regulatory requirements, other than the TS, and does not affect conformance with any GDC differently than described in the Safety Analysis Report (SAR).5.2 No Significant Hazards Consideration A change is proposed to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TSs) to relocate TS 3.4.7, Reactor Coolant System Chemistry, to the Technical Requirements Manual (TRM). The change is consistent with the improved standard TSs (ITS) of NUREG 1432.Entergy Operations, Inc. has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
| | TS 3.4.7 provides limits on the oxygen, chloride, and fluoride content in the RCS to minimize corrosion. Per the TS Bases, RCS chemistry parameters ensure that corrosion of RCS components is minimized, thus reducing the potential for RCS leakage or failure due to corrosion-based mechanisms. Maintaining' the chemistry within limits provides adequate corrosion protection to ensure the structural integrity of the RCS over the life of the plant. |
| Response:
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| No.The proposed change acts to relocate current Reactor Coolant System (RCS)chemistry limits and monitoring requirements from the TSs to the TRM. Monitoring and maintaining RCS chemistry minimizes the potential for corrosion of RCS piping and components.
| | ==4.0 TECHNICAL ANALYSIS== |
| Corrosion effects are considered a long-term impact on RCS structural integrity.
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| Because RCS chemistry will continue to be monitored and controlled, relocating the current TS requirements to the TRM will not present an adverse impact to the RCS and, subsequently, will not impact the probability or consequences of an accident previously evaluated.
| | RCS corrosion is a slow process which can be detected by in-service inspections or other means before significant degradation occurs. RCS chemistry is controlled to minimize corrosion over the long term. Although it is important to monitor and control RCS chemistry, limits and surveillance requirements do not meet the criteria of 10 CFR 50.36 for inclusion in the TSs. An assessment of the current RCS chemistry TS requirements against the 10 CFR 50.36 criteria is provided below. |
| Furthermore, once relocated to the TRM, changes to RCS chemistry limits or monitoring requirements will be controlled in accordance with 10 CFR 50.59.Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
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| : 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
| | Attachment to 2CAN030802 Page 2 of 4 |
| Response:
| | : 1. The RCS chemistry limits are not installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary. The RCS chemistry limits do not satisfy Criterion 1. |
| No.The proposed change does not result in any plant modifications or changes in the way the plant is operated.
| | : 2. The RCS chemistry limits are not a process variable, design feature, or operating restriction that is an initial condition of a DBA or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The RCS chemistry limits do not satisfy Criterion 2. |
| The proposed change only acts to relocate current RCS chemistry limits and monitoring requirements from the TSs to the TRM.Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
| | : 3. The RCS chemistry limits are not a structure, system or component that is part of the primary success path and which functions or actuates to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The RCS chemistry limits do not satisfy Criterion 3. |
| Attachment to 2CAN030802 Page 4 of 4 3. Does the proposed change involve a significant reduction in a margin of safety?Response:
| | : 4. The RCS chemistry limits are not a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. As discussed in Section 4.0, (Appendix A, page A-40) of topical report WCAP- 11618 (Reference 1), the RCS chemistry limits were found to be a non-significant risk contributor to core damage frequency and offsite releases (WCAP-1 1618, "Criteria Application," evaluated Limiting Conditions for Operation (LCOs) contained in TSs for Westinghouse pressurized water reactors with respect to the criteria of 10 CFR 50.36 to determine which LCOs satisfied any of the criteria). |
| No.The proposed change will maintain limits on RCS chemistry parameters and will continue to provide associated monitoring requirements.
| | In addition to the above, the RCS chemistry limits are not importantfor any scenarios modeled in the ANO-2 safety analyses. Therefore, the RCS chemistry limits do not meet Criterion 4. |
| Once relocated to the TRM, changes to RCS chemistry limits or monitoring requirements will be controlled in accordance with 10 CFR 50.59. In addition, the RCS chemistry limits are not a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.Therefore, the proposed change does not involve a significant reduction in a margin of safety.Based on the above, Entergy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
| | Since the 10 CFR 50.36 criteria have not been met, the RCS chemistry limits LCO and associated Applicability, Actions, and Surveillances may be relocated out of the TSs. The RCS chemistry specification will be relocated to the TRM. Changes to the TRM will be controlled under the provisions of 10 CFR 50.59. |
| 5.3 Environmental Considerations The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
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| Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
| | ==5.0 REGULATORY ANALYSIS== |
| Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
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| 6.0 PRECEDENCE Many plants have previously relocated their respective RCS chemistry TSs to the TRM. Most occurred during conversion of the plant specific TSs to the respective ITS NUREG. This amendment was largely based on discussions noted in previous ANO-1 and North Anna conversions to ITS. Because these were major conversions and involved multiple correspondence opportunities, no specific letter number or date is referenced here.
| | 5.3 Applicable Regulatory Requirements/Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. |
| | There are no specific General Design Criteria (GDC) associated with RCS chemistry. RCS sampling and chemistry limits are discussed in various documents, such as NUREG 0737 and Regulatory Guide 1.97. However, the proposed change does not eliminate monitoring and maintaining RCS chemistry, but only acts to relocate the requirements from the TSs to the TRM. Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will continue to be conducted in accordance with the site licensing basis, and (3) the approval of the proposed change will not be inimical to the common defense and security or to the health and safety of the public. |
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| | Attachment to 2CAN030802 Page 3 of 4 In conclusion, Entergy has determined that the proposed change does not require any exemptions or relief from regulatory requirements, other than the TS, and does not affect conformance with any GDC differently than described in the Safety Analysis Report (SAR). |
| | 5.2 No Significant Hazards Consideration A change is proposed to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TSs) to relocate TS 3.4.7, Reactor Coolant System Chemistry, to the Technical Requirements Manual (TRM). The change is consistent with the improved standard TSs (ITS) of NUREG 1432. |
| | Entergy Operations, Inc. has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below: |
| | : 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? |
| | Response: No. |
| | The proposed change acts to relocate current Reactor Coolant System (RCS) chemistry limits and monitoring requirements from the TSs to the TRM. Monitoring and maintaining RCS chemistry minimizes the potential for corrosion of RCS piping and components. Corrosion effects are considered a long-term impact on RCS structural integrity. Because RCS chemistry will continue to be monitored and controlled, relocating the current TS requirements to the TRM will not present an adverse impact to the RCS and, subsequently, will not impact the probability or consequences of an accident previously evaluated. Furthermore, once relocated to the TRM, changes to RCS chemistry limits or monitoring requirements will be controlled in accordance with 10 CFR 50.59. |
| | Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. |
| | : 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? |
| | Response: No. |
| | The proposed change does not result in any plant modifications or changes in the way the plant is operated. The proposed change only acts to relocate current RCS chemistry limits and monitoring requirements from the TSs to the TRM. |
| | Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. |
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| | Attachment to 2CAN030802 Page 4 of 4 |
| | : 3. Does the proposed change involve a significant reduction in a margin of safety? |
| | Response: No. |
| | The proposed change will maintain limits on RCS chemistry parameters and will continue to provide associated monitoring requirements. Once relocated to the TRM, changes to RCS chemistry limits or monitoring requirements will be controlled in accordance with 10 CFR 50.59. In addition, the RCS chemistry limits are not a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. |
| | Therefore, the proposed change does not involve a significant reduction in a margin of safety. |
| | Based on the above, Entergy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified. |
| | 5.3 Environmental Considerations The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment. |
| | 6.0 PRECEDENCE Many plants have previously relocated their respective RCS chemistry TSs to the TRM. Most occurred during conversion of the plant specific TSs to the respective ITS NUREG. This amendment was largely based on discussions noted in previous ANO-1 and North Anna conversions to ITS. Because these were major conversions and involved multiple correspondence opportunities, no specific letter number or date is referenced here. |
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| | ==7.0 REFERENCES== |
| | : 1. WCAP-11618, "Criteria Application," with Addendum, November 21, 1989. |
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| ==7.0 REFERENCES==
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| : 1. WCAP-11618, "Criteria Application," with Addendum, November 21, 1989.
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| Attachment 2 2CAN030802 Proposed Technical Specification Changes (mark-up) | | Attachment 2 2CAN030802 Proposed Technical Specification Changes (mark-up) |
| REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System operational leakage shall be limited to: a. No PRESSURE BOUNDARY LEAKAGE, b. 1 GPM UNIDENTIFIED LEAKAGE, c. 150 gallons per day primary to secondary leakage through any one steam generator (SG), d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and e. Leakage as specified in Table 3.4.6-1 for those Reactor Coolant System Pressure Isolation Valves identified in Table 3.4.6.1.APPLICABILITY: | | |
| MODES 1,2, 3and 4.ACTION: a. With any PRESSURE BOUNDARY LEAKAGE or any primary to secondary leakage not within limit, be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours.b. With any Reactor Coolant System operational leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and primary to secondary leakage, reduce the leakage rate to within limits within 4 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least two valves* in each high pressure line having a non-functional valve and be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.*These valve's may include check valves for which the leakage rate has been verified, manual valves or automatic valves. Manual and automatic valves shall be tagged as closed to preclude inadvertent valve opening.ARKANSAS -UNIT 2 3/4 4-14 Next Page is 3/4 4-18 Amendment No. 4-84,266, Order datod 4120/81 DMA('TC'nD f'fV't ANITr CVTCZF,:A LIMITING CONDITION FOR OPERATION 3.4.7 The Rat-r SyAtem -hmist; sha-ll be maintainaHed WithiR tho IlimRt Specifi8d RnTable3.4 1.APPLICABILITY. | | REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System operational leakage shall be limited to: |
| At all fimos.ACT-!ON: ..MODES 1, 2, 3 3fld 4 a. With any one Or more chemistry paramotor i exceGs Of itSsStepdy State Limit but within its Transient Limnit, restor the parametefr to Within its Stead" State Limif vvihmn 24 hours or be in at least HOT STANDBY within the neXt 6 hours and in COL'D SHUTDOWN within the following 30 hours.b. With any one or mere chemisrfy paramReteFr in excess of it; TFRnsient Limit, be in at least HOT STANIDBY wvithin 6- hou-rs and in COLD SHUTDOWN within the foEllo'wing 30 ho'-s.MODES 5 and 6 With the oRnGentr;ation of either chloride or fluoride in the RactOr Systor in eXcess Of its Stead" State Limnit for mere than 21 hours or in excess of its T-Fansient Lim~it, reduce the pressurizer pres to 500 psia, if applicable, and perform an enginreeing ealuatiýon to determine the efects Of the out of limit oRn the inrtegrfity f the Reactor Colant System; determine that the Reatofr Coolant System acceptable fo)r continued operatiRon prio r ;tRoiceasing the pressui pressure above 500 psia or prior to proceeding to MODE 4. | | : a. No PRESSURE BOUNDARY LEAKAGE, |
| REQUIREMENTS 4.4.7 The Reactor Coolant System; chemistry shall be determined to be within the lim~itG by analysis of t hoa tes at the frequ6enc-eS specified in Table 4.4 3.ARKANSAS UNIT 2 3/14 415 TABLE 3.4 1 REACTODR COOLANT SYSTEM CHrMISTRY LIMITS* imorit not applicablo with 425F, A IA Qt K 0Kir1 OlA ,4 ADVAMOA~ IkilT') ~IA A 4~ | | : b. 1 GPM UNIDENTIFIED LEAKAGE, |
| TABLE 4-4 A REACTOR COOLRNTESYSTEEM CHEMISTRY LIMITS SU11RVEILLANCE RE=QUIREMNT A KI/ IICA " I Illr 031A A 4"7 ArjIANI~Acy-I IKIIr '~ 'I}} | | : c. 150 gallons per day primary to secondary leakage through any one steam generator (SG), |
| | : d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and |
| | : e. Leakage as specified in Table 3.4.6-1 for those Reactor Coolant System Pressure Isolation Valves identified in Table 3.4.6.1. |
| | APPLICABILITY: MODES 1,2, 3and 4. |
| | ACTION: |
| | : a. With any PRESSURE BOUNDARY LEAKAGE or any primary to secondary leakage not within limit, be in at least HOT STANDBY within 6 hours and in COLD SHUTDOWN within the following 30 hours. |
| | : b. With any Reactor Coolant System operational leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and primary to secondary leakage, reduce the leakage rate to within limits within 4 hours or be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. |
| | : c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours by use of at least two valves* in each high pressure line having a non-functional valve and be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. |
| | *These valve's may include check valves for which the leakage rate has been verified, manual valves or automatic valves. Manual and automatic valves shall be tagged as closed to preclude inadvertent valve opening. |
| | ARKANSAS - UNIT 2 3/4 4-14 Amendment No. 4-84,266, Next Page is 3/4 4-18 Order datod 4120/81 |
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| | DMA('TC'nD f'fV't ANITr CVTCZF,:A LIMITING CONDITION FOR OPERATION 3.4.7 The Rat-r Coolan*t SyAtem -hmist; sha-ll be maintainaHed WithiR tho IlimRt Specifi8d RnTable3.4 1. |
| | APPLICABILITY. At all fimos. |
| | ACT-!ON: .. |
| | MODES 1, 2, 3 3fld 4 |
| | : a. With any one Or more chemistry paramotor i exceGs Of itSsStepdy State Limit but within its Transient Limnit, restor the parametefr to Within its Stead" State Limif vvihmn 24 hours or be in at least HOT STANDBY within the neXt 6 hours and in COL'D SHUTDOWN within the following 30 hours. |
| | : b. With any one or mere chemisrfy paramReteFr in excess of it; TFRnsient Limit, be in at least HOT STANIDBY wvithin 6- hou-rs and in COLD SHUTDOWN within the foEllo'wing 30 ho'-s. |
| | MODES 5 and 6 With the oRnGentr;ation of either chloride or fluoride in the RactOr * *lant Systor in eXcess Of its Stead" State Limnit for mere than 21 hours or in excess of its T-Fansient Lim~it, reduce the pressurizer pres to 500 psia, if applicable, and perform an enginreeing ealuatiýon todetermine the efects Of the out of limit condfit*on oRn the strGtr*all inrtegrfity f the Reactor Colant System; determine that the Reatofr Coolant System re*mrai-n acceptable fo)r continued operatiRon prio r ;tRoiceasing the pressui pressure above 500 psia or prior to proceeding to MODE 4. |
| | SURVEILL*NCE REQUIREMENTS 4.4.7 The Reactor Coolant System; chemistry shall be determined to be within the lim~itG by analysis of thoa tes at the frequ6enc-eS specified in Table 4.4 3. |
| | ARKANSAS UNIT 2 3/14 415 |
| | |
| | TABLE 3.4 1 REACTODR COOLANT SYSTEM CHrMISTRY LIMITS |
| | * imorit not applicablo with 425F, A QtIA A*IK I*CA 0Kir1 OlA ,4 4* |
| | ADVAMOA~ IkilT') ~IA A 4~ |
| | |
| | TABLE 4-4A REACTOR COOLRNTESYSTEEM CHEMISTRY LIMITS SU11RVEILLANCE RE=QUIREMNT A IICA KI/ " I Illr 031A A 4"7 ArjIANI~Acy- I IKIIr '~ 'I}} |
|
---|
Category:Letter type:
MONTHYEAR2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 0CAN092201, Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-09-29029 September 2022 Supplement to License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN092201, Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-09-0808 September 2022 Supplement to Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements 1CAN082201, Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period2022-08-24024 August 2022 Request for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fifth 10-Year Interval, First Period 2CAN072201, Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods2022-07-20020 July 2022 Response to Request for Additional Information Requests for Relief from American Society of Mechanical Engineers Section XI Volumetric Examination Requirements - Fourth 10-Year Interval, Second and Third Periods 0CAN072201, Registration of Cask Use2022-07-14014 July 2022 Registration of Cask Use 0CAN062202, Registration of Cask Use2022-06-0909 June 2022 Registration of Cask Use 1CAN062201, Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-06-0202 June 2022 Response to the Request for Additional Information Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 1CAN052201, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-0352022-05-31031 May 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Augmented Examination Requirements ANO1-ISI-035 2024-01-17
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23142A2022023-06-29029 June 2023 Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN082201, License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements2022-08-30030 August 2022 License Amendment Request for Approval of Changes to the Emergency Plan Staffing Requirements ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement 1CAN102101, SAR Amendment 30, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report2021-10-0606 October 2021 SAR Amendment 30, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN092101, License Amendment Request Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2021-09-30030 September 2021 License Amendment Request Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations ML21266A1612021-09-23023 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated ML21182A1582021-07-0101 July 2021 Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections 2CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2021-05-26026 May 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 1CAN052102, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2021-05-26026 May 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors 1CAN022102, Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2021-02-22022 February 2021 Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate 0CAN022102, Unit 2; License Amendment Request - One-Time Change to Support Proactive Upgrade of the Emergency - Cooling Pond Supply Piping2021-02-0808 February 2021 Unit 2; License Amendment Request - One-Time Change to Support Proactive Upgrade of the Emergency - Cooling Pond Supply Piping 2CAN112004, License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP)2020-11-17017 November 2020 License Amendment Request - Application to Adopt a Safety Function Determination Program (SFDP) 2CAN092003, License Amendment Request, Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2020-09-24024 September 2020 License Amendment Request, Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions 1CAN072001, Supplemental Information Related to License Amendment Request to Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2020-07-21021 July 2020 Supplemental Information Related to License Amendment Request to Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate 1CAN022001, License Amendment Request: Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2020-02-24024 February 2020 License Amendment Request: Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate 1CAN012002, License Amendment Request: Revise Loss of Voltage Relay Allowable Values2020-01-24024 January 2020 License Amendment Request: Revise Loss of Voltage Relay Allowable Values 2CAN121903, License Amendment Request, Revise Control Element Assembly Drop Time2019-12-18018 December 2019 License Amendment Request, Revise Control Element Assembly Drop Time 2CAN121901, License Amendment Request Technical Specification Deletions, Additions, and Relocations2019-12-16016 December 2019 License Amendment Request Technical Specification Deletions, Additions, and Relocations 1CAN101903, Supplement to License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2019-10-23023 October 2019 Supplement to License Amendment Request: Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO 0CAN091901, Unit 2: License Amendment Request - Change in Implementation Date for Amendments 263 and 3142019-09-0505 September 2019 Unit 2: License Amendment Request - Change in Implementation Date for Amendments 263 and 314 2CAN081903, License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-14322019-08-29029 August 2019 License Amendment Request Technical Specification (TS) Change Related to Revised Fuel Handling Accident Analysis and Adoption of TS Improvements Consistent with NUREG-1432 1CAN051901, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program.2019-05-29029 May 2019 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program. 0CAN041904, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis2019-04-29029 April 2019 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into the Licensing Basis 1CAN031901, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco.2019-03-25025 March 2019 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an Lco. CNRO-2019-00003, Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 42019-01-31031 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529 11 Clarify Use and Application Rules, 11 Revision 4 1CAN121801, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues2018-12-19019 December 2018 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues 2CAN121801, License Amendment Request, Add Actions to Address Inoperability of the Containment Building Sump2018-12-19019 December 2018 License Amendment Request, Add Actions to Address Inoperability of the Containment Building Sump 2CAN051801, License Renewal Pressurizer Surge Line and Safety Injection Nozzle Inspection2018-05-24024 May 2018 License Renewal Pressurizer Surge Line and Safety Injection Nozzle Inspection ML18094A1552018-03-29029 March 2018 Enclosures 2 - 6: Proposed EAL Technical Basis Document, NEI 99-01. Rev. 6., Proposed EAL Matrix Chart/Review Table and Supporting Referenced Document Pages 0CAN031801, Unit 2 - License Amendment Request - Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 62018-03-29029 March 2018 Unit 2 - License Amendment Request - Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 1CAN031801, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2018-03-12012 March 2018 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) 2CAN121702, License Amendment Request Post-Accident Instrumentation Technical Specification Revision2017-12-14014 December 2017 License Amendment Request Post-Accident Instrumentation Technical Specification Revision 2CAN111702, License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits2017-11-20020 November 2017 License Amendment Request - Updating the Reactor Coolant System Pressure-Temperature Limits 1CAN101701, License Amendment Request Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves2017-10-0202 October 2017 License Amendment Request Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves ML17268A2132017-09-21021 September 2017 ISFSI, River Bend Station Unit 1 & ISFSI, Waterford 3 Steam Electric Station & ISFSI, Grand Gulf Nuclear Station & ISFSI, Application for Order Approving Transfers of Licenses and Conforming License Amendments 2CAN081701, Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability.2017-08-14014 August 2017 Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability. 1CAN081701, Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability.2017-08-14014 August 2017 Application to Revise Technical Specifications to Adopt TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability. 2CAN071701, License Amendment Request, Application for Technical Specification Improvement to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-14322017-07-17017 July 2017 License Amendment Request, Application for Technical Specification Improvement to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432 1CAN071701, License Amendment Request, Application for Technical Specification Improvement to Revise Actions for Inoperable Using the Consolidated Line Item Improvement Process2017-07-17017 July 2017 License Amendment Request, Application for Technical Specification Improvement to Revise Actions for Inoperable Using the Consolidated Line Item Improvement Process 1CAN061701, Amendment 27 of the SAR, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report2017-06-0707 June 2017 Amendment 27 of the SAR, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report 1CAN041702, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line.2017-04-24024 April 2017 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line. 2CAN041702, License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection.2017-04-24024 April 2017 License Amendment Request Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. 2CAN101601, License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications2016-10-27027 October 2016 License Amendment Request to Revise the National Fire Protection Association (NFPA) Standard 805 Modifications 1CAN051602, Update to Tables S-1 and S-2 - Adoption of National Fire Protection Association Standard NFPA-8052016-05-19019 May 2016 Update to Tables S-1 and S-2 - Adoption of National Fire Protection Association Standard NFPA-805 2CAN031602, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the Asme..2016-03-25025 March 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing, and to Request an Alternative to the Asme.. 2023-07-27
[Table view] Category:Technical Specifications
MONTHYEARML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML21279A2312021-10-0606 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements Using the Consolidated Line-Item Improvement ML21208A4492021-09-20020 September 2021 Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels ML21088A4332021-04-14014 April 2021 Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition ML21027A4282021-03-23023 March 2021 Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent 1CAN022102, Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate2021-02-22022 February 2021 Supplement Related to License Amendment Request to Replace the Reactor Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent Sodium Tetraborate ML20160A1472020-06-30030 June 2020 Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML20135H1412020-06-30030 June 2020 Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis ML19232A3792019-09-19019 September 2019 Correction to Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force Traveler TSTF-425, Revision 3 ML19175A0422019-09-11011 September 2019 Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules ML17251A2112017-10-10010 October 2017 Issuance of Amendment No. 307 Revision of Steam Generator Technical Specifications to Reflect Adoption of Technical Specifications Task Force Traveler TSTF-510 (CAC MF9654; EPID L-2017-LLA-0222) ML16165A4232017-03-10010 March 2017 Issuance of Amendment No. 257 Adoption of Technical Specifications Task Force Traveler TSTF-545, Revision 3, ML16027A1092016-02-24024 February 2016 Issuance of Amendment Nos. 255 and 303 Cyber Security Plan Implementation Schedule (CAC Nos. MF6258 and MF6259) ML15096A3812015-04-29029 April 2015 Issuance of Amendment No. 302, Revise Technical Specification Surveillance Requirement 4.1.3.1.2 Note to Eliminate Movement of Control Element Assembly 18 for Remainder of Operating Cycle 24 ML15068A3192015-03-31031 March 2015 Issuance of Amendment No. 301, Request to Adopt Technical Specification Task Force (TSTF)-422, Revision 2, Change in Technical Specifications End States (CE NPSD-1186) ML15023A1472015-03-0303 March 2015 Issuance of Amendment No. 253, Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-431, Revision 3, Change in Technical Specifications End States (BAW-2441) ML14356A2272015-02-18018 February 2015 Issuance of Amendment No. 300, Request to Adopt National Fire Protection Association Standard NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants ML15014A0712015-02-0303 February 2015 Issuance of Amendment No. 252, Request to Revise Technical Specification 5.5.16, Reactor Building Leakage Rate Testing Program, to Extend Type a Test Frequency to 15 Years ML14350B2852015-01-22022 January 2015 Issuance of Amendment No. 299, Revise Technical Specification 6.5.16, Containment Leakage Rate Testing Program, for Requirements for Containment Building Emergency Escape Air Lock Doors ML14254A1332014-11-24024 November 2014 Issuance of Amendment No. 250, Adoption of Technical Specifications Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 1CAN111401, Arkansas Nuclear One, Unit 1, License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits2014-11-21021 November 2014 Arkansas Nuclear One, Unit 1, License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits 1CAN111401, License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits2014-11-21021 November 2014 License Amendment Request Update the Reactor Coolant System Pressure and Temperature and the Low Temperature Overpressure Protection System Limits 1CAN101407, Clarifications to Response to Request for Additional Information Associated with Technical Specification Change to Extend the Type a Test Frequency to 15 Years2014-10-28028 October 2014 Clarifications to Response to Request for Additional Information Associated with Technical Specification Change to Extend the Type a Test Frequency to 15 Years 1CAN031401, License Amendment Request - Revised Pages Extend the Type a Test Frequency to 15 Years2014-03-11011 March 2014 License Amendment Request - Revised Pages Extend the Type a Test Frequency to 15 Years 1CAN121302, License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years2013-12-20020 December 2013 License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years 1CAN081302, Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360.2013-08-28028 August 2013 Response to Request for Additional Information, Adoption of Technical Specification Task Force (TSTF)-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360. 2CAN061302, License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-4712013-06-18018 June 2013 License Amendment Request - Supplemental Technical Specification (TS) Change Related to Revised Fuel Assembly Drop Analysis and Adoption of TSTF-51, TSTF-272, TSTF-286, and TSTF-471 1CAN061301, License Amendment Request, Revision to Technical Specification 2.1.1.1 Reactor Core Safety Limits2013-06-11011 June 2013 License Amendment Request, Revision to Technical Specification 2.1.1.1 Reactor Core Safety Limits 1CAN011304, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360.2013-01-28028 January 2013 License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360. 2CAN011301, License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-3602013-01-28028 January 2013 License Amendment Request - Adoption of Technical Specification Task Force (TSTF)-500, Revision 2 DC Electrical Rewrite - Update to TSTF-360 CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications2012-11-20020 November 2012 Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications 1CAN061201, License Amendment Request Technical Specification Change Associated with Main Feedwater Valves2012-06-19019 June 2012 License Amendment Request Technical Specification Change Associated with Main Feedwater Valves 1CAN081001, License Amendment Request, Technical Specification Change Associated with Main Feedwater Isolation Valves2010-08-24024 August 2010 License Amendment Request, Technical Specification Change Associated with Main Feedwater Isolation Valves 2CAN051001, Response to Request for Additional Information Associated with Core Operating Limits Report References2010-05-17017 May 2010 Response to Request for Additional Information Associated with Core Operating Limits Report References 1CAN021004, Response to Request for Additional Information, Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec.2010-02-28028 February 2010 Response to Request for Additional Information, Application for Technical Specification Improvement to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Tech Spec. ML0930601322009-12-23023 December 2009 License Amendment No. 240, Revised Administrative Changes to Technical Specification 5.5.8, Inservice Testing Program, to Adopt TSTF-479-A and TSTF-497-A ML0931305282009-12-23023 December 2009 License Amendment No. 241, Modified Technical Specification 3.4.9, Pressurizer, to Delete Low Pressurizer Level Limit 1CAN080901, Changes to Reflect Revision to 10 CFR 50.55a Technical Change Travelers - TSTF-479-A and TSTF-497-A2009-08-0505 August 2009 Changes to Reflect Revision to 10 CFR 50.55a Technical Change Travelers - TSTF-479-A and TSTF-497-A 2CAN030901, License Amendment Request, Technical Specification Change to Modify the Mode of Applicability for Emergency Feedwater Actuation Signal2009-03-0202 March 2009 License Amendment Request, Technical Specification Change to Modify the Mode of Applicability for Emergency Feedwater Actuation Signal 1CAN020901, License Amendment Request, Technical Specification Change to Adopt Low Pressure Air Lock Seal Test2009-02-16016 February 2009 License Amendment Request, Technical Specification Change to Adopt Low Pressure Air Lock Seal Test ML0814000372008-09-0808 September 2008 Technical Specifications for Amendment No. 282 Technical Specification Task Force TSTF-490, Rev 0, Deletion of E Bar Definition and Revision to RCS Specific Activity. ML0812203132008-08-28028 August 2008 Tech Spec Pages for Amendment No. 281 Technical Specification Task Force Change TSTF-359, Increased Flexibility in Mode Restraints. ML0823801472008-08-21021 August 2008 License Amendment Request, Technical Specification Change to Extend Integrated Leak Rate Test Interval One-Time ML0814004492008-07-23023 July 2008 Tech Spec Pages for Amendment No. 280 Reactor Coolant System Relocation to TRM (Tac MD8313) 2CAN070805, License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers and Relocate TS 3.7.8 to the TRM2008-07-21021 July 2008 License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers and Relocate TS 3.7.8 to the TRM 1CAN070804, License Amendment Request Regarding Technical Specification Changes Associated with Adoption of TSTF-3592008-07-21021 July 2008 License Amendment Request Regarding Technical Specification Changes Associated with Adoption of TSTF-359 1CAN070803, License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers2008-07-21021 July 2008 License Amendment Request Regarding Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers ML0815402462008-07-0909 July 2008 License Page 3 & Technical Specifications for Issuance of Amendment No. 233 Containment Spray Nozzle Technical Specification Test Requirements 2023-04-14
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Text
Entergy Operations, Inc.
1448 SR, 333 Russellville. AR 72802 Tel 479-858-3110 Timothy G. Mitchell Vice President, Operalions Arkansas Nuclear One 2CAN030802 March 13, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
License Amendment Request Technical Specification Changes To Relocate RCS Chemistry Requirements to TRM Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
Pursuant to 10 CFR 50.90, Entergy Operations, Inc. (Entergy) hereby requests the following amendment for Arkansas Nuclear One, Unit 2 (ANO-2). The proposed change will relocate the Technical Specification (TS) 3.4.7, Reactor Coolant System Chemistry, to the Technical Requirements Manual (TRM). This change is consistent with the Improved Standard Technical Specifications for Combustion Engineering Plants of NUREG 1432.
The requirements for monitoring and maintaining Reactor Coolant System (RCS) chemistry limits do not meet the criteria of 10 CFR 50.36 and, therefore, are proposed for relocation to the station TRM. Changes to the TRM are controlled in accordance with the requirements of 10 CFR 50.59. The associated TS Bases, controlled in accordance with the TS Bases Control Program of TS 6.5.14, will also be relocated to the TRM. The relocation of the TS Bases is part of the ANO TS change implementation process; therefore, a markup of the TS Bases is not provided in this submittal.
The proposed change has been evaluated in accordance with 10 CFR 50.91 (a)(1) using criteria in 10 CFR 50.92(c) and it has been determined that the changes involve no significant hazards consideration. The bases for these determinations are included in the attached submittal.
The proposed change does not include any new commitments.
Entergy requests approval of the proposed amendment by April 1, 2009. Once approved, the amendment shall be implemented within 90 days.
A oo/
2CAN030802 Page 2 of 2 If you have any questions or require additional information, please contact David Bice at 479-858-5338.
I declare under penalty of perjury that the foregoing is true and correct. Executed on March 13, 2008.
Sincerely~,Q Attachments:
- 1. Analysis of Proposed Technical Specification Change
- 2. Proposed Technical Specification Changes (mark-up) cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P. 0. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS 0-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437
Attachment 1 2CAN030802 Analysis of Proposed Technical Specification Change
Attachment to 2CAN030802 Page 1 of 4
1.0 DESCRIPTION
This letter is a request to amend Operating License NPF-6 for Arkansas Nuclear One, Unit 2 (ANO-2).
The proposed change will relocate Technical Specification (TS) 3.4.7, Reactor Coolant System Chemistry, to the ANO-2 Technical Requirements Manual (TRM). Changes to the TRM are controlled in accordance with 10 CFR 50.59. The change is consistent with NUREG 1430, Improved Standard Technical Specifications for Combustion Engineering Plants, heretofore referred to as ITS.
Note that plant-specific TSs relating to Reactor Coolant System (RCS) chemistry were not included in the original version of NUREG 1432 because this TS did not meet the TS inclusion requirements of 10 CFR 50.36.
2.0 PROPOSED CHANGE
ANO-2 TS 3.4.7, Reactor Coolant System Chemistry, is proposed for relocation to the ANO-2 TRM. During relocation, the current TS Actions may be modified. Such modification, if performed, will be in accordance with the requirements of 10 CFR 50.59.
Note that the proposed location results in several TS pages being deleted. Therefore, a change to TS page 3/4 4-14 is included in the attached markups to state that the "next page is..." This supporting change is administrative in nature and is not discussed further in this submittal.
3.0 BACKGROUND
TS 3.4.7 provides limits on the oxygen, chloride, and fluoride content in the RCS to minimize corrosion. Per the TS Bases, RCS chemistry parameters ensure that corrosion of RCS components is minimized, thus reducing the potential for RCS leakage or failure due to corrosion-based mechanisms. Maintaining' the chemistry within limits provides adequate corrosion protection to ensure the structural integrity of the RCS over the life of the plant.
4.0 TECHNICAL ANALYSIS
RCS corrosion is a slow process which can be detected by in-service inspections or other means before significant degradation occurs. RCS chemistry is controlled to minimize corrosion over the long term. Although it is important to monitor and control RCS chemistry, limits and surveillance requirements do not meet the criteria of 10 CFR 50.36 for inclusion in the TSs. An assessment of the current RCS chemistry TS requirements against the 10 CFR 50.36 criteria is provided below.
Attachment to 2CAN030802 Page 2 of 4
- 1. The RCS chemistry limits are not installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary. The RCS chemistry limits do not satisfy Criterion 1.
- 2. The RCS chemistry limits are not a process variable, design feature, or operating restriction that is an initial condition of a DBA or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The RCS chemistry limits do not satisfy Criterion 2.
- 3. The RCS chemistry limits are not a structure, system or component that is part of the primary success path and which functions or actuates to mitigate a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. The RCS chemistry limits do not satisfy Criterion 3.
- 4. The RCS chemistry limits are not a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety. As discussed in Section 4.0, (Appendix A, page A-40) of topical report WCAP- 11618 (Reference 1), the RCS chemistry limits were found to be a non-significant risk contributor to core damage frequency and offsite releases (WCAP-1 1618, "Criteria Application," evaluated Limiting Conditions for Operation (LCOs) contained in TSs for Westinghouse pressurized water reactors with respect to the criteria of 10 CFR 50.36 to determine which LCOs satisfied any of the criteria).
In addition to the above, the RCS chemistry limits are not importantfor any scenarios modeled in the ANO-2 safety analyses. Therefore, the RCS chemistry limits do not meet Criterion 4.
Since the 10 CFR 50.36 criteria have not been met, the RCS chemistry limits LCO and associated Applicability, Actions, and Surveillances may be relocated out of the TSs. The RCS chemistry specification will be relocated to the TRM. Changes to the TRM will be controlled under the provisions of 10 CFR 50.59.
5.0 REGULATORY ANALYSIS
5.3 Applicable Regulatory Requirements/Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met.
There are no specific General Design Criteria (GDC) associated with RCS chemistry. RCS sampling and chemistry limits are discussed in various documents, such as NUREG 0737 and Regulatory Guide 1.97. However, the proposed change does not eliminate monitoring and maintaining RCS chemistry, but only acts to relocate the requirements from the TSs to the TRM. Based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will continue to be conducted in accordance with the site licensing basis, and (3) the approval of the proposed change will not be inimical to the common defense and security or to the health and safety of the public.
-I
Attachment to 2CAN030802 Page 3 of 4 In conclusion, Entergy has determined that the proposed change does not require any exemptions or relief from regulatory requirements, other than the TS, and does not affect conformance with any GDC differently than described in the Safety Analysis Report (SAR).
5.2 No Significant Hazards Consideration A change is proposed to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TSs) to relocate TS 3.4.7, Reactor Coolant System Chemistry, to the Technical Requirements Manual (TRM). The change is consistent with the improved standard TSs (ITS) of NUREG 1432.
Entergy Operations, Inc. has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed change acts to relocate current Reactor Coolant System (RCS) chemistry limits and monitoring requirements from the TSs to the TRM. Monitoring and maintaining RCS chemistry minimizes the potential for corrosion of RCS piping and components. Corrosion effects are considered a long-term impact on RCS structural integrity. Because RCS chemistry will continue to be monitored and controlled, relocating the current TS requirements to the TRM will not present an adverse impact to the RCS and, subsequently, will not impact the probability or consequences of an accident previously evaluated. Furthermore, once relocated to the TRM, changes to RCS chemistry limits or monitoring requirements will be controlled in accordance with 10 CFR 50.59.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change does not result in any plant modifications or changes in the way the plant is operated. The proposed change only acts to relocate current RCS chemistry limits and monitoring requirements from the TSs to the TRM.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
Attachment to 2CAN030802 Page 4 of 4
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The proposed change will maintain limits on RCS chemistry parameters and will continue to provide associated monitoring requirements. Once relocated to the TRM, changes to RCS chemistry limits or monitoring requirements will be controlled in accordance with 10 CFR 50.59. In addition, the RCS chemistry limits are not a structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, Entergy concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.3 Environmental Considerations The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 PRECEDENCE Many plants have previously relocated their respective RCS chemistry TSs to the TRM. Most occurred during conversion of the plant specific TSs to the respective ITS NUREG. This amendment was largely based on discussions noted in previous ANO-1 and North Anna conversions to ITS. Because these were major conversions and involved multiple correspondence opportunities, no specific letter number or date is referenced here.
7.0 REFERENCES
- 1. WCAP-11618, "Criteria Application," with Addendum, November 21, 1989.
Attachment 2 2CAN030802 Proposed Technical Specification Changes (mark-up)
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System operational leakage shall be limited to:
- a. No PRESSURE BOUNDARY LEAKAGE,
- b. 1 GPM UNIDENTIFIED LEAKAGE,
- c. 150 gallons per day primary to secondary leakage through any one steam generator (SG),
- d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and
- e. Leakage as specified in Table 3.4.6-1 for those Reactor Coolant System Pressure Isolation Valves identified in Table 3.4.6.1.
APPLICABILITY: MODES 1,2, 3and 4.
ACTION:
- a. With any PRESSURE BOUNDARY LEAKAGE or any primary to secondary leakage not within limit, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With any Reactor Coolant System operational leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and primary to secondary leakage, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two valves* in each high pressure line having a non-functional valve and be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- These valve's may include check valves for which the leakage rate has been verified, manual valves or automatic valves. Manual and automatic valves shall be tagged as closed to preclude inadvertent valve opening.
ARKANSAS - UNIT 2 3/4 4-14 Amendment No. 4-84,266, Next Page is 3/4 4-18 Order datod 4120/81
DMA('TC'nD f'fV't ANITr CVTCZF,:A LIMITING CONDITION FOR OPERATION 3.4.7 The Rat-r Coolan*t SyAtem -hmist; sha-ll be maintainaHed WithiR tho IlimRt Specifi8d RnTable3.4 1.
APPLICABILITY. At all fimos.
ACT-!ON: ..
MODES 1, 2, 3 3fld 4
- a. With any one Or more chemistry paramotor i exceGs Of itSsStepdy State Limit but within its Transient Limnit, restor the parametefr to Within its Stead" State Limif vvihmn 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the neXt 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COL'D SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With any one or mere chemisrfy paramReteFr in excess of it; TFRnsient Limit, be in at least HOT STANIDBY wvithin 6- hou-rs and in COLD SHUTDOWN within the foEllo'wing 30 ho'-s.
MODES 5 and 6 With the oRnGentr;ation of either chloride or fluoride in the RactOr * *lant Systor in eXcess Of its Stead" State Limnit for mere than 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> or in excess of its T-Fansient Lim~it, reduce the pressurizer pres to 500 psia, if applicable, and perform an enginreeing ealuatiýon todetermine the efects Of the out of limit condfit*on oRn the strGtr*all inrtegrfity f the Reactor Colant System; determine that the Reatofr Coolant System re*mrai-n acceptable fo)r continued operatiRon prio r ;tRoiceasing the pressui pressure above 500 psia or prior to proceeding to MODE 4.
SURVEILL*NCE REQUIREMENTS 4.4.7 The Reactor Coolant System; chemistry shall be determined to be within the lim~itG by analysis of thoa tes at the frequ6enc-eS specified in Table 4.4 3.
ARKANSAS UNIT 2 3/14 415
TABLE 3.4 1 REACTODR COOLANT SYSTEM CHrMISTRY LIMITS
- imorit not applicablo with 425F, A QtIA A*IK I*CA 0Kir1 OlA ,4 4*
ADVAMOA~ IkilT') ~IA A 4~
TABLE 4-4A REACTOR COOLRNTESYSTEEM CHEMISTRY LIMITS SU11RVEILLANCE RE=QUIREMNT A IICA KI/ " I Illr 031A A 4"7 ArjIANI~Acy- I IKIIr '~ 'I