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Category:Letter
MONTHYEARIR 05000317/20230042024-02-0101 February 2024 Integrated Inspection Report 05000317/2023004 and 05000318/2023004 ML24029A0102024-01-29029 January 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000317/2024010 and 05000318/2024010 ML24003A8872024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0033 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000318/LER-2023-004, Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-16016 January 2024 Submittal of LER 2023-004-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Submittal of Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer ML24011A0732024-01-11011 January 2024 Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping 05000318/LER-2023-002, Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer2024-01-0808 January 2024 Forward LER 2023-002-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Automatic Reactor Trip from Reactor Protection System Actuation Due to Loss of Unit Service Transformer 05000318/LER-2023-003, Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip2024-01-0808 January 2024 Forward LER 2023-003-00 for Calvert Cliffs Nuclear Power Plant, Unit 2, Manual Actuation of Auxiliary Feedwater System Due to 22 Steam Generator Feedwater Pump Trip ML24005A0222024-01-0505 January 2024 Revised Steam Generator Tube Inspection Reports ML23304A0642024-01-0202 January 2024 Issuance of Amendment No. 349 to Modify the Long-Term Coupon Surveillance Program RS-23-125, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) ML23331A2992023-11-27027 November 2023 Submittal of Condition Prohibited by Technical Specifications Due to Failure to Sample Diesel Generator Fuel Oil Storage Tank IR 05000317/20230102023-11-20020 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000317/2023010 and 05000318/2023010 ML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums ML23310A0442023-11-0707 November 2023 Project Manager Assignment IR 05000317/20230402023-11-0202 November 2023 95001 Supplemental Inspection Report 05000317/2023040 and Follow-Up Assessment Letter IR 05000317/20230032023-11-0101 November 2023 Integrated Inspection Report 05000317/2023003 and 05000318/2023003 IR 05000317/20230902023-10-26026 October 2023 Final Significance Determination of a White Finding with Assessment Follow-Up and Notice of Violation; Inspection Report 05000317/2023090 ML23289A1202023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML23279A1202023-10-0606 October 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000317/20230502023-09-29029 September 2023 Special Inspection Report 05000317/2023050 and Preliminary White Finding and Apparent Violation ML23272A1032023-09-29029 September 2023 Condition Prohibited by Technical Specifications Due to Inoperable Nuclear Instrumentation at Very Low Power IR 05000317/20234012023-09-18018 September 2023 Cyber Security Inspection Report 05000317/2023401 and 05000318/2023401 ML23254A0012023-09-0505 September 2023 Registration of Use of Casks to Store Spent Fuel IR 05000317/20230052023-08-31031 August 2023 Updated Inspection Plan for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Report 05000317/2023005 and 05000318/2023005) ML23158A1952023-08-30030 August 2023 R. E. Ginna - Issuance of Amendments to Adopt TSTF-273-A, Revision 2, Safety Function Determination Program Clarifications ML23241A8412023-08-29029 August 2023 Response to Request for Additional Information - Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping ML23240A3872023-08-28028 August 2023 Senior Reactor and Reactor Operator Initial License Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23219A1662023-08-16016 August 2023 Request for Additional Information Regarding Proposed Alternative to the Requirements for Repair/Replacement of Saltwater (SW) System Buried Piping (EPID: L-2023-LLR-0006) - Non-proprietary ML23228A1002023-08-15015 August 2023 Notification of Readiness for NRC 95001 Inspection ML23188A0402023-08-0808 August 2023 Issuance of Amendment Nos. 346 and 324 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23214A1572023-08-0707 August 2023 Correction to the Renewed Facility Operating License Page 3 in Amendment No 345 IR 05000317/20230022023-08-0303 August 2023 Integrated Inspection Report 05000317/2023002 ML23188A0512023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 336 and 314 ML23186A0372023-07-13013 July 2023 Correction to the Renewed Facility Operating License Pages in Amendment Nos. 340 and 318 IR 05000317/20233012023-07-12012 July 2023 Initial Operator Licensing Examination Report 05000317/2023301 and 05000318/2023301 IR 05000317/20230122023-07-10010 July 2023 Commercial Grade Dedication Report 05000317/2023012 and 05000318/2023012 ML23180A2362023-06-29029 June 2023 Correction of Errors on Technical Specification Pages RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators ML23156A6752023-06-20020 June 2023 Request for Withholding Information from Public Disclosure for Proposed Alternative to the Requirements for Repair/Replacement of Saltwater System Buried Piping 2024-02-01
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML23318A4722023-11-14014 November 2023 Supplement to License Amendment Request to Adopt TSTF-59-A ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration ML23164A1702023-06-13013 June 2023 License Amendment Request to Adopt TSTF-59-A, Incorporate (Combustion Engineering) NPSD-994 Recommendations Into the (Safety Injection Tanks) Specification, Revision 1 ML23153A0982023-06-0202 June 2023 Emergency License Amendment Request - One-Time Extension of the Control Room Emergency Ventilation System (CREVS) Technical Specification RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23052A0632023-02-21021 February 2023 License Amendment Request to Modify the Long-Term Coupon Surveillance Program ML22298A0112022-10-25025 October 2022 License Amendment Request to Adopt Technical Specification Task Force TSTF-295-A, Modify Note 2 to Actions of (Post-Accident Monitoring) PAM Table To. RS-22-086, R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam.2022-08-10010 August 2022 R. E. Ginna Nuclear Power Plant - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam. RS-22-017, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions for Calvert Cliffs2022-04-20020 April 2022 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions for Calvert Cliffs ML22067A0772022-03-31031 March 2022 Correction of License Amendment Nos. 337 and 315 to Revise Response Time Testing Definition RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments ML20329A3342020-11-24024 November 2020 Application to Revise Technical Specifications to Adopt TSTF-567 Rev 1, Add Containment Sump TS to Address GSI-191 Issues ML19347A7792019-12-12012 December 2019 License Amendment Request to Utilize Accident Tolerant Fuel Lead Test Assemblies ML19346E5362019-12-11011 December 2019 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Emergency Diesel Generator Surveillance Requirements for Frequency and Voltage Tolerances RS-19-092, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions2019-12-0909 December 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definitions ML19325C1282019-11-21021 November 2019 License Amendment Request - Revision to Technical Specification 5.5.7, Reactor Coolant Pump Flywheel Inspection Program RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19127A0762019-05-0606 May 2019 Application to Revise Technical Specifications to Adopt TSTF-490, Deletion of E-Bar Definition and Revision to RCS Specific Activity Tech Spec ML18333A0222018-11-28028 November 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors. ML18235A1992018-08-23023 August 2018 License Amendment Request: 10 CFR 50.90 Proposed Changes to Technical Specification (TS) 3.8.1 Actions A.3 and D.3 to Extend the Offsite Circuit Inoperable Completion Times from 72 Hours to ... ML18113A0902018-04-20020 April 2018 Administrative Change to Technical Specification 5.2.2, Unit Staff RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) ML17164A1432017-05-31031 May 2017 Enclosure 2C - EAL Basis Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1412017-05-31031 May 2017 Enclosure 2A - EAL Comparison Matrix Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1422017-05-31031 May 2017 Enclosure 2B - EAL Red-Line Basis Document for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17164A1452017-05-31031 May 2017 Enclosure 2E - Procedure Matrix for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 ML17087A3742017-03-28028 March 2017 License Amendment Request, Refueling Water Tank RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16266A0862016-09-22022 September 2016 License Amendment Request - Control Room Emergency Ventilation System ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16060A2232016-02-25025 February 2016 License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. ML16035A2272016-02-0404 February 2016 License Amendment Request - Change to Surveillance Requirement 3.5.3.1 ML15310A0642015-11-0505 November 2015 License Amendment Request to Relocate Surveillance Frequency Requirements ML15212A9022015-07-30030 July 2015 Supplemental Information Regarding TSTF-425 License Amendment Request ML15210A3142015-07-29029 July 2015 License Amendment Request to Revise the Emergency Plan Requalification Training Frequency for Emergency Response Organization Personnel RA-14-057, License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 82014-08-29029 August 2014 License Amendment Request Regarding the Cyber Security Plan Implementation Schedule for Milestone 8 ML14050A3742014-02-13013 February 2014 License Amendment Request Re Pressurizer Safety Valve Technical Specification Revision ML14050A3752014-02-13013 February 2014 Summary of Analysis Supporting Pressurizer Safety Valve Technical Change ML14015A1382014-01-13013 January 2014 License Amendment Request: Add Technical Specification for Atmospheric Dump Valves ML13308A3872013-10-31031 October 2013 Application for Technical Specification Improvement to Adopt TSTF-510-A, Revision 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection. ML13228A2652013-08-14014 August 2013 Independent Spent Fuel Storage Installations Application for Preemption Authority Pursuant to Section 161A of the Atomic Energy Act & License Amendment Request ML13232A1562013-08-0606 August 2013 ISFSI, Nine Mile Point, Units 1, 2 and ISFSI and R.E. Ginna, and ISFSI, Application for Order Approving Transfer of Operating Authority and Conforming License Amendments. Part 1 of 2 ML13030A1332013-01-28028 January 2013 License Amendment Request Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML13029A4562013-01-22022 January 2013 Emergency License Amendment Request: Revise Description of Operable Containment Air Cooling Train ML11222A0202011-08-0808 August 2011 License Amendment Request: Diesel Generator Surveillance Requirement 3.8.1.11 Revision 2023-08-21
[Table view] |
Text
T George H. Gellrich Calvert Cliffs Nuclear Power Plant, LLC Vice President 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410.495.5200 410.495.3500 Fax CENG.
a joint venture of Constellation CALVERT CLIFFS NUCLEAR POWER PLANT May 11,2011 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 License Amendment Request: Technical Specification 3.3.1 Revision Pursuant to 10 CFR 50.90, Calvert Cliffs Nuclear Power Plant, LLC (Calvert Cliffs) requests an administrative amendment to the Renewed Operating License Nos. DPR-53 and DPR-69 for Calvert Cliffs Unit Nos. I and 2, respectively that revises Technical Specification 3.3.1, Reactor Protective System (RPS) Instrumentation-Operating. The proposed amendment corrects the unit of measure listed in a table within Technical Specification 3.3.1.
The significant hazards discussion and the technical basis for this proposed amendment are provided in Attachment (1). The marked up page of the affected Technical Specification is provided in Attachment (2).
Calvert Cliffs requests approval of this proposed amendment by April 15, 2012 along with an implementation period of 45 days.
Document Control Desk May 11, 2011 Page 2 Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.
Very truly yours, STATE OF MARYLAND TO WIT:
COUNTY OF CALVERT I, George H. Gellrich, being duly sworn, state that I am Vice President - Calvert Cliffs Nuclear Power Plant, LLC (CCNPP), and that I am duly authorized to execute and file this License Amendment Request on behalf of CCNPP. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other CCNPP employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.
Subscribed and sworn before me, a Notary Public in and for the State of Maryland and County of t*
/*O*, ,this /f*-day of M V ,2011.
WITNESS my Hand and Notarial Seal:
Notary Publi,*/
My Commission Expires: *%bCA /*Date2O/*
Date GHG/KLG/bjd Attachments: (1) Evaluation of the Proposed Change (2) Marked Up Technical Specification Page
Document Control Desk May 11, 2011 Page 3 cc: D. V. Pickett, NRC Resident Inspector, NRC W. M. Dean, NRC S. Gray, DNR
ATTACHMENT (1)
EVALUATION OF THE PROPOSED CHANGE TABLE OF CONTENTS 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 4.2 Significant Hazards Consideration 4.3 Conclusions
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
Calvert Cliffs Nuclear Power Plant, LLC May 11, 2011
ATTACHMENT (1)
EVALUATION OF THE PROPOSED CHANGE 1.0
SUMMARY
DESCRIPTION This evaluation supports a request to modify a note within Technical Specification 3.3.1, Reactor Protective System (RPS) Instrumentation-Operating, that incorrectly lists the unit of measure as psig (pounds per square inch gauge) vice psia (pounds per square inch absolute). The proposed change will revise note (c) located within Table 3.3.1-1, to indicate the value at which the RPS trip function, Steam Generator Pressure-Low, is bypassed at 785 psia vice 785 psig.
2.0 DETAILED DESCRIPTION Note (c) within Table 3.3.1-1 of Technical Specification 3.3.1 currently states:
(c) Bistable trip unit may be bypassed when steam generator pressure is < 785 psig. Bypass shall be automatically removed when steam generator pressure is > 785 psig.
The proposed change would revise note (c) within Table 3.3.1-1 of Technical Specification 3.3.1 to read:
(c) Bistable trip unit may be bypassed when steam generator pressure is < 785 psia. Bypass shall be automatically removed when steam generator pressure is > 785 psia.
The proposed change to change the unit of measure to psia will align the note with other Technical Specifications and other site governing documents and operating practices associated with this RPS function. Since this proposed change does not have any effect on any other existing site governing document, procedure, or site instruction, this change therefore is considered to be administrative in nature.
3.0 TECHNICAL EVALUATION
The Calvert Cliffs RPS contains the necessary instrumentation and equipment to monitor selected Nuclear Steam Supply System parameters and initiate protective action if any of these parameters exceed an operational limit by either annunciating alarms, prohibiting control element assembly motion or tripping the reactor. The RPS is designed to ensure safe operation of the reactor through the establishment of limiting safety system settings that ensure safety limits are not exceeded during normal operations or anticipated operational occurrences. One of the RPS functions is the Steam Generator Pressure-Low Trip.
The Steam Generator Pressure-Low trip provides protection against an excessive rate of heat extraction from the steam generators, which would result in a rapid uncontrolled cooldown of the Reactor Coolant System as the result of a main steam line break accident. The Steam Generator Pressure-Low instrumentation also has an operating bypass circuitry that allows this trip function to be manually bypassed when steam generator pressure is reduced during startup and shutdown operating conditions.
The bypass is automatically removed when steam generator pressure is raised above the pretrip setpoint.
The steam generator pressure instrumentation for this RPS trip function has its trip and pretrip setpoint and bypass value established, and tested using psia as the unit of measure. This proposed change revises Technical Specification 3.3.1 to reflect this practice.
Table 7-1 of Calvert Cliffs Updated Final Safety Analysis Report includes a note that states for Steam Generator Pressure-Low RPS function "manual inhibit permitted below 785 psia: automatically removed above 785 psia." This proposed change brings the note in Technical Specification 3.3.1 in alignment with the Updated Final Safety Analysis Report.
A review of previous revisions of Calvert Cliffs Technical Specifications showed that prior to Calvert Cliffs adoption of the industry's Standard Technical Specifications, our equivalent note to the current note (c) of Technical Specification 3.3.1 used psia as the unit of measure. Calvert Cliffs adopted the Standard Technical Specification version of note (c) for this Technical Specification which used psig as I
ATTACHMENT (1)
EVALUATION OF THE PROPOSED CHANGE the unit of measure. It is important to note that Calvert Cliffs Technical Specification Table 3.3.4-1
[within Technical Specification 3.3.4, Engineered Safety Features Actuation System (ESFAS)
Instrumentation] contains the exact same note as in Table 3.3.1-1, however the note in Table 3.3.4-1 lists psia as the unit of measure. These items further support that the change to psig within note (c) of Table 3.3.1-1 was an administrative error that occurred during Calvert Cliffs conversion to the Standard Technical Specifications. Although the note (c) of Table 3.3-1-1 was changed to psig, the units continued to operate and test the trip and pre-trip setpoints and bypass valve using psia.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria The proposed change to Technical Specification 3.3.1 is administrative in nature and as such does not alter Calvert Cliffs Reactor Protective System's ability to meet all applicable regulatory requirements.
4.2 Significant Hazards Consideration Calvert Cliffs Nuclear Power Plant (Calvert Cliffs) is proposing a revision to Technical Specification 3.3.1. The proposed administrative change would correct the unit of measure listed in note (c) of Table 3.3.1-1 to read psia vice psig. This would align Technical Specification 3.3.1 with other Technical Specifications and other site governing documents and operating practices associated with Calvert Cliffs Reactor Protective System Steam Generator Pressure-Low trip function.
Calvert Cliffs has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92 "issuance of amendment" as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accidentpreviously evaluated?
Response: No.
The proposed administrative change to correct the unit of measure listed in note (c) of Technical Specification 3.3.1 to read psia vice psig does not affect any analyzed accident initiators, nor does it affect the unit's ability to successfully respond to any previously evaluated accident. In addition the proposed does not change the operation or maintenance that is performed on plant equipment.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accidentfrom any accident previously evaluated?
Response: No.
The proposed administrative change corrects the unit of measure listed in note (c) of Technical Specification 3.3.1 to read psia vice psig. The proposed change does not involve a physical alteration to the plant (no new or different type of equipment will be installed) or a change in the methods governing normal plant operation.
Therefore it is concluded that the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
2
ATTACHMENT (1)
EVALUATION OF THE PROPOSED CHANGE
- 3. Does the proposed amendment involve a significantreduction in a margin of safety?
Response: No.
The proposed administrative change corrects the unit of measure listed in note (c) of Technical Specification 3.3.1 to read psia vice psig. Since this is an administrative change the safety functions of plant equipment and their response to any analyzed accident scenario are unaffected by this proposed change and thus there is no reduction in any margin of safety.
Therefore the proposed change does not involve a significant reduction in the margin of safety for the operation of each unit.
Based on the above, Calvert Cliffs concludes that the proposed amendment change does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding or "no significant hazards consideration" is justified.
4.3 Conclusions In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will 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.
5.0 ENVIRONMENTAL CONSIDERATION
Calvert Cliffs review has determined that the proposed amendment only makes a minor administrative correction to Calvert Cliffs Technical Specifications. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10)(v). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
None 3
ATTACHMENT (2)
MARKED UP TECHNICAL SPECIFICATION PAGE Calvert Cliffs Nuclear Power Plant, LLC May 11, 2011
RPS Instrumentation-Operating 3.3.1 Table 3.3.1-1 (page 3 of 3)
Reactor Protective System Instrumentation SURVEILLANCE FUNCTION MODES REQUIREMENTS ALLOWABLE VALUE 9b. Asymmetric Steam 1, 2 SR 3.3.1.1 _ 135 psid Generator Transient SR 3.3.1.4 (ASGT)(b) SR 3.3.1.7 SR 3.3.1.8 SR 3.3.1.9
- 10. Loss of Load(d) 1(e) SR 3.3.1.6 NA SR 3.3.1.7 (a) Bistable trip unit may be bypassed when NUCLEAR INSTRUMENT POWER is <
1E-4% RTP or > 12% RTP. Bypass shall be automatically removed when NUCLEAR INSTRUMENT POWER is >_ 1E-45 RTP and < 12% RTP.
(b) Bistable trip unit may be bypassed when NUCLEAR INSTRUMENT POWER is <
1E-4%. Bypass shall be automatically removed when NUCLEAR INSTRUMENT POWER is _>1E-4% RTP. During testing pursuant to LCO 3.4.16, trips may be bypassed below 5% RTP.
(c) Bistable trip unit may be bypassed when steam generator pressure is
< 785 p . Bypass shall be automatically removed when steam generator pressure is _>785 p9-q.
p 5; o.
(d) Bistable trip unit may be bypassed when NUCLEAR INSTRUMENT POWER is <
15% RTP. Bypass shall be automatically removed when NUCLEAR INSTRUMENT POWER is 15% RTP.
(e) Trip is only applicable in MODE 1, NUCLEAR INSTRUMENT POWER Ž 15% RTP.
(f) CHANNEL CHECK only applies to Wide Range Logarithmic Neutron Flux Monitor.
CALVERT CLIFFS - UNIT 1 3.3.1-11 Amendment No. 232 CALVERT CLIFFS - UNIT 2 Amendment No. 208