ML091470216
| ML091470216 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/21/2009 |
| From: | Spina J A Constellation Energy Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML091470216 (12) | |
Text
James A. Spina Vice President 0Constellation Energy Nuclear Generation Group Calvert Cliffs Nuclear Power Plant, Inc.1650 Calvert Cliffs Parkway Lusby, Maryland 20657 410.495.5200 410.495.3500 Fax May 21, 2009 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
SUBJECT:
Document Control Desk Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 License Amendment Request for the Removal of the Table of Contents from the Technical Specifications In accordance with the provisions of 10 CFR 50.90, Calvert Cliffs Nuclear Power Plant, Inc. is submitting a request for an amendment to Renewed Operating Licenses DPR-53 and DPR-69. The proposed amendment would remove the Table of Contents from the Technical Specifications and place them under licensee control.Attachment (1) provides an evaluation of the proposed change. Attachment (2) provides marked up Technical Specification pages.Calvert Cliffs Nuclear Power Plant, Inc. requests approval of the proposed License Amendment Request by December 1, 2009, to be implemented within 60 days of the issuance of the license amendment.
The approval date was administratively selected to allow for Nuclear Regulatory Commission review, but the plant does not require this amendment to allow continued safe full power operations.
14001 Document Control Desk May 21, 2009 Page 2 Should you have questions regarding this matter, please contact Mr. Jay S. Gaines at (410) 495-5219.Very truly yours, STATE OF MARYLAND COUNTY OF CALVERT: TO WIT: I, James A. Spina, being duly sworn, state that I am Vice President
-Calvert Cliffs Nuclear Power Plant, Inc. (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 liable.Subscribed and sworn before me a Notary u lic in and for the State of Maryland and County of 4v, 10 ,this2/_day of ,2009.WITNESS my Hand and Notarial Seal: My Commission Expires: ja.e711Lfjf
-Notary Public Date JAS/RDW/bjd Attachments:
(1)(2)Evaluation of Proposed Change Marked-up Pages cc: D. V. Pickett, NRC S. J. Collins, NRC Resident Inspector, NRC S. Gray, DNR ATTACHMENT (1)EVALUATION OF 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 Precedent
4.3 Significant Hazards Consideration
4.4 Conclusions
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
Calvert Cliffs Nuclear Power Plant, Inc.May 21, 2009 ATTACHMENT (1)EVALUATIONOF PROPOSED CHANGE 1.0
SUMMARY
DESCRIPTION The proposed amendment would remove the Table of Contents (TOC) from the Technical Specifications (TS) and place them under licensee control.2.0 DETAILED DESCRIPTION The TOC for the TS is not being eliminated, rather, following approval of this license amendment request, responsibility for maintenance and issuance of updates to the TS TOC will transfer from the Nuclear Regulatory Commission (NRC) to Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP). The TOC will no longer be included in the NRC issued TSs and as such will no longer be part of the TS (Appendix A to the Operating License).
A TOC for the TSs will be maintained under CCNPP (licensee) control. The TOC will be issued by CCNPP in conjunction with the implementation of NRC-approved TS amendments.
3.0 TECHNICAL
EVALUATION The TOC does not meet the criteria specified in 10 CFR 50.36 requiring its inclusion within a plant's TS.10 CFR 50.36(b) states: "Each license authorizing operation of a production or utilization facility of a type described in § 50.21 or § 50.22 will include Technical Specifications.
The Technical Specifications will be derived from the analyses and evaluation included in the safety analysis report, and amendments thereto, submitted pursuant to § 50.34 ..." 10 CFR 50.36(c) states the "Technical Specifications will include items in the following categories:".
Review of 10 CFR 50.36(c) indicates that a TOC was not listed in the regulation as one of the categories.
10 CFR 50.36(a) indicates that a license application may provide other information associated with the TS, and gives an example of this information, i.e., the TS Bases, but 10 CFR 50.36(a) also clearly indicates that the Bases are not a part of the TS."Each applicant for a license ... shall include in his application proposed technical specifications in accordance with the requirements of this section. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the technical specifications." The TOC references where specific TS sections can be found throughout the TS, but does not contain technical information required by 10 CFR 50.36. Since the TOC does not include information required by 10 CFR 50.36 to be reviewed by the NRC staff, inclusion of a TOC within the TS is optional, and is not required by the regulation.
Removal of the TOC from the TS constitutes an administrative change and is therefore acceptable.
Additionally, the "Writer's Guide for Plant-Specific Improved Technical Specifications (ITS)" (Reference
- 1) was reviewed for guidance.
The Writer's Guide refers to the TOC as "Technical Specification Front Matter," which also includes the Title Page and List of Effective Pages.' The Writer's Guide describes the TS content as starting with Chapter 1, "Use and Application" and does not include the TOC as part of the content of the TS.A TOC for the TS will be maintained under CCNPP (licensee) control. The TOC will be issued by CCNPP in conjunction with the implementation of NRC-approved TS amendments.
1 ATTACHMENT (1)EVALUATION OF PROPOSED CHANGE
4.0 REGULATORY EVALUATION
4.1 Applicable
Regulatory Requirements/Criteria 10 CFR 50.36(a) states that "Each applicant for a license ... shall include in his application proposed Technical Specifications in accordance with the requirements of this section. A summary statement of the bases or reasons for such specifications, other than those covering administrative controls, shall also be included in the application, but shall not become part of the Technical Specifications." Similar to the TS Bases, the TOC does not meet the criteria specified in 10 CFR 50.36 for inclusion within a plant's TS.Calvert Cliffs Nuclear Power Plant has evaluated this change against the applicable regulatory requirements as described above. Based on this, there is reasonable assurance that the health and safety of the public, following approval of this change is unaffected.
4.2 Precedent
A license amendment was issued for the Waterford Steam Electric Station (Waterford
- 3) to remove the TS Index (which corresponds to the TOC) from the Waterford 3 TS on May 9, 2005 (Reference 2).Monticello Nuclear Generating Plant, License Amendment No. 152, was issued on November 8, 2007 (Reference 3). This amendment revised the Monticello Nuclear Generating Plant by removing the TOC from the TSs and placing it under-licensee control.4.3 Significant Hazards Determination In accordance with the requirements of 10 CFR 50.90, Calvert Cliffs Nuclear Power Plant (CCNPP)requests an amendment to remove the Table of Contents (TOC) from the Technical Specifications (TSs)and place it under licensee control. Calvert Cliffs Nuclear Power Plant 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 accident previously evaluated?
No.The proposed change is administrative and affects control of a document, the TOC, listing the specifications in the plant TSs. Transferring control from the Nuclear Regulatory Commission (NRC) to CCNPP (the licensee) does not affect the operation, physical configuration, or function of plant equipment or systems. It does not impact the initiators or assumptions of analyzed events; nor does it impact the mitigation of accidents or transient events. The change has no impact on, and hence cannot increase, the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
No.The proposed change is administrative and does not alter the plant configuration, require installation of new equipment, alter assumptions about previously analyzed accidents, or impact the operation or function of plant equipment or systems. Therefore, this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
2 ATTACHMENT (1)EVALUATION OF PROPOSED CHANGE 3. Does the proposed amendment involve a significant reduction in a margin of safety?No.The proposed change is administrative.
The TOC is not required by regulation to be in the TS.Removal does not impact any safety assumptions or have the potential to reduce a margin of safety as described in the TS Bases. The change involves a transfer of control of the TOC from the NRC to CCNPP. No change in the technical content of the TS specifications is involved.
Consequently, transfer from the NRC to CCNPP has no impact on the margin of safety, and hence cannot involve a significant reduction in the miargin of safety.Based on the above, CCNPP, concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
4.4 CONCLUSION
S In conclusion, based on the considerations discussed above, (1) there is a 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 health and safety of the public.5.0 ENVIRONMENTAL CONSIDERATION The proposed amendment is confined to changes to recordkeeping, reporting, or administrative procedures or requirements.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10).
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
- 1. Technical Specifications Task Force, TSTF-GG-05-01, dated June 2005, Writer's Guide for Plant-Specific Improved Technical Specifications
- 2. Letter from U.S. NRC to Entergy Operations, Inc., dated May 9, 2005, Waterford Steam Electric Station, Unit 3 -Issuance of Amendment Re: Modification of Technical Specification (TS) 5.3.1, Fuel Assemblies, TS 5.6.1, Criticality, TS 6.9.1.11.1, Core Operating Limits Reports, and Deletion of TS Index (TAC No. MC3584)3. Letter from U.S. NRC to Nuclear Management Co., LLC, dated November 8, 2007, Monticello Nuclear Generating Plant -Issuance of Amendment Re: Removal of the Table of Contents out of the Technical Specifications (TAC No. MD6027)3 ATTACHMENT (2)MARKED-UP PAGES Calvert Cliffs Nuclear Power Plant, Inc.May 21, 2009 TBLE OF CONTENTS 1.0 USE AND APPLICATION
........................................
1.1-1 1.1 Definitions
..........................................
.. 1.1-1 1.2 Logical Connectors
.....................................
1.2-1 1.3 Completion Times .......................................
1.3-1 1.4 Frequency
..............................................
1.4-1 2.0 SAFE LIMITS (SLs) .......................................
2.0-1 2.1 SL ...............................
2.0-1 2.2 SL
- lations ..........................................
2.0-1 3.0 LIMITING CO ITION FOR OPERATION (LCO) APPLICABILITY
....... 3.0-1 3.0 SURVEILLANCE EQUIREMENT (SR) APPLICABILITY...............
3.0-4 3.1 REACTIVITY C NTROL SYSTEMS .........
...................
3.1.1-1 3.1.1 SHUTDOWN RGIN (SDM) ..............................
3.1.1-1 3.1.2 Reactivity lance .....................
.........
3.1.2-1 3.1.3 Moderator Temn rature Coefficient (MTC) ............
3.1.3-1 3.1.4 Control Element Assembly (CEA) Alignment
...........
3.1.4-1 3.1.5 Shutdown Control lement Assembly (CEA) Insertion Limits ........
3.1.5-1 3.1.6 Regulating Control ement Assembly (CEA)Insertion Limits ..............................
3.1.6-1 3.1.7 Special Test Exception STE)-SHUTDOWN MARGIN (SDM) ..... .. ......
3.1.7-1 3.1.8 Special Test Exception (ST -MODES 1 and 2 ........ 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS ....... ...................
3.2.1-1 3.2.1 Linear Heat Rate (LHR) .........
...................
.3.2.1-1 3.2.2 Total Planar Radial Peaking Facto (F T ) ...........
3.2.2-1 3.2.3 Total Integrated Radial Peaking Fac or (Fr) ....... 3.2.3-1 3.2.4 AZIMUTHAL POWER TILT (Tq).......
..............
3.2.4-1 3.2.5 AXIAL SHAPE.INDEX (ASI).............
............
3.2.5-1 3.3 INSTRUMENTATION..............
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3.3.1-1 3.3.1 Reactor Protective System (RPS) Instrumenta ion-Operating
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3.3.1-1 3.3.2 Reactor Protective System (RPS) Instrumentatio
-Shutdown .. ... ... ...........
.. ... .3.3.2-1 3.3.3 Reactor Protective System (RPS) Logic and Trip Initiation
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3.3.3-1 CALVERT CLIFFS -UNIT 1 i Amendment No. 2 CALVERT CLIFFS -UNIT 2 Amendment No. 201 TWLE OF CONTENTS 3.3. Engineered Safety Features Actuation System (ESFAS) Instrumentation
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3.3.4-1 3.3.5 Engineered Safety Features Actuation System (ESFAS) Logic and Manual Actuation
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3.3.5-1 3.3.6 Diesel Generator (DG)-Loss of Voltage Start (LOVS) .........................................
3.3.6-1 3.3.7 Containment Radiation Signal (CRS) .................
3.3.7-1 3.3.8 Control Room Recirculation Signal (CRRS) ...........
3.3.8-1 3.3.9 emical and Volume Control System (CVCS)Isolation Signal ...............................
3.3.9-1 3.3.10 Pos -Accident Monitoring (PAM) Instrumentation
..... 3.3.10-1 3.3.11 Remot Shutdown Instrumentation
....................
3.3.11-1 3.3.12 Wide R ge Logarithmic Neutron Flux Monitor Chann Is .......................................
3.3.12-1 3.4 REACTOR COOLAN SYSTEM (RCS) .......................
3.4.1-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate B iling (DNB) Limits ..................
3.4.1-1 3.4.2 RCS Minimum Tem rature for Criticality
............
3.4.2-1 3.4.3 RCS Pressure and emperature (P/T) Limits ..........
3.4.3-1 3.4.4 RCS Loops -MODES and 2 .........................
3.4.4-1 3.4.5 RCS Loops -MODE 3 ............................
3.4.5-1 3.4.6 RCS Loops -MODE 4 ..............................
3.4.6-1 3.4.7 RCS Loops -MODE 5, Lo s Filled ..................
3.4.7-1 3.4.8 RCS Loops -MODE 5, Loop Not Filled ..............
3.4.8-1 3.4A Pressurizer
...........
........................
3.4.9-1 3.4.10 Pressurizer Safety Valves .........................
3.4.10-1 3.4.11 Pressurizer Power-Operated Re ief Valves (PORVs)...
3.4.11-1 3.4.12 Low Temperature Overpressure P tection (LTOP)System ............
...... ..................
3.4.12-1 3.4.13 RCS Operational LEAKAGE.........................
3.4.13-1 3.4.14 RCS.Leakage Detection Instrumentati
..............
3.4.14-1 3.4.15 RCS Specific Activity..............
.............
3.4.15-1 3.4.16 Special Test Exception (STE) RCS Loops -MODE 2.... 3.4.16-1 3.4.17 Special Test Exception (STE) RCS Loops -MODES 4 and 5 ..... ................
.........
3.4.17-1 3.4.18 Steam Generator (SG) Tube Integrity
........ ....... 3.4.18-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ............
.... 3.5.1-1 3.5.1 Safety Injection Tanks (SITs)....................
3.5.1-1 3.5.2 ECCS-Operating
...................................
.3.5.2-1 3. 5.3 ECCS-Shutdown
...................................
3.5.3-1 CALVERT CLIFFS -UNIT 1 ii Amendment No 278 CALVERT CLIFFS -UNIT 2 Amendment No. 55 TA LE OF CONTENTS Xa 3.5.4 Refueling Water Tank (RWT) .........................
3.5.4-1 3.5.5 Sodium Tetraborate (STB) ...........................
3.5.5-i 3.6 CONTAINMENT SYSTEMS ....................................
3.6.1-1 3.6.1 Containment
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3.6.1-1 3.6.2 Containment Air Locks ..............................
3.6.2-1 3.6.3 Containment Isolation Valves .......................
3.6.3-1 3.6.4 ontainment Pressure ...............................
3.6.4-1 3.6.5 C ntainment Air Temperature
........................
3.6.5-1 3.6.6 Con ainment Spray and Cooling Systems ..............
3.6.6-1 3.6.17 Dele ed 3.6.8 Iodine Removal System (IRS) .......................
3.6.8-1 3.7 PLANT'SYSTEM
.........................................
3.7.1-1 3.7.1 Main Steam afety Valves (MSSVs) ...................
3.7.1-1 3.7.2 Main Steam I olation Valves (MSIVs) ...............
'. 3.7.2-1 3.7.3 Auxiliary Fee ater (AFW) System ...................
3.7.3-1 3.7.4 Condensate Stor e Tank (CST) ......................
3.7.4-1 3.7.5 Component Cooling (CC) System ......................
3.7.5-1 3.7.6 Service Water (SRW System .........................
3.7.6-1 3.7.7 Saltwater (SW) Syste ..............................
3.7.7-1 3.7.8 Control Room Emergenc Ventilation System (CREVS)..
3.7.8-1 3.7.9 Control Room Emergency emperature System (CRETS)..
3.7.9-1 3.7.10 Emergency Core Cooling S tem (ECCS) Pump Room Exhaust Filtration Sys; m (PREFS) .............
3.7.10-1 3.7.11 Spent Fuel Pool Exhaust Ven tlation System (SFPEVS) ................
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3.7.11-1 3.7.12 Penetration Room Exhaust Ventil tion System (PREVS) ..... ............
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3.7.12-1 3.7.13 Spent Fuel Pool (SFP) Water Level .. ...............
3.7.13-1 3.7.14 Secondary Specific Activity ................
........ 3.7.14-1 3.7.15 Main Feedwater Isolation Valves (MFI ).........
3.7.15-1 3.7.16 Spent Fuel Pool (SFP) Boron Concentrati n ..........
3.7.16-1 3.7.17 Spent Fuel Pool (SFP) Storage ...........
.........
3.7.17-1 3.8 ELECTRICAL POWER SYSTEMS .......................
....... 3.8.1-1 3.8.1 AC Sources-Operating......................
..... 3.8.1-1 3.8.2 AC Sources -Shutdown..............................
3.8.2-1 3.8.3 Diesel Fuel Oil ..............................
.. 3.8.3-1 3.8.4 DC Sources-Operating...........................
3.8.4-1 3.8.5 DC Sources-Shutdown............................
3.8.5-1 3.8.6 Battery Cell Parameters
...........................
8.6-1 CALVERT CLIFFS -UNIT 1 iii Amendment No. 90 CALVERT CLIFFS -UNIT 2 Amendment No. 2 T LE OF CONTENTS 3.8.7 Inverters-Operating
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3.8.7-1 3.8.8 Inverters-Shutdown
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3.8.8-1 3.8.9 Distribution Systems-Operating
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3.8.9-1 3.8.10 Distribution Systems-Shutdown
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3.8.10-1 3.9 FUELING OPERATIONS,6
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3.9.1-1 3.9.1 Boron Concentration
......................
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3.9.1-1 3.9.2 uclear Instrumentation....
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3.9.2-1 3.9.3 C tainment Penetrations
...........................
3.9.3-1 3.9.4 Shu down Cooling (SDC) and Coolant Circulation-H h Water Level ....................
........3.9.4-1 3.9.5 Shutdo Cooling (SDC) and Coolant Circulation-Low ter Level ................................
3.9.5-1 3.9.6 Refueling ool Water Level .........................
3.9.6-1 4.0 DESIGN FEATURES .... ..................................
4.0-1 4.1 Site Location,..
... ...................................
4.0-1 4.2 Reactor Core ...........................................
4.0-1 4.3 Fuel Storage .........
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4.0-2 5.0 ADMINISTRATIVE CONTROLS ...... ...........
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5.1-1 5.1 Responsibility
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.. ..........................
5.1-1 5.2 Organization......
.. ........ .........................
5.2-1 5.2.1 Onsite and Offsite Organiz tions ...................
5.2-1 5.2.2 Unit Staff..............
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5.2-2 5.3 Unit Staff Qualifications
..........................
5 .3-1 5.4 Procedures
.......................................
5.4-1 5.5 Programs and Manuals ........ .........
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5.5-1 5.5.1 Offsite Dose CalculationManual
.................
5.5-1 5.5.2 Primary Coolant Sources Outside Cont nment ........ 5.5-2 5.5.3 Not Used ....... ..................
............
5.5-2 5.5.4 Radioactive Effluent Controls Program.............
5.5-2 5.5.5 Component Cyclic or Transient Limit......
.........
5.5-5 5.5.6 Concrete Containment Tendon Surveillance pr gram... 5.5-6 5.5.7 Reactor Coolant Pump Flywheel Inspection Pro am... 5.5-6 5.5.8 Inservice Testing Program..
.................
.... 5.5-6 5.5.9 Steam Generator (SG) Program ....................
.. 5.5-7 5.5.10 Secondary Water Chemistry Program ................
5.5-10 5.5.11 Ventilation Filter Testing 5.5.12 Explosive Gas and Storage Tank Radioactivity Monitoring Program ..........................
- 5. -13 5.5.13 Diesel Fuel Oil Testing Program ...................
5.5 14 CALVERT CLIFFS -UNIT I iv Amendment No. 278 CAL VERT CLIFFS -UNIT 2 Amendment No. 255
\TABLE OF CONTENTSTechnical Specifications Bases Control Program ..... 5.5-15Safety Function Determination Program (SFDP) ....... 5.5-15 5.5.16 \ Containment Leakage Rate Testing Program ...........
5.5-17 5.6 Reporting Requirements
............
....................
5.6-1 5.6.1 Deleted .................................
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5.6-1 5.6.2 Annual Radiological Environmental Operating report. 5.6-1 5.6.3 Radioactive Effluent Release Report ................
5.6-2 5.6.4 eleted ............................................
5.6-2 5.6.5 RE OPERATING LIMITS REPORT (COLR) ................
5.6-2 5.6.6 No Used ...........................................
5.6-8 5.6.7 Post Accident Monitoring Report ....................
5.6-9 5.6.8 Tendo Surveillance Report .........................
5.6-9 5.6.9 Steam Gnerator Tube Inspection Report .............
5.6-9 CALVERT CLIFFS -UNIT 1 v Amendment No. 278 CALVERT CLIFFS -UNIT 2 Amendment No. 55