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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20204B6321999-03-21021 March 1999 Plant Referenced Simulation Facility Four Year Performance Testing Rept ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy1998-02-28028 February 1998 Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20198G7211997-04-0303 April 1997 Hot Rolled XM-19 Stainless Steel Core Shroud Tie-Rod Matl - Crevice Corrosion Investigation ML20136H3771997-03-11011 March 1997 Rev 0 to Power Uprate Startup Test Rept for Cycle 13 ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day 1999-09-29
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20094J2421995-09-13013 September 1995 Rev 9 to Ja Fitzpatrick Nuclear Power Plant IST Program for Pumps & Valves Second Interval ML20078A5211995-01-18018 January 1995 Rev 2 to Core Operating Limits Rept ML20063L9621993-12-28028 December 1993 Rev 0 to DVP-01.02, Radiological Effluent Controls & Odcm ML20056D0151993-04-0606 April 1993 Rev 7 of Ja FitzPatrick IST Program for Pumps & Valves ML20115J1891992-08-31031 August 1992 Startup Readiness Evaluation (Sure) for James a Fitzpatrick Nuclear Power Plant ML20099J2081992-06-30030 June 1992 Assessment of Fitzpatrick Results Improvement Program ML20101H4711992-06-0808 June 1992 JAF-RPT-MISC-00543, Analog Transmitter Trip Sys Transmitter Response Time Testing Methodology JPN-91-054, Rev 4 to Second Interval Inservice Testing Program for Pumps & Valves1991-09-27027 September 1991 Rev 4 to Second Interval Inservice Testing Program for Pumps & Valves ML20012B0331989-12-20020 December 1989 Rev 7 to Odcm. ML20148A2251988-03-15015 March 1988 Hydrogen Water Chemistry Sys for James a Fitzpatrick Nuclear Power Plant. W/Three Oversize Drawings ML20235S6001987-06-30030 June 1987 Rev 2 to Procedure PDP-3. Direct Reading Dosimeter Calibr ML20235S6141987-05-15015 May 1987 Rev 3 to Procedure PDP-7, Dosimetry Sys Calibr & QC Procedure ML20206N1771987-03-31031 March 1987 Rev 5 to Ja Fitzpatrick Nuclear Power Plant Offsite Dose Calculation Manual. Two Oversize Maps Encl ML20235S6101987-03-0404 March 1987 Rev 4 to Procedure PDP-6, Rem Sys Instructions ML20209J0981987-01-0707 January 1987 Revised Emergency Plan Implementing Procedures,Including Rev 5 to IAP-2, Classification of Emergency Conditions, Rev 11 to EAP-1.1, Offsite Notifications & Rev 7 to EAP-2, Personnel Injury ML20207T6241986-12-31031 December 1986 Rev 4 to Offsite Dose Calculation Manual ML20206L4821986-07-30030 July 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 7 to EAP-17, Emergency Organization Staffing & Rev 7 to SAP-3, Emergency Communications Testing. W/Undated Release Memo ML19302A5181986-05-15015 May 1986 Advanced Technical Training Program for Ja Fitzpatrick Nuclear Power Plant. L-86-024, Installation Procedure ML-86-024, Limitorque Valve Actuator Qualification Insp/Upgrades. Result Summary of Limitorque Control Wire Insps,Per IE Info Notice 86-003,encl1986-03-0606 March 1986 Installation Procedure ML-86-024, Limitorque Valve Actuator Qualification Insp/Upgrades. Result Summary of Limitorque Control Wire Insps,Per IE Info Notice 86-003,encl ML20138A7651986-02-28028 February 1986 Revised Emergency Plan Implementing Procedures,Including Rev 3 to IAP-1, Emergency Plan Implementation Checklist, Rev 4 to IAP-2, Classification of Emergency Conditions & Rev 8 to EAP-1.1, Offsite Notifications ML20136H4721985-11-0101 November 1985 Revised Emergency Plan Implementing Procedures,Including Rev 5 to SAP-3 Re Emergency Communications Testing Rev 5 to EAP-22 Re Operation & Use of Radio Paging Device & Rev 14 to EAP-2 Re Personnel Injury ML20205C9461985-09-0606 September 1985 Rev 3 to Fitzpatrick Emergency Procedure Guidelines ML20129J7201985-06-30030 June 1985 Emergency Plan Implementing Procedures,Vols 2 & 3,including Rev 5 to EAP-4, Dose Estimates from Dose Assessment Calculator & Rev 3 to EAP-6, In-Plant Emergency Survey/Entry ML20212B1031985-06-25025 June 1985 Rev 2 to Offsite Dose Calculation Manual ML20128G9231985-06-19019 June 1985 Rev 0 to Procedure EDP-16, Procedure for Technical Review of Procurement Documents ML20116N6881985-04-30030 April 1985 Long-Term Pipe Support Insp & Evaluation Program Plan ML20205A9481985-04-17017 April 1985 Administrative Procedure AP 1.10, Process Control Program ML20205C9701985-02-0808 February 1985 Rev 5 to Administrative Procedure AP 2.2, Procedure for Emergency Operating Procedures ML20100A9571984-11-30030 November 1984 SPDS Implementation Plan for Ja Fitzpatrick Nuclear Power Plant ML20128G9091984-09-13013 September 1984 Rev 3 to Procedure PSO 28, Operating Experience Feedback ML20128G8981984-08-23023 August 1984 Rev 1 to Procedure EDP-12, Procedure for Establishing QA Category Classifications ML20094F5711984-07-18018 July 1984 Emergency Response Plan Exercise Manual for Ja Fitzpatrick Nuclear Power Plant ML20083N9001984-03-23023 March 1984 Rev 2 to Procedure RTP-34, Contamination Radiation Monitoring - Post-Accident ML20083N8961984-03-23023 March 1984 Rev 1 to Procedure RTP-46, Core Estimation Damage, Post-Accident Sampling Sys ML20087G6771984-02-29029 February 1984 Revised Proposed Disposal Procedures for Radioactively Contaminated Fuel Oil ML20092P6771984-02-0909 February 1984 Procedure 23, Post-Trip Evaluation ML20081B9441983-10-31031 October 1983 Revised Offsite Dose Calculation Manual ML20090H3041983-10-19019 October 1983 Detailed Control Room Design Review Program Plan for Ja Fitzpatrick Nuclear Power Plant ML20085K7581983-10-12012 October 1983 Emergency Response Plan Exercise Manual ML20072D3151983-06-21021 June 1983 Offsite Dose Calculation Manual ML20078J8471983-04-30030 April 1983 Rev 1 to Procedure SAP-1, Emergency Response Plan Exercise Manual ML20069E6861983-03-18018 March 1983 Change 1 to Rev 3 of Inservice Testing Program for Pumps & Valves 1999-10-13
[Table view] |
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- scenario accurately simulates operating events , it is not in-tended to assess all of the Operator's diagnostic capabilities, but rather provides sequences which ultimately demonstrate the Operator's ability to respond to events, and which results in exercising both. onsite and offsite emergency plans and proce-4 dures. Free play is encouraged and the referees will interfere only if operator / player action prematurely terminates the exer-
! cise or excessively deviates from the drill schedule, j In order to provide a conservative exercise, in terms of offsite doses, adverse meteorology was developed since actual meteorolo-gy would probably lead to projected radiological doses below es-
- tablished Protective Action Guides (PAGs).
} D. CONCEPT OF OPERATIONS AND CONTROL OF THE EXERCISE The licensee and the State of New York will supply official con-trollers / evaluators for locations where an emergency response is
. being demonstrated for the exercisa. Prior to the exercise, the
, controllers and evaluators will be provided with the appropriate
- locations, maps, time periods, guidelines (as appropriate train-ing in the use of equipment and procedures), and an observer j evaluation checklist for their exercise assignments.
l The exercise initiating events will be controlled by the lead
! referee at the JAFNPP. Simulated initiating events will consist l of two types of information: (1) information and data provided to Control Room personnel by the Control Room referee, (2) on-site and offsite dose rate data (simulated gamma and iodine dose i
rate measurements) provided to the site, County and Federal (if they participate) monitoring teams by controllers / referees.
4 The lead referee (ons,ite) and the State Exercise Director (off-site) will have the responsibility to control and coordinate the j time sequence of initiating events to ensure an orderly flow of :
exercise events.
I The state controllers or evaluators may supply " problems" for offsite participants (such as a disabled vehicle or a farmer who must return to his farm after the evacuation). All other ac-l
' tions during the exercise will occur through a free play re-sponse as the licensee, State and County participants respond to i the initiating events.
i As the initiating events are provided to the JAFNPP staff, they will determine the nature of the emergency and implement appro-1 priate plant emergency response procedures. These procedures l
! include a determination of the emergency classification in ac- l l
cordance with the JAFNPP Emergency Plan. After the emergency classification has been determined, the appropriate Federal, State and local authorities will be notified in accordance with ,
i the JAFNPP emergency response procedures.
Eh0 3 DR , ,1-7
- o. l Upon notification of the simulated accident at the JAFNPP, the State and Oswego County will complete their initial notifica-tions in accordance with their emergency plans and . procedures.
State and local personnel and facilities will be activated based on the initial accident classification provided by the site and confirmed by direct communication between appropriate agencies and the James A. FitzPatrick Nuclear Power Plant.
, The simulated accident will continue to develop based on data and information provided to the Control Room personnel by the Control Room referee. As the situation develops, information will be forwarded to New York State and the County assessment j teams. These agencies will analyze and act on the information
- as they would in a real emergency.
1 l -
Where information would normally be confirmed via an independent source, the confirmation data will be obtained. If the confir-mation data conflicts with simulation data provided by the site, i the simulation data will be utilized for accident assessment
, purposes. If any inconsistencies are noted in the initiating
~
events, these inconsistencies should be questioned by the acci-dent assessment teams as they would be in a real emergency.
Certain inconsistencies (such as plume width, release duration, '
technical reason for the simulated release, etc.) may be inten-
- tional and required due to the nature of simulating an accident that has never occurred, and the requirement to provide an exer-cise basis which tests the site, State, and local capabilities to the maximum extent feasible in a limited time frame. If an inconsistency is known or determined to be intentional, then the i accident assessment group will note the inconsistency and ignore
- it. The lead referee shall have the authority to resolve or ex-i plain any inconsistencies or problems that may occur during the j exercise.
l With the exception of the aforementioned potential inconsisten-cies, the internal operation of the site, State and local com-mand centers shall be identical with their intended operation in a real emergency.
E. PUBLIC INFORMATION AND AWARENESS l
Prior to the exercise, the public, within the affected area, will be informed of the impending conduct of a radiological emergency exercise through joint press releases. The New York Power Authority, New York State and Oswego County will develop coordinated press releases.
Agencies should make every effort to prevent the public from being misinformed about the nature of the exercise. Therefore, it is important to inform members of the public that an exercise is in progress and that their involvement is not required, when-ever public contact occurs in the field.
, 'l-8.f.k.
A pre-exercise briefing will also be conducted for the news media.
F. MAINTAINING EMERGENCY READINESS During the performance of an exercise, the ability to recognize a real emergency, terminate the exercise, and respond to the new situation must be maintained. Therefore, the exercise scenario and actions of aarticipants shall not include any actions which degrade the conc ition of systems, equipment or supplies, or af-
-fect the detection, assessment or response capability to radio-logical or other emergencies.
Actions taken by the participants shall also avoid actually re-ducing plant or public safety. The potential for creating real radiological or other emergencies shall be specifically avoided.
All messages about real events shall be clearly identified as such. For example, precede a real message with "This is NOT, repeat, NOT an exercise message".
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