Letter Sequence Other |
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MONTHYEARML0204602722002-02-14014 February 2002
Issuance of Amendment Integrated Leakage Rate Testing Interval Extension
Project stage: Approval
ML0205003902002-02-14014 February 2002
Tech Spec Pages for Amendment No. 178 Integrated Leakage Rate Testing Interval Extension
Project stage: Other
2002-02-14
[Table View] |
Tech Spec Pages for Amendment No. 178 Integrated Leakage Rate Testing Interval Extension| ML020500390 |
| Person / Time |
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| Site: |
Waterford  |
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| Issue date: |
02/14/2002 |
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| From: |
NRC/NRR/DLPM |
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| To: |
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| References |
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| TAC MB2461 |
| Download: ML020500390 (1) |
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Category:Technical Specifications
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Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times
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Correction to Issuance of Amendment Extension of the Integrated Leak Rate Testing to 15 Years
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Issuance of Amendment No. 245 Change to Updated Final Safety Analysis Report Clarifying Pressurizer Heaters Function for Natural Circulation at the Onset of a Loss of Offsite Power
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Issuance of Amendment No. 244 Extension of the Integrated Leak Rate Testing to 15 Years
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Orders Approving Transfer of Facility Operating Licenses and Indirect Transfer, Draft Conforming Amendment, and Safety Evaluation
W3F1-2015-0061, Provides Supplement to Revise Control Element Assembly Drop Times Associated with Technical Specification 3.1.3.42015-08-14014 August 2015
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Issuance of Amendment No. 241, Revise Operating License Condition for Change to Cyber Security Plan Milestone 8 Full Implementation Date
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License Amendment Request Technical Specification Change to Extend the Type a Test Frequency to 15 Years
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Technical Specification Change for Dry Cooling Tower Fans Out of Service for Ultimate Heat Sink
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Correction of an Error in Amendment No. 226, Administrative Changes to Technical Specifications 6.9.1.11 and 6.9.1.11.1 Relating to Core Operating Limits Report
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Attachment 2 to W3F1-2011-0021, Proposed Operating License Change (Mark-up) and Attachment 3, Revised Operating License Page
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Issuance of Amendment No. 228, Modify Technical Specification Tables 2.2-1 and 3.3-1 to Clarify Notes and Actions
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Issuance of Amendment No. 227, Modify Technical Specification 3/4.9.7, Crane Travel - Fuel Handling Building to Permit Certain Operations Needed for Dry Cask Storage of Spent Nuclear Fuel
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W3F1-2009-0045, License Amendment Request to Modify Technical Specification Information for Table 2.2-1 and Table 3.3-12009-10-22022 October 2009
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Tech Spec Pages for Amendment 214, Request to Support Next Generation Fuel; Review and Approval of ECCS Performance Analysis; and Review and Approval of Supplement to ECCS Performance Analysis
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W3F1-2008-0001, License Amendment Request NPF-38-275, Containment Isolation Valves.2008-01-0202 January 2008
License Amendment Request NPF-38-275, Containment Isolation Valves.
W3F1-2007-0033, License Amendment Request NPF-38-273 to Modify Requirements Regarding Control Room Envelope Habitability2007-08-16016 August 2007
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License Amendment Request to Allow the Use of Optimized Zirlo Fuel Rod Cladding
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Tech Spec Pages for Amendment 212 Reactor Coolant System Leakage Detection Instrumentation
ML0703704312007-02-0606 February 2007
Technical Specifications, Issuance of Amendment No. 211 to Facility Operating License Removal of Vendor Recommended Diesel Generator Surveillance Requirement
2023-07-26
[Table view] |
Text
ADMINISTRATIVE CONTROLS PROCESS CONTROL PROGRAM (Continued)
- 1. Sufficient information to support the change together with the appropriate analyses or evaluation justifying the change(s) and
- 2. A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
- b. Shall become effective after the approval of the General Manager Plant Operations.
6.14 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
6.14.2 Licensee-initiated changes to the ODCM:
- a. Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Manual. This document shall contain:
- 1. Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and
- 2. A determination that the change will maintain the level of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose or setpoint calculations.
- b. Shall become effective after the approval of the General Manager Plant Operations.
- c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
6.15 CONTAINMENT LEAKAGE RATE TESTING PROGRAM A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September 1995, except that the next Type A test performed after the May 12, 1991 Type A test shall be performed no later than May 11, 2006.
AMENDMENT NO. 66,-,116,I'4,-46, WATERFORD - UNIT 3 6-24 45£, 1-65-, 178