|
---|
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 ML20036A8241993-05-0707 May 1993 Proposed TS 4.3 Re Prestressed Concrete Reactor Vessel Water Leakage Protection 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 ML20034C7851990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-EP Q, Steam Leak or Inadvertent Lifting of Steam Relief Valve ML20034C7781990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-2, Abnormal Radioactive Gas Release from Plant ML20034C7831990-04-19019 April 1990 Issue 56 to Abnormal Operating Procedure AOP-N, Loss of Instrument Bus ML20034C7761990-04-19019 April 1990 Issue 55 to Abnormal Operating Procedure AOP D-1, Single Circulator Trip ML20034C7771990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-1, Abnormal Radioactive Liquid Waste from Plant ML20034C7841990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-P, Loss of DC Bus ML20034C7801990-04-19019 April 1990 Issue 59 to Abnormal Operating Procedure AOP-K-1, Environ Disturbances - Earthquake ML20034C7821990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20034C7791990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-3, High Activity in Plant 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 ML20034C7781990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-2, Abnormal Radioactive Gas Release from Plant ML20034C7851990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-EP Q, Steam Leak or Inadvertent Lifting of Steam Relief Valve ML20034C7841990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-P, Loss of DC Bus ML20034C7751990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-B, Reactor Scram ML20034C7771990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-1, Abnormal Radioactive Liquid Waste from Plant ML20034C7761990-04-19019 April 1990 Issue 55 to Abnormal Operating Procedure AOP D-1, Single Circulator Trip ML20034C7801990-04-19019 April 1990 Issue 59 to Abnormal Operating Procedure AOP-K-1, Environ Disturbances - Earthquake ML20034C7831990-04-19019 April 1990 Issue 56 to Abnormal Operating Procedure AOP-N, Loss of Instrument Bus ML20034C7791990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-3, High Activity in Plant ML20034C7821990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header 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 ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20154L8911988-03-31031 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 1997-06-17
[Table view] |
Text
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Pubuc Servke Publ.
Serv. ice-c -ee
' c '
4-ic P.o Don M0 Denver.Co 80201 OMO 16805 WCR 191/2, Platteville, Colorah 80651 August 16, 1991 Fort St. Vrain Unit No. 1 P-91259 U.S. Nuclear Regu'otory Commission ATTN: Document Control Desk Mail Stop P1-37 Washington, D.C.
20555 DOCKET NO:
50-267
SUBJECT:
ABNORMAL OPERATING PROCEDURE DISTRIBUTION Gentlemen:
We are transmitting herein the following:
Issue 2 of A0P-I-2 Two copies of this procedure have also been transmitted to Region IV, Emergency Response Coordinator, in accordance with 10CFR50.54(q)
(Reference P-91260).
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.
4
/
9108260348 910816ADOCK 0500 2 7 {?
,3p
{DR y
.4 i
P-91259 Page 2 August 16, 1991 If difficulties or questions arise in filing these procedures, please contact Mr. M. H. Holmes at (303) 480-6960.
Sincerely, hk 40 Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF/bj Attachments cc:
J. B. Baird Senior Resident Inspector Fort St. Vrain Gordon Kirk Emergency Planning Specialist Fort St. Vrain
N,e*l
~
Page 1 of 2 FORT ST. VRAIN NUCLEAR GEb 2 RATING STATION OPublic SOIVlCO*
PUBLIC SERVICE COMPANY OF COLORADO 08/07/91 ABNORMAL OPERATING PROCEDURES ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE A0P INTRO Abnormal Operating Procedures Introduction 56 02-13-91 A0P-A Moisture In-Leakage 58 02-13-91 AOP-B Reactor Scram 58 02-13-91 EP B-2 DELETED 01-09-88 A0P-EP C Loop Shutdown 57-Last 03-28-90 AOP 0-1 Single Circulator Trip 56 02-13-91 AOP-EP D-2 Three Circulator Trips 54-Last 03-21-90 A0P-EP E Abnormal Reactor Power Change 56-Last 03-28-90 A0P-F Restoration of Essential Electric Power 1
11-05-90 AOP-EP F-1 Main Turbine Emergencies 58-Last 03-28-90 AOP-EP F-2 Low Condenser Vacuum Turbine Trip 55-Last 03-28-90 A0P-EP F-3 Loss of Outside Power and Turbine Trip 55-Last 03-28-90 AOP-EP F-4 Loss of Outside Power and Turbine Trip with Failure of One Diesel Generator Set to Start 55-Last 03-28-90 A0P-EP G Loss of Active Core Cooling 56-Last 03-28-90 A0P-H-1 A~onormal Radioactive Liquid Waste From Plant 58 03-27-91 AOP-H-2 Abnormal Radioactive Gas Release From Plant 58 03-27-91 A0P-H-3 High Activity in the Plant 58 03-27-91 A0P-I Discussion of Fire 56 08-01-90 l AOP-I-2 Chemical, Petroleum, and l
Hazardous Waste Spill Response 2
08-07-91 FORM (D)372 22 3M3
l Pcge 2 of 2-O $9fVlC9' Public -
FORT-ST.- VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO 08/07/91 (N
U-ABNORMAL OPERATING PROCEDURES ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE c
J DELETED-05-14-82
-AOP-K-l' Environmental Disturbances - Earthquake 60 03-27-91 AOP-K-2:
Environmental Disturbances - Tornado 57 04-10-91 AOP-L Loss of an Instrument-Air Header 58 07-31-91 A0P-EP M Loss of Hydraulic Power 56-Last 03-21-90 A0P-N Loss of an Instrument Bus 57 03-27 ~
AOP-P Loss of a 0.C. Bus 58 03-27-3
-p'v AOP-EP Q' Steam Leak or Inadvertent
-Lifting of Steam Relief Valve 57-Last 04-25-90 L
AOP-R Loss of Access to Control Room 55 03-20-91 L
AOP-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 8
03-29-91 p-l-
I i
LO I
l I
3 FORM (o)372 22 36CI
. ~.,.
A0P-1-2
///:ps /
Issue 2 Public FORT ST, VRAIN NUCLEAR GENERATING STATION Page 1 of 7 l
) Service
- PUBLIC 3ERVICE COMPANY OF COLORADO l TITLE: CHEMICAL, PETROLEUM, AND HAZARDOUS WASTE SPILL RESPONSE RESPONSIBLE AUTHCRIZED IN. b. ' (t[Jht BY:
FOR:
07" "'" 444 PORC PORC 9 4 5 JUL 311991 EFFECTIVE REVIEW DATE b,l-9 l DCCF NUMBER (S) 41-0 41.o1 O
% l O
a__
AOP-I-2 Issue 2 age 2 of 7 Public FORT ST. VRAIN NUCLEAR GENERATING STATION SerVICO*
PUBUC SERVICE COMPANY OF COLORADO TABLE OF CONTENTS 1.0 OBJECTIVE................................................
3 2.0 SCOPE............
3 3.0 ENTRY CONDITIONS........................................
3 4.0 PRECAUTIONS AND LIMITATIONS............................
3 4.1 Precautions............................................
3 i.2 Limitations.................
3 1 5.0 EMERGENCY COORDINATOR ACTIONS..................
4 6.0 MONITORING ACTIONS
........ 7 1
7.0 REFERENCES
7 l 8.0 ATTACHMENTS............
7 l 9,0 COMMITMENTS...................................
7 l
FORMtD)372 22 3643
L
,AOP-1-2 j -.
' Issue 2 Page 3 of 7-O $9fVlC9' Public FORT. ST VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO
^
1.0 OBJECTIVE To: provide detailed instructions to the Shift Supervisor and l
Emergency Response Team for-responding to any chemical, i
l-pet _roleum, or hazardous material spill at Fort St. Vrain.
2.0 SCOPE This procedure provides instructions for ensuring that personnel i
l exposure is minimized during any spill events.
It also provides instructions for the additional reporting requirements required in a hazardous material / waste incident.
3.0 ENTRY CONDITIONS ANY condition where the Control Room is notified of a j
non-incic' ental chemical, petroleum, or hazardous waste spill or l
release to the plant site and/or environment other than planned releases within plant discharge limits.
4,0 PRECAUTIONS AND LIMITATIONS 4.1 PRECAUTIONS The on-site Emergency Response Team is trained to identify I
and contain spills.
Environmental Services will-provide l-assistance as needed for spill clean up.
4.2.
LIMITATIONS
'This procedure is designed to provide the minimum actions l
required during any chemical, petroleum, or hazardous material spill by the Shif t Supervisor and Emergency Response Team. Administrative Procedure G-35 contains the l
" Chemical, Petroleum, and Hazardous Waste Contingency.
l Plan".
60 i
(1 FORM (Ol372 22.'%3 l
A0P-1-2 Issue 2 Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION age 4 of 7 P
Service
l 5.0 EMERGENCY COORDINATOR ACTIONS l
INSTRUCTIONS CONTINGENLY ACTIONS l
l
.I l 5.1 Dispatch Emergency Response l 5.1 Fire Brigade Instructor and l l
Team to identify spilled l
FSV Hazardous Material /Wastel l
product.
I Coordinator can be called l
l 1
for additional assistance inl l
l product identification and l l
l containment.
l l
l I
I l 5.2 Notify personnel of the l 5.2 Have Emergency Response Teaml l l emergency via the Gai-Tronics l
Leader evacuate immediate l
ll and provide information I
area around spill, l
ll regarding location, hazards, 1
l ll and special evacuation routes l
l ll if applicable.
I l
ll l
I 1 l 5.3 Establish required communi-l 5.3 Utilize Control Room l
l cations with the Emergency I
reference materials to I
Response Team.
l assist Emergency Response l
l l
Team in identifying spilled l l
l product.
I l
5,4 IF Chemical hazard has been 5.4 _If Chemical Hazard has l
l identified, l
not been identified, 1
ll THEN proceed to next Step (5.5)l THEN proceed to Step 5.6.
I l
I l
l l 5.5 Refer to MSDS sheet and/or l
l ll 00T Emergency Response l
l l
Guidebook to evaluate l
l l
and adjust evacuation area l
l l
boundaries. Go to Step 5.6.
l I
I I
I l l 5.6 Consider evacuating larger l
l ll area.
If deemed appropriate, l
l ll Sound Fire Alarm to evacuate l
l ll unnecessary personnel to their l l
ll accountability areas.
l I
i 1
l l l 5.7 Direct Emergency Response Team l l
ll to contain product per G-35.
l l
}
l l
O FORM tD)772 22 3643
A0P-I-2 C_{
Issue 2 y*
A Public FORT ST. VRAIN NUCLEAR GENERATING STATION 107 Service
l.
INSTRUCTIONS CONTINGENCY ACTIONS l
l
-l.....................................;
l CAUTION: Envi_ronmental Affairs and l l
l the FSV Hazardous l
l l
Material / Waste Coordinator l l
l-shall be contacted-for
-l l
l all chemical spills except-l l
l incidental spills.
Inci--l l
dental spills are defined l l
I in Admin. G-35.
Environ-l l
ll mental Services will l
l classify spills for report-l l
-- l
-ability to outside l
l
-l hazardous material agencies l l
l based _on material spilled l l
l and the quantity that was l-l l
spilled. They can provide l l
1 i
assistance in obtaining l
l l
- off-site aid in spill l-l l
decontamination and cleanupl l
[
for spills outside of l
l l
Emergency Response Team l
l 1
l capabilities, j
-O j.....................................;
i l
I l l 5.8 Contact PSCo Emergency _0peratort 5.8 Alternate Phone Numbers are:l j
5-800-541-0918. Notify 1.
5-571-7511 ; PSC Operator l
-l Operator that there is-a l
5-294-3703 ; pSC Operator atl
-l chemical spill at-FSV. _Have-l Anaconda Tower 1-l the_ operator contact Environ-l 5-294-3781 ; PSC Industrial l
- l l.
mental Services and request l
Hygiene Coord-l-lj that Environmental Services I
inator
-l l_
call FSV:at 620-1090, l
l qlr....................................l l
l l CAUTION: Any spill even.t reported l
l
~
l l_
to agencies outside of PSC l l
ll shall be cl_assified.at a _ l-l ll minimum as a four hour-l 1
l l
.non-emergency report to l
l-l l..........NRC...........................
1 I
l:1 1
I j l 5.9 Refer to EP-Class for i
I ll determination of event l
l ll Classification.
l' l
I1 l
l 01 FORM (01772 22 360 a
AUP-1-4 Issue 2 0 SOfVICO*
PubilC FORT ST VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO
(-C/
l ll INSTRUCTIONS CONTINGENCY ACTIONS "l
l1 l
l l 5.10 Notify the Nuclear Regulatory l l
l l Commission (NRC) when l
l l l notification to other govern-l l
ll mental agencies have been, or l l
l l will be, made.
l l
l l 1
I l l 5.11 Contact FSV Hazardous Material l 5.11 Alternate FSV Hazardous l
l l Coordinator, Terry Staley at l
Material / Waste Coordinator, l l l 5-303-556-0679 : pager or l
Jesse Brungardt at j
l l or 1340 : Office in 14ED-Site l
5-303-556-1990 : pager or l
l l Bldg.
See Emergency Phone Listl 1519 Office in QA Bldg.
l l
for home phone number.
l See Emergency Phone List l
l l
for* home phone number.
l l
.__I I
l l 5.12 Refer to G-35, for guidance on l l
l l continuing spill mitigation l
l ll and clean-up requirements.
l l
l l l
l r~w N,]
g LJ FORM tD)I'2-22 3643
AOP-I-2 Issue 2 age 7 of 7 0 Public FORT ST. VRAIN NUCLEAR GENERATING STATION SOIVlCO*
PUBLIC SERVICE COMPANY OF COLORADO 6.0 MONITORING ACTIONS There are no specific monitoring actions for this procedure.
Environmental Affairs may request monitoring of the spill area until they can arrive on site to take over these duties.
l
7.0 REFERENCES
I 7.1 G-35, " Chemical, Petroleum, and Hazardous Waste l
Contingency Plan" l
7.2 DERP-TEAMS l 8.0 ATTACHMENTS I
None.
l 9.0 COMMITMENTS None.
I O
O FORM 10)372 3 3M3
_