Similar Documents at Ginna |
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17250B3061999-10-20020 October 1999 Proposed Tech Specs,Consisting of 1999 Changes to TS Bases ML17265A6941999-06-28028 June 1999 Proposed Tech Specs,Revising ITS Associated with RCS Leakage Detection Instrumentation,As Result of Commitment Submitted as Part of Staff Review of Application of leak-before-break Status to Protions of RHR Piping ML17265A6401999-05-12012 May 1999 Rev 11 to Technical Requirements Manual for Ginna Station. ML17265A6261999-04-18018 April 1999 Rev 10 to Technical Requirements Manual (Trm), for Ginna Station ML17311A0701999-04-14014 April 1999 Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure. ML17309A6521999-04-14014 April 1999 Rev 14 to AP-RCS.1, Reactor Coolant Leak. ML17309A6531999-04-13013 April 1999 Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr ML17265A6111999-03-26026 March 1999 Rev 9 to Technical Requirements Manual for Ginna Station. ML17265A5911999-03-0101 March 1999 Proposed Tech Specs Change Revising Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6) ML17265A5571999-02-25025 February 1999 Rev 4 to Technical Requirements Manual (Trm). ML17265A5491999-02-12012 February 1999 to EOP FR-H.5, Response to SG Low Level. ML17265A5481999-02-12012 February 1999 to EOP ATT-22.0, Attachment Restoring Feed Flow. ML17265A5461999-02-12012 February 1999 0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required. ML17309A6481999-01-25025 January 1999 Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr ML17265A5151999-01-14014 January 1999 Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index ML17265A5081999-01-0808 January 1999 Rev 7 to Technical Requirements Manual, for Ginna Station ML17265A4961998-12-18018 December 1998 Rev 6 to Technical Requirements Manual. ML20198C0361998-12-14014 December 1998 Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required ML20198C0121998-12-14014 December 1998 Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow ML20198C0581998-12-14014 December 1998 Rev 5 to FR-Z.1, Response to High Containment Pressure ML20198C0411998-12-14014 December 1998 Rev 16 to FR-C.1, Response to Inadequate Core Cooling ML20198C0521998-12-14014 December 1998 Rev 13 to FR-S.1, Response to Reactor Restart/Atws ML17265A4661998-11-24024 November 1998 Proposed Tech Specs 4.2.1,revising Description of Fuel Cladding Matl & Updating List of References Provided in TS 5.6.5 for COLR ML20155G0301998-10-30030 October 1998 Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop ML17265A4091998-08-24024 August 1998 Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr ML17265A3721998-07-16016 July 1998 Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr ML17265A3151998-06-0404 June 1998 Proposed Tech Specs Basis Re Main Steam Isolation Setpoint ML17265A2941998-05-21021 May 1998 Tech Specs Consisting of Submittal Changes for 1998 ML17265A2861998-05-0606 May 1998 Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr ML17265A2461998-04-27027 April 1998 Proposed Tech Specs Revising Requirements Associated W/Sfp to Reflect Planned Mod to Storage Racks & Temporarily Addressing Boraflex Degradation within Pool ML17265A1821998-02-20020 February 1998 Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria. ML17265A1491997-12-31031 December 1997 Rev 1 to Inservice Testing Program. ML17264B0731997-10-14014 October 1997 Rev 4 to Technical Requirements Manual (TRM) for Ginna Station. ML17264B0671997-10-0808 October 1997 Proposed Tech Specs,Correcting & Clarifying Info Re RCS Pressure & Temp Limits Rept Administrative Controls Requirements ML17264B0441997-09-29029 September 1997 Proposed Tech Specs Revising Adminstrative Controls W/ Respect to Reactor Coolant Sys Pressure & Temp Limits Rept ML17264B0391997-09-29029 September 1997 Proposed Tech Specs Revising Allowable Value & Trip Setpoint for High Steam Flow Input Into LCO Table 3.3.2-1,Function 4d (Main Steam Isolation) to Address Issues Identified in Rev Revised Setpoint Analysis Study ML17265A1541997-09-16016 September 1997 Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification. ML17264B0031997-08-19019 August 1997 Proposed Tech Specs Allowing Testing of Three ECCS motor- Operated Valves in Mode 4 Which Currently Requires Entry Into LCO 3.0.3 ML17264A9991997-08-19019 August 1997 Proposed Tech Specs Correcting Specified Accumulator Borated Water Volume Values in SR 3.5.1.2 to Match Associated Accumulator Percent Level Values ML17264A9791997-08-0505 August 1997 Rev 7 to AP-RCS.3, High Reactor Coolant Activity. ML17264A9781997-08-0505 August 1997 Rev 12 to AP-RCS.1, Reactor Coolant Leak. ML17264A9771997-08-0505 August 1997 Rev 11 to AP-RCP.1, RCP Seal Malfunction. ML17264A9751997-08-0505 August 1997 Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses. ML17264A9851997-08-0404 August 1997 Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants. ML17264A9391997-07-0707 July 1997 Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev ML17264A9341997-07-0101 July 1997 to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624 ML17264A9461997-06-20020 June 1997 to Inservice Insp (ISI) Program. ML17264A9241997-06-0303 June 1997 Proposed Tech Specs Clarifying Issues Re Low Temperature Overpressure Protection ML17311A0471997-05-22022 May 1997 Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr ML17264A8671997-04-24024 April 1997 Proposed Tech Specs,Revising Rcs,Pt & Administrative Control Requirements 1999-06-28
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17265A6401999-05-12012 May 1999 Rev 11 to Technical Requirements Manual for Ginna Station. ML17265A6261999-04-18018 April 1999 Rev 10 to Technical Requirements Manual (Trm), for Ginna Station ML17309A6521999-04-14014 April 1999 Rev 14 to AP-RCS.1, Reactor Coolant Leak. ML17311A0701999-04-14014 April 1999 Rev 10 to AP-PRZR.1, Abnormal Pressurizer Pressure. ML17309A6531999-04-13013 April 1999 Rev 1 to FIG-2.0, Figure Sdm. with 990413 Ltr ML17265A6111999-03-26026 March 1999 Rev 9 to Technical Requirements Manual for Ginna Station. ML17265A5571999-02-25025 February 1999 Rev 4 to Technical Requirements Manual (Trm). ML17265A5481999-02-12012 February 1999 to EOP ATT-22.0, Attachment Restoring Feed Flow. ML17265A5491999-02-12012 February 1999 to EOP FR-H.5, Response to SG Low Level. ML17265A5461999-02-12012 February 1999 0 to EOP AP-TURB.1, Turbine Trip Without Rx Trip Required. ML17309A6481999-01-25025 January 1999 Revised Ginna Station Emergency Operating Procedures. with 990125 Ltr ML17265A5151999-01-14014 January 1999 Revised Emergency Operating Procedures,Including Rev 14 to AP-SW.1,rev 3 to ATT-5.2,rev 5 to ATT-8.0,rev 1 to ATT-14.6, Rev 17 to E-1,rev 16 to ECA-1.1,rev 26 to ES-1.3,rev 4 to FR-Z.2 & Index ML17265A5081999-01-0808 January 1999 Rev 7 to Technical Requirements Manual, for Ginna Station ML17265A4961998-12-18018 December 1998 Rev 6 to Technical Requirements Manual. ML20198C0581998-12-14014 December 1998 Rev 5 to FR-Z.1, Response to High Containment Pressure ML20198C0361998-12-14014 December 1998 Rev 11 to ECA-0.2, Loss of All AC Power Recovery with SI Required ML20198C0521998-12-14014 December 1998 Rev 13 to FR-S.1, Response to Reactor Restart/Atws ML20198C0411998-12-14014 December 1998 Rev 16 to FR-C.1, Response to Inadequate Core Cooling ML20198C0121998-12-14014 December 1998 Rev 10 to AP-RCS.2, Loss of Reactor Coolant Flow ML20155G0301998-10-30030 October 1998 Rev 13 to EOP AP-CCW.1, Leakage Into Component Cooling Loop ML17265A4091998-08-24024 August 1998 Rev 13 to AP-SW.1, Svc Water Leak. W/980824 Ltr ML17265A3721998-07-16016 July 1998 Rev 14 to EOP AP-CW.1, Loss of Circ Water Pump. W/980716 Ltr ML17265A2861998-05-0606 May 1998 Rev 19 to EOP ECA-3.2, SGTR W/Loss of Reactor Coolant Saturated Recovery Desired & Updated ECA Index.W/980506 Ltr ML17265A1821998-02-20020 February 1998 Rev 1 to EWR 5111, MOV Qualification Program Plan, Calculation Assumption Verification Criteria. ML17265A1491997-12-31031 December 1997 Rev 1 to Inservice Testing Program. ML17264B0731997-10-14014 October 1997 Rev 4 to Technical Requirements Manual (TRM) for Ginna Station. ML17265A1541997-09-16016 September 1997 Rev 1 to DA EE-92-089-21, Design Analysis Ginna Station Instrument Loop Performance Evaluation & Setpoint Verification. ML17264A9751997-08-0505 August 1997 Rev 14 to AP-ELEC.1, Loss of 12A & 12B Busses. ML17264A9771997-08-0505 August 1997 Rev 11 to AP-RCP.1, RCP Seal Malfunction. ML17264A9791997-08-0505 August 1997 Rev 7 to AP-RCS.3, High Reactor Coolant Activity. ML17264A9781997-08-0505 August 1997 Rev 12 to AP-RCS.1, Reactor Coolant Leak. ML17264A9851997-08-0404 August 1997 Rev 2 to Summary Description of Compliance w/10CFR73 Amend Protection Against Malevolent Use of Vehicles at Nuclear Power Plants. ML17264A9391997-07-0707 July 1997 Rev 3 to Technical Requirements Manual for Ginna Station, Inserting New Tabs Accordingly Per Previous Transmittal for Rev ML17264A9341997-07-0101 July 1997 to Technical Requirements Manual (TRM) & inter-office Correspondence Dtd 970624 ML17264A9461997-06-20020 June 1997 to Inservice Insp (ISI) Program. ML17311A0471997-05-22022 May 1997 Revised Eops,Including Procedures Index,Rev 5 to ATT-15.0, Rev 3 to ATT-15.2,rev 3 to AP-ELEC.3,rev 13 to ECA-0.1 & Rev 9 to ECA-0.2.W/970522 Ltr ML20140B8291997-03-24024 March 1997 Rev 3 to EOP ATT-12.0, Attachment N2 Porvs ML17264A8221997-02-0606 February 1997 Rev 15 to FR-P.1, Response to Imminent Pressurized Thermal Shock Condition. ML17264A8201997-02-0606 February 1997 Rev 7 to AP-RCC.2, Rcc/Rpi Malfunction. ML17264A8081997-01-23023 January 1997 Revised Emergency Operating Procedures,Including Rev 14 to E-1,Rev 19 to E-3,Rev 14 to ECA-2.1,Rev ECA-3.3,Rev 20 to ES-1.3,Rev 13 to FR-C.1,Rev 12 to FR-C.2 & Rev 14 to FR-P.1 ML20133N3351997-01-10010 January 1997 Rev 7 to FR-C.3, Response to Saturated Core Cooling ML17264A8881996-10-10010 October 1996 Rev 9 to ODCM for Ginna Station. ML20128N0681996-10-0303 October 1996 Revised Emergency Operating Procedures,Including Rev 5 to Att-10.0, Attachment Faulted S/G & Rev 6 to Att-16.0, Attachment Ruptured S/G ML17264A5311996-05-31031 May 1996 Revised Emergency Operating Procedures,Including Rev 10 to AP-RCP.1,Rev 12 to ECA-0.1,Rev 12 to ECA-2.1,Rev 3 to FR-H.2,Rev 3 to FR-H.4,Rev 7 to FR-I.1,Rev 12 to FR-P.1,Rev 10 to FR-S-1 & Rev 6 to FR-S.2 ML17264A5161996-05-22022 May 1996 Rev 2 to Technical Requirements Manual (TRM) ML17264A4581996-04-0808 April 1996 Rev 7 to ODCM for Ginna Station. ML17264A4371996-04-0101 April 1996 Rev 1 to Technical Requirements Manual (TRM) ML17264A4391996-04-0101 April 1996 Rev 1 to Updated Technical Requirements Manual (TRM) ML17264A4191996-02-24024 February 1996 Rev 0 to Technical Requirements Manual (Trm). ML17264A6901996-02-23023 February 1996 Rev 0 to Inservice Testing Program. 1999-05-12
[Table view] |
Text
CATEGORY 1, REGULA Y INFORMATION DISTRIBUTION SYSTEM (RIDS)
- r. <
ACCESSION NBR:9903050332 DOC.DATE: 99/02/25 NOTARIZED:. NO DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 050 0244 AUTH..NEGATE AUTHOR AFFILIATION
- Rochester Gas & Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION V
rzr~y/
SUBJECT:
Revi to "Technical Requirements Manual (TRM)."
C
,DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72) . 05000244 E
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL G PD1-1 LA PD1-1'D VISSING,G.
INTERNAL: NRR/DE/ECGB/A NRR/DE/EMCB NRR/DRCH/HICB NRR/DSSA/SPLB NRR/DSSA/SRXB NRR/SPSB JUNG,1 NUDOCS-ABSTRACT OGC/HDS3 EXTERNAL: NOAC NRC PDR D
0 N
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR ENCL 13
1 S ~
DISR061 CHESTER GAS Ec'ELECTRIC C ORATION DOCUMENT CONTROL Document Transmittal Transmittal: 9902082N 055 .
To: DOCUMENT CONTROL DESK Date: 02/24/1999 US NRC Holder: 1217 ATT: ALLEN JOHNSON PROJECT DOCTORATE 1-1 WASHINGTON DC 20555 LISTED BELOW ARE NEW OR REVISED CONTROLLED DOCUMENTS. REVIEW THE ATTACHED INSTRUCTION LETTER (IF APPLICABLE)~ AND UPDATE YOUR CONTROLLED DOCUMENT IN ACCORDANCE WITH RM-RDM-1.
Doc Id Doc Title Rev Rev Date Qty TRM TECHNICAL REQUIREMENTS MANUAL FOR 008 02/25/1999 1 GINNA STATION 9903050332 9'70225 PDR ADQCK 05000244 PDR Receipt Acknowledgement and Action Taken:
Signature Date Return to: Rochester Gas &. Electric Corporation Ginna Station - Records Management 1503 Lake Road Ontario, New York 14519
Rochester Gas and Electric Corporation Inter-Office Correspondence February 24, 1999
Subject:
Technical Requirements Manual (TRM) Revision 8 TQI Distribution Attached are the associated revised pages for the Ginna Station Technical Requirements Manual (TRM). The changes included within Revision 8 are summarized as follows:
- 1. New TRs and surveillances were added to provide the requirements for spent fuel pool cooling during normal conditions and during a full core ofHoad.
Revision 8 of the TRM is considered effective February 25, 1999. Instructions for the necessary changes to your controlled copy of the ITS are as follows:
Volume Section Remove Insert III TRM Cover Page Cover Page III TRM LEP-i LEP-i m TRM TOC i III TRM Chapter 3.7 TRM 3.7-25 III TRM Chapter 3.7 TRM 3.7-26 III TRM Chapter 3.9 TRM 3.9-2 TRM 3.9-2 III TRM Chapter 3.9 TRM 3.9-3 TRM 3.9-3 III TRM Chapter 3.9 TRM 3.9-5 III TRM Chapter 3.9 TRM 3,9-6 III TRM Chapter 3.9 TRM 3.9-7 Please contact Tom Harding (extension 3384) if you ha e any questions.
Thomas L. Harding
0 ~ 1 GINNA STATION TR Re ision 7 TECHNICAL FIEQUI MENTS MANUAL
{T M}
7.
Responsible Hanaget Effective Date Conti ol l ed y No. /~l
List of Effective Pages (TRH)
Page Rev. Page Rev. Page Rev. Page Rev.
TOC Section 3.3 Section 3.7 (con'd) (con'd)
TRN 3.3-13 TRN 3. 7-10 6 TRH 3.3-14 TRN 3.7-11 1 Section 1.0 TRH 3.3-15 TRH 3.7-12 3.3-16 'RN TRH 3. 7-13 1 TRM 1.0-1 0 , TRH 3.7-14 1 Section 3.4 TRM 3.7-15 4 Section TRH 3.7-16 1 TRH:3: 4-.'.1 1- 3.7-17
'6
.2.0='RH
~ TRM 6 2.0-1 TRH 3.4-2 1 TRM 3.7-18 1 TRH 3.4-3 0 TRN 3.7-19 1 Section 3.0 TRN 3.4-4 0 TRN 3.7-20 6 TRN 3.4-5 . 0 TRM 3.7-21 6 TRH 3.0;1 1 TRN,3. 4-6 0 TRN 3.7-22 6 f 'JRH 3.4-7 0 3.7-23 TRM 1 Section 3.1"- TRH 3.4-.8 TRM 3.7-24 1
-TRN 3.4-9 TRH 3.1-1 0 TRN 3.4-10, --3 Section 3.8 TRH 3..1-2 1 TRN 3.4-1'1.;."--' 3 TRM 3.1-3" 2 TRH 3.4 . 3 TRH 3.8-1 0 TRH 3.1-4 , 0 TRN'3.4-13" 3 TRH 3.8-2 3 TRM 3.1-5 5 TRN 3.4-14 TRH 3.8-'3 6 TRH 3.1-6, TRH 3.1-7 '2 1 Section 3.5 Section 3.9 Section,3.2 'RM 3;5-1 0 TRH 3.9-1 TRM 3.9-2 TRN 3.2-1 Section 3.6 TRH 3.9-3 TRN 3.9-4 Section 3.3 TRH 3.6-1 0 Section 4.0 TRH 3.3-1 1 Section 3.7 TRH 3.3-2 0 TRN 4.0-1 TRN 3.3-3 1 TRN 3.7-1 1 TRH 3.3-4 0 TRH 3.7-2 1 Section 5.0 TRH 3.3-5 0 TRH 3.7-3. 6 TRN 3.3-6 0 TRH 3.7-4 ,4 TRH 5.0-1 TRN 3.3-7 ~
1 'TRH 3;7-5'RH 1 TRM 5.0-2 TRN 3.3-8 1 3.7-6 1 TRN 3.3-9 6 TRH"3.7-7. 3 TRM 3.3-10 4 TRH 3.7-8'.
TRH 3.3-11 4 TRH 3, 7-'9 1 TRN 3.3-12 4 Ginna Station TRH LEP-i Revision 7
~ ~
TABLE OF CONTENTS 1.0 USE AND APPLICATION .................... 1.0-1 2.0 SAFETY, LIMITS (SLs) 2.0-1 3.0 LIHITING CONDITION FOR OPERATION (LCO) APPLICABILITY 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY 3.0-1 3.1 REACTIVITY CONTROL SYSTEMS . 3.1-1 3.1.1 Boron Injection System-MODES 1, 2, 3, and 4 . . . . 3.1-1 3.1.2 Boron Injection System-MODE 5 . 3.1-6 3.2 POWER DISTRIBUTION LIMITS . . . . . : . . . . . . . . . 3.2-1 3.3 INSTRUMENTATION 3.3-1 3.3.1 Control Room Emergency Air Treatment System (GREATS)
Instrumentation 3.3-1 3.3.2 Circulating Water Flood Protection Instrumentation . 3 ~3 3 3.3.3 Movable In-Core Instrumentation 3.3-6 3.3.4 Fire Detection Instrumentation . 3 ~3 7 3.3.5 Low Temperature Overpressure Protection (LTOP)
Arming Logic 3.3-14 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4-1 3.4.1 Reactor Vessel Head Vents 3.4-1 3.4.2 RCS Chemistry 3.4-3 3.4.3 Anticipated Transients Without Scram (ATWS)
Mitigation 3.4-8 3.5 EMERGENCY CORE COOLING SYSTEHS (ECCS) 3.5-1 3.6 CONTAINMENT SYSTEMS 3.6-1 3.7 PLANT SYSTEMS 3.7-1 3.7.1 Fire Suppression Water Sources . ~ ~ t ~ 3.7-1 3.7.2 Fire Suppression Spray and Sprinkler Systems 3.7-6 3.7.3 Halon Systems 3.7-11 3.7.4 Fire Hose Stations . 3.7-14 3.7.5 Fire Barrier Penetration Seals . 3.7-18 3.7.6 Fire Yard Loop . 30723 3.8 ELECTRICAL POWER SYSTEMS . 3.8-1 3.8.1 Offsit'e Power Sources 3.8-1 3.8.2 Instrument Bus D . 3.8-2 3.9 REFUELING OPERATIONS . 3.9-1 3.9.1 Fuel Storage in Spent Fuel Pool (SFP) Region 2 3.9-1 3.9.2 Fuel Assembly Movement in Auxiliary Building 3.9-2 3.9.3 Refueling Manipulator Crane Interlocks . 3.9-4 Ginna Station TRH Revision
~ + l I
Fuel Assembly Movement in Auxil iary Building TR 3.9.?
3.9 REFUELING OPERATIONS 3.9.2 Fuel Assembly Movement in Auxiliary Building TR 3.9.2 During movement of irradiated fuel assemblies, the following sha' be met:
- a. Radiation levels in the spent fuel pool (SFP) area shall be monitored c'ohtinuously;
- b. A load in excess of one fuel assembly and it.", handling tool shall not be stationed nr transferred ovei the storage racks containing spent fuel; and
- c. The SFP temperature shall be z 150'F.
-NOTE-The load restriction is not applicable for movement of consolidated fuel rod canisters if the spent fuel racks beneath the transported canister only contain fuel which has decayed z 60 days since being irradiated.
APPLICABILITY: During movement of irradiated fuel assemblies in the operating floor area of the Auxiliary Building.
ACTIONS CONDITION REQUIRED ACTION COMPLETION T IHE A. Radiation levels not A.I Suspend movement of Immediately continuously irradiated fuel monitored. assemblies.
OR Load restriction not met.
OR SFP temperature not within limit.
Ginna Station TRH TRH 3.9-2 Revision 0
~ ~ J Fuel Assembly Movement in Auxiliary Building TH 3.9.?
SURVEILLANCE RE(UIPEMENTS SURVEILLANCE FREQUENCY
'lSR 3.9.2.1 Verify no load in excess of one fuel Once prior to assembly and its handling tool is stationed moving loads or transferred over the storage racks. over the storage rac).'ontaining spent iuel TSR 3.9.2,2 Verify radiation monitors in SFP area are 24 hours OPERABLE.
TSR 3.9.2.3 Verify SFP temperature is within limit. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Ginna Station TRM TRM 3.9 ~
3 Revision 0