Letter Sequence Other |
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MONTHYEARML20204E3301980-07-0202 July 1980 Discusses Objectives & Conclusions Re Helium Circulator C-2102 Insp.Forwards Ga Co rept,GA-C15847,re Insp Results. Requests Review of Proposed Inservice Insp Program in Draft Tech Specs Submitted 800331.W/o Rept Project stage: Draft Other ML20237K2111987-07-31031 July 1987 Monthly Operating Rept for Jul 1987 Project stage: Other ML20237G7401987-08-21021 August 1987 Notification of 870911 Meeting W/Util in Arlington,Tx to Discuss Plant Circulator Failure & Recovery Project stage: Meeting ML20235H4731987-09-11011 September 1987 Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification for Returning to Power Operation Project stage: Other 05000267/LER-1987-018, Summarizes Util Commitments to Support Continued Operation of Plant,Per 870911 Meeting W/Nrc Re Damage in Helium Circulator C-2101 (Ref LER 87-018)1987-09-21021 September 1987 Summarizes Util Commitments to Support Continued Operation of Plant,Per 870911 Meeting W/Nrc Re Damage in Helium Circulator C-2101 (Ref LER 87-018) Project stage: Meeting ML20235H4401987-09-21021 September 1987 Summary of 870911 Meeting W/Util in Arlington,Tx Re Failure of Plant Circulator S/N C-2101 & Licensee Program to Recover from Failure.Licensee Rept, Preliminary Rept of Helium Circulator S/N C-2101 Damage & Justification... Encl Project stage: Meeting ML20236U5651987-11-20020 November 1987 Forwards Interim Safety Evaluation Re Helium Circulator S/N C-2101 Damage & Util Commitments for Continued Plant Operation.Reactor Will Be Shut Down Until Corrective Actions Are Completed Project stage: Approval ML20236U5761987-11-20020 November 1987 Safety Evaluation Re Helium Circulator S/N C-2101 Damage. Util Corrective Action Program Initiated Project stage: Approval ML20237A8151987-12-0808 December 1987 Forwards List of Questions Re New Bolting Matls for Helium Circulator C2101,per 871118 Telcon.One of Key Issues Was Util Decision to Use A286 Spec Bolts to Fasten circulator- Steam Scroll to Bearing Housing Project stage: Other ML20148G8301987-12-14014 December 1987 Metallurgical Analysis of Components from Helium Circulator C-2101 Project stage: Other ML20148G7711988-01-22022 January 1988 Forwards Rept of Helium Circulator S/N C-2101 & Inlet Piping S/N 2001 Repair & Mod Activities, Per Commitment in . Insp Findings & Proposed Tech Spec Amend to Be Submitted 8 Months Following Removal of Circulator for Insp Project stage: Other ML20148G7941988-01-22022 January 1988 Rept of Helium Circulator S/N C-2101 & Inlet Piping S/N 2001 Repair & Mod Activities Project stage: Other ML20148G8511988-01-22022 January 1988 Helium Circulator Insp Schedule Project stage: Other ML20153A8551988-03-0909 March 1988 Summary of 880304 Meeting W/Util to Discuss 880122 Submittal Re Helium Circulator Failure & Recovery.Attendee List & Viewgraphs Encl Project stage: Meeting ML20151L8911988-04-14014 April 1988 Discusses Revised Helium Circulator Outage Schedule,Per NRC 880304 Meeting.Schedule for 12 Wk Outage for Refurbishment of Helium Circulators Will Start on 880705 Instead of 880502 Project stage: Meeting ML20195K0591988-06-15015 June 1988 Forwards SER Concurring W/Util Proposed Corrective Actions in Engineering Rept Entitled, Helium Circulator S/N C-2101 Damage & Inlet Piping S/N 2001 Repair & Mod Activities Project stage: Approval 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 Project stage: Other 1987-08-21
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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20101E5761992-05-31031 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/ 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 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 ML20086C5451991-10-31031 October 1991 Monthly Operating Rept for Oct 1991 for Fort St Vrain.W/ ML20085D9861991-09-30030 September 1991 Monthly Operating Rept for Sept 1991 for Fort St Vrain.W/ ML20082U6151991-08-31031 August 1991 Monthly Operating Rept for Aug 1991 for Fort St Vrain Unit 1 ML20082J0071991-07-31031 July 1991 Monthly Operating Rept for Jul 1991 for Fort St Vrain,Unit 1 ML20076C5621991-06-30030 June 1991 Monthly Operating Rept for June 1991 for Fort St Vrain.W/ ML20077F8391991-05-31031 May 1991 Monthly Operating Rept for May 1991 for Fort St Vrain ML20077C2591991-04-30030 April 1991 Monthly Operating Rept for Apr 1991 for Fort St Vrain ML20084U7831991-03-31031 March 1991 Monthly Operating Rept for Mar 1991 for Fort St Vrain ML20070P4811991-02-28028 February 1991 Monthly Operating Rept for Feb 1991 for Fort St Vrain.W/ ML20066G5561991-01-31031 January 1991 Monthly Operating Rept for Jan 1991 for Fort St Vrain Unit 1 ML20070A5841990-12-31031 December 1990 Monthly Operating Rept for Dec 1990 for Fort St Vrain Unit 1 ML20065R0331990-11-30030 November 1990 Monthly Operating Rept for Nov 1990 for Fort St Vrain Unit 1 ML20058H8821990-10-31031 October 1990 Monthly Defueling Operations Rept for Oct 1990 for Fort St Vrain Nuclear Generating Station ML20197H8721990-10-31031 October 1990 Monthly Operating Rept for Oct 1990 for Fort St Vrain.W/ ML20059P0661990-09-30030 September 1990 Monthly Operating Rept for Sept 1990 for Fort St Vrain Nuclear Generating Station ML20059J1061990-08-31031 August 1990 Monthly Defueling Operating Rept for Aug 1990 for Fort St Vrain ML20058Q1661990-07-31031 July 1990 Monthly Operating Rept for Jul 1990 for Fort St Vrain ML20043G1141990-05-31031 May 1990 Monthly Operating Rept for May 1990 for Fort St Vrain. W/900615 Ltr ML20043A1121990-04-30030 April 1990 Monthly Operating Rept for Apr 1990 for Fort St Vrain. W/900515 Ltr ML20042E6421990-03-31031 March 1990 Monthly Defueling Operations Rept for Mar 1990 for Fort St Vrain.W/900413 Ltr ML20006F5441990-01-31031 January 1990 Monthly Defueling Operations Rept for Jan 1990 for Fort St Vrain.W/900215 Ltr ML19354E0791989-12-31031 December 1989 Monthly Operating Rept for Dec 1989 for Fort St Vrain, Unit 1.W/900112 Ltr ML19351A6521989-11-30030 November 1989 Monthly Operating Rept for Nov 1989 for Fort St Vrain, Unit 1.W/891206 Ltr ML19351A6531989-10-31031 October 1989 Monthly Operating Rept for Oct 1989 for Fort St Vrain, Unit 1.W/891206 Ltr ML19327B1821989-09-30030 September 1989 Monthly Defueling Operating Rept for Sept 1989 for Fort St Vrain Nuclear Generating Station ML20247H2111989-08-31031 August 1989 Monthly Operating Rept for Aug 1989 for Fort St Vrain ML20245L5831989-07-31031 July 1989 Monthly Operating Rept for Jul 1989 for Fort St Vrain Nuclear Generating Station ML20246Q2241989-06-30030 June 1989 Monthly Operating Rept for June 1989 for Fort St Vrain Unit 1 ML20245C4471989-05-31031 May 1989 Monthly Operating Rept for May 1989 for Fort St Vrain ML20247A8961989-04-30030 April 1989 Monthly Operating Rept for Apr 1989 for Fort St Vrain Nuclear Generating Station ML20244E2151989-03-31031 March 1989 Monthly Operating Rept for Mar 1989 for Fort St Vrain ML20236C3731989-02-28028 February 1989 Monthly Operating Rept for Feb 1989 for Fort St Vrain Nuclear Generating Station ML20235J6181989-01-31031 January 1989 Monthly Operating Rept for Jan 1989 for Fort St Vrain Nuclear Generating Station ML20206F6871988-10-31031 October 1988 Monthly Operating Rept for Oct 1988 for Fort St Vrain Nuclear Generating Station ML20207N3841988-09-30030 September 1988 Monthly Operating Rept for Sept 1988 for Fort St Vrain ML20154H5331988-08-31031 August 1988 Monthly Operating Rept for Aug 1988 for Fort St Vrain.W/ ML20151V7821988-07-31031 July 1988 Monthly Operating Rept for Jul 1988 for Fort St Vrain Unit 1 ML20151E8951988-06-30030 June 1988 Monthly Operating Rept for June 1988 for Fort St Vrain ML20196C0671988-05-31031 May 1988 Monthly Operating Rept for May l988 for Fort St Vrain Nuclear Generating Station ML20154C2741988-04-30030 April 1988 Monthly Operating Rept 171 for Apr 1988 ML20151G1941988-03-31031 March 1988 Monthly Operating Rept for Mar 1988 ML20153B1361988-02-29029 February 1988 Monthly Operating Rept for Feb 1988 ML20149F8441988-01-31031 January 1988 Monthly Operating Rept 168 for Jan 1988 1992-05-31
[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
, . .
I PUBLIC SERVICE COMPANY OF COLORADO l
i FORT ST. VRAIN NUCLEAR GENERATING STATION i
l l
MONTHLY OPERATIONS REPORT NO. 162 July, 1987 E
' 8708190136 870731
)/$
PDR ADOCK 05000267 PDR _
R
____m_____ _ _ _ _____
W l
1 This report contains the highlights of the Fort St. Vrain, Unit No. 1, activities operated under the provisions of the Nuclear Regulatory Commission Operating License DPR-34 This report is for the month of July,1987.
1.0 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE AND MAJOR SAFETY RELATED MAINTENANCE On July 2, 1987, the Office of Nuclear Reactor Regulation authorized operation of Fort St. Vrain above 35 percent of full power, not to exceed 82 percent, based on reanalysis of safe shutdown cooling following a 90 minute interruption of forced cooling.
On July 3, 1987,, with the Average Region Outlet Temperature greater than 1200 degrees Fahrenheit, the 10 day grace period for Technical Specification LCO 4.2.10 was entered at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> when primary coolant oxidants exceeded 10 PPM. Oxidants peaked at approximately 26.4 PPM on July 4, and then gradually reduced to approximately 18 PPM. Reactor power was reduced to lower the Average Region Outlet Temperature to less than 1200 degrees l
Fahrenheit at 1852 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.04686e-4 months <br /> on July 12, thereby exiting the grace l period of LCO 4.2.10.
On July 10, 1987, and again on July 11, 1987, with the reactor l operating at 57 percent power, the group III Loop II steam I generator penetration interspace operating below primary coolant pressure, with and RIS-2264 inoperable, grab samples were not collected fror the Loop II steam generator penetration interspace as required per Technical Specification LCO 4.2.9. This incident occurred as a result of personnel error in combination with a deficient procedure. This incident has beaa investigated and reported to the Nuclear Regulatory Commission in Licensee Event Report 87-017.
d Primary coolant oxidants were reduced to less than 10 PPM on l
July 16. On July 17, reactor power was increased and the Average Region Outlet Temperature exceeded 1200 degrees Fahrenheit at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />. The 10 day grace period for LCO 4.2.10 was entered
- at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> when the total primary coolant oxidants exceeded i
10 PPM. j l
l On July 22, 1987, at 0012 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, C helium circulator tripped on l Circulator Speed /Feedwater Flow Mismatch. At 0517 hours0.00598 days <br />0.144 hours <br />8.54828e-4 weeks <br />1.967185e-4 months <br />, with. C helium circulator self-turbining, D helium circulator )
automatically tripped on high speed. Loop II secondary flow was 1 manually isolated and reactor power was reduced to less than 2 i percent to recover Loop II. During the Loop II recovery,
- excessive wobble and erratic speed indications were observed on D
, helium circulator. O circulator was shutdown and the Loop II l recovery proceeded on C helium circulator. The turbine generator
[ was synchronized to the grid on July 25, at 0956 hours0.0111 days <br />0.266 hours <br />0.00158 weeks <br />3.63758e-4 months <br />.
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4 l j ,t _ q, i On July;_28, 1987,' , ,a pur'ified herium bil,of approximately 800 ,
i pounds 'per e.?y cevehped in ti+, int esuce on D helium ,.
T:4Micu Specification, 100 d.2.9 required the cirettlator. >
c ,i rea: tor to be rhutdown and depressurized.i.n less than 100 psia 'i^> '
within 24 hours Si nce the leak rate was in excess of 400 pounds l<
per day. The tuttir.e gbnerator was removed from service on l July 29, at 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />. A manual reactor shutdown was complet7d*
at 1026 hour0.0119 days <br />0.285 hours <br />0.0017 weeks <br />3.90393e-4 months <br /> 3 Following the reactor shutdown, it was deter ined that D heltum circulator would be replaced. This/eventwillbe .
investigated 'and reported to tr.o duclear Regulatory Commissio Jn , 1 Licensee Event Report 87-018.V t 2.0 SINGLE PELEASES OF RADIOACTIVITY OR RADIATION EXPOSURE IN EXCESS OF IC% OF THE ALLOWABLE AMNUAL VALUE I
.4
?
None ,
3.0 INDICATION OF FAILED FUEL RESULTING FROW IRRADIATED FUEL EXAMINATIONS 'i t
None l 4.0 MONTHLY OPERATING DATA REPGRT l
l Attached l
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- ePreATIN CATA RTr0T* DoctET ra. __50-267 dan Auoust 14. 19R7
/
! coxrLETED al F. J. Novachek ,
(303) 620-1007 f masonE opExAnn: STAT >s NOTES
- a. Unit Name: Fort St. Vrain. Unit No. 1
- 3. Reporting Period: 870701 throuah 870731
- 3. Licensed Thermal Power (Wt): 842
- 6. Nameplate Rating (Cross We): 342
- 5. Design Electrical Rating (Net We): 330
- 6. Maxinum Dependable Capacity (Gross We): __342
- 7. Maximum Dependable Capacity (Net We): 330
- 8. If Changes occur in Capacity Eatings (Items Nummer 3 Through 7) Since Last Erport. Give Reasons:
None i
- 9. Power Level To Which Kestricted, If Any (Net Wet: 270.6
- 10. Reasons f or Restrictions, If Any: Reanalysis of safe shutdown coolino followina a 90 minute interruption of forced coolina.
This Month Tear to Date Cu:nulative i n. sours in Reporting Period 744 5.087 70.872
- 12. Nu:eer of sours aeactor was critical 682.4 2.392.4 32.930.2
- 13. Reactor Reserve Shutdown Ecurs 0.0 0.0 0.0
~
- 14. nour Generator on-Line . 597.1 1.811.7 21.366 4._
l 15. unit a serve Shutdown Boars 0.0 _
0.0 0.0
- 16. Cross Thermal Energy Generated (WH) 248.206.R 576.546.1 10.841.945.9
- 17. Cross Electrical Energy Generated (WH) 91.227.0 189.789.0 3J;23.785.0
- 18. Net Electrical Energy Generated (WB) R4_273_O 163_3Q7_O 3.1I1.677_O
- 19. Unit Service Factor 80.3 35.6 30.1 t
- 20. Unit Availability Tactor 80.3 35.6 3 0 .1_____ j l 21. Unit capacity Factor (Using MDC Net) 34.3 9.7 13.3 {
1 l 22. Unit Ca acity factor (1' zing DER Net) 34.3 9.7 13.3 I 23. unit rorces outare Rate 19.7 64.4 62.7 i ,
! 24. Shutdovcs Scheduled over Next 6 lbnths (Type. Date, and Duration of Each): RpDlaro O helium '
cirenlator. R70A01. 1732 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.59026e-4 months <br />
- 25. If Shut Down at End of Report Period. Estinar.ed Date of Startup: ,,$6ptember 21. 19R7
- 26. Units In Test Status (Prior to Cor::mercial operaticn): rotecast Achieved innAt cRmerl.in N/A N/A InnAt rucmcm N/A N/A comEnc:AL orExancs N/A N/A
[ o J
AVERA3E' DAILY UNIT POWER LEVEL Docket No, 50-267 Unit Fort St. Vrain Unit No. 1 Date August 14, 1987 Completed Ey F. J. Novachek Telephone (303) 620-1007 Month JULY DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 90.1 17 145.7 2 91.8 18 177.4 l 3 142.2 19 191.6 4 164.4 20 198.5 5 163.2 21 216.8 6 164.5 22 16.5 7 171.5 23 0.0 8 169.2 24 0.0 9 172.6 25 33.6 10 174.3 26 85.8 11 173.9 27 127.4 12 134.4 28 123.1 13 105.7 29 0.0*
14 104.5 30 0.0 15 101.8 31 0.0 16 96.8
- Generator on line but no net generation.
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1 REFUELING INFORMATION I l l l 1. Name of Facility 1 Fort St. Vrain Unit No. 1 l l l l l 2. Scheduled date for next l l l refueling shutdown. I October 15, 1988 l l l l l 3. Scheduled date for restart l December 15, 1988 l l following refueling. l l l l l l 4. Will refueling or resumption ofl No l
! operation thereafter require a l l l technical specification change l l l or other license amendment? I l l l l l If answer is yes, what, in l ---------------- l i general, will these be? l l l l l l If answer is no, has the reloadj l l fuel design and core configura-l l l tion been reviewed by your l l l Plant Safety Review Committee l No l l to determine whether any unre- l l l viewed safety questions are l l l associated with the core reload l l l (Reference 10 CFR Section l l l 50.59)? I l l 1 l l If no such review has taken l 1987 l l place, when is it scheduled? l l l l l l 5. Scheduled date(s) for submit- l l l ting proposed licensing action j ---------------- l l and supporting information. l l l l l l 6. Important licensing considera- l l ,
I tions associated with refuel- l l )
l ing, e.g., new or different l l l fuel design or supplier, unre- l ---------------- l l viewed design or performance l l l analysis methods, significant l l l changes in fuel design, new l l l operating procedures. l l l l l l 7. The number of fuel assemblies l l l (a) in the core and (b) in the l a) 1482 HTGR fuel elements l l spent fuel storage pool. I b) 0 spent fuel elements l ,
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e REFUELING INFORMATION (CONTINUE 0) l I I l 8. The present licensed spent fuell l l pool storage capacity and the l l j size of any increase in l Capacity is limited in size to l l licensed storage capacity that l about one-third of core l l has been requested or is l (approximately 500 HTGR elements).1 l planned, in number of fuel l No change is planned. l l assemblies. l l 1 I l l 9. The projected date of the last l 1992 under Agreements AT(04-3)-633l l refueling that can be dis- l and DE-SC07-791001370 between l l charged to the spent fuel pool l Public Service Company of I l assuming the present licensed l Colorado, and General Atomic l l capacity. l Company, and DOE.* l
- The 1992 estimated date is based on the understanding that spent fuel l discharged during the term of the Agreements will be stored by DOE at the Idaho Chemical Processing Plant. The storage capacity has evidently been sized to accommodate _ eight fuel segments. It is estimated that the eighth fuel segment will be discharged in 1992.
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l O Public Service ~ Company of Colorado i
16805 WCR 19 1/2, Platteville, Colorado 80651 August 14, 1987 Fort St. Vrain
. Unit No. I l P-87291
- I l U. S. Nuclear Regulatory Commission I i
ATTN: Document Control Desk Washington, D.C. 20555 i Docket No. 50-267 I
SUBJECT:
MONTHLY OPERATIONS 1 REPORT FOR JULY,1987
REFERENCE:
Facility Operating License No. DPR-34
Dear Sir:
Enclosed, please find the Monthly Operations Report for the month of i July, 1987. !
If you have any questions, please contact Mr. M. H. Holmes at (303) I 480-6960.
Sincerely, hv' R. O. Williams, Jr.
Vice President, Nuclear Operations Enclosure cc: Mr. J. E. Gagliardo U.S. NRC, Region IV >
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