|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML20064B2111989-11-0909 November 1989 Fort St Vrain Cycle 4 RT-500L Test Rept ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys 1997-06-17
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20154M4361988-09-0909 September 1988 Rev a to EE-FP-0005, Evaluation of Cable Trays Outside of Congested Cable Area ML20154L8751988-05-26026 May 1988 Simulation Facility Program Plan ML20154L8911988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20150E3141988-03-18018 March 1988 Issue 1 to Procedure SR 5.4.1.3.8.abcd-R1, Steam Line Rupture Detection/Isolation Sys (Slrdis) Calibr & Testing for Panel I-93543 ML20150E2901987-12-31031 December 1987 Issue 5 to Procedure SR 5.3.4b1-A Loop I Shutdown Cooling Power Operated Valve Test ML20238E3541987-08-0707 August 1987 Rev a to EE-ISI-002, Condensate Line Erosion Insp Program ML20236N8681987-08-0505 August 1987 Exercise Manual Fort St Vrain Nuclear Generating Station Nrc/Fema Graded Exercise 870805 ML20235Y7861987-07-29029 July 1987 Issue 2 to MAP-4, Maint Dept Personnel Experience, Qualification & Training Requirements ML20237J6921987-06-0909 June 1987 Issue 6 to MQCIM-1, Maint QC Insp Program. Annotated Page to Rev 4 to Updated FSAR Encl ML20235Y7731987-05-25025 May 1987 Training Mgt Procedure Index ML20237J7151987-05-0101 May 1987 Issue 12 to Q-18, QA Monitoring & Audit Program ML20215H9731987-04-30030 April 1987 Revised Buckle Users Manual:Creep Collapse of Thin-Walled Circular Cylindrical Shells Subj to Radial Pressure & Thermal Gradients ML20215H6101987-04-10010 April 1987 Program Plan for Integrated Validation of NUREG-0737 Initiatives ML20215H6031987-04-10010 April 1987 SOAP-2,Issue 1 of Guidelines for Preparation of Emergency Procedures ML20215H5951987-04-10010 April 1987 Procedures Generation Package:Public Svc Co of Colorado Fort St Vrain Nuclear Generating Station ML20150E3041987-03-20020 March 1987 Issue 1 to Procedure SR 5.4.1.3.8.abcd-R2, Steam Line Rupture Detection/Isolation Sys (Slrdis) Calibr & Testing for Panel I-93544 ML20237J7231987-02-20020 February 1987 Issue 5 to QAAP-1, Planning & Scheduling Fort St Vrain QA Audits ML20212B3081987-02-15015 February 1987 Issue 7 to Procedure G-9, Controlled Work Procedures ML20210E3001987-02-0303 February 1987 Revised Administration Procedures Consisting of Issue 7 to G-3, Action Request-Preparation & Processing, Issue 21 to G-2, Fort St Vrain Procedure Sys & Issue 6 to G-6, Compliance w/10CFR21 Requirements ML20210A7571987-01-30030 January 1987 Fort St Vrain 1987 Power Ascension Plan ML20237J7421987-01-19019 January 1987 QA Audit QAA-502-87-01, Audit Plan - QA Program for Transport of Radioactive Matls ML20212B2851986-10-24024 October 1986 Issue 10 to Procedure Q-3, Design Control Sys ML20238E3461986-10-0202 October 1986 Rev C to EE-ISI-0001, Extraction Steam Lines & Turbine Vent & Drain Lines Erosion Insp Program 1997-06-17
[Table view] |
Text
- ..
. O. Pubile Sery co' gglc-Denver, co 8020b eMO 16805 WCR 19 1/2, Platteville, Colorado 80551
., April 5, 1991 Fort St. Vrain
{
Unit No. 1 P-91114 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop P1-37 Washi'igton, D.C. 20555 DOCKET NO: 50-267
SUBJECT:
PROCEDURE DISTRIBUTION ,
i Gentlemen: _.
We are transmitting herein the following -
Issue 55 of Abnormal Operating Procedure R 4
Two copies of this procedure have also been transmitted to Region IV.
Emergency Response Coordinator, in accordance with 200FR50.54(q)
(ReferenceP-91115).
In accordance with 10CFR50.54(q), we have determined.that the changes in this issue do not. decrease the effectiveness of.the Fort St. Vrain Emergency Plans and the plans, as changed,. continue to meet the ,
intent of 10CFR50.47(b) and 10CFR50 Appendix E. '!
If difficulties or questions arise in filing this procedure, please contactMr.M,H.Holmesat(303)480-6960.
Sincerely.
. Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear 1 Generating Station I CHF/bj Attachments cc: J. B. Baird Senior Resident Inspector Fort St. Vrain
- Renee Millison /
tanine Fmeroency Planning Specialist 90133 2 TsR"ngggg0;ggCqg6, P Pf0R
.p';-)i
- Page 2 of 2 FORT ST. VRAIN NUCLEAR GENERATING STATION O Public Service
- Puntic senvice company or cotonApo 03/20/91
,. . ABNORMAL OPERATING PROCEDURES ISSVE EFFECTIVE NO. SUBJECT NUMBER DATE J DELETED 05-14 82 AOP-K-1 Environmantal 01sturbances - Earthquake 59 04-19-90 AOP-K-2 Environmental Disturbances - Tornado 56 04-19-90 AOP L Loss of an Instrument Air Header 57 04 19-90 AOP-EP M Loss of Hydraulic Power 56-Last 03-21-90
. c AOP-N Loss of an Instrument Bus 56 04-19-90 AOP-P Loss of a 0.C. Bus 57 04-19-90 AOP-EP Q $ team Leak or inadvertent Lifting of Steam Relief Valve 57-Last 04-25-90 l A0P-EP R Loss of Access to Control I Room 55 03-20-91 A0P-EP S Loss of HVAC to 480 Volt Switchgear Room 54-Last 03-28-90 AOP-V Restoration of PCRV Integrity 1 11-05-90 EP CLASS Event and Emergency Classification Overview 7 07-26-89 l
I O
q
. -j 1
- j Pub llC FORT ST, VRAIN NUCLEAR GENERATING STATION , "h
$4fYlCO' Pusuc sanv6cs COMPANY OF COLORADO 03/20/91 '
O
.. . ABNORMAL OPERATING PPOCEDURES
!$$UE EFFECT!VE NO. $UBJECT NUMBER DATE AOP INTRO Abnormal Operating Procedures Introduction t6 02-13 91 AOP-A Moisture In-Leakage 58 02-13 91 AOP B Reactor $ cram $8 02-13-91 1
EP B-2 DELETED 01-09-88 AOP EP c Loop Shutdown 57-Last 03-28-90 , ,
A0D 0-1 Single Circulator Trip $6 02-13-91 A0P-EP 0 2 Three Circulator Trips 54 Last 03-21-90 AOP-EP E Abnomal Reactor Power Change $6-Last 03-28-90 O AOP F Restoration of Essential Electric Power 1 11-05 90 AOP F,p F 1 Main Turbine Emergencies 58-Last 03-28-90 '
AOP-EP F-2 Low Condenser Vacuum Turbine Trip 55-Last 03-28-90 AOP-EP F-3 Loss of Outside Power and Turbine Trip 55-Last 03-28 90 A0P-EP F-4 Loss of Outside Power and Turbine Trip with Failure of One Diesel l Generator $et to Start 55-Last 03-28-90 AOP-EP G Loss of Active Core Cooling 56-Last 03-28 90 AOP-H-1 Abnormal Radioactive Liquid Waste From Plant 57 04-19-90 l AOP-H-2 Abnormal Radioactive Gas Release From Plant 57 04-25-90 AOP-H-3 High Activity in the Plant 57 04-19-90 AOP-! Discussion of Fire - 56 08-01-90 l AOP-I-2 Chemical Spill Response 1 01-16-91 FORM (Ol372 22 3M3 - - -
4
.; , 1 AOP-R i Issue 55 v l
., Public FORT ST. VRAIN NUCLEAR GENERATING STATION \\ l
, $9fVlC9' Pustic SERVICE COMPANY OF COLORADO I l
TITLE: LOSS OF ACCESS TO CONTROL ROOM RESPONSIBLE R
. [ LT,$/k ,8Y: AUTHORIZED FOR: 7 _
u m >
AUTH(RIZED BY' Ia W 'cwE nj@w PCfC 9 2TM 131991 $7Te g,bq i DCCF NUMBER (S) kh \2LJ-h 4
0
. ~ ~ ._.
~
l p.L. S '~
NON,cmr' pRAIN .
ven n c : , : m" c L E O Mb. STAyug C '"wt ceguneur o
FORM (E)372 22 3042
- - . - , - ~ . . _ , _ . , _ . _ . . - . . _ , . . . _ . - - . . . _ . - _ , _ . . . - . . . - _ _ _ __
. l AOP-R Issue 55 Page 2 of 2 4
8 Public FORT ST. VRAIN NUCLEAR GENERATING STATION l %)7 Service
- Pusuc senvece comeAuv or cotonAno O (R)
LOSS OF ACCESS TO CONTROL ROOM t
SYMPTOM-ACTION MATRIX l ~
l l l l l l l SYMPTOM l I l ~~~ I l l l l 1.1 l l l ACTIONS l Loss of Access. l l l l0f Control Room l l l l l 1 l l OPERATOR ACTION l l l 2.1 l l l Evacuate to I-49 and XX XX l l l terminate Defueling l l l activities.
l I .
l l l l 1 2.2 l l l Monitor the start up channel l XX XX l l l recorder at I-49 (alternately l l l l monitor the log nuclear powerl l l l Indication at I-49) to ensure.: l l l reactor is shutdown.
l l 2.3 l XX XX- l l l Utilize OPOP III.D to l l l l maintain liner cooling. l l I I l l
l O l l
- FORM (01372 22 3643 l
__ ~. . ._. _ _ _ . . - _ , . - , , , - . _ , . _ _ _ . . _ . _ , . . _ . , . . . _ _
1 AOP APP R Issue 55
'9'
%
- hPublic FORT ST. VRAIN NUCLEAR GENERATING STATION pusuc sanvece comeAwy or cotonaoo NGF Service *'
INTRODUCTION l In the event that immediate Control Room evacuation is necessary, the l Plant can still be monitored from a redundant control panel in the l 480V switchgear room and local indication in the plant.
DISCUSSION OF SYMPTOMS I SYMPTOMS l 1.1 Loss of Access to Of Control Room l If Control Room evacuation is required and defueling i activities have not been terminated from the Control Room, notify Fuel Deck from I-49 Panel Area.
Control Room access may be lost due to fire, smoke, structural damage, intruders, radiation, toxic fumes, or any other reason, but should be very apparent. ,
O!$CUSSION OF OPERATOR ACTION OPERATOR ACTION O l 2.1 Evacuate to I-49 and Terminate Oefueling Activities
)
l When Control Room evacuation is required: !
- 1) Evacuate to I-49 in the-480V Swftchgear Room.
l Terminate defueling activities and ensure all PCRV l openings closed, j 2.2 Monitor the Startup Channel Recorder at I-49 l Ensure that reactor is shutdown by monitoring the startup I channel recorder nn I-49. If startup channel recorder is l not available then. monitor the log nuclear power l indication on I-49.
l 2.3 Utilize OPOP 111.0 to Maintain Liner Coolina l OPOP 111.0 provides methods for liner cooling.
O FoRMtol372 22 36(I
!