Similar Documents at Surry |
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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2 ML18152B7621998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2 ML18153A3141998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610 ML18152B8161998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2 ML18153A2951998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ ML18153A2871998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Surry Power Station,Units 1 & 2 ML18153A3671998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Surry Power Station,Units 1 & 2 ML18153A3521997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Surry Power Station,Units 1 & 2 ML18153A3861997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Surry Power Station,Units 1 & 2 ML18153A3981997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Surry Power Station Units 1 & 2 ML18153A4501997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Surry Power Station,Units 1 & 2 ML18153A4421997-08-31031 August 1997 Monthly Operating Repts for Aug 1997 for Surry Power Station,Units 1 & 2 ML18153A4291997-07-31031 July 1997 Monthly Operating Repts for Jul 1997 for Surry Power Station,Units 1 & 2 ML18153A4241997-06-30030 June 1997 Monthly Operating Repts for June 1997 for SPS ML18153A4161997-05-31031 May 1997 Monthly Operating Repts for May 1997 for Surry Power Station Units 1 & 2 ML18152A5521997-04-30030 April 1997 Monthly Operating Repts for Apr 1997 for Surry Power Station Units 1 & 2 ML18153A4171997-04-30030 April 1997 Corrected Page 3 of 19 to MOR for Apr 1997 for Surry Power Station Unit 1 ML18152A4051997-03-31031 March 1997 Monthly Operating Repts for Mar 1997 for Surry Power Station Units 1 & 2 ML18152A5121997-02-28028 February 1997 Monthly Operating Repts for Feb 1997 for SPS ML18153A4941997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Surry Power Station,Units 1 & 2 ML18152A4041996-12-31031 December 1996 Monthly Operating Repts for Dec 1996 for Surry Power Station Units 1 & 2 ML18153A6441996-11-30030 November 1996 Monthly Operating Repts for Nov 1996 for Surry Power Station Units 1 & 2 ML18153A6301996-10-31031 October 1996 Monthly Operating Repts for Oct 1996 for Surry Power Station Units 1 & 2 ML18153A0861996-09-30030 September 1996 Monthly Operating Repts for Sept 1996 for Surry Power Station Units 1 & 2 ML18152A5491996-08-31031 August 1996 Monthly Operating Repts for Aug 1996 for Surry Power Station Units 1 & 2 ML18153A0421996-07-31031 July 1996 Monthly Operating Repts for Jul 1996 for Surry Power Station Units 1 & 2 ML18153A0221996-06-30030 June 1996 Monthly Operating Repts for June 1996 for Surry Power Station Units 1 & 2 ML18152A4031996-05-31031 May 1996 Monthly Operating Repts for May 1996 for Surry Power Station Units 1 & 2 ML18153A4571996-04-30030 April 1996 Monthly Operating Repts for Apr 1996 for Surry Power Station Units 1 & 2 ML18153A6871996-03-31031 March 1996 Monthly Operating Repts for Mar 1996 for Sps,Units 1 & 2 ML18153A5291996-02-29029 February 1996 Monthly Operating Repts for Feb 1996 for SPS ML18153A5931996-01-31031 January 1996 Monthly Operating Repts for Jan 1996 for Surry Power Station ML18153A5741995-12-31031 December 1995 Monthly Operating Repts for Dec 1995 for Surry Power Station Units 1 & 2 ML18153A5551995-11-30030 November 1995 Monthly Operating Repts for Nov 1995 for Surry Power Units 1 & 2 ML18153A6691995-10-31031 October 1995 Monthly Operating Repts for Oct 1995 for Surry Power Station Units 1 & 2 ML18153A7861995-09-30030 September 1995 Monthly Operating Repts for Sept 1995 for Surry Power Station Units 1 & 2 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619 05000281/LER-1999-004-02, :on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed1999-10-0101 October 1999
- on 981109,EDG Was Inoperable Longer than Allowed by TS Due to Governor Compensation Valve.Root Cause Evaluation Being Performed to Determine How Compensation Valve Became Closed
ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With ML18152B3371999-09-24024 September 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Request for Relief SR-026 for Surry Power Station Unit 2 ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 05000280/LER-1999-006, :on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With1999-08-27027 August 1999
- on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With
05000280/LER-1999-005-01, :on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed1999-08-27027 August 1999
- on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18152B3841999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section Xa Requirements for Containment Insp ML18152B3631999-08-23023 August 1999 Safety Evaluation Supporting Eddy Current Techniques Used by VEPCO to Determine Depth of Degradation Evident in Units SG Tubing & VEPCO Approach for Dispositioning Tubes with Avb Wear Indications ML18152B3831999-08-23023 August 1999 Safety Evaluation Granting Relief Request from ASME Section XI Requirements for Containment Insp 05000280/LER-1999-004-01, :on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms1999-08-13013 August 1999
- on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 05000281/LER-1999-003-02, :on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP1999-07-30030 July 1999
- on 990705,auto Reactor Trip on Low Coolant Flow,Occurred.Caused by Loop Stop Valve Failure.Approved RCE Recommendations,Designed to Prevent Recurrence of Similar Event Will Be Implemented Through CAP
ML20196J4781999-07-0101 July 1999 Safety Evaluation Supporting Amends 221 & 221 to Licenses DPR-32 & DPR-37,respectively ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With ML20195D3571999-06-0707 June 1999 Safety Evaluation Supporting Amends 220 & 220 to Licenses DPR-32 & DPR-37,respectively ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 05000281/LER-1999-002-02, :on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With1999-05-18018 May 1999
- on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With
ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 05000280/LER-1999-003-01, :on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With1999-04-28028 April 1999
- on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With
ML18152B6481999-04-14014 April 1999 Safety Evaluation Supporting Relief Requests IWE-2,4.5.6 & IWL-2 to Licenses DPR-32 & DPR-37 Respectively ML18152B6451999-04-13013 April 1999 SER Accepting Util Reactor Pressure Vessel Fluence Methodology for Surry Power Stations,Units 1 & 2 & North Anna Power Station,Units 1 & 2 Subject to Listed Limitations 05000281/LER-1999-001-02, :on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip1999-03-31031 March 1999
- on 990301,RPS Relay Not Placed in Trip Resulted in Violation of TS 3.7.Caused by Lack of Procedural Guidance.Developed New Procedure to Provide More Explicit Instructions for Placing Stop Valve in Relay Trip
ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 05000280/LER-1999-002-01, :on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 9902121999-03-29029 March 1999
- on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
05000280/LER-1998-013, :on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr1999-03-19019 March 1999
- on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML20207L8081999-03-12012 March 1999 Safety Evaluation Supporting Amends 219 & 219 to Licenses DPR-32 & DPR-37 ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With ML18152B5381999-02-16016 February 1999 SER Accepting Third 10-year Interval Inservice Insp Request for Relief for Surry Power Station,Unit 1.Staff Concludes That Licensee Proposed Alternative Will Provide Acceptable Level of Quality & Safety.Technical Ltr Rept Also Encl ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements 05000280/LER-1999-001, :on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable1999-01-21021 January 1999
- on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With ML18152B5861998-12-18018 December 1998 SER Approving Request Relief Related to Inservice Testing Program at Surry Power Station Unit 1 ML20198F9221998-12-16016 December 1998 Safety Evaluation Supporting Amends 217 & 217 to Licenses DPR-32 & DPR-37,respectively 05000280/LER-1998-014, :on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition1998-12-16016 December 1998
- on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5901998-12-16016 December 1998 Safety Evaluation Authorizing Request to Use Code Case N-577 as Alternative to Requirements of ASME Code Section XI for Surry Power Station,Unit 1 ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened 05000280/LER-1998-012, :on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With1998-12-0101 December 1998
- on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With
ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With ML20151U7261998-09-0303 September 1998 Safety Evaluation Approving Exemption from Certain 10CFR20 Requirements Re Use of self-contained Breathing Apparatus with Enriched Oxygen in Subatmospheric Containments at SPS ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML20237E9721998-08-26026 August 1998 Safety Evaluation Supporting Amends 216 & 216 to Licenses DPR-32 & DPR-37,respectively ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2 05000280/LER-1998-010, :on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status1998-07-31031 July 1998
- on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
1999-09-30
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 10, 1999 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.
SPS Lic/JSA Docket Nos.
License Nos.99-095 RO 50-280 50-281 DPR-32 DPR-37 The Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of January *i 999 is provided in the attachment.
If you have any questions or require additional information, please contact us.
Very truly yours, E. S. Grecheck, Site Vice President Surry Power Station Attachment Commitments made by this letter: None cc:
U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, S. W.
. Q 1 i*, (:~
S *t 23T85
- 1. r, '.
'* ',.)
u1 e J....J Atlanta, Georgia 30303 Mr. R. A. Musser NRG Senior Resident Inspector Surry Power Station 9902220181 990131 PDR ADOCK 05000280 R
- PDR, L ____....
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I VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 99-01 Approved:
'(
Date
e TABLE OF CONTENTS Section Surry Monthly Operating Report No. 99-01 Page 2 of 16 Page Operating Data Report - Unit No. 1............................................................................................................................ 3 Operating Data Report - Unit No. 2............................................................................................................................ 4 Unit Shutdowns and Power Reductions - Unit No. 1.................................................................................................. 5 Unit Shutdowns and Power Reductions - Unit No. 2.................................................................................................. 6 Average Daily Unit Power Level - Unit No. 1.............................................................................................................. 7 Average Daily Unit Power Level - Unit No. 2.............................................................................................................. 8 Summary of Operating Experience - Unit Nos. 1 and 2............................................................................................. 9 Facility Changes That Did Not Require NRC Approval............................................................................................ 1 O Procedure or Method of Operation Changes That Did Not Require NRC Approval................................................. 12 Tests and Experiments That Did Not Require NRC Approval.................................................................................. 13 Chemistry Report..................................................................................................................................................... 14 Fuel Handling - Unit Nos. 1 and 2............................................................................................................................ 15 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications....................................................................................................................... 16
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
OPERATING DATA REPORT e Surry Monthly Operating Report No. 99-01 Page 3 of 16 Docket No.:
Date:
Completed By:
50-280 02/02/99 R. Stief Unit Name:...........................................................
Reporting Period:.................................................
Licensed Thermal Power (MWt):..........................
Nameplate Rating (Gross MWe):.........................
Design Electrical Rating (Net MWe):....................
Maximum Dependable Capacity (Gross MWe):...
Maximum Dependable Capacity (Net MWe):.......
Surry Unit 1 January 1999 2546 847.5 788 840 801 Telephone:
(757) 365-2486
- 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9.
Power Level To Which Restricted, If Any (Net MWe):
- 10.
Reasons For Restrictions, If Any:
This Month Year-To-Date Cumulative
- 11.
Hours in Reporting Period 744.0 744.0 228888.0
- 12.
Hours Reactor Was Critical 744.0 744.0 162060.5
- 13.
Reactor Reserve Shutdown Hours 0.0 0.0 3774.5
- 14.
Hours Generator On-Line 744.0 744.0 159515.4
- 15.
Unit Reserve Shutdown Hours 0.0 0.0 3736.2
- 16.
Gross Thermal Energy Generated (MWH) 1893674.1 1893674.1 376084631.6
- 17.
Gross Electrical Energy Generated (MWH) 631358.0 631358.0 123401514.0
- 18.
Net Electrical Energy Generated (MWH) 610294.0 610294.0 117596898.0
- 19.
Unit Service Factor 100.0%
100.0%
69.7%
- 20.
Unit Availability Factor 100.0%
100.0%
71.3%
- 21.
Unit Capacity Factor (Using MDC Net) 102.4%
102.4%
65.9%
- 22.
Unit Capacity Factor (Using DER Net) 104.1%
104.1%
65.2%
- 23.
Unit Forced Outage Rate 0.0%
0.0%
14.4%
- 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25.
If Shut Down at End of Report Period, Estimated Date of Start-up:
- 26.
Unit In Test Status (Prior to Commercial Operation):
FORECAST INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
OPERATING DATA REPORT e Surry Monthly Operating Report No. 99-01 Page 4 of 16 Docket No.:
Date:
Completed By:
50-281 02/02/99 R. Stief Unit Name:...........................................................
Reporting Period:.................................................
Licensed Thermal Power (MWt):..........................
Nameplate Rating (Gross MWe):.........................
Design Electrical Rating (Net MWe):....................
Maximum Dependable Capacity (Gross MWe):...
Maximum Dependable Capacity (Net MWe):.......
Surry Unit 2 January 1999 2546 847.5 788 840 801 Telephone:
(757) 365-2486
- 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9.
Power Level To Which Restricted, If Any (Net MWe):
- 10.
Reasons For Restrictions, If Any:
This Month Year-To-Date
- 11.
Hours in Reporting Period 744.0 744.0
- 12.
Hours Reactor Was Critical 744.0 744.0
- 13.
Reactor Reserve Shutdown Hours 0.0 0.0
- 14.
Hours Generator On-Line 744.0 744.0
- 15.
Unit Reserve Shutdown Hours 0.0 0.0
- 16.
Gross Thermal Energy Generated (MWH) 1894101.8 1894101.8
- 17.
Gross Electrical Energy Generated (MWH) 636210.0 636210.0
- 18.
Net Electrical Energy Generated (MWH) 615013.0 615013.0
- 19.
Unit Service Factor 100.0%
100.0%
- 20.
Unit Availability Factor 100.0%
100.0%
- 21.
Unit Capacity Factor (Using MDC Net) 103.2%
103.2%
- 22.
Unit Capacity Factor (Using DER Net) 104.9%
104.9%
- 23.
Unit Forced Outage Rate 0.0%
0.0%
- 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling, April 19, 1999, 35 Days
- 25.
If Shut Down at End of Report Period, Estimated Date of Start-up:
- 26.
Unit In Test Status (Prior to Commercial Operation):
FORECAST INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED Cumulative 225769.0 160654.3 328.1 158637.5 0.0 375689750.8 123184103.0 117437040.0 70.3%
70.3%
66.5%
66.0%
11.3%
I~
e Surry Monthly Operating Report No. 99-01 Page 5 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL TO OR GREATER THAN 20%)
(1)
F:
Forced S:
Scheduled (4)
REPORT MONTH: January 1999 None during the Reporting Period (2)
REASON:
A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NU REG 0161)
Docket No.:
50-280 Unit Name: Surry Unit 1 Date:
02/01/99 Completed by:
J. R. Pincus Telephone:
(757) 365-2863 (3)
METHOD:
1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit 1 - Same Source
e Surry Monthly Operating Report No. 99-01 Page 6 of 16 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
(1)
F:
Forced S:
Scheduled (4)
REPORT MONTH: January 1999 None during the Reporting Period (2)
REASON:
A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NU REG 0161)
Docket No.: 50-281 Unit Name:
Surry Unit 2 Date:
02/01/99 Completed by:
J. R. Pincus Telephone:
(757) 365-2863 (3)
METHOD:
1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit 1 - Same Source
MONTH:
January 1999 Day 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 INSTRUCTIONS e
e Surry Monthly Operating Report No. 99-01 Page 7 of 16 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)
Day 821 17 820 18 822 19 822 20 821 21 821 22 822 23 822 24 823 25 823 26 822 27 822 28 818 29 816 30 821 31 821 Docket No.: 50-280 Unit Name:
Surry Unit 1 Date: 02/02/99 Completed by:
J. S. Ashley Telephone: (757) 365-2161 Average Daily Power Level (Mwe - Net) 821 821 819 819 820 820 821 820 820 821 816 814 820 821 819 On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.
MONTH:
January 1999 Day 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 INSTRUCTIONS e
Surry Monthly Operating Report No. 99-01 Page 8 of 16 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (Mwe - Net)
Day 827 17 827 18 827 19 827 20 826 21 826 22 825 23 827 24 827 25 826 26 825 27 826 28 827 29 828 30 827 31 828 Docket No.:
50-281 Unit Name:
Surry Unit 2 Date:
02/02/99 Completed by:
J. S. Ashley Telephone:
(757) 365-2161 Average Daily Power Level (Mwe - Net) 827 827 827 824 825 826 827 827 827 826 827 828 828 827 827 On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: January 1999 e
Surry Monthly Operating Report No. 99-01 Page 9 of 16 The following chronological sequence by unit is a summary of operating experiences for this month that required load reductions or resulted in significant non-load related incidents.
UNIT ONE:
01/01/99 01/31/99 UNIT Two:
01/01/99 01/31/99 0000 2400 0000 2400 Unit starts the month at 100% / 855 MWe.
Unit finishes the month at 100% / 845 MWe.
Unit starts the month at 100% / 859 MWe.
Unit finishes the month at 100% / 860 MWe.
DCP 97-052 DCP 97-004 DCP 98-069 FS98-038 DCP 97-056 FS98-030 e
e Surry Monthly Operating Report No. 99-01 Page 10 of 16 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: January 1999 Design Change Package (Safety Evaluation 97-145 Rev. 2) 01/28/99 Design Change Package 97-052, "Control Rod Drive Mechanism (CROM) Housing Leak Repair/Surry/Unit 2", describes the repairing of two reactor vessel head nozzle canopy seal weld leaks using Canopy Seal Clamp Assemblies (CSCA). CSCA is a permanent non-welded mechanical method of leak repair developed by ABB Combustion Engineering and has been fully tested at operating temperature, pressure and seismic conditions for nuclear power plant use. Revision 2 of Safety Evaluation 97-145 documents the revising of ABB's Design Report to envelop the Surry Power Plant specific design criteria.
Design Change Package (Safety Evaluation 97-158 Rev. 1) 01/28/99 Design Change Package 97-004 "Spent Fuel Pool Cooling Pump Power Upgrade & Piping Reclassification/Surry/1&2", describes providing the Spent Fuel Pool (SFP) cooling pumps with emergency bus power. Pumps were previously powered from the Station Service buses. Revision 1 of Safety Evaluation 97-158 describes the actions necessary should the SPF cooling pumps be de-powered due to the Containment Spray pumps starting and loading on the Emergency Diesel Generator (EOG) if a HI-HI-CLS with a loss of offsite power has occurred.
Design Change Package (Safety Evaluation 98-115 Rev. 1) 01/28/99 Design Change Package 98-069, "Control Rod Drive Mechanism (CROM) Housing Leak Repair/Surry/Unit 1 ", describes the repairing of two reactor vessel head nozzle canopy seal weld leaks using Canopy Seal Clamp Assemblies (CSCA). CSCA is a permanent non-welded mechanical method of leak repair developed by ABB Combustion Engineering and has been fully tested at operating temperature, pressure and seismic conditions for nuclear power plant use. Revision 1 of Safety Evaluation 98-115 documents the revising of ABB's Design Report to envelop the Surry Power Plant specific design criteria.
UFSAR Change Request (Safety Evaluation 99-003) 01/14/99 This change clarifies the Topical Report (TR) Table 17.2.0 to add a second records vault for storage of QA records at the Innsbrook Technical Center. Both vaults meet the ANSI N45.2.9-197 4 requirement.
Design Change Package UFSAR Change Request (Safety Evaluation 99-004) 01/14/99 The current two Unit 1 555-ton chillers will be replaced with 350-ton chillers and Bearing Cooling (BC) water will be used to cool the new chillers instead of Service Water. There are no UFSAR or Technical Specifications limiting conditions or special requirements associated with this design change.
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1 FS98-037 FS87-035 e Surry Monthly Operating Report No. 99-01 Page 11 of 16 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: January 1999 UFSAR Change Request (Safety Evaluation 99-005) 01/25/99 UFSAR Change Request FS98-037 contains corrections and clarifications to the UFSAR sections that discuss Surry's Auxiliary Feedwater (AFW) system as a result of the Integrated Configuration Management project review of the AFW system. Safety Evaluation 99-005 also includes information pertaining to UFSAR Change Request 87-035 that dealt with implementing administrative changes. These changes are to enhance accuracy and do not affect any AFW system or structure, or any of its component's operation or performance.
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PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: January 1999 None during the Reporting Period Surry Monthly Operating Report No. 99-01 Page 12 of 16
e Surry Monthly Operating Report No. 99-01 Page13of16 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: January 1999 None during the Reporting Period
CHEMISTRY REPORT MONTHNEAR: January 1999 Unit No. 1 Primary Coolant Analysis Max.
Min.
AvQ.
Gross Radioactivity, µCi/ml 4.27E-1 2.06E-1 3.27E-1 Suspended Solids, ppm Gross Tritium, µCi/ml 5.43E-1 2.60E-1 4.10E-1 1131, µCi/ml 4.04E-4 2.37E-4 3.06E-4 113111133 0.09 0.03 0.06 HydroQen, cc/kQ 44.5 35.8 39.2 Lithium, ppm 2.41 2.09 2.24 Boron - 10, ppm*
250.7 240.5 245.5 OxyQen, (DO), ppm 0.005 0.005 0.005 Chloride, ppm 0.025 0.020 0.022 pH @ 25 degree Celsius 6.50 6.24 6.37 Boron - 10 = Total Boron x 0.196 Comments:
None e
Surry Monthly Operating Report Unit No. 2 Max.
Min.
2.01E-1 6.81 E-2 2.57E-1 1.57E-1 1.57E-4 4.35E-5 0.18 0.02 41.1 32.9 1.52 1.11 37.2 17.4 0.005 0.005 0.003 0.001 7.51 7.10 No. 99-01 Page14of16 AvQ.
1.29E-1 2.08E-1 8.10E-5 0.09 37.6 1.32 27.1 0.005 0.002 7.30 J
New Fuel Shipment or Cask No.
FUEL HANDLING UNITS 1 & 2 MONTHNEAR: January 1999 Number of Date Stored or Assemblies Received per Shipment Assembly Number ANSI Number None during the Reporting Period
-Surry Monthly Operating Report No. 99-01 Page 15 of 166 Initial Enrichment New or Spent Fuel Shipping Cask Activity
e Surry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: January 1999 None during the Reporting Period No. 99-01 Page 16 of 16