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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20210M8251999-08-0303 August 1999 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
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20210M8251999-08-0303 August 1999 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 ML20210L9601997-08-15015 August 1997 Certified Fuel Handler Training & Retraining Program ML20135F7261997-03-0707 March 1997 Restart Readiness Plan 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 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) ML20204G1191988-08-31031 August 1988 Rev 1 to Procedure 26.1, Offsite Dose Calculation Manual ML20155D3801988-02-0101 February 1988 Rev 3 to Procedure 18-340-1, Maine Yankee Simulator Work Order ML20237G2191987-08-10010 August 1987 Co Simulator Certification Test Plan ML20237H9901987-06-30030 June 1987 Rev 0 to Procedure 26.1, Maine Yankee Atomic Power Co Offsite Dose Calculation Manual ML20215E3641987-06-30030 June 1987 Rev 0 to Emergency Response Exercise & Evaluation Plan ML20205L2201986-03-18018 March 1986 Emergency Operating Procedures Generation Package,Including Rev 1 to Plant Technical Guidelines, Rev 1 to Writers Guide & Verification of Emergency Operating Procedures for Maine Yankee Using Treat Code ML20138F3521985-10-0303 October 1985 Public Version of Rev 11 to Emergency Plan Implementing Procedure 2.50.17, Emergency Notification. W/851021 Release Memo ML20137G5921985-08-15015 August 1985 Rev 6 to Procedure 3.17.1, Class a - Integrated Containment Leak Rate Test ML20127P4391985-06-30030 June 1985 Rev 3 to 1985 Maine Yankee Nuclear Power Station Emergency Response Exercise & Evaluation Plan ML20129F1371985-06-10010 June 1985 Public Version of Rev 3 to Emergency Plan Implementing Procedure 2.50.15, Release of Public Info During Emergencies. W/850709 Release Memo ML20128B2001985-05-20020 May 1985 Core Damage Assessment Methodology ML20134J2431985-05-16016 May 1985 Rev 16 to Procedure 9.1.15, Shipment of Radioactive Matl ML20126H6461985-05-10010 May 1985 Rev 12 to Procedure 1-18-4, Spent Resin Storage & Processing ML20129B8681985-04-25025 April 1985 Public Version of Revised Emergency Plan Implementing Procedures,Including 2.50.17 Re Emergency Notification, 2.50.1 Re Notification of Unusual Event & 2.50.3 Re Site Area Emergency.W/Jm Felton 850708 Memo ML20129F1571985-04-25025 April 1985 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 10 to 2.50.4 Re General Emergency & Rev 8 to 2.50.10 Re Evaluation of Radiological Data. W/850709 Release Memo ML20129H5401984-12-0606 December 1984 Rev 10 to Procedure 3.7.4.2, Secondary Chemistry Test Frequencies & Specs ML20062B1081982-07-0909 July 1982 Public Version of Revision 3 to Emergency Plan Implementing Procedure 2.50.0, Declaration & Categorization of Emergency Condition. Revised Table of Contents Encl ML20054H6101982-06-30030 June 1982 Program to Establish Seismic Safety Margins Using Revised Criteria & Analytical Methods ML20054E8001982-05-24024 May 1982 Public Version of Procedural Change Rept 82-155 for Revision 3 to Emergency Plan Implementing Procedure 2.50.17, Emergency Notification. Receipt Form Encl ML20126G6741981-02-24024 February 1981 Me Yankee Inservice Insp Program,Revision 1,re Pump & Valve Testing ML20153B2291978-11-27027 November 1978 Inservice Insp Rept from 780129-780828,covering 1978 Refueling Outage Insp W/Abstract of Examinations Performed by Nuclear Engineering Svcs & NDT Engineering Personnel 1999-08-03
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ATTACHMENT B HAINE YANKEE ATOMIC POWER COMPANY SIMULATOR CERTIFICATION TEST PLAN l
Prepared by: ()
W. M. Svartz' Supervisor, Simulator Group Reviewed by: 7k . F M. D. Evrir$1am Operations Training Section Head p
,/
MM A. R. Shean Manager, Training Approved by: ~'
/
T. D. Frizzle Manager of Operations August 10, 1987 41 v
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1.0. OBJECTIVE-1.1 To describe the testing that will be conducted to ensure the Maine Yankee Simulator continues to meet its certification criteria, 1.2 To prescribe the method for documenting the results of simulator testing.
1.3 .To describe the administ,rative limitations on changes to the simulator testing plan and the corresponding implementing procedure.
2.0 DISCUSSION Maine Yankee Atomic Power Company owns and operates a plant specific simulator referenced to the Maine Yankee Plant. Maine Yankee has certified this simulator to the NRC in accordance with 10CFR55.45 (b)(5)(1) to the criteria contained in ANSI /ANS 3.5 as modified by Maine Yankee's form WRC-474. By certifying the simulator, Maine Yankee intends for the NRC to use the device as the simulation ,
facility for administering the operating tests to Maine Yankee operator and senior operator license _ applicants. In order to continue this use, Maine Yankee must demonstrate that their simulator continues to meet the certification
' criteria.
This plan summarizes the process used to demonstrate continued compliance with the simulator certification criteria. The detailed implementation of this plan i is controlled by a Maine Yankee approved procedure.
3.0 LIMITATIONS 3.1 ; Maine Yankee may modify this plan or its implementing procedure without notifying the NRC as long as the changes do not decrease the scope or frequency of testing.
3.2 The testing described herein will be performed or directed by an individual licensed by the NRC as a Maine Yankee Santor Reactor Operator.
4.0 TEST PLAN The following testing will be performed and the results documented on a calendar year basis:
- 1. Reactor Coolant System Heat-Up The simulator is initialized to cold shutdown, operational data is taken from the simulator and compared to reference plant data. The plant heat-up procedure is used to bring the plant (simulator) to a hot shutdown condition.
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- 2. Reactor Startup J The Reactor Startup procedure is used to perform a reactor startup to bring the simulator to a het standby condition. Once again referenced plant data is compared to siinulator data.
- 3. Low Power Physics Tests This section tests the r.eactivity coefficients of the core model to ensure i they are within acceptable guidelines.
- 4. Power Escalation Testing The simulator 1s taken to power by using actual plant procedures. Further core physics tests are performed using actual plant procedures. During this test we also perform the simulator stability test, heat balance comparison (simulator vs. reference plant) and an instrument comparison where the applicable instrument readings from the reference plant and the simulator are compared and a report is automatically generated. It should be noted that not all instruments are compared since there are many that are not applicable, such as tide level and certain electric plant readings that are dependant upon dispatacher loading.
- 5. Plant Shutdown and Cooldown The simulator is shutdown (100% power to 07.) and cooled down in accordance with plant procedures.
- 6. Malfunction Testing The Maine Yankee simulator has approximately 160 malfunctions at this time.
These malfunctions are sorted by systems (ie, Reactor Coolant, Main Steam, CVCS, etc.). Approximately 25% of the malfunctions are performed every year 1 so as to test each malfunction at least once during a 4 year cycle.
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- 7. Surveil'ance Testing Safeguards related surveillance procedures that are conducted monthly or less are performed on the simulator using the actual plant procedure. Plant data is compared to simulator data on valve stroke times, discharge pressures and flows of pumps, amp readings on pumps, etc.
- 8. Simulator Operation Testing This section of the procedure deals with items that are specific to simulator operations rather than the operational ability (fidelity) of the simulator. Each year major panel (we have 4) annunciators are tested to ensure " Cry Holf" is operational and all offsets are correct. All annunciators are thereby tested every 4 years. To ensure the simulator is operating in real time, a time and memory test is performed. This is backed up by an operational timing test when specific equipment modeled by the simulator is operated within certain time limits. The final portion of this section tests the emergency shutdown buttons on each panel.
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- 9. -Benchmark Analysis '
Subsequent to acceptance of the Simulator, Maine Yankee contracted Yankee Atomic Electric Co. to perform a benchmark analysis for specific
't transients. The transients were:
- 1. Symmetric steam line break downstream of the steam stop valves.
- 2. Loss of-feedwater ATHS.
These transients were ru'n using best estimate versions of RELAP and RETRAN, the transients were then run on the simulator. Every year we perform these
-same transients.and compare them to the original best estimate results.
- 10. Simulator Base Line Transients These are transients that are performed every year. The data collection i method and types of transients are based upon Appendix B to ANSI /ANS-3.5,.
1985. The parameters are graphed with the previous year compared to the present year to ensure no changes were made to the-coding that causes these transient responses to be incorrect. l 5.0 DOCUMENTATION l The results of the annual simulhtor testing will be documented in the simulator. l annual report. The annual report will provide the information described in !
Appendix A to ANSI /ANS 3.5 and will be retained on file at the plant site for H the life of the simulator.
6.0. REFERENCES 6.1 Title 10, Code of Federal Regulations, Part 55, " Operator Licenses."
6.2 American National Standard Nuclear Power Plant Simulators for use in ;
Operator Training, ANSI /ANS-3.5-1985. !
l 6.3 U.S. Nuclear Regulatory Guide 1.149 " Nuclear Power Plant Simulation )
Facilities for use in Operator License Examinations", April 1987. l 6.4 Maine Yankee letter to the NRC, MN-87-90, subject: Certification of the Maine Yankee Simulator, dated with attached Form NRC-474. i 2557t