ML20150G053
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| ML20150G053 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 03/28/1988 |
| From: | Maine Yankee |
| To: | |
| Shared Package | |
| ML20150E410 | List: |
| References | |
| NUDOCS 8804060178 | |
| Download: ML20150G053 (2) | |
Similar Documents at Maine Yankee | |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20236T4781998-07-14014 July 1998
[Table view]Proposed Tech Specs Revising Liquid & Gaseous Release Rate Limits to Reflect Replacement of Former 10CFR20.106 Requirements W/Existing 10CFR20.1302 Requirements ML20216F8951998-04-13013 April 1998 Proposed Tech Specs Re Fuel Storage Pool Water Level ML20216E1841998-03-10010 March 1998 Updated TS Pages 5-8 Through 5-14,which Includes Specifications Relating to Cold Weather Operations & Spent Fuel Pool Water Chemistry ML20202H5041998-02-10010 February 1998 Proposed Tech Specs Page 5-8,including Specification Re Cold Weather Operations ML20212A6211997-10-20020 October 1997 Proposed Tech Specs Re Permanently Defueled Status of Plant ML20210M5871997-08-15015 August 1997 Proposed Tech Specs Revising Facility Staffing & Training Requirements ML20137S8891997-04-0808 April 1997 Proposed Tech Specs Reducing RCS Flow ML20136B5261997-03-0505 March 1997 Proposed Tech Specs,Requesting Approval of Alternative Sleeving Repair Process for SG Tubes at Plant ML20134J6641997-02-0707 February 1997 Proposed Tech Specs Pages 3.12-1,3.12-2 & 3.12-3 Re 115 Kv Offsite Power Requirements ML20134J6311997-02-0707 February 1997 Proposed Tech Specs 4.10.C.2 Re SG Tube Surveillance Requirements ML20133N0471997-01-15015 January 1997 Proposed Tech Specs 4.4 Re Containment Testing ML20133A7131996-12-19019 December 1996 Proposed Tech Specs 3.13 Re Refueling & Fuel Consolidation Operations & Table 4.2-1 Re Minimum Frequencies for Sampling Tests ML20129F8831996-09-25025 September 1996 Proposed Tech Specs Re Organization Change Affecting Nuclear Safety Audit & Review Committee ML20127P2471993-01-25025 January 1993 Proposed Tech Specs Change 177 Re Main Yankee Spent Fuel Pool Reracking ML20126B6911992-12-15015 December 1992 Proposed TS 3.19 Re Position Restrictions on Loop Isolation Valves,Safety Injection Header Isolation Valves & Safety Injection Tank Isolation Valves ML20198D0771992-05-0808 May 1992 Proposed Tech Spec 1.4.D, Containment Purge Sys ML20141M1181992-03-24024 March 1992 Proposed TS Spec 1.3 Re Fuel Enrichment Limit in Reactor Core ML20062D2851990-11-0505 November 1990 Proposed Tech Specs Re Removal of cycle-specific Operating Limits ML20058B6071990-10-15015 October 1990 Proposed Tech Specs Modifying 3.22, Feedwater Trip Sys, by Adding Exception Specifically Addressing Operation of Emergency Feedwater Sys During Plant Startups & Shutdowns ML20058L9311990-07-30030 July 1990 Proposed Tech Spec Page 5.2-2 Re Manager Qualification for Operations ML20055G3121990-07-10010 July 1990 Proposed Tech Specs Consisting of Proposed Change 155 Re Safety Injection Actuation Sys ML20055E0981990-07-0505 July 1990 Proposed Tech Specs Re Qualification Requirements for Operations Manager ML20235H5581989-02-15015 February 1989 Proposed Tech Specs,Adding Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouples Channel Operability & Surveillance Requirements to Sections 3.9 & 4.1 ML20196B5301988-11-22022 November 1988 Proposed Tech Specs Supporting Change 134 Re Main Steam Excess Flow Check Valve & Turbine Valve Testing Frequency ML20206F2341988-11-0808 November 1988 Proposed Tech Spec 1.1, Fuel Storage ML20206C2901988-10-26026 October 1988 Proposed Tech Specs,Deleting Offsite & Facility Organization Charts,Figures 5.2-1 & 5.2-2 ML20205M9751988-10-18018 October 1988 Proposed Tech Specs,Modifying Specified Surveillance Interval for Control Element Assembly Partial Movement Test Frequency,Per C-E STS ML20207E2611988-08-0202 August 1988 Errata to Proposed Tech Specs Figure 3.10-4,showing Allowable Unrodded Radial Peak as Function of Cycle Average Burnup for Cycle 11 Operation ML20150E9021988-06-30030 June 1988 Proposed Tech Specs,Consisting of Proposed Change 141,to Reflect Operating Parameters for Cycle 11 ML20150G0531988-03-28028 March 1988 Proposed Tech Specs,Increasing Max Nominal Fuel Enrichment from 3.5% to 3.7% U-235 ML20147G9011988-03-0101 March 1988 Proposed Tech Specs Reflecting Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure ML20235A8321988-01-0606 January 1988 Proposed Tech Specs,Revising Offsite & Facility Organizational Charts ML20236G5111987-07-30030 July 1987 Proposed Tech Specs,Consisting of Proposed Change 132, Replacing Page 3.10-4 Re Incore Monitoring Sys ML20216B8871987-06-23023 June 1987 Revised Tech Spec Page 5.8-2 Re Process Control Program ML20212K9901987-02-24024 February 1987 Proposed Tech Spec Change 130,reflecting Revised LOCA Limits ML20212D9851987-02-24024 February 1987 Proposed Tech Specs 5.9.1.6 & 5.9.1.7,allowing Addl Time for Filing of Supplemental Dose & Meteorological Summary Repts & Ensuring That Spec Refs Consistent W/Current Tech Specs, Respectively ML20212L1581987-01-13013 January 1987 Proposed Tech Specs Re RCS Emergency Vent Sys ML20207P5301987-01-12012 January 1987 Proposed Tech Spec Pages 2.2-1,3.10-9,3.10-12 & 3.10-13,re Reactor Core Safety Limits & Power Dependent Insertion Limit,Supporting Proposed Change 128 for Cycle 10 Operation ML20215C2431986-12-0808 December 1986 Proposed Tech Specs Re Limiting Overtime of Staff Personnel ML20212C0281986-07-29029 July 1986 Proposed Tech Specs Re Reporting Requirements for Primary Coolant Sys Iodine Spikes ML20203F1331986-07-16016 July 1986 Proposed Tech Specs Removing Cycle Reload Specific Parameters ML20203Q3181986-05-0505 May 1986 Proposed Tech Specs,Incorporating Proposed Change 122, Substituting Table 4.2-2, Min Frequencies for Equipment Tests, for Existing Table Re Turbine Valve Test Frequencies ML20204A3841986-05-0101 May 1986 Revised Tech Spec 3.11.5,adding Five Manual Isolation Valves of post-accident Hydrogen Purge & Analysis Sys to List of Manual Containment Isolation Valves That May Be Repositioned W/O Implementing Compensatory Measures ML20151U4741986-02-0303 February 1986 Proposed Tech Spec,Adding Administrative Controls on Limiting Overtime of Personnel & Removing Offsite & Onsite Organizational Charts from Tech Spec 5.2 ML20137Q9061986-01-29029 January 1986 Proposed Tech Spec Change 115, Adopting Model for LER Reporting Requirements Re Iodine Spikes in Primary Coolant, Per Generic Ltr 85-19 ML20138M5971985-12-16016 December 1985 Proposed Tech Specs,Incorporating Limiting Condition for Operations for turbine-driven Auxiliary Feedwater Pump ML20138P6361985-12-13013 December 1985 Suppl 1 to Proposed Change 110 Revising Tech Spec Pages 4.6-1,4.6-3 Through 4.6-6 & 4.1-9 Re Emergency Feedwater Sys ML20138J3341985-12-0909 December 1985 Proposed Tech Spec Change 118,allowing Consideration of Fire Hazards in Vicinity of Affected Penetration When Determining Level of Compensatory Fire Protection ML20133K5791985-10-16016 October 1985 Proposed Tech Spec,Deleting Present Requirement for Emergency Diesel Generator Testing in Event That Any Component in One Train of Cooling Sys Becomes Inoperable ML20133F4341985-10-0707 October 1985 Proposed Change 114,Suppl 1,revising Tech Spec Pages 3.11-2 & 3.11-5 Re Containment Isolation Valves Under Administrative Controls 1998-07-14 Category:TECHNICAL SPECIFICATIONS & TEST REPORTS MONTHYEARML20210M8251999-08-0303 August 1999
[Table view]Draft License Termination/Amend Plan for Maine Yankee Atomic Power Co ML20206D7981998-11-10010 November 1998 Revised Maine Yankee Odcm ML20237D0671998-08-19019 August 1998 Rev 1 to Maine Yankee Certified Fuel Handler Training & Retraining Program ML20236T4781998-07-14014 July 1998 Proposed Tech Specs Revising Liquid & Gaseous Release Rate Limits to Reflect Replacement of Former 10CFR20.106 Requirements W/Existing 10CFR20.1302 Requirements ML20216F8951998-04-13013 April 1998 Proposed Tech Specs Re Fuel Storage Pool Water Level ML20216E1841998-03-10010 March 1998 Updated TS Pages 5-8 Through 5-14,which Includes Specifications Relating to Cold Weather Operations & Spent Fuel Pool Water Chemistry ML20202H5041998-02-10010 February 1998 Proposed Tech Specs Page 5-8,including Specification Re Cold Weather Operations ML20212A6211997-10-20020 October 1997 Proposed Tech Specs Re Permanently Defueled Status of Plant ML20210M5871997-08-15015 August 1997 Proposed Tech Specs Revising Facility Staffing & Training Requirements ML20210L9601997-08-15015 August 1997 Certified Fuel Handler Training & Retraining Program ML20137S8891997-04-0808 April 1997 Proposed Tech Specs Reducing RCS Flow ML20135F7261997-03-0707 March 1997 Restart Readiness Plan ML20136B5261997-03-0505 March 1997 Proposed Tech Specs,Requesting Approval of Alternative Sleeving Repair Process for SG Tubes at Plant ML20134J6641997-02-0707 February 1997 Proposed Tech Specs Pages 3.12-1,3.12-2 & 3.12-3 Re 115 Kv Offsite Power Requirements ML20134J6311997-02-0707 February 1997 Proposed Tech Specs 4.10.C.2 Re SG Tube Surveillance Requirements ML20133N0471997-01-15015 January 1997 Proposed Tech Specs 4.4 Re Containment Testing ML20133G3281996-12-23023 December 1996 Cycle 15 Startup Test Rept Suppl 5 ML20133A7131996-12-19019 December 1996 Proposed Tech Specs 3.13 Re Refueling & Fuel Consolidation Operations & Table 4.2-1 Re Minimum Frequencies for Sampling Tests ML20129F8831996-09-25025 September 1996 Proposed Tech Specs Re Organization Change Affecting Nuclear Safety Audit & Review Committee ML20138F4031996-04-11011 April 1996 Revised Maine Yankee Odcm ML20148C6581994-12-31031 December 1994 Guidelines for Diagnostic Evaluation,Dec 1994,Rev 4 ML20148C6511994-12-31031 December 1994 Diagnostic Evaluation Team Managers Handbook,Dec 1994, Rev 1 ML20128D6761993-01-28028 January 1993 Co ISI Program for Third ISI Interval 921228-021228 ML20127P2471993-01-25025 January 1993 Proposed Tech Specs Change 177 Re Main Yankee Spent Fuel Pool Reracking ML20126B6911992-12-15015 December 1992 Proposed TS 3.19 Re Position Restrictions on Loop Isolation Valves,Safety Injection Header Isolation Valves & Safety Injection Tank Isolation Valves ML20198D0771992-05-0808 May 1992 Proposed Tech Spec 1.4.D, Containment Purge Sys ML20141M1181992-03-24024 March 1992 Proposed TS Spec 1.3 Re Fuel Enrichment Limit in Reactor Core ML20062D2851990-11-0505 November 1990 Proposed Tech Specs Re Removal of cycle-specific Operating Limits ML20058B6071990-10-15015 October 1990 Proposed Tech Specs Modifying 3.22, Feedwater Trip Sys, by Adding Exception Specifically Addressing Operation of Emergency Feedwater Sys During Plant Startups & Shutdowns ML20059N7671990-10-0101 October 1990 Cycle 12 Startup Test Rept ML20058L9311990-07-30030 July 1990 Proposed Tech Spec Page 5.2-2 Re Manager Qualification for Operations ML20055G3121990-07-10010 July 1990 Proposed Tech Specs Consisting of Proposed Change 155 Re Safety Injection Actuation Sys ML20055E0981990-07-0505 July 1990 Proposed Tech Specs Re Qualification Requirements for Operations Manager ML20055D4651990-02-20020 February 1990 Rev 3 to Procedure 0-07-1, Matl Receipt ML20055D4691989-08-15015 August 1989 Rev 4 to Procedure 0-15-1, Nonconformance Repts (Ncr) ML20235H5581989-02-15015 February 1989 Proposed Tech Specs,Adding Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouples Channel Operability & Surveillance Requirements to Sections 3.9 & 4.1 ML20196B5301988-11-22022 November 1988 Proposed Tech Specs Supporting Change 134 Re Main Steam Excess Flow Check Valve & Turbine Valve Testing Frequency ML20206F2341988-11-0808 November 1988 Proposed Tech Spec 1.1, Fuel Storage ML20246H5281988-10-31031 October 1988 Reactor Containment Bldg Integrated Leak Rate Test for Oct 1988 ML20206C2901988-10-26026 October 1988 Proposed Tech Specs,Deleting Offsite & Facility Organization Charts,Figures 5.2-1 & 5.2-2 ML20205M9751988-10-18018 October 1988 Proposed Tech Specs,Modifying Specified Surveillance Interval for Control Element Assembly Partial Movement Test Frequency,Per C-E STS ML20204G1191988-08-31031 August 1988 Rev 1 to Procedure 26.1, Offsite Dose Calculation Manual ML20207E2611988-08-0202 August 1988 Errata to Proposed Tech Specs Figure 3.10-4,showing Allowable Unrodded Radial Peak as Function of Cycle Average Burnup for Cycle 11 Operation ML20150E9021988-06-30030 June 1988 Proposed Tech Specs,Consisting of Proposed Change 141,to Reflect Operating Parameters for Cycle 11 ML20150G0531988-03-28028 March 1988 Proposed Tech Specs,Increasing Max Nominal Fuel Enrichment from 3.5% to 3.7% U-235 ML20147G9011988-03-0101 March 1988 Proposed Tech Specs Reflecting Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure ML20155D3801988-02-0101 February 1988 Rev 3 to Procedure 18-340-1, Maine Yankee Simulator Work Order ML20235A8321988-01-0606 January 1988 Proposed Tech Specs,Revising Offsite & Facility Organizational Charts ML20237G2191987-08-10010 August 1987 Co Simulator Certification Test Plan ML20236G5111987-07-30030 July 1987 Proposed Tech Specs,Consisting of Proposed Change 132, Replacing Page 3.10-4 Re Incore Monitoring Sys 1999-08-03 |
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h$8hIleYaintee AT'ACHMENT 8 1.3 REACTOR 6policability Applies to the reactor vessel, vessel core and internals, as well as the Reactor Coolant System and components, including associated Emergency Core Cooling Systems.
Objectivei To define those design criteria essential in providing for safe system operation which are not covered in Sections 2 and 3.
Sgtcification A. Bfactor Core The reactor core shall contain 217 fuel assemblies with each assembly containing 176 rods. Each fuel rod clad with Zircaloy-4 shall have a nominal active fuel length of 136.7 inches. The fuel shall have a maximum nominal enrichment of 3.70 weight percent U-235. 3 The core excess reactivity shall be controlled by a combination of boric acid chemical shim, Control Element Assemblies (CEAs) and mechanically fixed non-fuel rods when required. The non-fuel rods may be fixed alumina-boron carbide, solid metal or open tubes.
There are a total of eighty-one (81) full-length, full-strength CEAs provided. Forty (40) of these are paired to form twenty (20) dual CEAs.
Seventy-seven (77) CEAs, including all dual CEAs, are trippable. Four (4) of the CEAs are nontrippable.
8804060170 000324 PDR ADOC6. 05000309 P PDR 1,3-1 03/28/88 9636L-RPJ
MaineYankee 1
ATTACHHENT C CRITICALITY ANALYSIS OF MAINE YANKEE'S SPENT FUEL POOL AND NEH FUEL VAULT YAEC-1637, February, 1988 l
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