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MONTHYEARML0411701652004-04-23023 April 2004 Technical Specifications, Approve Administrative Procedures and Offsite Dose Calculation Manual Project stage: Acceptance Review ML0403403172004-04-23023 April 2004 License-Operating Amendment, Revises Technical Specification (TS) in Response to Application Dated January 14, 2003 Project stage: Acceptance Review 2004-04-23
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Category:Technical Specification
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Reactor Pressure Vessel Water Inventory Control.2017-12-0606 December 2017 Application to Revise Technical Specifications to Adopt TSTF-542. Reactor Pressure Vessel Water Inventory Control. ML17305A2382017-10-23023 October 2017 Technical Specification Bases, Rev. 11 L-17-108, Application to Revise Technical Specifications to Adopt TSTF -529. Clarify Use and Application Rules2017-08-11011 August 2017 Application to Revise Technical Specifications to Adopt TSTF -529. 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[Table view] Category:Amendment
MONTHYEARL-22-249, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener2023-06-0505 June 2023 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A Revision 2, Change TS 3.8.1. AC Sources-Operating. to Clarify the Power Factor Requirements When Performing Diesel Gener L-20-239, Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-08-0505 August 2022 Application to Revise the Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position L-21-176, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements2021-10-19019 October 2021 Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements L-19-274, License Amendment Request for Adoption of Technical Specification Task Force (Tsft) Traveler TSTF-500, Revision 2, DC Electrical Rewrite-Update to TSFT-3602020-04-24024 April 2020 License Amendment Request for Adoption of Technical Specification Task Force (Tsft) Traveler TSTF-500, Revision 2, DC Electrical Rewrite-Update to TSFT-360 L-18-174, Response to Request for Additional Information Regarding a Request to Revise the Technical Specifications to Adopt TSTF-542 Reactor Pressure Vessel Water Inventory Control2018-07-24024 July 2018 Response to Request for Additional Information Regarding a Request to Revise the Technical Specifications to Adopt TSTF-542 Reactor Pressure Vessel Water Inventory Control L-17-247, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-3602017-12-20020 December 2017 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 L-17-108, Application to Revise Technical Specifications to Adopt TSTF -529. Clarify Use and Application Rules2017-08-11011 August 2017 Application to Revise Technical Specifications to Adopt TSTF -529. Clarify Use and Application Rules L-17-042, Request for Licensing Action to Revise the Technical Specifications2017-06-0808 June 2017 Request for Licensing Action to Revise the Technical Specifications L-15-235, Response to Request for Additional Information Regarding License Amendment to Adopt Technical Specification Task Force Traveler-4252015-08-24024 August 2015 Response to Request for Additional Information Regarding License Amendment to Adopt Technical Specification Task Force Traveler-425 L-09-031, Application for Technical Specification Change Regarding Revision of Control Rod Application for Technical Specification Change Regarding Revision of Control2009-03-11011 March 2009 Application for Technical Specification Change Regarding Revision of Control Rod Application for Technical Specification Change Regarding Revision of Control ML0711401262007-04-19019 April 2007 Technical Specification Pages, Deleting License Condition 2.F ML0630502502006-10-27027 October 2006 Issuance of Technical Specification Page Clarify Wording of Emergency Closed Cooling Water SR 3.7.10.2 ML0616700762006-06-0606 June 2006 License Amendment Requests to Revise Technical Specification 5.5.7, Ventilation Filter Test Program to Correct Referenced Flow Units ML0500700132005-01-0606 January 2005 Tech Spec Pages for Amendment 131 Regarding Increase Flexibility in Mode Restraint ML0411701652004-04-23023 April 2004 Technical Specifications, Approve Administrative Procedures and Offsite Dose Calculation Manual ML0432202062004-04-0505 April 2004 License Amendment Request Pursuant to 10CFR50.90: Revision of the Minimum Critical Power Ratio Safety Limit ML0312200312003-04-29029 April 2003 Issuance of Amendment, Technical Specifications ML0309808202003-04-0808 April 2003 Issuance of Amendment, Technical Specification Page RBG-46072, Proposed Amendment of Facility Operating License to Remove Operating Mode Restrictions for Performing Division 1 & 2 Emergency Diesel Generator Load Reject Testing2003-03-14014 March 2003 Proposed Amendment of Facility Operating License to Remove Operating Mode Restrictions for Performing Division 1 & 2 Emergency Diesel Generator Load Reject Testing ML0231004072002-10-30030 October 2002 License Amendment Request Pursuant to 10 CFR 50.90: Elimination of Requirements for Post Accident Sampling System Using Consolidated Line Item Improvement Process 2023-06-05
[Table view] |
Text
Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation
- and shall delegate in writing the succession to this responsibility during his absence.
The plant manager, or his designee, shall approve. prior to implementation. each proposed test, experiment, or modification to systems or equipment that affect nuclear safety.
5.1.2 The shift supervisor (SS) shall be responsible for the control room command function. During any absence of the SS from the control room while the unit is in MODE 1. 2. or 3. an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function. During any absence of the SS from the control room while the unit is in MODE 4 or 5. an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.
PERRY - UNIT 1 5.0-1 Amendment No. 129
Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Scope Written procedures/instructions shall be established. implemented, and maintained covering the following activities:
- a. The applicable procedures recommended in Regulatory Guide 1.33. Revision 2. Appendix A. February 1978;
- b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1:
- c. Quality assurance for effluent and environmental monitoring:
and
- d. All programs specified in Specification 5.5.
5.4.2 Responsibility The above procedures will be approved by procedurally authorized individuals.
PERRY - UNIT 1 5.0-5 Amendment No. 129
Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs and manuals shall be established. implemented. and maintained.
5.5.1 Offsite Dose Calculation Manual (ODCM)
- a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints. and in the conduct of the radiological environmental monitoring program; and
- b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring programs.
and descriptions of the information that should be included in the Annual Radiological Environmental Operating and Radioactive Effluent Release reports.
Licensee initiated changes to the ODCM:
- a. Shall be documented and records of reviews performed shall
.be retained. This documentation shall contain:
- 1. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s). and
- 2. a determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302. 40 CFR 190. 10 CFR 50.36a, and 10 CFR 50, Appendix I. and not adversely impact the accuracy or reliability of effluent. dose, or setpoint calculations:
- b. Shall become effective after review and acceptance including approval by the procedurally authorized individual: and (continued)
PERRY - UNIT 1 5.0-6 Amendment No.129
D. FENOC is exempted from: 1)the requirements of Section IlI.D.2(b)(ii), containment airlock testing requirements, Appendix J to 10 CFR Part 50, due to the special
. circumstance described in Section 6.2.6 of SER Supplement No. 7 authorized by 10 CFR 50.12(a)(2)(iii) and 2) the requirements of Section IV.F., Full Participation Exercise, of Appendix E to 10 CFR Part 50, due to the special circumstance described in the Exemption dated November 6, 1986. These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. The exemptions are hereby granted pursuant to 10 CFR 50.12. With the granting of these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E. FENOC shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Perry Nuclear Power Plant Physical Security Plan," with revisions submitted through September 11, 1987; "Perry Nuclear Power Plant Guard Training and Qualification Plan,"
with revisions submitted through August 12, 1986; and "Perry Nuclear Power Plant Safeguards Contingency Plan" (Chapter 8 of the Security Plan), with revisions submitted through May 15, 1986. Changes made In accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
F. Except for Section 2.C.(2), FENOC shall report any violations of the requirements contained in Section 2.C of this license in the following manner Initial notification shall be made within 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> to the NRC Operations Center via the Emergency Notification System with written followup in accordance with the procedures described In 10 CFR 50.73(a)(1), (b), (c), and (e).
G. The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
Amendment No. 129