|
|---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20141K9961997-05-0505 May 1997
Safety Evaluation Supporting Amend 89 to License DPR-34
ML20128D7191992-12-0101 December 1992
Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant
ML20246J3261989-08-30030 August 1989
Safety Evaluation Supporting Amend 72 to License DPR-34
ML20245J3781989-08-14014 August 1989
Safety Evaluation Supporting Amend 71 to License DPR-34
ML20245J4511989-08-0808 August 1989
Safety Evaluation Responding to Issues Re Tech Spec Upgrade & Plant Defueling.Stated Tech Spec Sections Should Be Upgraded
ML20246J3131989-07-0707 July 1989
Safety Evaluation Concluding That Operators Role in Mitigating High Energy Line Break at Facility Acceptable
ML20247R2261989-05-26026 May 1989
Final Safety Evaluation Re LER 87-20 Concerning Interactions Between Steamline Rupture Detection/Isolation Sys,Plant Protective Sys & Control Sys at Facility
ML20245C5031989-04-18018 April 1989
Safety Evaluation Supporting Amend 70 to License DPR-34
ML20248D6501989-03-31031 March 1989
Safety Evaluation Supporting Amend 69 to License DPR-34
ML20236A1401989-02-27027 February 1989
Safety Evaluation Supporting Amend 68 to License DPR-34
ML20235T4511989-02-24024 February 1989
Safety Evaluation Re Facility Core Support Flow Vent Sys. Continued Operation of Facility W/Current Core Support Flow Sys Configuration Acceptable
ML20235J3421989-02-16016 February 1989
Safety Evaluation Supporting Util Action in Response to Generic Ltr 83-28,item 2.1 (Part 2) Confirming Establishment of Interface W/Either NSSS Vendor or Vendors of Each Component in Reactor Trip Sys
ML20235J3841989-02-13013 February 1989
Safety Evaluation Concluding That Continued Operation of Facility Not Affected by Steam Generator Tube Failures Experienced by Advanced gas-cooled Reactors
ML20195D3911988-10-27027 October 1988
Safety Evaluation Supporting Corrective Actions of LER 86-017
ML20205G0021988-10-24024 October 1988
Safety Evaluation Supporting Amend 65 to License DPR-34
ML20154J8021988-09-15015 September 1988
Safety Evaluation Supporting Amend 64 to License DPR-34
ML20154J4621988-09-15015 September 1988
Safety Evaluation Supporting Amend 63 to License DPR-34
ML20207F0571988-08-10010 August 1988
Safety Evaluation Supporting Util 870206 Submittal Re Safe Shutdowns During Postulated Accident Conditions
ML20207F0431988-08-0505 August 1988
Safety Evaluation Supporting Amend 61 to License DPR-34
ML20207F2411988-08-0505 August 1988
Safety Evaluation Supporting Amend 62 to License DPR-34
ML20151M1601988-07-21021 July 1988
Safety Evaluating Supporting Requirements for Redundancy in Responding to Rapid Depressurization Accident
ML20151A9961988-06-20020 June 1988
Safety Evaluation Supporting Amend 60 to License DPR-34
ML20195K0651988-06-15015 June 1988
SER Concurring W/Util Proposed Corrective Actions in Engineering Rept Entitled, Rept of Helium Circulator S/N 2101 Damage & Inlet Piping S/N 2001 Repair & Mod Activities
ML20195F9661988-06-15015 June 1988
Safety Evaluation Re Destructive Exam Rept for Fuel Test Assembly-2.Fuel Represented by Fuel Test Assembly-2 Predicted to Be Safe for Operation in Facility for 1,800 EFPDs
ML20154F8891988-05-10010 May 1988
Safety Evaluation Re Proposed Safe Shutdown Sys & Exemption Requests Concerning 10CFR50,App R.Licensee Request for Exemptions in Listed Areas Should Be Granted.Concept for Providing post-fire Shutdown Acceptable
ML20148S6031988-04-0707 April 1988
Safety Evaluation Supporting Amend 59 to License DPR-34
ML20151B6651988-04-0101 April 1988
Supplemental Safety Evaluation Supporting Util Compliance w/10CFR50.App R Re Safe Shutdown DHR Capacity
ML20150C4541988-03-10010 March 1988
Safety Evaluation Concluding That Seismic Analysis Methods for Bldg 10 & Walkover Structure Conservative.Gaps Provided Adequate to Accommodate Relative Motions Which Occur Between Subj Structures & Walkover Structure & Turbine Bldg
ML20147C8181988-02-25025 February 1988
Safety Evaluation Supporting Changes to Interim Tech Specs 3/4.1.7, Reactivity Change W/Temp
NUREG-1220, Safety Evaluation Accepting Plant Special Senior Licensed Fuel Handler Initial & Requalification Operator Training Program,Per NUREG-1220, Training Review Criteria & Procedures1988-01-13013 January 1988
Safety Evaluation Accepting Plant Special Senior Licensed Fuel Handler Initial & Requalification Operator Training Program,Per NUREG-1220, Training Review Criteria & Procedures
ML20237D7631987-12-18018 December 1987
Safety Evaluation Updating 861118 Fire Protection Sys Safety Evaluation.Util Alternate Fire Protection Configuration Acceptable
ML20149E1621987-12-18018 December 1987
Marked-up Safety Evaluation Re Proposed Safe Shutdown Sys & Exemption Requests Concerning 10CFR50,App R
ML20236U6961987-11-23023 November 1987
Safety Evaluation Supporting Amend 57 to License DPR-34. Addendum to Review of Proposed Tech Spec Change:Core Inlet Valves/Min Helium Flow & Max Core Region Temp Rise,Limiting Condition for Operation..., Technical Evaluation Rept Encl
ML20236U5761987-11-20020 November 1987
Safety Evaluation Re Helium Circulator S/N C-2101 Damage. Util Corrective Action Program Initiated
ML20236R3001987-11-13013 November 1987
Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components
ML20238C7621987-09-0202 September 1987
Safety Evaluation Concurring W/Util 870702 & 27 Ltrs & 870818 Telcon Re Elimination or Reduction of Maint Requirements on Certain Fire Seals
ML20235N6491987-07-13013 July 1987
Safety Evaluation Supporting Amend 56 to License DPR-34
ML20235F5281987-07-0202 July 1987
Safety Evaluation Re Safe Shutdown of Steam Generator Matls. Under Severe Transient Conditions,Fuel Temp Can Be Maintained Under Accepted Temp Limits & Plant Can Be Safely Shutdown
ML20235F5151987-07-0202 July 1987
Safety Evaluation Re Safe Emergency Shutdown of Reactor Sys. Operation at 82% Acceptable
ML20235F5441987-07-0202 July 1987
Safety Evaluation Re Effect of Firewater Cooldown on Steam Generator Structural Integrity.All Tests Acceptable
ML20235E5281987-06-29029 June 1987
Safety Evaluation Supporting Amend 55 to License DPR-34
ML20216G9511987-06-24024 June 1987
Revised Safety Evaluation Re Steam Line Rupture Detection & Isolation Sys (Slrdis).Slrdis Meets Requirements of 10CFR50, App A,Gdc 20 & GDC 4
ML20216G9911987-06-24024 June 1987
Supplemental Safety Evaluation Supporting Application for Amend to License DPR-34 Re Tech Specs for Steam Line Rupture Detection & Isolation Sys
ML20215J5401987-06-22022 June 1987
Draft Safety Evaluation Re Safe Emergency Shutdowns.Facility Operation at 82% Power Acceptable
ML20216J1921987-06-17017 June 1987
Safety Evaluation Re Mods to Reduce Moisture Ingress Into Reactor Vessel.Periodic Insps & Preventive Maint Should Be Performed on Pertinent Components.Operational Performance Should Be Continuously Upgraded
ML20214M4681987-05-20020 May 1987
Safety Evaluation Supporting Amend 54 to License DPR-34
ML20215J8271987-05-0505 May 1987
Safety Evaluation Supporting Amend 53 to License DPR-34
ML20209D7561987-04-22022 April 1987
Safety Evaluation Supporting Util 870211 Submittal Re Performance Enhancement Program,Finding 4-10
ML20206J9331987-04-0606 April 1987
Safety Evaluation Supporting Amend 52 to License DPR-34
ML20205S1141987-03-31031 March 1987
Safety Evaluation Accepting Util 831104 Response to Generic Ltr 83-28,Item 4.5.2, Reactor Trip Sys Reliability On-Line Testing. Facility Designed to Permit on-line Functional Testing,Including Testing of Reactor Trip Contactors
1997-05-05
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20196G6731997-07-0101 July 1997
Informs Commission That Decommissioning Process Has Been Completed at PSC of Colorado Fsvngs,Unit 1 Located in Town of Platteville in Weld County,Co
ML20141K9961997-05-0505 May 1997
Safety Evaluation Supporting Amend 89 to License DPR-34
ML20140E1121997-04-10010 April 1997
Confirmatory Survey of Group Effluent Discharge Pathway Areas for Fsv Nuclear Station,Platteville,Co
ML20134D1661997-01-30030 January 1997
Rev 1,Vol 6 to Final Survey Rept,Final Survey of Group E (Book 2A of 2)
ML20137S6111996-12-31031 December 1996
Annual Rept Pursuant to Section 13 or 15(d) of Securities Exchange Act 1934, for Fy Ended Dec 1996
ML20134G6401996-10-29029 October 1996
Rev 0,Volume 6,Books 1 & 2 of 2 to Final Survey of Group E
ML20134G6171996-10-29029 October 1996
Rev 2,Volume 1,Books 1 & 2 of 2 to Final Survey Description & Results
ML20134G7271996-10-29029 October 1996
Rev 0,Volume 11,Book 1 of 1 to Final Survey of Group J
ML20134G6861996-10-29029 October 1996
Rev 0,Volume 8,Books 1 & 2 of 2 to, Final Survey of Group G
ML20134G6321996-10-26026 October 1996
Rev 1,Volume 5,Books 2 & 3 of 3 to Final Survey of Group D
ML20133D7831996-10-22022 October 1996
Preliminary Rept - Orise Support of NRC License Insp at Fsv on 960930-1003
ML20116A4661996-07-19019 July 1996
Fsv Final Survey Exposure Rate Measurements
ML20112J6861996-05-31031 May 1996
June 1996 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.Rept Covers Period of 960216-0531
ML20112C1531996-05-17017 May 1996
Fsv Final Survey Exposure Rate Measurements
ML20101G5521996-03-21021 March 1996
Confirmatory Survey Activities for Fsv Nuclear Station PSC Platteville,Co, Final Rept
ML20097E3201996-01-31031 January 1996
Nonproprietary Fort St Vrain Technical Basis Documents for Piping Survey Instrumentation
ML20095K4131995-12-26026 December 1995
Rev 3 to Decommissioning Plan
ML20095H7211995-12-20020 December 1995
Revs to Fort St Vrain Decommissioning Fire Protection Plan Update
ML20095K9751995-12-15015 December 1995
Fort St Vrain Project Update Presentation to NRC, on 951207 & 15
ML20096C1671995-12-13013 December 1995
Rev 4 to Decommissioning Fire Protection Plan
ML20094M1651995-11-30030 November 1995
Nonproprietary Fsv Technical Basis Documents for Piping Survey Implementation
ML20092F3461995-09-14014 September 1995
Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning, Covering Period of 950516-0815.W/
ML20137H3531994-12-31031 December 1994
Partially Withheld, Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, App D,Comments by Mkf & Westinghouse Team & Responses
ML20137S2331994-12-31031 December 1994
Rept of Independent Counsel Investigation Concerning Issues at Fort St Vrain Nuclear Generating Station Decommissioning Project, Dec 1994
ML20029C6031993-12-31031 December 1993
1993 Annual Rept Public Svc Co of Colorado. W/940405 Ltr
ML20058Q3791993-12-21021 December 1993
Rev 1 to Decommissioning Plan for Fort St Vrain Nuclear Generating Station
ML20045B3641993-06-30030 June 1993
June 1993 Quarterly 10CFR50.59 Rept of Changes,Tests & Experiments for Fsv Decommissioning.
ML20045A4291993-06-0303 June 1993
LER 93-003-00:on 930505,new Source of Natural Gas Introduced within 0.5 Miles of ISFSI & Reactor Bldg W/O Prior NRC Approval.Caused by Field Routing of Natural Gas Pipe.Well Isolated by Well operator.W/930603 Ltr
ML20077D1631993-05-10010 May 1993
Enforcement Conference, in Arlington,Tx
ML20125C7161992-12-0707 December 1992
Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl
ML20128D7191992-12-0101 December 1992
Safety Evaluation Approving Exemption from Requirement of 10CFR50.54(q) to Change to Biennial Emergency Plan Exercise Rather than Annual Following Completion of Next Scheduled Exercise at Plant
ML20127P5861992-11-23023 November 1992
Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl
ML20127F5691992-11-0303 November 1992
Informs Commission of Intent to Issue Order Approving Plant Decommissioning Plan & Corresponding Amend to License DPR-34
ML20101E5761992-05-31031 May 1992
Monthly Defueling Operations Rept for May 1992 for Fort St Vrain
ML20096E8221992-04-30030 April 1992
Monthly Operating Rept for Apr 1992 for Fort St Vrain.W/
ML20095E9601992-04-17017 April 1992
Rev to Fort St Vrain Proposed Decommissioning Plan
ML20100R7431992-03-31031 March 1992
Monthly Operating Rept for Mar 1992 for Fort St Vrain.W/
ML20090L0621992-02-29029 February 1992
Monthly Operating Rept for Feb 1992 for Fort St Vrain Unit 1
ML20092D0081992-01-31031 January 1992
Monthly Operating Rept for Jan 1992 for Fort St Vrain Nuclear Generating Station
ML20102B2241992-01-22022 January 1992
Fort St Vrain Station Annual Rept of Changes,Tests & Experiments Not Requiring Prior Commission Approval Per 10CFR50.59, for Period 910123-920122
ML20094N6701991-12-31031 December 1991
Public Svc Co Annual Financial Rept for 1991
ML20091J6251991-12-31031 December 1991
Monthly Operating Rept for Dec 1991 for Fort St Vrain.W/
ML20094D6711991-11-30030 November 1991
Monthly Operating Rept for Nov 1991 for Fort St Vrain Unit 1
ML20090M1871991-11-20020 November 1991
FOSAVEX-91 Scenario for 1991 Plant Exercise of Defueling Emergency Response Plan
ML20086D6891991-11-15015 November 1991
Proposed Decommissioning Plan for Fort St Vrain Nuclear Generating Station
ML20085N1451991-11-0505 November 1991
Revised Ro:Operability Date of 910830 for Electric Motor Driven Fire Water Pump P-4501 Not Met.Pump Not Actually Declared Operable Until 911025.Caused by Unforseen Matl & Testing Problems.Equivalent Pump Available
ML20086C5451991-10-31031 October 1991
Monthly Operating Rept for Oct 1991 for Fort St Vrain.W/
ML20085H6611991-10-10010 October 1991
Assessment of Mgt Modes for Graphite from Reactor Decommissioning
ML20091D7671991-10-0101 October 1991
Rev B to Engineering Evaluation of Prestressed Concrete Reactor Vessel & Core Support Floor Structures for Proposed Sys 46 Temp Change
ML20085D9861991-09-30030 September 1991
Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/
1997-07-01
[Table view] |
Text
_ _ - _ - - _ _ - _ _ - _ _ _ - -
y .
r .' .
pmcoq
- , - J je UNITED STATES 1 y ,, c ' gg NUCLEAR REGULATORY COMMISSION
, .. p' WASHINGTON, D. C. 20555
\ ..... /
SAFETY. EVALUATION.BY.THE OFFICE OF. NUCLEAR REACTOR REGULATION RELATED T0. AMENDMENT.NO.70 TO FACILITY .0PERATING LICENSE.NO. DPR-34 PUBLIC. SERVICE-COMPANY.0F. COLORADO FORT.ST..YRAIN. NUCLEAR GENERATING. STATION DOCKET.NO. 50-267 1.0' INTRODUCTION By letter dated January 13, 1989, the licensee requested that the staff amend the Facility Operating License No. DPR-34 to allow the possessien of an increased amount of radioactive material for calibration purposes. The licensee also requested that the license be reformatted to resemble recently issued licenses. These changes would allow the licensee to possess appropriate scurces for calibration of the high range detector instrumentation.
2.0 EVALUATION The specific portions of the license updated are as follows:
Parts 2.C.(2), 2.C.(3), 2.C.(4), and 2.C.(5) concerning receipt possession and use of. source, byproduct and special nuclear material.
In each case, these sections have been updated to reflect the format of . I newer licenses. Appropriate limits on the amount of materials received, i possessed er utilized are contained in the Regulations or the Final Safety )
AnalysisReport(FSAR). The format followed reflects that of licenses recently issued by the Comission and reflects an earlier request by the Comission to update this license.
The staff therefore concludes that these proposed changes are acceptable.
3.0 _ ENVIRONMENTAL CONSIDERATION The amendment involves a change in the installation or use of a facility ccmponent located within the restricted area as defined in 10 CFR Part 20.
The staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any l effluents that may be released offsite, and that there is no significant '
increase in incividual or cumulative occupational radiation exposures.
The Comission has previously issued a proposed finding that the amendment i involves no significant hazards consideration and there has been no public I
comment on such finding. Accordingly, the amendment meets the eligibility 8904270178 890418 PDR ADOCK 05000267 P PDC
-__-._-_a _ - - - _ . - - - _ - - - _ _ . - . _ . - . - _ _ - - - _ _ _ - _ - . - . _ . _ - - _ _ _ _ - . - - . - _ _ . _ - _ - _ _ _ _ _ . - . . . - . - - - - .
~
l l
critericforcategoricalexclusionsetforthin10CFRSection51.22(c)(9).
Pursuant to 10 CFR 51.22(b), no environmental impact statement or environ-mental assessment need be prepared in connection with the issuance of the amendment.
4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner, and (2) public such activities will be conducted in compliance with the Commission's regulations, and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Date: April 18, 1989 Principal Contributor: Kenneth L. Heitntr, PD-IV l
l
}
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _
