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| {{#Wiki_filter:November 2, 2006MEMORANDUM TO:Martin Murphy, Acting ChiefPlant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:Timothy Kobetz, Chief /RA/Technical Specifications Branch Division of Inspections and Regional Support Office of Nuclear Reactor Regulation | | {{#Wiki_filter:November 2, 2006 MEMORANDUM TO: Martin Murphy, Acting Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Timothy Kobetz, Chief /RA/ |
| | Technical Specifications Branch Division of Inspections and Regional Support Office of Nuclear Reactor Regulation |
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| ==SUBJECT:== | | ==SUBJECT:== |
| DUANE ARNOLD NUCLEAR PLANT - STAFF'S REVIEW OFTHE ADOPTION OF TSTF-484, REV. 0, "USE OF TS 3.10.1 FOR SCRAM TIME TESTING ACTIVITIES" TECHNICAL SPECIFICATION AMENDMENT (TAC NO. MD0293)By letter dated March 01, 2006 (ML060720038), FPL Energy Duane Arnold, LLC (the licensee)submitted a license amendment request (LAR) regarding Duane Arnold Nuclear Plant system leakage and hydrostatic testing operation technical specifications (TSs). The proposed amendment would revise the existing system leakage and hydrostatic testing operation TS to be consistent with the U.S. Nuclear Regulatory Commission's approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-484, "Use of TS 3.10.1 for Scram Time Testing Activities," Revision 0. TSTF-484 is part of the consolidated line item improvement process (CLIIP). The staff of the Technical Specifications Branch (ITSB) of the Division of Inspections andRegional Support (DIRS) has completed its review of the LAR. The staff's review is enclosed. Docket No.: 50-331 | | DUANE ARNOLD NUCLEAR PLANT - STAFFS REVIEW OF THE ADOPTION OF TSTF-484, REV. 0, USE OF TS 3.10.1 FOR SCRAM TIME TESTING ACTIVITIES TECHNICAL SPECIFICATION AMENDMENT (TAC NO. MD0293) |
| | By letter dated March 01, 2006 (ML060720038), FPL Energy Duane Arnold, LLC (the licensee) submitted a license amendment request (LAR) regarding Duane Arnold Nuclear Plant system leakage and hydrostatic testing operation technical specifications (TSs). The proposed amendment would revise the existing system leakage and hydrostatic testing operation TS to be consistent with the U.S. Nuclear Regulatory Commissions approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities, Revision 0. TSTF-484 is part of the consolidated line item improvement process (CLIIP). |
| | The staff of the Technical Specifications Branch (ITSB) of the Division of Inspections and Regional Support (DIRS) has completed its review of the LAR. The staffs review is enclosed. |
| | Docket No.: 50-331 |
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| ==Enclosure:== | | ==Enclosure:== |
| Staff Safety Evaluation CONTACTS: Aron Lewin, ITSB/DIRS 301-415-2259
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| ML062990378OFFICEITSB:DIRSBC:ITSB:DIRSNAMEALewinTKobetzDATE10/26/200611/2/06 STAFF SAFETY EVALUATIONDUANE ARNOLD NUCLEAR PLANT SYSTEM LEAKAGE AND HYDROSTATIC TESTINGOPERATION TECHNICAL SPECIFICATION AMENDMENTTAC NO. MD0293DOCKET NO. 50-33
| | Staff Safety Evaluation CONTACTS: Aron Lewin, ITSB/DIRS 301-415-2259 |
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| ==11.0INTRODUCTION==
| | ML062990378 OFFICE ITSB:DIRS BC:ITSB:DIRS NAME ALewin TKobetz DATE 10/26/2006 11/2/06 STAFF SAFETY EVALUATION DUANE ARNOLD NUCLEAR PLANT SYSTEM LEAKAGE AND HYDROSTATIC TESTING OPERATION TECHNICAL SPECIFICATION AMENDMENT TAC NO. MD0293 DOCKET NO. 50-331 |
| By application dated March 01, 2006, (Agencywide Documents Access and ManagementSystem Accession No. ML060720038) FPL Energy Duane Arnold, LLC (the licensee) requested changes to the Technical Specifications (TS) for the Duane Arnold Nuclear Plant.The proposed changes would revise Limiting Condition for Operation (LCO) 3.10.1, and theassociated Bases, to expand its scope to include provisions for temperature excursions greater than 212 oF as a consequence of inservice leak and hydrostatic testing, and as a consequenceof scram time testing initiated in conjunction with an inservice leak or hydrostatic test, while considering operational conditions to be in Mode 4.
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| ==2.0REGULATORY EVALUATION== | | ==1.0 INTRODUCTION== |
| 2.1 Inservice Leak and Hydrostatic TestingThe Reactor Coolant System (RCS) serves as a pressure boundary and also serves to providea flow path for the circulation of coolant past the fuel. In order to maintain RCS integrity, Section XI of the American Society of Mechanical Engineers (ASME) Pressure Vessel Code requires periodic hydrostatic and leakage testing. Hydrostatic tests are required to be performed once every ten years and leakage tests are required to be performed each refueling outage. Appendix G to 10 CFR Part 50 states that pressure tests and leak tests of the reactor vessel that are required by Section XI of the American Society of Mechanical Engineers (ASME) Pressure Vessel Code must be completed before the core is critical.NUREG-1433, General Electric Plants, BWR/4, Revision 3, Standard Technical Specifications(STS) and NUREG-1434, General Electric Plants, BWR/6, Revision 3, STS both currently contain LCO 3.10.1, "Inservice Leak and Hydrostatic Testing Operation." LCO 3.10.1 was created to allow for hydrostatic and leakage testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212 oF provided certain secondarycontainment LCOs are met. TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, modifiesLCO 3.10.1 to allow a licensee to implement LCO 3.10.1, while hydrostatic and leakage testing is being conducted, should average reactor coolant temperature exceed 212 oF during testing. This modification does not alter current requirements for hydrostatic and leakage testing as required by Appendix G to 10 CFR Part 50. 2.2CONTROL ROD SCRAM TIME TESTINGControl rods function to control reactor power level and to provide adequate excess negativereactivity to shut down the reactor from any normal operating or accident condition at any time during core life. The control rods are scrammed by using hydraulic pressure exerted by the control rod drive (CRD) system. Criterion 10 of Appendix A to 10 CFR Part 50 states that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. The scram reactivity used in design basis accidents (DBA) and transient analyses is based on an assumed control rod scram time.NUREG-1433, General Electric Plants, BWR/4, Revision 3, STS and NUREG-1434, GeneralElectric Plants, BWR/6, Revision 3, STS both currently contain surveillance requirements (SR) to conduct scram time testing when certain conditions are met in order to ensure that Criterion 10 of Appendix A to 10 CFR Part 50 is satisfied. SR 3.1.4.1 requires scram time testing to be conducted following a shutdown greater than 120 days while SR 3.1.4.4 requires scram time testing to be conducted following work on the CRD system or following fuel movement within the affected core cell. Both SRs must be performed at reactor steam dome pressure greater than or equal to 800 psig and prior to exceeding 40 percent rated thermal power (RTP).The Duane Arnold Nuclear Plant TS contain cross references and nomenclatures that areslightly different from the STS. Duane Arnold Nuclear Plant TS contain SR 3.1.4.1 and SR 3.1.4.2 that are equivalent to STS SR 3.1.4.1 and SR 3.1.4.4 that are discussed above. TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, would modifyLCO 3.10.1 to allow SR 3.1.4.1 and SR 3.1.4.2 to be conducted in Mode 4 with average reactor coolant temperature greater than 212 oF. Scram time testing would be performed in accordancewith LCO 3.10.4, "Single Control Rod Withdrawal - Cold Shutdown." This modification to LCO 3.10.1 does not alter the means of compliance with Criterion 10 of Appendix A to 10 CFR Part 50.
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| ==3.0TECHNICAL EVALUATION==
| | By application dated March 01, 2006, (Agencywide Documents Access and Management System Accession No. ML060720038) FPL Energy Duane Arnold, LLC (the licensee) requested changes to the Technical Specifications (TS) for the Duane Arnold Nuclear Plant. |
| The existing provisions of LCO 3.10.1 allow for hydrostatic and leakage testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212 oF, while imposingMode 3 secondary containment requirements. Under the existing provision, LCO 3.10.1 would have to be implemented prior to hydrostatic and leakage testing. As a result, if LCO 3.10.1 was not implemented prior to hydrostatic and leakage testing, hydrostatic and leakage testing would have to be terminated if average reactor coolant temperature exceeded 212 oF during theconduct of the hydrostatic and leakage test. TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, modifies LCO 3.10.1 to allow a licensee to implement LCO 3.10.1, while hydrostatic and leakage testing is being conducted, should average reactor coolant temperature exceed 212 oF during testing. The modification will allow completion of testingwithout the potential for interrupting the test in order to reduce reactor vessel pressure, cool the RCS, and restart the test below 212 oF. Since the current LCO 3.10.1 allows testing to beconducted while in Mode 4 with average reactor coolant temperature greater than 212 oF, theproposed change does not introduce any new operational conditions beyond those currently allowed. SR 3.1.4.1 and SR 3.1.4.2 require that control rod scram time be tested at reactor steam domepressure greater than or equal to 800 psig and before exceeding 40 percent rated thermal power (RTP). Performance of control rod scram time testing is typically scheduled concurrent with inservice leak or hydrostatic testing while the RCS is pressurized. Because of the number of control rods that must be tested, it is possible for the inservice leak or hydrostatic test to be completed prior to completing the scram time test. Under existing provisions, if scram time testing can not be completed during the LCO 3.10.1 inservice leak or hydrostatic test, scram time testing must be suspended. Additionally, if LCO 3.10.1 is not implemented and average reactor coolant temperature exceeds 212 oF while performing the scram time test, scram timetesting must also be suspended. In both situations, scram time testing is resumed during startup and is completed prior to exceeding 40 percent RTP. TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, modifies LCO 3.10.1 to allow a licensee to complete scram time testing initiated during inservice leak or hydrostatic testing. As stated earlier, since the current LCO 3.10.1 allows testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212 oF, the proposed change does not introduce any newoperational conditions beyond those currently allowed. Completion of scram time testing prior to reactor criticality and power operations results in a more conservative operating philosophy with attendant potential safety benefits.It is acceptable to perform other testing concurrent with the inservice leak or hydrostatic testprovided that this testing can be performed safely and does not interfere with the leak or hydrostatic test. However, it is not permissible to remain in TS 3.10.1 solely to complete such testing following the completion of inservice leak or hydrostatic testing and scram time testing.Since the tests are performed with the reactor pressure vessel (RPV) nearly water solid, at lowdecay heat values, and near Mode 4 conditions, the stored energy in the reactor core will be very low. Small leaks from the RCS would be detected by inspections before a significant loss of inventory occurred. In addition, two low-pressure emergency core cooling systems (ECCS) injection/spray subsystems are required to be operable in Mode 4 by TS 3.5.2, ECCS-Shutdown. In the event of a large RCS leak, the RPV would rapidly depressurize and allow operation of the low pressure ECCS. The capability of the low pressure ECCS would be adequate to maintain the fuel covered under the low decay heat conditions during these tests.
| | The proposed changes would revise Limiting Condition for Operation (LCO) 3.10.1, and the associated Bases, to expand its scope to include provisions for temperature excursions greater than 212oF as a consequence of inservice leak and hydrostatic testing, and as a consequence of scram time testing initiated in conjunction with an inservice leak or hydrostatic test, while considering operational conditions to be in Mode 4. |
| Also, LCO 3.10.1 requires that secondary containment and standby gas treatment system be operable and capable of handling any airborne radioactivity or steam leaks that may occur during performance of testing. The protection provided by the normally required Mode 4 applicable LCOs, in addition to thesecondary containment requirements required to be met by LCO 3.10.1, minimizes potential consequences in the event of any postulated abnormal event during testing. In addition, the requested modification to LCO 3.10.1 does not create any new modes of operation or operating conditions that are not currently allowed. Therefore, the staff finds the proposed change acceptable.
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| ==4.0STATE CONSULTATION== | | ==2.0 REGULATORY EVALUATION== |
| In accordance with the Commission's regulations, the Iowa State official was notified of theproposed issuance of the amendment. The State official had [no] comments. [If comments were provided, they should be addressed here].
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| ==5.0ENVIRONMENTAL CONSIDERATION==
| | 2.1 Inservice Leak and Hydrostatic Testing The Reactor Coolant System (RCS) serves as a pressure boundary and also serves to provide a flow path for the circulation of coolant past the fuel. In order to maintain RCS integrity, Section XI of the American Society of Mechanical Engineers (ASME) Pressure Vessel Code requires periodic hydrostatic and leakage testing. Hydrostatic tests are required to be performed once every ten years and leakage tests are required to be performed each refueling outage. Appendix G to 10 CFR Part 50 states that pressure tests and leak tests of the reactor vessel that are required by Section XI of the American Society of Mechanical Engineers (ASME) Pressure Vessel Code must be completed before the core is critical. |
| The amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. TheCommission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding issued on [Date] ([ ] FR [ ]) . Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. | | NUREG-1433, General Electric Plants, BWR/4, Revision 3, Standard Technical Specifications (STS) and NUREG-1434, General Electric Plants, BWR/6, Revision 3, STS both currently contain LCO 3.10.1, Inservice Leak and Hydrostatic Testing Operation. LCO 3.10.1 was created to allow for hydrostatic and leakage testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212oF provided certain secondary containment LCOs are met. |
| | TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, modifies LCO 3.10.1 to allow a licensee to implement LCO 3.10.1, while hydrostatic and leakage testing is being conducted, should average reactor coolant temperature exceed 212oF during testing. |
| | This modification does not alter current requirements for hydrostatic and leakage testing as required by Appendix G to 10 CFR Part 50. |
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| ==6.0CONCLUSION==
| | 2.2 CONTROL ROD SCRAM TIME TESTING Control rods function to control reactor power level and to provide adequate excess negative reactivity to shut down the reactor from any normal operating or accident condition at any time during core life. The control rods are scrammed by using hydraulic pressure exerted by the control rod drive (CRD) system. Criterion 10 of Appendix A to 10 CFR Part 50 states that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. The scram reactivity used in design basis accidents (DBA) and transient analyses is based on an assumed control rod scram time. |
| The Commission has concluded, based on the considerations discussed above, that: (1) thereis reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. | | NUREG-1433, General Electric Plants, BWR/4, Revision 3, STS and NUREG-1434, General Electric Plants, BWR/6, Revision 3, STS both currently contain surveillance requirements (SR) to conduct scram time testing when certain conditions are met in order to ensure that Criterion 10 of Appendix A to 10 CFR Part 50 is satisfied. SR 3.1.4.1 requires scram time testing to be conducted following a shutdown greater than 120 days while SR 3.1.4.4 requires scram time testing to be conducted following work on the CRD system or following fuel movement within the affected core cell. Both SRs must be performed at reactor steam dome pressure greater than or equal to 800 psig and prior to exceeding 40 percent rated thermal power (RTP). |
| | The Duane Arnold Nuclear Plant TS contain cross references and nomenclatures that are slightly different from the STS. Duane Arnold Nuclear Plant TS contain SR 3.1.4.1 and SR 3.1.4.2 that are equivalent to STS SR 3.1.4.1 and SR 3.1.4.4 that are discussed above. |
| | TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, would modify LCO 3.10.1 to allow SR 3.1.4.1 and SR 3.1.4.2 to be conducted in Mode 4 with average reactor coolant temperature greater than 212oF. Scram time testing would be performed in accordance with LCO 3.10.4, Single Control Rod Withdrawal - Cold Shutdown. This modification to LCO 3.10.1 does not alter the means of compliance with Criterion 10 of Appendix A to 10 CFR Part 50. |
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| ==7.0REFERENCES== | | ==3.0 TECHNICAL EVALUATION== |
| 1.NUREG-1433, "General Electric Plants, BWR/4, Revision 3, Standard TechnicalSpecifications (STS)", August 31, 20032.NUREG-1434, General Electric Plants, BWR/6, Revision 3, Standard TechnicalSpecifications (STS)", August 31, 20033.Request for Additional Information (RAI) Regarding TSTF-484, April, 7, 2006, ADAMSaccession number ML060970568 4.Response to NRC RAIs Regarding TSTF-484, June 5, 2006, ADAMS accession numberML061560523 5.TSTF-484 Revision 0, "Use of TS 3.10.1 for Scram Times Testing Activities", May 5,2005, ADAMS accession number ML0529301026.TSTF Response to NRC Notice for Comment, September 20, 2006, ADAMS accessionnumber ML062650171 Principal Contributor: Aron LewinDate: October 25, 2006}} | | |
| | The existing provisions of LCO 3.10.1 allow for hydrostatic and leakage testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212oF, while imposing Mode 3 secondary containment requirements. Under the existing provision, LCO 3.10.1 would have to be implemented prior to hydrostatic and leakage testing. As a result, if LCO 3.10.1 was not implemented prior to hydrostatic and leakage testing, hydrostatic and leakage testing would have to be terminated if average reactor coolant temperature exceeded 212oF during the conduct of the hydrostatic and leakage test. TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, modifies LCO 3.10.1 to allow a licensee to implement LCO 3.10.1, while hydrostatic and leakage testing is being conducted, should average reactor coolant temperature exceed 212oF during testing. The modification will allow completion of testing without the potential for interrupting the test in order to reduce reactor vessel pressure, cool the RCS, and restart the test below 212oF. Since the current LCO 3.10.1 allows testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212oF, the proposed change does not introduce any new operational conditions beyond those currently allowed. |
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| | SR 3.1.4.1 and SR 3.1.4.2 require that control rod scram time be tested at reactor steam dome pressure greater than or equal to 800 psig and before exceeding 40 percent rated thermal power (RTP). Performance of control rod scram time testing is typically scheduled concurrent with inservice leak or hydrostatic testing while the RCS is pressurized. Because of the number of control rods that must be tested, it is possible for the inservice leak or hydrostatic test to be completed prior to completing the scram time test. Under existing provisions, if scram time testing can not be completed during the LCO 3.10.1 inservice leak or hydrostatic test, scram time testing must be suspended. Additionally, if LCO 3.10.1 is not implemented and average reactor coolant temperature exceeds 212oF while performing the scram time test, scram time testing must also be suspended. In both situations, scram time testing is resumed during startup and is completed prior to exceeding 40 percent RTP. TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, modifies LCO 3.10.1 to allow a licensee to complete scram time testing initiated during inservice leak or hydrostatic testing. As stated earlier, since the current LCO 3.10.1 allows testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212oF, the proposed change does not introduce any new operational conditions beyond those currently allowed. Completion of scram time testing prior to reactor criticality and power operations results in a more conservative operating philosophy with attendant potential safety benefits. |
| | It is acceptable to perform other testing concurrent with the inservice leak or hydrostatic test provided that this testing can be performed safely and does not interfere with the leak or hydrostatic test. However, it is not permissible to remain in TS 3.10.1 solely to complete such testing following the completion of inservice leak or hydrostatic testing and scram time testing. |
| | Since the tests are performed with the reactor pressure vessel (RPV) nearly water solid, at low decay heat values, and near Mode 4 conditions, the stored energy in the reactor core will be very low. Small leaks from the RCS would be detected by inspections before a significant loss of inventory occurred. In addition, two low-pressure emergency core cooling systems (ECCS) injection/spray subsystems are required to be operable in Mode 4 by TS 3.5.2, ECCS-Shutdown. In the event of a large RCS leak, the RPV would rapidly depressurize and allow operation of the low pressure ECCS. The capability of the low pressure ECCS would be adequate to maintain the fuel covered under the low decay heat conditions during these tests. |
| | Also, LCO 3.10.1 requires that secondary containment and standby gas treatment system be operable and capable of handling any airborne radioactivity or steam leaks that may occur during performance of testing. |
| | The protection provided by the normally required Mode 4 applicable LCOs, in addition to the secondary containment requirements required to be met by LCO 3.10.1, minimizes potential consequences in the event of any postulated abnormal event during testing. In addition, the requested modification to LCO 3.10.1 does not create any new modes of operation or operating conditions that are not currently allowed. Therefore, the staff finds the proposed change acceptable. |
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| | ==4.0 STATE CONSULTATION== |
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| | In accordance with the Commissions regulations, the Iowa State official was notified of the proposed issuance of the amendment. The State official had [no] comments. [If comments were provided, they should be addressed here]. |
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| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
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| | The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding issued on [Date] ([ ] FR [ ]) . Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment. |
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| | ==6.0 CONCLUSION== |
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| | The Commission has concluded, based on the considerations discussed above, that: (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 be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. |
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| | ==7.0 REFERENCES== |
| | : 1. NUREG-1433, General Electric Plants, BWR/4, Revision 3, Standard Technical Specifications (STS), August 31, 2003 |
| | : 2. NUREG-1434, General Electric Plants, BWR/6, Revision 3, Standard Technical Specifications (STS), August 31, 2003 |
| | : 3. Request for Additional Information (RAI) Regarding TSTF-484, April, 7, 2006, ADAMS accession number ML060970568 |
| | : 4. Response to NRC RAIs Regarding TSTF-484, June 5, 2006, ADAMS accession number ML061560523 |
| | : 5. TSTF-484 Revision 0, Use of TS 3.10.1 for Scram Times Testing Activities, May 5, 2005, ADAMS accession number ML052930102 |
| | : 6. TSTF Response to NRC Notice for Comment, September 20, 2006, ADAMS accession number ML062650171 Principal Contributor: Aron Lewin Date: October 25, 2006}} |
Letter Sequence Other |
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TAC:MD0293, Use of TS 3.10.1 for SCRAM Time Testing Activities (Approved, Closed) |
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MONTHYEARNG-06-0250, Technical Specification Change Request (TSCR-078): Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities, Affected Technical Specifications: Section 3.10.12006-03-0101 March 2006
Technical Specification Change Request (TSCR-078): Adoption of TSTF-484, Rev. 0, Use of TS 3.10.1 for Scram Time Testing Activities, Affected Technical Specifications: Section 3.10.1
Project stage: Other
ML0619906342006-07-24024 July 2006
RAI, Proposed Amendment to Revise the Limiting Condition for Operation 3.10.1
Project stage: RAI
NG-06-0516, Response to Request for Additional Information Related to Proposed Amendment to Revise Limiting Condition for Operation 3.10.12006-08-17017 August 2006
Response to Request for Additional Information Related to Proposed Amendment to Revise Limiting Condition for Operation 3.10.1
Project stage: Response to RAI
ML0629903782006-11-0202 November 2006
TSTF-484 LAR SE
Project stage: Other
ML0703804842007-02-0505 February 2007
Technical Specification, System Leakage and Hydrostatic Testing Operation
Project stage: Other
ML0635204082007-02-0505 February 2007
Issuance of Amendment, System Leakage and Hydrostatic Testing Operation
Project stage: Approval
2006-07-24
[Table View] |
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Category:Memoranda
MONTHYEARML22040A2752022-02-11011 February 2022
NSIR Staff Review of the Duane Arnold Energy Center Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, for the Verification of ASM EA-02-104 Incorporation
ML21062A0932021-04-21021 April 2021
Memo to File: Final Ea/Fonsi of 2012 and 2015 Decommissioning Funding Plans for Duane Arnold Energy Center Independent Spent Fuel Storage Installation (2012 and 2015)
ML21078A1272021-03-30030 March 2021
Final-LIC-504 Closure Memo - 03/30/2021
ML20315A1172020-12-25025 December 2020
DAEC-LIC504-Immediate-Determination-11-02
ML20233A7902020-08-20020 August 2020
Summary of the July 30, 2020, Public Webinar to Discuss the NRC 2019 End-Of-Cycle Plant Performance Assessment of the Duane Arnold Energy Center and the Point Beach Nuclear Plant
ML17115A0782017-04-24024 April 2017
Summary of Outreach/Open House to Discuss the NRC 2016 End-Of-Cycle Plant Performance Assessment of the Duane Arnold Energy Center
ML16313A0742016-11-0808 November 2016
NextEra Audit Plan Nov 2016 (DAEC SFP Criticality LAR)
ML16225A6772016-08-11011 August 2016
FEMA Letter Dated August 11, 2016, Regarding Approval of Boundary Change for the Duane Arnold Energy Center 10-mile Emergency Planning Zone for Linn County, Iowa
ML16088A2042016-03-28028 March 2016
Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template)
ML16088A2052016-03-28028 March 2016
Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations
ML14104A9272014-04-23023 April 2014
U.S. Nuclear Regulatory Commission Staff'S Spot-Check Review of Corn Belt Power Cooperative'S 10 Percent Ownership Interest in Duane Arnold Energy Center, Docket No. 50-331, on April 9, 2014 -Finding of No Potential Issues
ML14104A9032014-04-23023 April 2014
U.S. Nuclear Regulatory Commission Staff'S Spot-Check Review of Central Iowa Power Cooperative'S 20 Percent Ownership Interest in Duane Arnold Energy Center, Docket No. 50-331, on April 10, 2014- Finding of No Potential Issues
ML13309A0802013-12-11011 December 2013
Memorandum to File: Transcript for 10 CFR 2.206 Petition from Beyond Nuclear (Et Al) Regarding General Electric Mark I and Mark II Boiling-Water Reactors
ML13154A5112013-06-0404 June 2013
Rai'S Following Ifib Analysis of NextEra Energy'S 2013 Decommissioning Funding Status Reports for Duane Arnold Energy Center and Point Beach Units 1 and 2
ML11250A1712011-09-14014 September 2011
Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs)
ML11126A0962011-05-12012 May 2011
Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors
ML1106104272011-03-0707 March 2011
Notice of Forthcoming Pre-Application Meeting with Florida Power & Light Company and NextEra Energy Regarding Turkey Point, Units 3 and 4, St. Lucie, Units 1 and 2, Point Beach, Units 1, and 2, and Duane Arnold
ML1027301332010-10-0707 October 2010
Filing of Federal Register Notice of Availability for the Final Plant-Specific Supplement 42 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants (GEIS) Regarding Duane Arnold Energy Center
ML1025301122010-09-10010 September 2010
Minutes for the Meeting of the Duane Arnold Plant License Renewal Subcommittee, June 8, 2010 - Rockville, MD
ML1023805222010-09-0202 September 2010
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RAI, MD7420- Draft - Request for Additional Information
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TSTF-484 LAR SE
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All Region III Facility Training Managers Revised NRC Form 398 - Personal Qualification Statement Licensee
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Transmittal of Draft Request for Additional Information on Proposed Amendment to Change Pressure-Temperature Limit Curves
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[Table view]
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Text
November 2, 2006 MEMORANDUM TO: Martin Murphy, Acting Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: Timothy Kobetz, Chief /RA/
Technical Specifications Branch Division of Inspections and Regional Support Office of Nuclear Reactor Regulation
SUBJECT:
DUANE ARNOLD NUCLEAR PLANT - STAFFS REVIEW OF THE ADOPTION OF TSTF-484, REV. 0, USE OF TS 3.10.1 FOR SCRAM TIME TESTING ACTIVITIES TECHNICAL SPECIFICATION AMENDMENT (TAC NO. MD0293)
By letter dated March 01, 2006 (ML060720038), FPL Energy Duane Arnold, LLC (the licensee) submitted a license amendment request (LAR) regarding Duane Arnold Nuclear Plant system leakage and hydrostatic testing operation technical specifications (TSs). The proposed amendment would revise the existing system leakage and hydrostatic testing operation TS to be consistent with the U.S. Nuclear Regulatory Commissions approved Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-484, Use of TS 3.10.1 for Scram Time Testing Activities, Revision 0. TSTF-484 is part of the consolidated line item improvement process (CLIIP).
The staff of the Technical Specifications Branch (ITSB) of the Division of Inspections and Regional Support (DIRS) has completed its review of the LAR. The staffs review is enclosed.
Docket No.: 50-331
Enclosure:
Staff Safety Evaluation CONTACTS: Aron Lewin, ITSB/DIRS 301-415-2259
ML062990378 OFFICE ITSB:DIRS BC:ITSB:DIRS NAME ALewin TKobetz DATE 10/26/2006 11/2/06 STAFF SAFETY EVALUATION DUANE ARNOLD NUCLEAR PLANT SYSTEM LEAKAGE AND HYDROSTATIC TESTING OPERATION TECHNICAL SPECIFICATION AMENDMENT TAC NO. MD0293 DOCKET NO. 50-331
1.0 INTRODUCTION
By application dated March 01, 2006, (Agencywide Documents Access and Management System Accession No. ML060720038) FPL Energy Duane Arnold, LLC (the licensee) requested changes to the Technical Specifications (TS) for the Duane Arnold Nuclear Plant.
The proposed changes would revise Limiting Condition for Operation (LCO) 3.10.1, and the associated Bases, to expand its scope to include provisions for temperature excursions greater than 212oF as a consequence of inservice leak and hydrostatic testing, and as a consequence of scram time testing initiated in conjunction with an inservice leak or hydrostatic test, while considering operational conditions to be in Mode 4.
2.0 REGULATORY EVALUATION
2.1 Inservice Leak and Hydrostatic Testing The Reactor Coolant System (RCS) serves as a pressure boundary and also serves to provide a flow path for the circulation of coolant past the fuel. In order to maintain RCS integrity,Section XI of the American Society of Mechanical Engineers (ASME) Pressure Vessel Code requires periodic hydrostatic and leakage testing. Hydrostatic tests are required to be performed once every ten years and leakage tests are required to be performed each refueling outage. Appendix G to 10 CFR Part 50 states that pressure tests and leak tests of the reactor vessel that are required by Section XI of the American Society of Mechanical Engineers (ASME) Pressure Vessel Code must be completed before the core is critical.
NUREG-1433, General Electric Plants, BWR/4, Revision 3, Standard Technical Specifications (STS) and NUREG-1434, General Electric Plants, BWR/6, Revision 3, STS both currently contain LCO 3.10.1, Inservice Leak and Hydrostatic Testing Operation. LCO 3.10.1 was created to allow for hydrostatic and leakage testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212oF provided certain secondary containment LCOs are met.
TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, modifies LCO 3.10.1 to allow a licensee to implement LCO 3.10.1, while hydrostatic and leakage testing is being conducted, should average reactor coolant temperature exceed 212oF during testing.
This modification does not alter current requirements for hydrostatic and leakage testing as required by Appendix G to 10 CFR Part 50.
2.2 CONTROL ROD SCRAM TIME TESTING Control rods function to control reactor power level and to provide adequate excess negative reactivity to shut down the reactor from any normal operating or accident condition at any time during core life. The control rods are scrammed by using hydraulic pressure exerted by the control rod drive (CRD) system. Criterion 10 of Appendix A to 10 CFR Part 50 states that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. The scram reactivity used in design basis accidents (DBA) and transient analyses is based on an assumed control rod scram time.
NUREG-1433, General Electric Plants, BWR/4, Revision 3, STS and NUREG-1434, General Electric Plants, BWR/6, Revision 3, STS both currently contain surveillance requirements (SR) to conduct scram time testing when certain conditions are met in order to ensure that Criterion 10 of Appendix A to 10 CFR Part 50 is satisfied. SR 3.1.4.1 requires scram time testing to be conducted following a shutdown greater than 120 days while SR 3.1.4.4 requires scram time testing to be conducted following work on the CRD system or following fuel movement within the affected core cell. Both SRs must be performed at reactor steam dome pressure greater than or equal to 800 psig and prior to exceeding 40 percent rated thermal power (RTP).
The Duane Arnold Nuclear Plant TS contain cross references and nomenclatures that are slightly different from the STS. Duane Arnold Nuclear Plant TS contain SR 3.1.4.1 and SR 3.1.4.2 that are equivalent to STS SR 3.1.4.1 and SR 3.1.4.4 that are discussed above.
TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, would modify LCO 3.10.1 to allow SR 3.1.4.1 and SR 3.1.4.2 to be conducted in Mode 4 with average reactor coolant temperature greater than 212oF. Scram time testing would be performed in accordance with LCO 3.10.4, Single Control Rod Withdrawal - Cold Shutdown. This modification to LCO 3.10.1 does not alter the means of compliance with Criterion 10 of Appendix A to 10 CFR Part 50.
3.0 TECHNICAL EVALUATION
The existing provisions of LCO 3.10.1 allow for hydrostatic and leakage testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212oF, while imposing Mode 3 secondary containment requirements. Under the existing provision, LCO 3.10.1 would have to be implemented prior to hydrostatic and leakage testing. As a result, if LCO 3.10.1 was not implemented prior to hydrostatic and leakage testing, hydrostatic and leakage testing would have to be terminated if average reactor coolant temperature exceeded 212oF during the conduct of the hydrostatic and leakage test. TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, modifies LCO 3.10.1 to allow a licensee to implement LCO 3.10.1, while hydrostatic and leakage testing is being conducted, should average reactor coolant temperature exceed 212oF during testing. The modification will allow completion of testing without the potential for interrupting the test in order to reduce reactor vessel pressure, cool the RCS, and restart the test below 212oF. Since the current LCO 3.10.1 allows testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212oF, the proposed change does not introduce any new operational conditions beyond those currently allowed.
SR 3.1.4.1 and SR 3.1.4.2 require that control rod scram time be tested at reactor steam dome pressure greater than or equal to 800 psig and before exceeding 40 percent rated thermal power (RTP). Performance of control rod scram time testing is typically scheduled concurrent with inservice leak or hydrostatic testing while the RCS is pressurized. Because of the number of control rods that must be tested, it is possible for the inservice leak or hydrostatic test to be completed prior to completing the scram time test. Under existing provisions, if scram time testing can not be completed during the LCO 3.10.1 inservice leak or hydrostatic test, scram time testing must be suspended. Additionally, if LCO 3.10.1 is not implemented and average reactor coolant temperature exceeds 212oF while performing the scram time test, scram time testing must also be suspended. In both situations, scram time testing is resumed during startup and is completed prior to exceeding 40 percent RTP. TSTF-484, Revision 0, Use of TS 3.10.1 for Scram Time Testing Activities, modifies LCO 3.10.1 to allow a licensee to complete scram time testing initiated during inservice leak or hydrostatic testing. As stated earlier, since the current LCO 3.10.1 allows testing to be conducted while in Mode 4 with average reactor coolant temperature greater than 212oF, the proposed change does not introduce any new operational conditions beyond those currently allowed. Completion of scram time testing prior to reactor criticality and power operations results in a more conservative operating philosophy with attendant potential safety benefits.
It is acceptable to perform other testing concurrent with the inservice leak or hydrostatic test provided that this testing can be performed safely and does not interfere with the leak or hydrostatic test. However, it is not permissible to remain in TS 3.10.1 solely to complete such testing following the completion of inservice leak or hydrostatic testing and scram time testing.
Since the tests are performed with the reactor pressure vessel (RPV) nearly water solid, at low decay heat values, and near Mode 4 conditions, the stored energy in the reactor core will be very low. Small leaks from the RCS would be detected by inspections before a significant loss of inventory occurred. In addition, two low-pressure emergency core cooling systems (ECCS) injection/spray subsystems are required to be operable in Mode 4 by TS 3.5.2, ECCS-Shutdown. In the event of a large RCS leak, the RPV would rapidly depressurize and allow operation of the low pressure ECCS. The capability of the low pressure ECCS would be adequate to maintain the fuel covered under the low decay heat conditions during these tests.
Also, LCO 3.10.1 requires that secondary containment and standby gas treatment system be operable and capable of handling any airborne radioactivity or steam leaks that may occur during performance of testing.
The protection provided by the normally required Mode 4 applicable LCOs, in addition to the secondary containment requirements required to be met by LCO 3.10.1, minimizes potential consequences in the event of any postulated abnormal event during testing. In addition, the requested modification to LCO 3.10.1 does not create any new modes of operation or operating conditions that are not currently allowed. Therefore, the staff finds the proposed change acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Iowa State official was notified of the proposed issuance of the amendment. The State official had [no] comments. [If comments were provided, they should be addressed here].
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding issued on [Date] ([ ] FR [ ]) . Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (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 be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1. NUREG-1433, General Electric Plants, BWR/4, Revision 3, Standard Technical Specifications (STS), August 31, 2003
- 2. NUREG-1434, General Electric Plants, BWR/6, Revision 3, Standard Technical Specifications (STS), August 31, 2003
- 3. Request for Additional Information (RAI) Regarding TSTF-484, April, 7, 2006, ADAMS accession number ML060970568
- 4. Response to NRC RAIs Regarding TSTF-484, June 5, 2006, ADAMS accession number ML061560523
- 5. TSTF-484 Revision 0, Use of TS 3.10.1 for Scram Times Testing Activities, May 5, 2005, ADAMS accession number ML052930102
- 6. TSTF Response to NRC Notice for Comment, September 20, 2006, ADAMS accession number ML062650171 Principal Contributor: Aron Lewin Date: October 25, 2006
