Similar Documents at Cook |
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Category:Legal-Correspondence
MONTHYEARML0927104922009-09-28028 September 2009 Letter from Annette L. Vietti-Cook, Secy to Dr. Edwin Lyman, Union of Concerned Scientists Re DD-09-02 ML0307104332003-03-0303 March 2003 Indiana Michigan Power Co. Answer to Nuclear Regulatory Commission Order Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors ML18219D5011977-09-22022 September 1977 Letter from Indiana & Michigan Power Co to NRC Submitting Chlorine Monitoring Data, as Requested ML18219D5041977-09-15015 September 1977 Referring Impc Letter of 8/26/1977, Advising Error in Data Contained in Radioactive Material Release During Calendar Year of 1976 ML18219D5111977-05-27027 May 1977 05/27/1977 Letter Enclosed as Attachment a Is an Update of Section III D.3.C. of the Final Environmental Statement ML18219D5121977-05-13013 May 1977 05/13/1977 Letter Request for Changes to Appendix B Technical Specifications ML18219D5201977-03-16016 March 1977 03/16/1977 Letter Request for Temporary Change to Environmental Technical Specification 2.2.3.2 to Allow One-Time Chemical Cleaning Operation of the Unit No. 2 Condensate and Feedwater Systems ML18219D6821976-08-0505 August 1976 08/05/1976 Legal Correspondence Request for All Communications to Instead Be Forwarded to Citizens for a Better Environment 2009-09-28
[Table view] Category:Letter
MONTHYEARIR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 ML24004A1582024-01-19019 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0039 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) AEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23338A2642023-12-0505 December 2023 Confirmation of Initial License Examination AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20234032023-09-19019 September 2023 Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403 IR 05000315/20230112023-08-31031 August 2023 Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011 ML23242A1832023-08-30030 August 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004 AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023 Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III IR 05000315/20230122023-06-22022 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012 IR 05000315/20235012023-06-21021 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501 AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report ML23159A0192023-06-13013 June 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report ML23131A3282023-05-11011 May 2023 D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404 IR 05000315/20230012023-05-0303 May 2023 Integrated Inspection Report 05000315/2023001 and 05000316/2023001 AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report ML23117A0062023-04-27027 April 2023 Review of the Spring 2022 Steam Generator Tube Inspections Report ML23114A1142023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023 Annual Report of Individual Monitoring for 2022 AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023 Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023 Annual Report of Property Insurance AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report ML23076A0212023-03-20020 March 2023 Request for Information for NRC Commercial Grade Dedication Inspection; Inspection Report 05000315/2023011; 05000316/2023011 IR 05000315/20234012023-03-16016 March 2023 Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401 ML23066A1882023-03-0707 March 2023 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Donald C. Cook Nuclear Plant IR 05000315/20220062023-03-0101 March 2023 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006) IR 05000315/20220042023-02-0101 February 2023 Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report IR 05000315/20230102023-01-31031 January 2023 Phase 4 Post-Approval License Renewal Inspection Report 05000315/2023010 and 05000316/2023010 AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023 Request for Approval of Change Regarding Neutron Flux Instrumentation ML22363A5622023-01-0404 January 2023 Relief Request ISIR-5-06 Related to ASME Code Case N-729-6 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in ML22340A1392022-11-30030 November 2022 Submittal of Revision 31 to Updated Final Safety Analysis Report and 10CFR50.71(e) Updated and Related Site Change Reports IR 05000315/20220112022-11-0404 November 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011 IR 05000315/20220032022-10-28028 October 2022 Integrated Inspection Report 05000315/2022003 and 05000316/2022003 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06 2024-01-08
[Table view] Category:Technical Specifications
MONTHYEARML22046A2332022-06-21021 June 2022 Issuance of Amendment Nos. 360 and 342 Regarding Change to the Technical Specification Requirement for Containment Water Level Instrumentation ML21125A5762021-04-19019 April 2021 9 Technical Specification Bases, List of Effective Pages (Unit 2) ML21125A5482021-04-19019 April 2021 2 to Technical Specifications Bases, List of Effective Pages (Unit 1) ML20366A1552021-01-15015 January 2021 Issuance of Amendments Nos. 357 and 336 Regarding Revision to Technical Specifications Bases Control Program ML20329A0012021-01-12012 January 2021 Issuance of Amendment No. 356 Regarding Updating the Reactor Coolant System Pressure-Temperature Limits ML20322A4282021-01-0606 January 2021 Issuance of Amendment Nos. 355 and 335, Revision to Technical Specifications to Adopt Technical Specification Task Force Traveler 567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues AEP-NRC-2020-78, License Amendment Request Regarding a Change to the Steam Generator (SG) Program to Allow for a One-Time Deferral of SG Inspections2020-12-14014 December 2020 License Amendment Request Regarding a Change to the Steam Generator (SG) Program to Allow for a One-Time Deferral of SG Inspections ML19170A3622019-08-0101 August 2019 Issuance of Amendment Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping ML17131A2772017-06-0707 June 2017 Issuance of Amendments License Amendment Request Regarding Containment Leakage Rate Testing Program ML16195A0042016-08-0404 August 2016 Issuance of Amendments to Revise Technical Specifications to Adopt Technical Specifications Task Force - 523, Generic Letter 2008 01, Managing Gas Accumulation ML14197A0972015-11-30030 November 2015 Issuance of Amendment Regarding Restoration of Normal Reactor Coolant System Pressure and Temperature Consistent with Previously Licensed Conditions ML15328A4512015-11-19019 November 2015 Enclosures 1 - 5: Affirmation, Description of Proposed Changes, Probabilistic Risk Assessment Technical Adequacy, and CNP Units 1 & 2 TS Pages Marked to Show Proposed Changes ML15187A0022015-07-10010 July 2015 Issuance of Amendment No. 328 (Exigent) Regarding Revision to Technical Specifications for Engineered Safety Feature Actuation System AEP-NRC-2015-62, Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2015-06-29029 June 2015 Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML15076A2262015-04-0606 April 2015 Issuance of Amendments Adoption of TSTF-427, Allowance for Non-Technical Specification Barrier Degradation on Supported System Operability, Revision 2 AEP-NRC-2015-05, Correction of Technical Specification Typographical Error2015-02-0202 February 2015 Correction of Technical Specification Typographical Error ML14282A1182014-11-20020 November 2014 Issuance of Amendments Regarding Containment Divider Barrier Seal AEP-NRC-2014-09, License Amendment Request to Revise Technical Specification Section 5.5.14, Containment Leakage Rate Testing Program2014-03-0707 March 2014 License Amendment Request to Revise Technical Specification Section 5.5.14, Containment Leakage Rate Testing Program ML13282A2142013-10-0909 October 2013 Issuance of Amendment Revision to Technical Specification 3.6.9, Distributed Ignition System (Dis) (Emergency Circumstances) AEP-NRC-2013-79, License Amendment Request Regarding Restoration of Normal Reactor Coolant System Operating Pressure and Temperature Consistent with Previously Licensed Conditions, with Enclosures 1 Through 52013-10-0808 October 2013 License Amendment Request Regarding Restoration of Normal Reactor Coolant System Operating Pressure and Temperature Consistent with Previously Licensed Conditions, with Enclosures 1 Through 5 ML11182A1782011-07-28028 July 2011 License Amendment, Issuance of Amendments Cyber Security Plan AEP-NRC-2009-71, Response to Request for Additional Information Regarding a License Amendment Request Associated with the Large-Break Loss-of-Coolant Accident Analysis Methodology2009-11-20020 November 2009 Response to Request for Additional Information Regarding a License Amendment Request Associated with the Large-Break Loss-of-Coolant Accident Analysis Methodology AEP-NRC-2009-23, License Amendment Request Regarding Large Break Loss-of-Coolant Accident Analysis Methodology2009-03-19019 March 2009 License Amendment Request Regarding Large Break Loss-of-Coolant Accident Analysis Methodology ML0903502102009-01-14014 January 2009 License Amendment Request to Revise Operating Licenses DPR-58 and DPR-74, Appendix B, Environmental Technical Specifications, Part II, Non-Radiological Environmental Protection Plan ML0826004692008-09-0404 September 2008 Supplement to Emergency Diesel Generator Maximum Steady State Frequency Amendment Request ML0815108932008-05-28028 May 2008 Correction of Amendment No. 304 for Unit 1 and 287 for Unit 2, (Tac Nos. MD6317 & MD6318) - Tech Specs ML0812302692008-04-28028 April 2008 Tech Spec Pages for Amendments 305 and 288 Regarding Maximum Ventilation System Filter Pressure Drop ML0812302702008-04-28028 April 2008 Tech Spec Pages for Amendments 304 & 287 to Add a Surveillance Requirement for When Offsite Power Is Provided Via Backfeed Through the Main Transformer and a Unit Auxiliary Transformer ML0806600672008-03-0505 March 2008 Tech Spec Page for Amendments 302 & 285 to Revise a Specification Inadvertently Omitted by Previous Amendments Power Range Neutron Flux High Negative Rate Trip Function ML0801106652008-01-11011 January 2008 Tech Spec Pages for Amendments 301 and 284 Regarding Operational Test of the Reactor Trip on Turbine Trip ML0800800492008-01-0404 January 2008 Technical Specifications, Correction of Amendment No. 282 Containment Sump Modifications Per Generic Letter 2004-02 ML0735204032007-12-17017 December 2007 Technical Specifications, Issuance of Amendment RTS and ESFAS Bypass Testing Capability ML0729501002007-10-18018 October 2007 Technical Specifications, Issuance of Amendments Containment Sump Modifications Per Generic Letter 2004-02 (TAC Nos. MD5901 & MD5902) ML0725306592007-09-19019 September 2007 Technical Specifications, Issuance of Amendment Replacement of Resistance - Temperature Detectors and Associated Piping ML0714200712007-05-11011 May 2007 Technical Specification Change of Conditional Surveillance Frequency ML0710100972007-04-0606 April 2007 Technical Specification Page Correction of Administrative Error in Amendment No. 298, Steam Generator Tube Integrity ML0708607652007-03-14014 March 2007 Corrections to Technical Specification Table of Contents ML0708101332007-03-14014 March 2007 D.C. Cook, Technical Specifications, Steam Generator Integrity ML0700305172006-12-26026 December 2006 Supplement to Application for Technical Specification (TS) Improvement Regarding Steam Generator Tube Integrity ML0628303132006-10-0606 October 2006 D.C. Cook, Tech Spec Pages for Amendment 296, Regarding Elimination of the Resistance Temperature Detector (RTD) Bypass Loop ML0624901142006-09-0101 September 2006 D.C. Cook, Technical Specification Pages Re AC Sources - Operating ML0618801572006-07-0505 July 2006 Technical Specifications Pages Regarding Leakage ML0616004492006-05-31031 May 2006 Application for Amendment to Revise Technical Specification Surveillance Requirement for Channel Calibration of Overtemperature Differential Temperature and Overpower Differential Temperature Reactor Protection System Functions ML0610805842006-04-21021 April 2006 Correction of Amendments Technical Specifications, Conversion to Improved Format ML0610404022006-04-13013 April 2006 Technical Specification - Issuance of Amendment Under Emergency Circumstances Regarding Diesel Generator Votage Limit Requirements ML0607603742006-03-0707 March 2006 Application for Amendment to Revise Technical Specification 5.5.2, Leakage Monitoring Program. ML0604400222006-02-10010 February 2006 Technical Specifications, Delete the Power Range Neutron Flux High Negative Rate Trip Function ML0601700302006-01-12012 January 2006 Tech Spec Pages for Amendments 292 and 274 Regarding Elimination of Requirements for Monthly Operating Reports and Occupational Radiation Exposure Reports ML0527303202005-09-30030 September 2005 Tech Spec Pages for Amendments 291 and 273 Safety Evaluation Regarding Allowed Outage Time Extension for the Emergency Diesel Generators ML0526900432005-09-23023 September 2005 Tech Spec Pages for Amendments 290 and 272 Requirements of Improved Technical Specification Surveillance Requirement 3.8.1.8 with the Wording of Previous Technical Specification SR 4.8.1.1.2.e.11 with Minor Editorial.. 2022-06-21
[Table view] |
Text
U.O, NUCLEAR REGULAtORV COMMISSION HRC FORM 195
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I'ILE NUMBER EDSON G. CASE FROM:INDIANA & MICHIGAN POWER DATE OF DOCUMENT TO:
5/13/77 CO.'EW YORK, N.Y.
J. TILLINGHASZ DATE RECEIVED 5/19/77
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DcscRIPTIoN LTR. NOTARIZED 5-13-77 ~ .. ENCLOSURE IAAF LTR. REQUESTING CHANGES zTO THE DONALD C. COOK.
UCLEAR PLANT APPENDIX B TECH. SPECS...W/ATTACHE EVZSEDIPAGES 1.1-1, 5:l-l;, g)NQ'.$ ,4;,g TO INDICAT AI llvl, v<J. lag) laL X'l'V: <i~ wW L HE,CHAR(ES PROPOSED......."+->>: '
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INDIANA g, MICHIGAN POWER COMPANY P. O. BOX 18 BO WL I N G G R E EN STAT ION NEW YORK, N. Y. 10004 May 13, 1977 Donald C. Cook Nuclear Plant Unit No. 1 Docket No. 50-315 License No. DPR-58
'g'egulatory Docket fjLa Mr. Edson G. Case, Acting Director
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Office of Nuclear Reactor Regulation +~9 >yy U.S. Nuclear Regulatory Commission ~iS'SS~4~
g4ogg 8 Washington, D.C. 20555
Dear Mr. Case:
This letter is a request for changes to the Donald C. Cook Nuclear Plant Appendix B Technical Specifications.
We have attached revised pages 1.1-1, 5.1-1, and 5.4-6 to indicate the changes we propose.
&wee inconsistencies between Appendix A and Appendix B of the Cook Nuclear Plant Technical Specifications have been brought to our attention by Mr. M. H. Fletcher of the NRC Division of Operating Reactors.
The first of these concerns Section 5.1 of Appendix B which states that "the organisation, review and audit shall be in accordance with Section 6, Appendix A." However, Sections 6.5.1.6.a and 6.8.1 of Appendix A do not specify review of procedures for environmental matters. Similarly, the environ-mental activities are not listed in Section 6.5.2.1 of Appendix A as requiring independent review and audit.
To correct this situation we propose detailing the duties of the Plant Nuclear Safety Review Committee and the Nuclear Safety S Design Review Committee with regards to environmental matters in Section 5 of Appendix B with no changes to Appendix A. See the attached revised page 5.1-1.
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Mr. E. G. Case The second conflict concerns our interpretation of the reporting requirements in Appendix B, which differs from that in Appendix A, and has resulted in our reporting of failures to perform environmental monitoring as Abnormal Environmental Occurrences whether or not a specification in Appendix B, Section 2 was exceeded. If a specification is not exceeded, then a failure to perform environmental monitoring should be reported only if it represents an observed inadequacy in the implementation of administrative controls. This under-.
standing of the reporting requirements conforms with the December 1975 "For Comment" issue of Regulatory Guide 4.8, "Environmental Technical=Specifications for Nuclear Power Plants."
A revision to Appendix B, Definitions (see attached page 1.1-1), is proposed to require reportability, only when an event, "Results in noncompliance with, or is in violation of, the s ecification section of a limiting condition for operation (section 2)."
Finally, Appendix B, specification 5.4.2.1 requires submission of an "Abnormal Environmental Occurrence Report" within one week, whereas Regulatory Guide 10.1, Item 105, and Regulatory Guide 4.8, Section 5.6.2, indicate a 10-day or 30-day timing. The attached revised page 5.4-6 shows our proposed change for consistency with the applicable Regulatory Guides.
The requested revisions do not change the intent of the specifications involved, they clarify the reporting requirements and remove inconsistencies between Appendix A and Appendix B Technical Specifications.
Very truly yours, s
lang a JT mam Vice Preside Attachment Sworn and subscribed to before me this /3+ day of May 1977 in New York County, New York KATIILEENBARRY NOTARY PUBLIC, Stere of Now York No. '41-4606792 Notary Public Qudified in Queens County Certificete filed in New York County Cornnussron Lxprrus rhareh BO, 'y7$
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DEFINITIONS The following terms are defined for uniform interpretation of these specifications.
1 1 ABNORMAL ENVIRONMENTAL OCCKNZNCE (AEO An abnormal environmental occurrence is one th'at:
1.1 1 Results in noncompliance with, or is in violation of, the specification section of a limiting condition for operation (section 2);
.L.l.2 Results in uncontrolled-or-unplanned-release. of. chemical, .....-, .
= -
radioactive, thermal, or other discharges from the Donald C.
Cook Nuclear Plant in excess of the applicable regulations of governing agencies, or 1.1.3 Results in a significant adverse environmental impact.
i+2 ABSORPTION FIELD.
'The area where plant. waste water which includes sewage plant effluent is discharged on the ground and absorbed into it with no surface water runoff. This area is shown as sanitary waste ponds and process waste waste pond Xn Figure 4.1.1.5-1.
1 3 AMBIENT LAKE WATER TEMPERATURE The temperature of the water in the upper one meter in the vicinity of the Plant in the absence of any influence of Plant Operation. The method of estimating ambient lake water temperature is addressed in section 2.1.3.2.
1 4 APPARENT AVERAGE MONTHLY GROWTH
..Used with, periphyton. ..The average ofreplicate monthlyisamples..of periphyton growth. Essentially an estimate of net productivity minus some loss by wave action and grazing by herbivores.
.5 1.5.1 Benthos macroscopic aquatic invertebrate animals living
. on or in the sediment.
1.5.2 Macrophyte rooted aquatic plant.
1.1-1
5 Administrative Controls 5.1.1 Or anization Review and Audit Organization, review and audit shafl be in accordance with Section 6, Appendix A.
5.1.2 The Nuclear Safet s Desi n Review Committee shall review:-
- a. Proposed changes..in Technical Specifications.
- b. Abnormal Environmental Occurrences.
Cs Proposed procedure changes which could have environmental significance, which affect the Plant's environmental impact, and which are brought to the NSDRC's attention by the PNSRC.
- d. 'roposed plant system or equipment .changes or modifications which could have environmental significance to determine the environmental impact .of-.the. changes.
- 5. 1.3 The Plant Nuclear Safet Review Committee shall review:
- a. Proposed changes in Technical Specifications.
- b. Abnormal Environmental Occurrences.
- c. Proposed plant procedures having environmental significance as described in Section 5.3, and proposed changes thereto which affect the Plant's environmental impact.
- d. Proposed changes or modifications to Plant systems. ..
or equipment having envixonmental significance to determine the environmental impact of the changes.
5.1-1
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4>> 'Total body doses to individuals and popula ns in unrestricted areas from direct radiation from the facility.
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5>> Total body doses to, the, population and average doses,to individuals Sn the population from all receiving~ater related pathways.
6>> T tal body doses .to the-population-and-average.. doses-.to,.;individuals in the population, gaseous effluents to a 'distance of 50 miles',from .
the site ,I' significantly large population area is Lo'cated just beyond 50 mlles from rhe sdte, the dose to thds p opnlatlongroup should be considered
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I>> lfeteorolo ical Data
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- --=The report should Xnclude~h~unnrlative joint frequency. distribution. of =-
. <<iei speed, wind direction, .and atmospheric stability for the stability foi the quarterly.;.periods. Similar data should be reported separately for the.qeteoralogical conditions during batch releases..
., lfcmthly reports-on-Ash.impingement (Section 4.l.2.1.2) shall be submitted
. to the Office of Nuclear Reactor Regulation.
5 A>>2 NON-ROUTINE REPORTS e
5 4>>2 1 Abnormal Environmenteal":Occurrence-,(AEO).:==-
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the event" of an-AEO"-as-defined in'Sectio'n 1;1 'a"prompt"-report -shall be
.'within 24 III; made'-
.: hours by telephone pr telegraph to the. Director, Region Office of Inspection and Enforcement, followed by a written report within 10 days to the Director, Region III, Office of Inspection and Enforcement
. (cc to Director of. Office of Nuclear Reactor Regulation). The written teport~"and-to the-extent- possible the preliminary, telephone and telegraph Tepott~ -shall:- (a)-describe;=-analyze and evaluate the.AEO, including.
extent and magnitude of the impact, (b) describe the cause of the AEO and (c) indicate the corrective action (including= any significant changes made Xn procedures) taken to preclude repetition of the AEO. and to
- . prevent similar AEOs involving similar components or systems.---
Those events not requiring prompt reports shall be reported within 30 days by a written report, to the Director, Region XZZ, Office of Inspection and Enforcement (cc to Director of
.Office of Nuclear Reactor Regulation). The criteria for events requiring such'-reports may be.-found in Regulatory-- -.--
Guide .l. 16,'ection C.2.b.
j,d 2 2~Cha.n .es When a change to thetplant-designp.rto-the plant=operation, =or to the ytocedures described in Section 5e3 is planned which involves an .environ-mental ~tter or question not previously reviewed and evaluated by the KK,
.,:a report cn the change shai:L"bmmade. to:the-Office of-Nuclear..Reactor ~
.Regulation..prior to imple=entation. The- report shall include a- desciiption
~
and evaluation of the change.
1 Changes or, additions to permits and certificates required by Federal, State, local and regional authorities for the protection of-.the. environ-ment shall be .reported. When. the required changes are submitted .to the
RECElVEO OOCUHEHT PROCESSING UHlT 19V MAY l9 Nf 9 l4