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| | number = ML070090485 | | | number = ML070090485 |
| | issue date = 12/29/2006 | | | issue date = 12/29/2006 |
| | title = Perry Nuclear Plant Application for a Technical Specification Improvement to Revise Technical Specification 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process | | | title = Application for a Technical Specification Improvement to Revise Technical Specification 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process |
| | author name = Pearce L W | | | author name = Pearce L |
| | author affiliation = FirstEnergy Nuclear Operating Co | | | author affiliation = FirstEnergy Nuclear Operating Co |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:FENOC Perry Nuclear Power Station 10CetrRa FirstEnergy Nuclear Operating Company Perry, Ohio 44081 L. William Pearce 440-280-5382 Vice President Fax: 440-280-8029 December 29, 2006 Docket Number 50-440 License Number NPF-58 PY-CE I/N RR-2995L 10 CFR 50.90 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 | | {{#Wiki_filter:FENOC Perry Nuclear Power Station 10CetrRa FirstEnergy Nuclear Operating Company Perry, Ohio 44081 L. William Pearce 440-280-5382 Vice President Fax: 440-280-8029 December 29, 2006 Docket Number 50-440 License Number NPF-58 PY-CE I/N RR-2995L 10 CFR 50.90 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 |
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| ==Subject:== | | ==Subject:== |
| Perry Nuclear Power Plant Application for a Technical Specification Improvement to Revise Technical Specification 3.1.8, 'Scram Discharge Volume (SDV) Vent and Drain Valves," Using the Consolidated Line Item Improvement Process In accordance with the provisions of 10 CFR 50.90, the FirstEnergy Nuclear Operating Company (FENOC) is submitting a request for an amendment to the Technical Specifications (TSs) for the Perry Nuclear Power Plant.The proposed changes would revise the Required Action in TS 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable. | | Perry Nuclear Power Plant Application for a Technical Specification Improvement to Revise Technical Specification 3.1.8, 'Scram Discharge Volume (SDV) Vent and Drain Valves," |
| These changes are based on Technical Specification Task Force (TSTF) change traveler TSTF-404 (Revision 0), which has been approved generically for the Boiling Water Reactor (BWR) BWR6 Standard Technical Specification NUREG-1434. | | Using the Consolidated Line Item Improvement Process In accordance with the provisions of 10 CFR 50.90, the FirstEnergy Nuclear Operating Company (FENOC) is submitting a request for an amendment to the Technical Specifications (TSs) for the Perry Nuclear Power Plant. |
| The availability of this TS improvement was announced in the Federal Register on April 15, 2003, as part of the Consolidated Line Item Improvement Process (CLIIP).Enclosure 1 provides a description of the proposed change and confirmation of applicability, the existing TS pages marked-up to show the proposed change, and the existing TS Bases pages marked-up to reflect the proposed change (for information only). There are no new regulatory commitments associated with this proposed change.Approval of the license amendment is requested prior to December 30, 2007, with the amendment to be implemented within 90 days following its effective date.In accordance with 10 CFR 50.91, a copy of.this application, with enclosure, is being provided to the designated State of Ohio Official. | | The proposed changes would revise the Required Action in TS 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable. These changes are based on Technical Specification Task Force (TSTF) change traveler TSTF-404 (Revision 0), which has been approved generically for the Boiling Water Reactor (BWR) BWR6 Standard Technical Specification NUREG-1434. The availability of this TS improvement was announced in the Federal Register on April 15, 2003, as part of the Consolidated Line Item Improvement Process (CLIIP). |
| December 29, 2006 Docket Number 50-440 License Number NPF-58 PY-CEI/N RR-2995L Page 2 of 2 If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager -FENOC Fleet Licensing, at 330-315-7243.
| | Enclosure 1 provides a description of the proposed change and confirmation of applicability, the existing TS pages marked-up to show the proposed change, and the existing TS Bases pages marked-up to reflect the proposed change (for information only). There are no new regulatory commitments associated with this proposed change. |
| I declare under penalty of perjury that the foregoing is true and correct. Executed on December 29, 2006.Enclosure.
| | Approval of the license amendment is requested prior to December 30, 2007, with the amendment to be implemented within 90 days following its effective date. |
| : 1. Perry Nuclear Power Plant Evaluation for a Proposed License Amendment to Revise Technical Specification 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves" cc: NRC Project Manager NRC Resident Inspector NRC Region Ill N. Dragani, Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
| | In accordance with 10 CFR 50.91, a copy of.this application, with enclosure, is being provided to the designated State of Ohio Official. |
| Enclosure 1 PY-CEI/N RR-2995L Page 1 of 3 PERRY NUCLEAR POQWER PLANT EVALUATION FOR A PROPOSED LICENSE AMENDMENT TO REVISE TECHNICAL SPECIFICATION 3.1.8, "SCRAM DISCHARGE VOLUME (S DV) VENT AND DRAIN VALVES"
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| ==1.0 DESCRIPTION==
| | December 29, 2006 Docket Number 50-440 License Number NPF-58 PY-CEI/N RR-2995L Page 2 of 2 If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager - FENOC Fleet Licensing, at 330-315-7243. |
| | I declare under penalty of perjury that the foregoing is true and correct. Executed on December 29, 2006. |
| | Enclosure. |
| | : 1. Perry Nuclear Power Plant Evaluation for a Proposed License Amendment to Revise Technical Specification 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves" cc: NRC Project Manager NRC Resident Inspector NRC Region Ill N. Dragani, Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison) |
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| OF PROPOSED AMENDMENT 2.0 ASSESSMENT
| | Enclosure 1 PY-CEI/N RR-2995L Page 1 of 3 PERRY NUCLEAR POQWER PLANT EVALUATION FOR A PROPOSED LICENSE AMENDMENT TO REVISE TECHNICAL SPECIFICATION 3.1.8, "SCRAM DISCHARGE VOLUME (S DV) VENT AND DRAIN VALVES" |
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| ===2.1 APPLICABILITY=== | | ==1.0 DESCRIPTION== |
| | OF PROPOSED AMENDMENT 2.0 ASSESSMENT 2.1 APPLICABILITY OF PUBLISHED SAFETY EVALUATION 2.2 OPTIONAL CHANGES AND VARIATIONS |
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| OF PUBLISHED SAFETY EVALUATION
| | ==3.0 REGULATORY ANALYSIS== |
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| ===2.2 OPTIONAL===
| | 3.1 NO SIGNIFICANT HAZARDS CONSIDERATION 3.2 VERIFICATION AND COMMITMENTS 4.0 ENVIRONMENTAL EVALUATION 5.0 PRECEDENT |
| CHANGES AND VARIATIONS
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| ===3.0 REGULATORY=== | | ==6.0 REFERENCES== |
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| ANALYSIS 3.1 NO SIGNIFICANT HAZARDS CONSIDERATION
| | 7.0 ATTACHMENTS |
| | : 1. Proposed Operating License Change (Hand Mark-up) |
| | : 2. Proposed Technical Specification Bases Changes (For Information Only) |
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| ===3.2 VERIFICATION===
| | Enclosure 1 PY-CEI/NRR-2995L Page 2 of 3 |
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| AND COMMITMENTS
| | ==1.0 DESCRIPTION== |
| | OF PROPOSED AMENDMENT The proposed license amendment would revise Required Action in Technical Specification 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable. These changes are based on Technical Specification Task Force (TSTF) change traveler TSTF-404 (Revision 0), which has been approved generically for the Boiling Water Reactor 6 Standard Technical Specifications, NUREG-1434. The availability of this Technical Specification improvement was announced in the Federal Register on April 15, 2003 (68 FR 18294) as part of the Consolidated Line Item Improvement Process (OLIIP). Refer to Attachment 1 for a mark-up of the existing TS reflecting the proposed changes. |
| | 2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation FirstEnergy Nuclear Operating Company (FENOC) has reviewed the NRC safety evaluation published on April 15, 2003 (68 FR 18294) as part of the CLIIP. This verification included a review of the NRC staff's evaluation as well as the information provided to support TSTF-404. |
| | FENOC has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to the Perry Nuclear Power Plant (PNPP) and justify this amendment for the incorporation of the changes into the PNPP Technical Specifications. |
| | 2.2 Optional Changes and Variations FENOC is not proposing any variations or deviations from the Technical Specification changes described in TSTF-404 or the NRC staff's model safety evaluation published on April 15, 2003 (68 FR 18294). |
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| ===4.0 ENVIRONMENTAL=== | | ==3.0 REGULATORY ANALYSIS== |
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| EVALUATION | | 3.1 No Significant Hazards Consideration FENOC has reviewed the proposed no significant hazards consideration determination published on April 15, 2003 as part of the CLIIP. FENOC has concluded that the proposed determination presented in the notice is applicable to PNPP and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a). |
| | 3.2 Verification and Commitments There are no new regulatory commitments associated with this proposed change. |
| | 4.0 ENVIRONMENTAL EVALUATION FENOC has reviewed the environmental evaluation included in the model safety evaluation published on April 15, 2003, as part of the CLIIP. FENOC has concluded that the NRC staff's |
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| ===5.0 PRECEDENT===
| | Enclosure 1 PY-CEI/NRR-2995L Page 3 of 3 findings presented in that evaluation are applicable to PNPP and the evaluation is hereby incorporated by reference for this application. |
| | 5.0 PRECEDENT This application is being made in accordance with the OLIIP. FENOC is not proposing variations or deviations from the Technical Specification changes described in the NRC staff's model safety evaluation published on April 15, 2003 (68 FR 18294). |
| | Similar changes to Technical Specification SDV ACTIONS were approved by the NRC for the Pilgrim Nuclear Power Station (TAC NO. MC5422 - ADAMS Accession Number ML051870257) dated July 29, 2005; and for the Hope Creek Generating Station (TAC NO. MC6697 - ADAMS Accession Number ML060050304) dated January 13, 2006. |
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| ==6.0 REFERENCES== | | ==6.0 REFERENCES== |
| | : 1. Federal Register, "Notice of Availability of Model Application Concerning Technical Specifications Improvement Regarding Scram Discharge Volume Vent and Drain Valves Actions for Boiling Water Reactors Using the Consolidated Line Item Improvement Process," April 15, 2003 (68 FR 18294) |
| | : 2. Technical Specifications Task Force (TSTF) Change Traveler 404, Revision 0 7.0 ATTACHMENTS |
| | : 1. Proposed Operating License Change (Hand Mark-up) |
| | : 2. Proposed Technical Specification Bases Changes (For Information Only) |
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| |
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| ==7.0 ATTACHMENTS==
| | Attachment 1 PY-CE I/N RR-2995L Page 1 of 2 PROPOSED OPERATING LICENSE CHANGE (HAND MARK-UP) |
| : 1. Proposed Operating License Change (Hand Mark-up)2. Proposed Technical Specification Bases Changes (For Information Only)
| |
| Enclosure 1 PY-CEI/NRR-2995L Page 2 of 3
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| ==1.0 DESCRIPTION==
| | Attachment 1 PY-C EI/N RR-2995L Page 2 of 2 SDV Vent and Drain Valves 3.1 RECIIYCONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent ah'd Drain Valves LCO 3.1.8 Each SDV vent and drain valve shall be OPERABLE. |
| | APPLICABILITY: MODES I and 2. |
| | ACTIONS |
| | -------------------------- - -NOTE--/ý------------------------------- |
| | t~Se arate Condition entry is allowe SDV vent and drain line. |
| | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent A.1 Rftzt-oe mlV~ |
| | " ti 7 days or drain lines with OPERADLE status. |
| | one valve inoperable. :1oUr T)-h* /45c; B. One or more SDV vent B.1 -- |
| | or drain lines with -Aýn isolated line may both valves be unisolated under inoperable, administrative control to allow draining and venting Isolate the 8 hours associated line. |
| | C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion |
| | .Time not met. |
| | PERRY - UNIT*1 3.1-24 PERR No. 69 |
| | - NIT 3.-24Amendment |
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| OF PROPOSED AMENDMENT The proposed license amendment would revise Required Action in Technical Specification 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable.
| | Attachment 2 PY-CEI/NRR-2995L Page 1 of 3 PROPOSED TECHNICAL SPECIFICATION BASES CHANGES |
| These changes are based on Technical Specification Task Force (TSTF) change traveler TSTF-404 (Revision 0), which has been approved generically for the Boiling Water Reactor 6 Standard Technical Specifications, NUREG-1434.
| | .(FOR INFORMATION ONLY) |
| The availability of this Technical Specification improvement was announced in the Federal Register on April 15, 2003 (68 FR 18294) as part of the Consolidated Line Item Improvement Process (OLIIP). Refer to Attachment 1 for a mark-up of the existing TS reflecting the proposed changes.2.0 ASSESSMENT
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| ===2.1 Applicability===
| | Attachment 2 PY-CEIINRR-2995L Page 2 of 3 INFOR" AT10DOJliLL SDV Vent and Drain Valves B 3.1.8 BAS ES APPLICABLE allow continuous drainage of the SDV during normal plant SAFETY ANALYSES operation to ensure the SDV has sufficient capacity to (continued) contain the reactor coolant discharge during a full core scram. To automatically ensure this capacity, a reactor scram (LCO 3.3.1.1, "Reactor Protection System (RPS) |
| | Instrumentation") is initiated ifthe SDV water level exceeds a specified setpoint. The setpoint is chosen such that all control rods are inserted before the SDV has insufficient volume to accept a full scram. |
| | SDV vent and drain valves satisfy Criterion 3 of the NRC Policy Statement. |
| | LCO The OPERABILITY of all SDV vent and drain valves ensures that, during a scram, the SDV vent and 'drain valves will close to contain reactor water discharged to the SDV piping. |
| | Since the vent and drain lines are provided with two valves in series, the single failure of one valve inthe open position will not impair the isolation function of the system. Additionally, the valves are required to be open to ensure that a path is available for the SDV piping to drain freely at other times. |
| | APPLICABILITY InMODES 1 and 2. scram may be required, and therefore, the SDV vent and drain valves must be OPERABLE. InMODES 3 and 4. control rods are not able to be withdrawn since the reactor mode switch is inthe shutdown position and a control rod block isapplied. Also, during MODE 5, only a single control rod can be withdrawn from a core cell containing fuel assemblies. Therefore, the SDV vent and drain valves are not required to be OPERABLE inthese MODES since the reactor is subcritical and only one rod may be withdrawn and subject to scram. |
| | ACTIONS The ACTIONS table ismodified by/ANoteyindicating that a separate Condition entry is allowed for each SDV vent and drain line. This isacceptable, since the Required Actions |
| | *for each Condition provide appropriate compensatory actions xk"s-P' U URDV for each inoperable SDV line. Complying with .the Required Fam IN ORIA INActions may allow for continued operation, and subsequent Po E3J'I-47 inoperable SDV lines are governed by subsequent Condition entry and application of associated Required Actions.p. |
| | y ~(conti nued) |
| | PFRRY - UNIT 1B31-6Rvso B 3.1-46 No I Revision No. 1 |
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| of Published Safety Evaluation FirstEnergy Nuclear Operating Company (FENOC) has reviewed the NRC safety evaluation published on April 15, 2003 (68 FR 18294) as part of the CLIIP. This verification included a review of the NRC staff's evaluation as well as the information provided to support TSTF-404.FENOC has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to the Perry Nuclear Power Plant (PNPP)and justify this amendment for the incorporation of the changes into the PNPP Technical Specifications.
| | Attachment 2 PY-CEI/NRR-2995L Page 3 of 3 IN ,0Ihim0 0N I. YSDV ATI Vent and Drain Valves B 3.1.8 BASES ACTIONS A.1 the reacfcp cccJ4?i,0 cir ~CiV.":; r" |
| | | ,(cotined) When one SDV vent or drain valve is inoperable inone o more lines, the ,avzmtbortrdtoOEABE ttu |
| ===2.2 Optional===
| | -w-i 4---ds The-pCompletion Time isreasonable, given the |
| Changes and Variations FENOC is not proposing any variations or deviations from the Technical Specification changes described in TSTF-404 or the NRC staff's model safety evaluation published on April 15, 2003 (68 FR 18294).3.0 REGULATORY ANALYSIS 3.1 No Significant Hazards Consideration FENOC has reviewed the proposed no significant hazards consideration determination published on April 15, 2003 as part of the CLIIP. FENOC has concluded that the proposed determination presented in the notice is applicable to PNPP and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).3.2 Verification and Commitments There are no new regulatory commitments associated with this proposed change.4.0 ENVIRONMENTAL EVALUATION FENOC has reviewed the environmental evaluation included in the model safety evaluation published on April 15, 2003, as part of the CLIIP. FENOC has concluded that the NRC staff's Enclosure 1 PY-CEI/NRR-2995L Page 3 of 3 findings presented in that evaluation are applicable to PNPP and the evaluation is hereby incorporated by reference for this application.
| | ,--7ev-e-Fof--re-du-ndancy inthe lines and the ]ow~probability of a scram occurring during the time the valve(s) are inooerabL1e The SDV isstill isolable since the redundant valve inthe affected line isOPERABLE. Since the SDV is anct &he- h4i still isolable, the affected SDV line may be opened. This no,+~ isclcte~d- allows any accumulated water inthe line to be drained, to preclude a reactor scram on SDV high level. During these periods, the single failure criterion may not be preserved, and a higher risk exists to allow reactor water out of the primary system during a scram. |
| | | B.1 Ifboth valves ina line are inoperable, the line must be isolated to contain the reactor coolant durnn control Thinei ,salowsanyccuulaed atr ian therSVtobe dr~ained to preclud a reactoisicreamnsedV. ihlvl Thea8dhurCmlto hgSD to Tie ee isolcrated thriei aed, o thelowproabiityof scam ccurin whleDheringteise nerots telnmabeuisolatedad unliklioo ofsgiiadmntsCratisea leakage Ifonyrl Reqire actions and associlated Competion time isD notb mriet, theplantlustde broughttor scamMoDin which thevelCD does not accppaly. Toiachee the disistratusvte plantrmust bensr if~ |
| ===5.0 PRECEDENT===
| | ~ wt |
| This application is being made in accordance with the OLIIP. FENOC is not proposing variations or deviations from the Technical Specification changes described in the NRC staff's model safety evaluation published on April 15, 2003 (68 FR 18294).Similar changes to Technical Specification SDV ACTIONS were approved by the NRC for the Pilgrim Nuclear Power Station (TAC NO. MC5422 -ADAMS Accession Number ML051870257) dated July 29, 2005; and for the Hope Creek Generating Station (TAC NO. MC6697 -ADAMS Accession Number ML060050304) dated January 13, 2006.
| | ~ ~heln~ ntioltd |
| | | ~ anued)cr |
| ==6.0 REFERENCES==
| | ~ ~ (ot IN OR AT O 0 LYrCmlto iet soaeteln sbsdo PERRY - UNIT 1B31-7RvsoN.1 B 3.1-47 Revision No. I}} |
| : 1. Federal Register, "Notice of Availability of Model Application Concerning Technical Specifications Improvement Regarding Scram Discharge Volume Vent and Drain Valves Actions for Boiling Water Reactors Using the Consolidated Line Item Improvement Process," April 15, 2003 (68 FR 18294)2. Technical Specifications Task Force (TSTF) Change Traveler 404, Revision 0 7.0 ATTACHMENTS
| |
| : 1. Proposed Operating License Change (Hand Mark-up)2. Proposed Technical Specification Bases Changes (For Information Only)
| |
| Attachment 1 PY-CE I/N RR-2995L Page 1 of 2 PROPOSED OPERATING LICENSE CHANGE (HAND MARK-UP)
| |
| Attachment 1 PY-C EI/N RR-2995L Page 2 of 2 SDV Vent and Drain Valves 3.1 RECIIYCONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent ah'd Drain Valves LCO 3.1.8 Each SDV vent and drain valve shall be OPERABLE.APPLICABILITY:
| |
| MODES I and 2.ACTIONS--------------------------
| |
| --NOTE--/ý-------------------------------
| |
| t~Se arate Condition entry is allowe S DV vent and drain line.-- ------------------------
| |
| -------------------------------
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent A.1 Rftzt-oe mlV~ " ti 7 days or drain lines with OPERADLE status.one valve inoperable.
| |
| :1oUr T)-h /45c;B. One or more SDV vent B.1 --or drain lines with -Aýn isolated line may both valves be unisolated under inoperable, administrative control to allow draining and venting Isolate the 8 hours associated line.C. Required Action and C.1 Be in MODE 3. 12 hours associated Completion.Time not met.PERRY -UNIT*1 3.1-24 PERR -NIT 3.-24Amendment No. 69 Attachment 2 PY-CEI/NRR-2995L Page 1 of 3 PROPOSED TECHNICAL SPECIFICATION BASES CHANGES.(FOR IN FORMATION ONLY)
| |
| Attachment 2 PY-CEIINRR-2995L Page 2 of 3 SDV Vent and Drain Valves B 3.1.8 INFOR" AT10DOJ liLL BAS ES APPLICABLE SAFETY ANALYSES (continued) allow continuous drainage of the SDV during normal plant operation to ensure the SDV has sufficient capacity to contain the reactor coolant discharge during a full core scram. To automatically ensure this capacity, a reactor scram (LCO 3.3.1.1, "Reactor Protection System (RPS)Instrumentation")
| |
| is initiated if the SDV water level exceeds a specified setpoint.
| |
| The setpoint is chosen such that all control rods are inserted before the SDV has insufficient volume to accept a full scram.SDV vent and drain valves satisfy Criterion 3 of the NRC Policy Statement.
| |
| LCO The OPERABILITY of all SDV vent and drain valves ensures that, during a scram, the SDV vent and 'drain valves will close to contain reactor water discharged to the SDV piping.Since the vent and drain lines are provided with two valves in series, the single failure of one valve in the open position will not impair the isolation function of the system. Additionally, the valves are required to be open to ensure that a path is available for the SDV piping to drain freely at other times.APPLICABILITY In MODES 1 and 2. scram may be required, and therefore, the SDV vent and drain valves must be OPERABLE.
| |
| In MODES 3 and 4. control rods are not able to be withdrawn since the reactor mode switch is in the shutdown position and a control rod block is applied. Also, during MODE 5, only a single control rod can be withdrawn from a core cell containing fuel assemblies.
| |
| Therefore, the SDV vent and drain valves are not required to be OPERABLE in these MODES since the reactor is subcritical and only one rod may be withdrawn and subject to scram.ACTIONS The ACTIONS table is modified by/ANoteyindicating that a separate Condition entry is allowed for each SDV vent and drain line. This is acceptable, since the Required Actions*for each Condition provide appropriate compensatory actions xk"s-P'U URDV for each inoperable SDV line. Complying with .the Required Fam IN OR IA INActions may allow for continued operation, and subsequent Po E3J'I-47 inoperable SDV lines are governed by subsequent Condition entry and application of associated Required Actions.p.
| |
| y ~(conti nued)PFRRY -UNIT 1B31-6Rvso No 1 B 3.1-46 Revision No. I Attachment 2 PY-CEI/NRR-2995L Page 3 of 3 IN I 0 ATI ,0 him 0N I. YSDV Vent and Drain Valves B 3.1.8 BASES ACTIONS A.1 the reacfcp cccJ4?i,0 cir ~CiV.":; r" ,(cotined)
| |
| When one SDV vent or drain valve is inoperable in one o more lines, the ,avzmtbortrdtoOEABE ttu-w-i 4---ds The-pCompletion Time is reasonable, given the ,--7ev-e-Fof--re-du-ndancy in the lines and the ]ow~probability of a scram occurring during the time the valve(s) are inooerabL1e The SDV is still isolable since the redundant valve in the affected line is OPERABLE. | |
| Since the SDV is anct &he- h4i still isolable, the affected SDV line may be opened. This no,+~ isclcte~d-allows any accumulated water in the line to be drained, to preclude a reactor scram on SDV high level. During these periods, the single failure criterion may not be preserved, and a higher risk exists to allow reactor water out of the primary system during a scram.B.1 If both valves in a line are inoperable, the line must be isolated to contain the reactor coolant durnn control Thinei ,salowsany ccuulaed atr ian therSVtobe dr~ained to preclud a reacto isicreamnsedV. | |
| ihlvl Thea 8dhurCmlto Tie to hgSD ee isolcrated thriei aed, o thelowproabiityof scam ccurin whleDheringteise nerots telnmabeuisolatedad unliklioo ofsgiiadmntsCratisea leakage Ifonyrl Reqire actions and associlated Competion time isD notb mriet, the plantlustde broughttor scam MoDin which thevelCD does not accppaly. | |
| Toiachee the disistratusvte plantrmust bensr if ~ ~ ~ ~ ~ ~ ~ ~ (ot anued)cr wt heln ntioltd IN OR AT O 0 LYrCmlto iet soaeteln sbsdo PERRY -UNIT 1B31-7RvsoN.1 B 3.1-47 Revision No. I}} | |
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MONTHYEARML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-24-207, License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 12024-09-16016 September 2024 License Renewal Application for the Perry Nuclear Power Plant-Response to Request for Additional Information - Set 1 ML24225A0512024-09-13013 September 2024 Issuance of Alternative Request VR-9, Revision 0, Associated with the Fourth 10-Year Inservice Testing Interval ML24256A0872024-09-11011 September 2024 Fws to NRC, Concurrence with Endangered Species Act Nlaa Determinations for Perry License Renewal L-24-201, Spent Fuel Storage Cask Registration2024-09-0909 September 2024 Spent Fuel Storage Cask Registration ML24250A0412024-09-0606 September 2024 Fws to NRC, Perry Nuclear Plant, Unit 1, License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected ML24166A0172024-09-0606 September 2024 Ltr. to Glenna Wallace, Chief, Eastern Shawnee Tribe of Oklahoma; Re., NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0782024-09-0606 September 2024 Ltr. to Kenneth Meshigaud, Chairperson, _ Re., NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0752024-09-0606 September 2024 Letter to Charles Diebold, Chief_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0762024-09-0606 September 2024 Letter to Douglas Lankford, Chief_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0862024-09-0606 September 2024 Letter to Regina Gasco-Bentley, Chairperson_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24249A0882024-09-0606 September 2024 Letter to Rickey Armstrong, President_ Re. NOA of the Draft Site-Specific EIS and Finding of No Historic Properties Affected by Perry Plant Unit 1 Lr ML24247A0212024-09-0606 September 2024 NRC Request for Concurrence with Endangered Species Act Determinations for Perry License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment (Consultation Code: 2024-0006782) L-24-200, License Renewal Application for Revision to Supplement 4 for Editorial Corrections2024-09-0505 September 2024 License Renewal Application for Revision to Supplement 4 for Editorial Corrections ML24228A1712024-09-0303 September 2024 Ltr to Brian Dickens, EPA-Perry Nuclear Power Plant Unit 1-Notice of Avail of the Draft Supp 61 to the GEIS for License Renew of Nuclear Plants ML24228A1702024-09-0303 September 2024 Ltr to Rod L. Penfield-Perry Nuclear Power Plant Unit 1-Notice of Avail of the Draft Supp 61 to the GEIS for License Renew of Nuclear Plants L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 ML24240A1482024-08-27027 August 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-24-190, Spent Fuel Storage Cask Registration2024-08-26026 August 2024 Spent Fuel Storage Cask Registration ML24239A7782024-08-26026 August 2024 Aging Management Audit - Perry Unit 1 - License Renewal Application August 26 2024 IR 05000440/20240052024-08-22022 August 2024 Updated Inspection Plan for Perry Nuclear Power Plant (Report 05000440/2024005) L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule L-24-174, Response to Perry Nuclear Power Plant License Renewal Environmental Report Severe Accident Mitigation Alternatives 2nd Round Request for Additional Information2024-08-15015 August 2024 Response to Perry Nuclear Power Plant License Renewal Environmental Report Severe Accident Mitigation Alternatives 2nd Round Request for Additional Information L-24-178, License Renewal Application Revision O - Supplement 42024-08-0808 August 2024 License Renewal Application Revision O - Supplement 4 IR 05000440/20240022024-08-0808 August 2024 Integrated Inspection Report 05000440/2024002 L-24-189, License Renewal Application for Revision O - Supplement 12024-08-0707 August 2024 License Renewal Application for Revision O - Supplement 1 L-24-171, Spent Fuel Storage Cask Registration2024-07-30030 July 2024 Spent Fuel Storage Cask Registration ML24150A2022024-07-25025 July 2024 Letter to Rod L. Penfield-Perry Nuclear Power Plant Unit 1-License Renewal Scoping Summary Rpt L-24-108, License Renewal Application, Revision 0 - Supplement 32024-07-24024 July 2024 License Renewal Application, Revision 0 - Supplement 3 L-24-168, Technical Specification Required Shutdown Due to Increase in RCS Unidentified Leakage2024-07-15015 July 2024 Technical Specification Required Shutdown Due to Increase in RCS Unidentified Leakage IR 05000440/20244012024-07-0909 July 2024 Security Baseline Inspection Report 05000440/2024401 L-24-020, License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 22024-06-27027 June 2024 License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 2 L-24-155, Reactor Water Clean Up Leak Detection Loss of Safety Function2024-06-27027 June 2024 Reactor Water Clean Up Leak Detection Loss of Safety Function L-24-036, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-27027 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-24-140, Operation of the Residual Heat Removal Loops B and C Alternate Keep Fill Configuration Was Prohibited by Technical Specifications and Resulted in an Unanalyzed Condition2024-06-20020 June 2024 Operation of the Residual Heat Removal Loops B and C Alternate Keep Fill Configuration Was Prohibited by Technical Specifications and Resulted in an Unanalyzed Condition IR 05000440/20240112024-06-17017 June 2024 Fire Protection Team Inspection Report 05000440/2024011 ML24157A3782024-06-0606 June 2024 – Revised Request for Information for NRC License Renewal Inspection: Inspection Report 05000440/2024010 ML24141A1632024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-116, Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification2024-05-16016 May 2024 Response to License Renewal Environmental Report Severe Accident Mitigation Alternatives Requests for Additional Information and Request for Clarification L-24-085, Nudear Power Plant, Submittal of Emergency Plan, Revision 622024-05-0606 May 2024 Nudear Power Plant, Submittal of Emergency Plan, Revision 62 L-24-103, Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams2024-05-0202 May 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation & Scheduling of Operator Licensing Exams ML24117A1222024-04-26026 April 2024 Confirmation of Initial License Examination IR 05000440/20240012024-04-24024 April 2024 Integrated Inspection Report 05000440/2024001 L-24-097, Submittal of 2023 Annual Radiological Effluent Release Report2024-04-22022 April 2024 Submittal of 2023 Annual Radiological Effluent Release Report L-24-096, Submittal of Annual Radiological Environmental Operating Report2024-04-22022 April 2024 Submittal of Annual Radiological Environmental Operating Report ML24095A3282024-04-19019 April 2024 License Renewal Revised Schedule Letter L-24-066, Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency2024-04-15015 April 2024 Response to Request for Additional Information Regarding 10 CFR 50.55a Request Number VR-9, Feedwater Check Valve Exercising Test Frequency 2024-09-09
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARL-24-200, License Renewal Application for Revision to Supplement 4 for Editorial Corrections2024-09-0505 September 2024 License Renewal Application for Revision to Supplement 4 for Editorial Corrections L-24-178, License Renewal Application Revision O - Supplement 42024-08-0808 August 2024 License Renewal Application Revision O - Supplement 4 L-24-189, License Renewal Application for Revision O - Supplement 12024-08-0707 August 2024 License Renewal Application for Revision O - Supplement 1 L-24-108, License Renewal Application, Revision 0 - Supplement 32024-07-24024 July 2024 License Renewal Application, Revision 0 - Supplement 3 L-24-020, License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 22024-06-27027 June 2024 License Renewal Application for the Perry Nuclear Power Plant Revision 0, Supplement 2 ML24124A0162024-05-28028 May 2024 Issuance of Amendment No. 204 to Adopt Technical Specifications Task Force Traveler TSTF-264, Revision 0 L-23-207, License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2024-01-24024 January 2024 License Amendment Request (LAR) for Adoption of TSTF-264-A Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-001, License Amendment Request to Remove the Table of Contents from the Technical Specifications2023-08-0707 August 2023 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-23-146, License Renewal Application for the Perry Nuclear Power Plant2023-07-0303 July 2023 License Renewal Application for the Perry Nuclear Power Plant L-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-22-221, Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-10-18018 October 2022 Supplement to Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position L-20-239, Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-08-0505 August 2022 Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position L-22-099, Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis2022-06-0101 June 2022 Supplement to License Amendment Request to Revise the Methodology Used for Flood Hazard Analysis ML21106A0202021-04-0707 April 2021 Enclosure a - Evaluation of Proposed Change L-20-240, License Amendment Request to Adopt TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control2021-03-0505 March 2021 License Amendment Request to Adopt TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control L-20-129, Emergency Plan Amendment Request2020-12-28028 December 2020 Emergency Plan Amendment Request L-20-166, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-24024 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements L-20-188, ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names2020-06-26026 June 2020 ISFSI, Davis-Besse Unit 1, and ISFSI, Perry, Unit 1, and ISFSI, Decommissioning Trust: Amendments to Decommissioning Trust Agreements to Update Company Names L-19-274, License Amendment Request for Adoption of Technical Specification Task Force (Tsft) Traveler TSTF-500, Revision 2, DC Electrical Rewrite-Update to TSFT-3602020-04-24024 April 2020 License Amendment Request for Adoption of Technical Specification Task Force (Tsft) Traveler TSTF-500, Revision 2, DC Electrical Rewrite-Update to TSFT-360 L-19-213, Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR2019-12-18018 December 2019 Application to Revise Technical Specifications to Adopt TSTF-564. Safety Limit MCPR L-19-265, License Amendment Request to Extend Refueling Special Lifting Devices' Interval for Testing to Verify Continuing Compliance2019-12-18018 December 2019 License Amendment Request to Extend Refueling Special Lifting Devices' Interval for Testing to Verify Continuing Compliance L-19-219, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-09-25025 September 2019 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-200, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-08-29029 August 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI - Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-19-073, ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2019-04-26026 April 2019 ISFSI, Davis-Besse, Unit 1, ISFSI, and Perry, Unit 1, ISFSI - Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-18-046, License Amendment Request to Extend Containment Leakage Test Frequency2018-03-0707 March 2018 License Amendment Request to Extend Containment Leakage Test Frequency L-17-350, Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement2018-02-14014 February 2018 Application to Revise Technical Specifications to Adopt TSTF-546, Revise APRM Channel Adjustment Surveillance Requirement L-17-045, Application to Revise Technical Specifications to Adopt TSTF-542. Reactor Pressure Vessel Water Inventory Control.2017-12-0606 December 2017 Application to Revise Technical Specifications to Adopt TSTF-542. Reactor Pressure Vessel Water Inventory Control. L-17-089, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips2017-06-20020 June 2017 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips L-17-042, Request for Licensing Action to Revise the Technical Specifications2017-06-0808 June 2017 Request for Licensing Action to Revise the Technical Specifications L-17-043, Request for Licensing Action to Revise the Environmental Protection Plan2017-04-26026 April 2017 Request for Licensing Action to Revise the Environmental Protection Plan L-17-052, Supplemental Request Associated with the License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 32017-02-0606 February 2017 Supplemental Request Associated with the License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3 L-16-179, License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1. Reactor Core Safety Limits.2016-11-0101 November 2016 License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1. Reactor Core Safety Limits. L-16-236, License Amendment Request for Adoption of Technical Specifications Task Force (Tstr Traveler TSTF-501. Revision 1. Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2016-10-27027 October 2016 License Amendment Request for Adoption of Technical Specifications Task Force (Tstr Traveler TSTF-501. Revision 1. Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control L-16-304, Supplement to Request for License Amendment Approval Delay2016-10-25025 October 2016 Supplement to Request for License Amendment Approval Delay L-16-083, License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 32016-03-15015 March 2016 License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3 L-15-195, Application for Order Consenting to Transfer of Licenses and Approving Conforming License Amendments2015-06-30030 June 2015 Application for Order Consenting to Transfer of Licenses and Approving Conforming License Amendments L-14-271, Request for Licensing Action to Amend Technical Specification 3.8.4, DC Sources - Operating2014-11-24024 November 2014 Request for Licensing Action to Amend Technical Specification 3.8.4, DC Sources - Operating L-13-306, Request for Licensing Action Pursuant to 10 CFR 50.59. 50.67. and 50.90: Full Implementation of Alternative Accident Source Term Design Basis Accident Analyses. and an Associated Technical Specification Change2013-12-0606 December 2013 Request for Licensing Action Pursuant to 10 CFR 50.59. 50.67. and 50.90: Full Implementation of Alternative Accident Source Term Design Basis Accident Analyses. and an Associated Technical Specification Change ML13281A5362013-10-15015 October 2013 Meeting Slide for FENOC Presubmittal Guidance Checklist Part I L-12-397, Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest2013-02-19019 February 2013 Request to Amend the Price-Anderson Indemnities and Notification of a Name Change to Documents of Regulatory Interest ML12249A3592012-09-0505 September 2012 License Amendment Request for Adoption of TSTF-275-A, Rev. 0, Clarify Requirement for EDG Start Signal on Rpv... & TSTF-300-A L-12-064, Request for an Amendment to Revise Technical Specification 3.10.1. Inservice Leak and Hydrostatic Testing Operation, Using the Consolidated Line Item Improvement Process2012-02-22022 February 2012 Request for an Amendment to Revise Technical Specification 3.10.1. Inservice Leak and Hydrostatic Testing Operation, Using the Consolidated Line Item Improvement Process L-11-331, License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating.2011-10-11011 October 2011 License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating. L-11-322, License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating.2011-10-0303 October 2011 License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating. ML1126402462011-09-20020 September 2011 License Amendment Request to Change the Name of an Owner Licensee to Firstenergy Nuclear Generation, LLC L-11-038, License Amendment Request to Adopt Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation2011-04-12012 April 2011 License Amendment Request to Adopt Technical Specification Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation L-10-200, License Amendment Request to Modify Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-222-A, Revision 12010-12-15015 December 2010 License Amendment Request to Modify Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-222-A, Revision 1 ML1029804462010-10-21021 October 2010 License Amendment Request to Modify Technical Specification 2.1.1, Reactor Core Sls, to Incorporate Revised Safety Limit Minimum Critical Power Ratio Values 2024-09-05
[Table view] Category:Technical Specifications
MONTHYEARML23353A0012024-02-21021 February 2024 – Issuance of Amendment No. 202 to Adopt TSTF-276, Revision 2, Revise DG Full Load Rejection Test ML22210A0102022-09-16016 September 2022 Energy Harbor Fleet- Issuance of Amendments Regarding Adoption of TSTF 554, Revise Reactor Coolant Leakage Requirements ML21361A2172021-12-20020 December 2021 Supplemental Information for Revision 22 to Updated Safety Analysis Report, Revision 13 to Technical Specification Bases TS Bases ML21271A0782021-11-0505 November 2021 Issuance of Amendment No. 195 Regarding the Adoption of TSTF-230, Add New Condition B to LCO 3.6.2.3, 'Rhr Suppression Pool Cooling' ML21307A1762021-10-28028 October 2021 2 to Updated Safety Analysis Report, Chapter 16, Technical Specifications ML21158A2122021-07-12012 July 2021 Issuance of Amendment No. 194 Regarding the Adoption of TSTF-002, Relocate the 10 Year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML21035A1702021-03-0101 March 2021 Issuance of Amendment No. 192, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20099A1022020-05-22022 May 2020 Issuance of Amendment No. 188, Regarding Revision to Technical Specifications to Adopt TSTF-564, Safety Limit (Minimum Critical Power Ratio) MCPR ML17325B6902018-01-18018 January 2018 Issuance of Amendment Concerning Adoption of Technical Specification Task Force (TSTF) Traveler 400-A, Revision 1, Clarify SR on Bypass of DG Automatic Trips (CAC No. MF9855, EPID L-2017-LLA-0246) (L-17-089) ML17305A2132017-10-23023 October 2017 Perry Nuclear Power Plant Revision 20 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML15307A3492016-02-23023 February 2016 Issuance of Amendment Concerning Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control (CAC No. MF3720) (L-14-106) ML15243A1532015-09-0202 September 2015 Correction of Typographical Error Incurred During Prior License Amendment No. 162 ML15201A5292015-08-17017 August 2015 Issuance of Amendment Concerning Technical Specification 3.8.4 DC Sources - Operating (TAC No. MF5298) (L-14-271) ML15160A0282015-06-23023 June 2015 Issuance of Amendment Concerning Adoption of TSTF-535, Revise Shutdown Margin Definition to Address Advanced Fuel Designs (TAC No. MF4791)(L-14-137) ML15141A4822015-06-12012 June 2015 Issuance of Amendment Concerning Changes to Pressure Temperature Curves (TAC No. MF4351)(L-14-150) ML15133A5022015-06-10010 June 2015 Issuance of Amendment Concerning Extension of Cyber Security Milestone 8 (TAC No. MF5557)(L-14-421) L-11-338, Supplemental Information for License Amendment Request Regarding Offsite Electric Power System Acceptability Until December 12, 20112011-10-17017 October 2011 Supplemental Information for License Amendment Request Regarding Offsite Electric Power System Acceptability Until December 12, 2011 L-11-333, Supplemental Information for License Amendment Request Regarding Offsite Electric Power System Acceptability Until December 12, 20112011-10-13013 October 2011 Supplemental Information for License Amendment Request Regarding Offsite Electric Power System Acceptability Until December 12, 2011 L-11-322, License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating.2011-10-0303 October 2011 License Amendment Request Regarding Use of a Delayed Access Circuit as a Required Offsite Circuit in Technical Specification 3.8.1, AC Sources - Operating. ML1116608152011-06-16016 June 2011 Correction Letter License Amendment No. 157 L-10-201, License Amendment Request to Revised Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-460, Revision 02010-12-15015 December 2010 License Amendment Request to Revised Technical Specification 3.1.4, Control Rod Scram Times, to Incorporate TSTF-460, Revision 0 ML1029804462010-10-21021 October 2010 License Amendment Request to Modify Technical Specification 2.1.1, Reactor Core Sls, to Incorporate Revised Safety Limit Minimum Critical Power Ratio Values L-09-025, ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-25025 March 2009 ISFSI, and Perry, Application for Technical Specification (TS) Change for Adoption of TSTF-511 Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. ML0824608772008-08-28028 August 2008 Tech Spec Page for Amendment 150 TSTF-476, Improved Banked Position Withdrawal Sequence Control Rod Insertion Process, Per the Consolidated Line Item Improvement Process ML0817503002008-06-19019 June 2008 TS Pages - Issuance of Amendment Revise TSs 3.6.1, 3.6.4 and 3.6.5 ML0811905752008-04-25025 April 2008 TS Pages - Issuance of Amendment No. TSTF-448, Revision 3, Control Room Habitability. ML0726808522007-09-18018 September 2007 License Amendment Request Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0725505472007-09-0505 September 2007 License Amendment Request to Revise Technical Specification 3.6.1, 3.6.4, and 3.6.5 for Containment and Drywell Isolation Device ML0721102792007-07-30030 July 2007 Tech Spec Pages for Amendment 147 to Clarify Technical Specification Requirements Related to Annulus Exhaust Gas Treatment (Aegt) System ML0719402902007-07-12012 July 2007 Technical Specifications, Issuance of Amendment ASTM Standards for Fuel Oil Testing ML0717704662007-06-22022 June 2007 Tech Spec Page for Amendment 145 Scram Discharge Volume Vent and Drain Valves ML0717202522007-06-14014 June 2007 Beaver and Perry, Technical Specifications, Issuance of Amendments Modification of Technical Specification Requirements for Inoperable Snubbers ML0713403922007-05-0909 May 2007 Technical Specifications (Ts), Revise TS 5.5.7, Ventilation Filter Test Program, to Correct Referenced Flow Units ML0712005032007-04-30030 April 2007 Tech Spec Pages for Amendment 142 Regarding Emergency Diesel Generator Surveillance Testing Voltage and Frequency Limits ML0712102912007-04-27027 April 2007 Technical Specifications, Issuance of Amendment Revise TS to Change the Frequency of the Mode 5 Intermediate Range Monitoring Instrumentation Channel Functional Test L-06-172, Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2007-01-11011 January 2007 Units 1 and 2, License Amendment Requests to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML0700904852006-12-29029 December 2006 Application for a Technical Specification Improvement to Revise Technical Specification 3.1.8, Scram Discharge Volume (SDV) Vent and Drain Valves, Using the Consolidated Line Item Improvement Process ML0629704472006-10-13013 October 2006 License Amendment Request to Eliminate Unnecessary Reporting Requirements in the Operating License and the Administrative Controls Section of the Technical Specifications ML0618700962006-06-30030 June 2006 Technical Specification, Modifies the Existing TS 3.3.1.3, Oscillation Power Range Monitor (OPRM) Instrumentation, Surveillance Requirement 3.3.1.3.5 ML0615903492006-06-0101 June 2006 License Amendment Request - Revise Mode 3 Hot Shutdown Requirements to Add a Note Addressing Situations When Both Residual Heat Removal (RHR) Shutdown Cooling Subsystems Are Inoperable ML0615903292006-06-0101 June 2006 License Amendment Request - Revise Mode 4 Residual Heat Removal Shutdown Cooling Requirements to Add a Default Condition Addressing Situations When Condition a Cannot Be Met within Its Completion Time ML0605404392006-02-14014 February 2006 Amendment Request to Revise Technical Specification 3.3.1.1 Intermediate Range Monitoring Instrumentation Mode 5 Channel Functional Testing Surveillance Frequency from 7 Days to 31 Days ML0605306202006-02-10010 February 2006 License Amendment Request to Revise Required Action B.1 in the Emergency Core Cooling System Instrumentation Technical Specification to Be Consistent with the Improved Standard Technical Specifications ML0529903232005-10-14014 October 2005 Submittal of Technical Specification Bases, Revision 5 ML0522902522005-08-16016 August 2005 Tech Spec Pages for Amendment 136 Elimination of Monthly Operating Reports and Occupational Radiation Exposure Reports ML0512501942005-04-19019 April 2005 4/19/05, Perry - TS Pages - Issuance of Amendment Elimination of Requirements for Hydrogen Recombiners and Hydrogen Monitors Using the Consolidated Line Item Improvement Process ML0509600872005-03-31031 March 2005 Tech Spec Pages for Amendment 134 Single Recirculation Loop Operation ML0504505712005-02-10010 February 2005 Tech Spec Pages for Amendment 133 Testing of Safety/Relief Valves ML0503503642005-02-0303 February 2005 Technical Specification Pages Revision of the Minimum Critical Power Ratio Safety Limit ML0419401992004-07-0909 July 2004 Technical Specifications, Issuance of Amendment Regarding Primary Containment and Drywell Isolation Instrumentation to Increase the Analytical Limit for Detected Temperature 2024-02-21
[Table view] |
Text
FENOC Perry Nuclear Power Station 10CetrRa FirstEnergy Nuclear Operating Company Perry, Ohio 44081 L. William Pearce 440-280-5382 Vice President Fax: 440-280-8029 December 29, 2006 Docket Number 50-440 License Number NPF-58 PY-CE I/N RR-2995L 10 CFR 50.90 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Perry Nuclear Power Plant Application for a Technical Specification Improvement to Revise Technical Specification 3.1.8, 'Scram Discharge Volume (SDV) Vent and Drain Valves,"
Using the Consolidated Line Item Improvement Process In accordance with the provisions of 10 CFR 50.90, the FirstEnergy Nuclear Operating Company (FENOC) is submitting a request for an amendment to the Technical Specifications (TSs) for the Perry Nuclear Power Plant.
The proposed changes would revise the Required Action in TS 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable. These changes are based on Technical Specification Task Force (TSTF) change traveler TSTF-404 (Revision 0), which has been approved generically for the Boiling Water Reactor (BWR) BWR6 Standard Technical Specification NUREG-1434. The availability of this TS improvement was announced in the Federal Register on April 15, 2003, as part of the Consolidated Line Item Improvement Process (CLIIP).
Enclosure 1 provides a description of the proposed change and confirmation of applicability, the existing TS pages marked-up to show the proposed change, and the existing TS Bases pages marked-up to reflect the proposed change (for information only). There are no new regulatory commitments associated with this proposed change.
Approval of the license amendment is requested prior to December 30, 2007, with the amendment to be implemented within 90 days following its effective date.
In accordance with 10 CFR 50.91, a copy of.this application, with enclosure, is being provided to the designated State of Ohio Official.
December 29, 2006 Docket Number 50-440 License Number NPF-58 PY-CEI/N RR-2995L Page 2 of 2 If there are any questions or if additional information is required, please contact Mr. Gregory A. Dunn, Manager - FENOC Fleet Licensing, at 330-315-7243.
I declare under penalty of perjury that the foregoing is true and correct. Executed on December 29, 2006.
Enclosure.
- 1. Perry Nuclear Power Plant Evaluation for a Proposed License Amendment to Revise Technical Specification 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves" cc: NRC Project Manager NRC Resident Inspector NRC Region Ill N. Dragani, Executive Director, Ohio Emergency Management Agency, State of Ohio (NRC Liaison)
Enclosure 1 PY-CEI/N RR-2995L Page 1 of 3 PERRY NUCLEAR POQWER PLANT EVALUATION FOR A PROPOSED LICENSE AMENDMENT TO REVISE TECHNICAL SPECIFICATION 3.1.8, "SCRAM DISCHARGE VOLUME (S DV) VENT AND DRAIN VALVES"
1.0 DESCRIPTION
OF PROPOSED AMENDMENT 2.0 ASSESSMENT 2.1 APPLICABILITY OF PUBLISHED SAFETY EVALUATION 2.2 OPTIONAL CHANGES AND VARIATIONS
3.0 REGULATORY ANALYSIS
3.1 NO SIGNIFICANT HAZARDS CONSIDERATION 3.2 VERIFICATION AND COMMITMENTS 4.0 ENVIRONMENTAL EVALUATION 5.0 PRECEDENT
6.0 REFERENCES
7.0 ATTACHMENTS
- 1. Proposed Operating License Change (Hand Mark-up)
- 2. Proposed Technical Specification Bases Changes (For Information Only)
Enclosure 1 PY-CEI/NRR-2995L Page 2 of 3
1.0 DESCRIPTION
OF PROPOSED AMENDMENT The proposed license amendment would revise Required Action in Technical Specification 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable. These changes are based on Technical Specification Task Force (TSTF) change traveler TSTF-404 (Revision 0), which has been approved generically for the Boiling Water Reactor 6 Standard Technical Specifications, NUREG-1434. The availability of this Technical Specification improvement was announced in the Federal Register on April 15, 2003 (68 FR 18294) as part of the Consolidated Line Item Improvement Process (OLIIP). Refer to Attachment 1 for a mark-up of the existing TS reflecting the proposed changes.
2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation FirstEnergy Nuclear Operating Company (FENOC) has reviewed the NRC safety evaluation published on April 15, 2003 (68 FR 18294) as part of the CLIIP. This verification included a review of the NRC staff's evaluation as well as the information provided to support TSTF-404.
FENOC has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to the Perry Nuclear Power Plant (PNPP) and justify this amendment for the incorporation of the changes into the PNPP Technical Specifications.
2.2 Optional Changes and Variations FENOC is not proposing any variations or deviations from the Technical Specification changes described in TSTF-404 or the NRC staff's model safety evaluation published on April 15, 2003 (68 FR 18294).
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration FENOC has reviewed the proposed no significant hazards consideration determination published on April 15, 2003 as part of the CLIIP. FENOC has concluded that the proposed determination presented in the notice is applicable to PNPP and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).
3.2 Verification and Commitments There are no new regulatory commitments associated with this proposed change.
4.0 ENVIRONMENTAL EVALUATION FENOC has reviewed the environmental evaluation included in the model safety evaluation published on April 15, 2003, as part of the CLIIP. FENOC has concluded that the NRC staff's
Enclosure 1 PY-CEI/NRR-2995L Page 3 of 3 findings presented in that evaluation are applicable to PNPP and the evaluation is hereby incorporated by reference for this application.
5.0 PRECEDENT This application is being made in accordance with the OLIIP. FENOC is not proposing variations or deviations from the Technical Specification changes described in the NRC staff's model safety evaluation published on April 15, 2003 (68 FR 18294).
Similar changes to Technical Specification SDV ACTIONS were approved by the NRC for the Pilgrim Nuclear Power Station (TAC NO. MC5422 - ADAMS Accession Number ML051870257) dated July 29, 2005; and for the Hope Creek Generating Station (TAC NO. MC6697 - ADAMS Accession Number ML060050304) dated January 13, 2006.
6.0 REFERENCES
- 1. Federal Register, "Notice of Availability of Model Application Concerning Technical Specifications Improvement Regarding Scram Discharge Volume Vent and Drain Valves Actions for Boiling Water Reactors Using the Consolidated Line Item Improvement Process," April 15, 2003 (68 FR 18294)
- 2. Technical Specifications Task Force (TSTF) Change Traveler 404, Revision 0 7.0 ATTACHMENTS
- 1. Proposed Operating License Change (Hand Mark-up)
- 2. Proposed Technical Specification Bases Changes (For Information Only)
Attachment 1 PY-CE I/N RR-2995L Page 1 of 2 PROPOSED OPERATING LICENSE CHANGE (HAND MARK-UP)
Attachment 1 PY-C EI/N RR-2995L Page 2 of 2 SDV Vent and Drain Valves 3.1 RECIIYCONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent ah'd Drain Valves LCO 3.1.8 Each SDV vent and drain valve shall be OPERABLE.
APPLICABILITY: MODES I and 2.
ACTIONS
- -NOTE--/ý-------------------------------
t~Se arate Condition entry is allowe SDV vent and drain line.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent A.1 Rftzt-oe mlV~
" ti 7 days or drain lines with OPERADLE status.
one valve inoperable. :1oUr T)-h* /45c; B. One or more SDV vent B.1 --
or drain lines with -Aýn isolated line may both valves be unisolated under inoperable, administrative control to allow draining and venting Isolate the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> associated line.
C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion
.Time not met.
PERRY - UNIT*1 3.1-24 PERR No. 69
- NIT 3.-24Amendment
Attachment 2 PY-CEI/NRR-2995L Page 1 of 3 PROPOSED TECHNICAL SPECIFICATION BASES CHANGES
.(FOR INFORMATION ONLY)
Attachment 2 PY-CEIINRR-2995L Page 2 of 3 INFOR" AT10DOJliLL SDV Vent and Drain Valves B 3.1.8 BAS ES APPLICABLE allow continuous drainage of the SDV during normal plant SAFETY ANALYSES operation to ensure the SDV has sufficient capacity to (continued) contain the reactor coolant discharge during a full core scram. To automatically ensure this capacity, a reactor scram (LCO 3.3.1.1, "Reactor Protection System (RPS)
Instrumentation") is initiated ifthe SDV water level exceeds a specified setpoint. The setpoint is chosen such that all control rods are inserted before the SDV has insufficient volume to accept a full scram.
SDV vent and drain valves satisfy Criterion 3 of the NRC Policy Statement.
LCO The OPERABILITY of all SDV vent and drain valves ensures that, during a scram, the SDV vent and 'drain valves will close to contain reactor water discharged to the SDV piping.
Since the vent and drain lines are provided with two valves in series, the single failure of one valve inthe open position will not impair the isolation function of the system. Additionally, the valves are required to be open to ensure that a path is available for the SDV piping to drain freely at other times.
APPLICABILITY InMODES 1 and 2. scram may be required, and therefore, the SDV vent and drain valves must be OPERABLE. InMODES 3 and 4. control rods are not able to be withdrawn since the reactor mode switch is inthe shutdown position and a control rod block isapplied. Also, during MODE 5, only a single control rod can be withdrawn from a core cell containing fuel assemblies. Therefore, the SDV vent and drain valves are not required to be OPERABLE inthese MODES since the reactor is subcritical and only one rod may be withdrawn and subject to scram.
ACTIONS The ACTIONS table ismodified by/ANoteyindicating that a separate Condition entry is allowed for each SDV vent and drain line. This isacceptable, since the Required Actions
- for each Condition provide appropriate compensatory actions xk"s-P' U URDV for each inoperable SDV line. Complying with .the Required Fam IN ORIA INActions may allow for continued operation, and subsequent Po E3J'I-47 inoperable SDV lines are governed by subsequent Condition entry and application of associated Required Actions.p.
y ~(conti nued)
PFRRY - UNIT 1B31-6Rvso B 3.1-46 No I Revision No. 1
Attachment 2 PY-CEI/NRR-2995L Page 3 of 3 IN ,0Ihim0 0N I. YSDV ATI Vent and Drain Valves B 3.1.8 BASES ACTIONS A.1 the reacfcp cccJ4?i,0 cir ~CiV.":; r"
,(cotined) When one SDV vent or drain valve is inoperable inone o more lines, the ,avzmtbortrdtoOEABE ttu
-w-i 4---ds The-pCompletion Time isreasonable, given the
,--7ev-e-Fof--re-du-ndancy inthe lines and the ]ow~probability of a scram occurring during the time the valve(s) are inooerabL1e The SDV isstill isolable since the redundant valve inthe affected line isOPERABLE. Since the SDV is anct &he- h4i still isolable, the affected SDV line may be opened. This no,+~ isclcte~d- allows any accumulated water inthe line to be drained, to preclude a reactor scram on SDV high level. During these periods, the single failure criterion may not be preserved, and a higher risk exists to allow reactor water out of the primary system during a scram.
B.1 Ifboth valves ina line are inoperable, the line must be isolated to contain the reactor coolant durnn control Thinei ,salowsanyccuulaed atr ian therSVtobe dr~ained to preclud a reactoisicreamnsedV. ihlvl Thea8dhurCmlto hgSD to Tie ee isolcrated thriei aed, o thelowproabiityof scam ccurin whleDheringteise nerots telnmabeuisolatedad unliklioo ofsgiiadmntsCratisea leakage Ifonyrl Reqire actions and associlated Competion time isD notb mriet, theplantlustde broughttor scamMoDin which thevelCD does not accppaly. Toiachee the disistratusvte plantrmust bensr if~
~ wt
~ ~heln~ ntioltd
~ anued)cr
~ ~ (ot IN OR AT O 0 LYrCmlto iet soaeteln sbsdo PERRY - UNIT 1B31-7RvsoN.1 B 3.1-47 Revision No. I