Letter Sequence Supplement |
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MONTHYEARML1006200112010-02-25025 February 2010
Oyster Creek, License Amendment Request, Changes to Trunnion Room Secondary Containment Boundary
Project stage: Other
ML1008200062010-03-23023 March 2010
E-mail, Miller, NRR, to Gropp, Exelon, Acceptance Review for Trunion Room LAR
Project stage: Acceptance Review
ML1016806172010-06-18018 June 2010
Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Allow Temporary Changes to Secondary Containment Boundary During Shutdown Conditions
Project stage: Draft RAI
RA-10-059, Response to Draft Request for Additional Information - License Amendment Request to Allow Changes to Secondary Containment Boundary During Shutdown Conditions2010-07-0909 July 2010
Response to Draft Request for Additional Information - License Amendment Request to Allow Changes to Secondary Containment Boundary During Shutdown Conditions
Project stage: Draft Request
RA-10-079, Supplemental Information Regarding License Amendment Request to Allow Changes to Secondary Containment Boundary During Shutdown Conditions2010-10-14014 October 2010
Supplemental Information Regarding License Amendment Request to Allow Changes to Secondary Containment Boundary During Shutdown Conditions
Project stage: Supplement
RA-10-080, Supplemental Information Regarding License Amendment Request to Allow Changes to Secondary Containment Boundary During Shutdown Conditions2010-10-15015 October 2010
Supplemental Information Regarding License Amendment Request to Allow Changes to Secondary Containment Boundary During Shutdown Conditions
Project stage: Supplement
ML1024305512010-10-18018 October 2010
Issuance of Amendment Secondary Containment Boundary Definition During Shutdown Conditions
Project stage: Approval
2010-02-25
[Table View] |
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Category:Letter type:RA
MONTHYEARRA-19-091, Commitment Change Summary Report - 20192019-12-27027 December 2019
Commitment Change Summary Report - 2019
RA-19-080, Response to Request for Additional Information (RAI) Related to Oyster Creek Nuclear Generating Station - Post-Shutdown Decommissioning Activities Report2019-10-18018 October 2019
Response to Request for Additional Information (RAI) Related to Oyster Creek Nuclear Generating Station - Post-Shutdown Decommissioning Activities Report
RA-19-076, Request for Continuation of NRC Actions and Approvals Following Transfer of the Licenses from Exelon Generation to Holtec Decommissioning International, LLC2019-09-12012 September 2019
Request for Continuation of NRC Actions and Approvals Following Transfer of the Licenses from Exelon Generation to Holtec Decommissioning International, LLC
RA-19-065, Signature Verification and Acceptance of Amendment 19 to Indemnity Agreement No B-37 to Renewed Facility License No. DPR-162019-08-28028 August 2019
Signature Verification and Acceptance of Amendment 19 to Indemnity Agreement No B-37 to Renewed Facility License No. DPR-16
RA-19-052, Security Plan, Training Qualification Plan, Safeguards Contingency Plan, (Revision 18)2019-06-11011 June 2019
Security Plan, Training Qualification Plan, Safeguards Contingency Plan, (Revision 18)
RA-19-023, Annual Radioactive Effluent Release Report for 20182019-04-30030 April 2019
Annual Radioactive Effluent Release Report for 2018
RA-19-019, Submittal of Changes to Technical Specifications Bases2019-04-12012 April 2019
Submittal of Changes to Technical Specifications Bases
RA-19-012, Supplement for License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements2019-03-0707 March 2019
Supplement for License Amendment Request - License Condition Revision for Removal of Cyber Security Plan Requirements
RA-19-007, Response to RAI and Supplemental Information Re Request for Changing Emergency Preparedness License Amendment 294 Effective Date (Change to Adiabatic Heat-Up Calculation)2019-02-13013 February 2019
Response to RAI and Supplemental Information Re Request for Changing Emergency Preparedness License Amendment 294 Effective Date (Change to Adiabatic Heat-Up Calculation)
RA-19-003, Amendment No. 17 to Indemnity Agreement No. 8-372019-01-0808 January 2019
Amendment No. 17 to Indemnity Agreement No. 8-37
RA-18-103, Annual Sea Turtle Incidental Take Report - 20182018-12-13013 December 2018
Annual Sea Turtle Incidental Take Report - 2018
RA-18-080, License Amendment Request: License Condition Revision for Removal of Cyber Security Plan Requirements2018-11-12012 November 2018
License Amendment Request: License Condition Revision for Removal of Cyber Security Plan Requirements
RA-18-098, License Amendment Request Supplement - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-11-0606 November 2018
License Amendment Request Supplement - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme
RA-18-097, Exelon Nuclear Radiological Emergency Plan and Addendum Revisions2018-10-24024 October 2018
Exelon Nuclear Radiological Emergency Plan and Addendum Revisions
RA-18-092, License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-10-22022 October 2018
License Amendment Request - Proposed Change of Effective and Implementation Dates of License Amendment No. 294, Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme
RA-18-093, Request to Reinitiate Consultation Regarding the OCNGS Sea Turtle Incidental Take Statement2018-10-16016 October 2018
Request to Reinitiate Consultation Regarding the OCNGS Sea Turtle Incidental Take Statement
RA-18-091, Request to Reclassify Oyster Creek Nuclear Generating Station Under 10 CFR 171.15, Annual Fees: Reactor Licenses and Independent Spent Fuel Storage Licenses2018-10-0101 October 2018
Request to Reclassify Oyster Creek Nuclear Generating Station Under 10 CFR 171.15, Annual Fees: Reactor Licenses and Independent Spent Fuel Storage Licenses
RA-18-090, Notice Regarding Proposed Amendment No. 1 to Master Terms for Decommissioning Trust Agreements2018-10-0101 October 2018
Notice Regarding Proposed Amendment No. 1 to Master Terms for Decommissioning Trust Agreements
RA-18-083, Certification of Permanent Removal of Fuel from the Reactor Vessel for Oyster Creek Nuclear Generating Station2018-09-25025 September 2018
Certification of Permanent Removal of Fuel from the Reactor Vessel for Oyster Creek Nuclear Generating Station
RA-18-088, Radiological Emergency Plan Addendum Revision. Includes EP-AA-1010, Addendum 3, Revision 4, Emergency Action Levels for Oyster Creek.2018-09-25025 September 2018
Radiological Emergency Plan Addendum Revision. Includes EP-AA-1010, Addendum 3, Revision 4, Emergency Action Levels for Oyster Creek.
RA-18-087, Response to Request for Additional Information (RAI) Related to Post-Shutdown Decommissioning Activities Report2018-09-24024 September 2018
Response to Request for Additional Information (RAI) Related to Post-Shutdown Decommissioning Activities Report
RA-18-084, Secondary Containment Capability Test2018-09-14014 September 2018
Secondary Containment Capability Test
RA-18-078, Submittal of Sea Turtle Incidental Take Report 2018-0042018-08-15015 August 2018
Submittal of Sea Turtle Incidental Take Report 2018-004
RA-18-077, Sea Turtle Incidental Take Report 2018-0032018-08-14014 August 2018
Sea Turtle Incidental Take Report 2018-003
RA-18-072, Pressure and Temperature Limit Report Revision 12018-06-29029 June 2018
Pressure and Temperature Limit Report Revision 1
RA-18-066, Response to Questions Pertaining to Licensed Operator2018-06-18018 June 2018
Response to Questions Pertaining to Licensed Operator
RA-18-070, Submittal of Sea Turtle Incidental Take Report 2018-001 on June 04, 20182018-06-0808 June 2018
Submittal of Sea Turtle Incidental Take Report 2018-001 on June 04, 2018
RA-18-068, Response to Request for Additional Information (RAI) Regarding Request for Approval of Decommissioning Quality Assurance Program, Revision 0 for Oyster Creek Nuclear Generating Station2018-06-0606 June 2018
Response to Request for Additional Information (RAI) Regarding Request for Approval of Decommissioning Quality Assurance Program, Revision 0 for Oyster Creek Nuclear Generating Station
RA-18-065, Registration of Use of Cask to Store Spent Fuel2018-05-31031 May 2018
Registration of Use of Cask to Store Spent Fuel
RA-18-059, Request for Relief and Rescission of Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2018-05-30030 May 2018
Request for Relief and Rescission of Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events
RA-18-055, 10 CFR 50.46 Annual Report2018-05-23023 May 2018
10 CFR 50.46 Annual Report
RA-18-053, Update to Spent Fuel Management Plan2018-05-21021 May 2018
Update to Spent Fuel Management Plan
RA-18-052, Supplement to Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance and Supplement to Request for Exemption from 10 CFR 140.11(a)(4), Concerning Primary and Secondary ...2018-05-0808 May 2018
Supplement to Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance and Supplement to Request for Exemption from 10 CFR 140.11(a)(4), Concerning Primary and Secondary ...
RA-18-049, Registration of Use of Cask to Store Spent Fuel2018-05-0707 May 2018
Registration of Use of Cask to Store Spent Fuel
RA-18-046, Oyster Creek, Transmittal of Annual Radiological Environmental Operating Report for 20172018-04-30030 April 2018
Oyster Creek, Transmittal of Annual Radiological Environmental Operating Report for 2017
RA-18-047, Annual Radioactive Effluent Release Report for 20172018-04-30030 April 2018
Annual Radioactive Effluent Release Report for 2017
RA-18-018, Submittal of Changes to Technical Specifications Bases2018-04-13013 April 2018
Submittal of Changes to Technical Specifications Bases
RA-18-021, Request for Exemption from Record Retention Requirements2018-04-12012 April 2018
Request for Exemption from Record Retention Requirements
RA-18-028, Request for Rescission of Commission Order Modifying License with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)2018-04-12012 April 2018
Request for Rescission of Commission Order Modifying License with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order Number EA-13-109)
RA-18-027, Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2018-04-12012 April 2018
Request for Rescission of Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)
RA-18-036, Response to Request for Additional Information (RAI) and Supplement Regarding License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ...2018-03-29029 March 2018
Response to Request for Additional Information (RAI) and Supplement Regarding License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled ...
RA-18-019, Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance2018-03-29029 March 2018
Request for Exemption from 10 CFR 50.54(w)(1), Concerning On-Site Property Damage Insurance
RA-18-020, Request for Exemption from 1 O CFR 140.11 (a)(4), Concerning Primary and Secondary Liability Insurance2018-03-29029 March 2018
Request for Exemption from 1 O CFR 140.11 (a)(4), Concerning Primary and Secondary Liability Insurance
RA-18-032, Revision to Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues2018-03-27027 March 2018
Revision to Commitments Relating to Resolution of Anchor Darling Double Disc Gate Valve Part 21 Issues
RA-18-034, Request for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv)2018-03-22022 March 2018
Request for Exemption from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv)
RA-18-015, Withdrawal of Application to Revise Technical Specifications to Implement BWRVIP-18, Revision 2-A and Relief Request for Extension of Torus Examinations2018-02-15015 February 2018
Withdrawal of Application to Revise Technical Specifications to Implement BWRVIP-18, Revision 2-A and Relief Request for Extension of Torus Examinations
RA-18-014, Response to Request for Additional Information (RAI) and Supplemental Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme2018-02-13013 February 2018
Response to Request for Additional Information (RAI) and Supplemental Regarding License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Emergency Plan and Emergency Action Level Scheme
RA-18-008, Summary of Changes to Quality Assurance Topical Report, NO-AA-102018-02-0808 February 2018
Summary of Changes to Quality Assurance Topical Report, NO-AA-10
RA-18-010, Supplement to Relief Request for Extension of Torus Examinations2018-01-24024 January 2018
Supplement to Relief Request for Extension of Torus Examinations
RA-17-086, Commitment Change Summary Report - 20172017-12-21021 December 2017
Commitment Change Summary Report - 2017
2019-09-12
[Table view] |
Text
10 CFR 50.90 RA-10-080 October 15, 2010 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, DC 20555-0001 Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 Docket No. 50-219
Subject:
Supplemental Information Regarding License Amendment Request to Allow Changes to Secondary Containment Boundary During Shutdown Conditions
References:
- 1) Letter from Pamela B. Cowan to U.S. Nuclear Regulatory Commission License Amendment Request - Changes to Trunnion Room Secondary Containment Boundary, dated February 25,2010
- 2) U.S. Nuclear Regulatory Commission facsimile dated June 18, 2010, Oyster Creek Nuclear Generating Station - Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Allow Temporary Changes to Secondary Containment Boundary During Shutdown Conditions (TAC No. ME3475)
- 3) Letter from Pamela B. Cowan to U.S. Nuclear Regulatory Commission, Response to Draft Request for Additional Information - License Amendment Request to Allow Changes to Secondary Containment Boundary During Shutdown Conditions, dated July 9, 2010
- 4) Letter from Pamela B. Cowan to U.S. Nuclear Regulatory Commission, Supplemental Response License Amendment Request to Allow Changes to Secondary Containment Boundary During Shutdown Conditions, dated October 14, 2010 By letter dated February 25,2010 (Reference 1), Exelon Generation Company, LLC (Exelon) submitted a request to revise the Oyster Creek Nuclear Generating Station (OCNGS) Technical Specifications (TS). The proposed change would allow the Reactor Building Secondary Containment associated with the Trunnion Room boundary to be relocated on a temporary basis during shutdown conditions to support refueling and maintenance outage related activities.
U.S. Nuclear Regulatory Commission License Amendment Request Trunnion Room Secondary Containment Boundary Supplemental Response Docket No. 50-219 October 1 2010 Page 2 Subsequently, during follow-up teleconference discussions between Exelon and U.S. Nuclear Regulatory Commission (NRC) representatives on October 15, 2010, Exelon agreed to provide additional clarifying information for the proposed wording in the affected Technical Specifications (TS) sections (I.e., TS Definition 1.14, "Secondary Containment Integrity," and the revised TS Surveillance Requirement 4.5.G.3).
Exelon has concluded that the information provided in this response does not impact the conclusions of the: 1) Technical Analysis, 2) No Significant Hazards Consideration under the standards set forth in 10 CFR 50.92(c), or 3) Environmental Consideration as provided in the original submittal (Reference 1).
There are no regulatory commitments contained in this submittal.
Should you have any questions concerning this letter, please contact Mr. Richard Gropp at (610) 765-5557.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 15th day of October 2010.
Respectfully, David P. Helker Manager - Licensing Licensing and Regulatory Affairs Exelon Generation Company, LLC
Attachment:
Revised Technical Specifications Pages (Mark-ups) cc: Regional Administrator - NRC Region I NRC Senior Resident Inspector - OCNGS NRC Project Manager, NRR - OCNGS Director, Bureau of Nuclear Engineering, New Jersey Department of Environmental Protection
ATTACHMENT Oyster Creek Nuclear Generating Station Supplemental Response License Amendment Request Changes to Trunnion Room Secondary Containment Boundary During Shutdown Conditions Revised Technical Specifications Pages (Mark-ups) 1.0-3 4.5-4
1.14 SECONDARY CONTAINMENT INTEGRITY Secondary containment integrity means that the reactor bUilding is closed and the following conditions are met:
A. At least one door at each access opening is closed.
(Note: Momentary opening and closing of the trunnion room door does not constitute a loss of secondary containment intergrity.
door r~rn::li:n B. The standby gas treatment system is operable.
C. All automatic secondary containment isolation valves are operable or are secured in the closed position.
1.15 (DELETED) 1.16 RATED FLUX Rated flux is the neutron flux that corresponds to a steady state power level of 1930 MW(t). Use of the term 100 percent also refers to the 1930 thermal megawatt power level.
1.17 REACTOR THERMAL POWER-TO-WATER Reactor thermal power-to-water is the sum of (1) the instantaneous integral over the entire fuel clad outer surface of the product of heat transfer area increment and position dependent heat flux and (2) the instantaneous rate of energy deposition by neutron and gamma reactions in all the water and core components except fuel rods in the cylindrical volume defined by the active core height and the inner surface of the core shroud.
1.18 PROTECTIVE INSTRUMENTATION LOGIC DEFINITIONS A. Instrument Channel An instrument channel means an arrangement of a sensor and auxiliary equipment required to generate and transmit to a trip system a single trip signal related to the plant parameter monitored by that instrument channel.
B. Trip System A trip system means an arrangement of instrument channel trip signals and auxiliary equipment required to initiate action to accomplish a protective trip function. A trip system may require one or more instrument channel trip signals related to one or more plant parameters in order to initiate trip system action.
Initiation of protective action may require the tripping of a single trip system (e.g.,
initiation of a core spray loop, automatic depressurization, isolation of an isolation condenser, offgas system isolation, reactor building isolation, standby gas treatment and rod block) or the coincident tripping of two trip systems (e.g.,
initiation of scram, isolation condenser, reactor isolation, and primary containment isolation).
OYSTER CREEK 1.0-3 Change 7, Amendment No.: 10, 160, 168, 211, 233,
(3) At least four of the suppression chamber - drywell vacuum breakers shall be inspected. If deficiencies are found, all vacuum breakers shall be inspected and deficiencies corrected such that Specification 3.5.A.5.a can be met.
(4) A drywell to suppression chamber leak rate test shall be performed once every 24 months to demonstrate that with an initial differential pressure of not less than 1.0 psi, the differential pressure decay rate shall not exceed the equivalent of air flow through a 2-inch orifice.
G. Reactor Building
- 1. Secondary containment capability tests shall be conducted after isolating the reactor building and placing either Standby Gas Treatment System filter train in operation.
The tests shall be performed at the frequency specified in the Surveillance Frequency Control Program and shall demonstrate the capability to maintain a 1/4 inch of water vacuum under calm wind conditions with a Standby Gas Treatment System Filter train flow rate of not more than 4000 cfm.
A secondary containment capability test shall be conducted at each refueling outage prior to refueling.
- 45. The results of the secondary containment capability tests shall be in the subject of a summary technical report which can be included in the reports specified in Section 6.
H. Standby Gas Treatment System
- 1. The capability of each Standby Gas Treatment System circuit shall be demonstrated by:
- a. At the frequency specified in the Surveillance Frequency Control Program, after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of operation, and following significant painting, fire, or chemical release in the reactor building during operation of the Standby Gas Treatment System by verifying that:
(1) The charcoal absorbers remove 2:99% of a halogenated hydrocarbon refrigerant test gas and the HEPA filters remove 2:99% of the DOP in a cold DOP test when tested in accordance with ANSI N510-1975.
OYSTER CREEK 4.5-4 Amendment No.: 144,186,193,219,276,