ML18153A352
| ML18153A352 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1997 |
| From: | Christian D, Marshall G, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 98-027, 98-27, NUDOCS 9801210211 | |
| Download: ML18153A352 (18) | |
Text
e e
VIRGINIA ELECTRIC AND POWER COMP.ANY RICHMOND, VIRGINIA 23261 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC J,ND POWER COMPANY SURRY P0\\1\\/ER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.
SPS Lic/JDK Docket Nos.
License Nos.98-027 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 Deicember *1997 is provided in the attachment.
If you have any questions or require additional information, please contact us.
Very trul:r yours,
~Jc.CLx::-
D. A. Cl1ristian, Station Manager 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. \\N.
Suite 23T85 Atlanta, Georgia 30303
e Surry Monthly Operating Report No. 97-12 Page 1 of 17 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 97-12 Approved:
~~~
I
- I'S... -,'IS Station Manager Date
TABLE OF CONTENTS Section Surry Monthly Operating Report No. 97-12 Page 2 of 17 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 NRG Approval....................................................................................... 10 Procedure or Method of Operation Changes That Did Not Require NRG Approval............................................. 12 Tests and Experiments That Did Not Require NRG 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................................................................................................................. 17
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
e OPERATING DATA REPORT e
Surry Monthly Operating Report No. 97-12 Page 3 of 17 Docket No.:
Date:
50-280 01/05/98 Completed By:
D. K. Mason (757) 365-2459 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 December, 1997 2546 847.5 788 840 801 Telephone:
- 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 8760.0 219384.0
- 12.
Hours Reactor Was Critical 744.0 7191.1 154025.8
- 13.
Reactor Reserve Shutdown Hours 0.0 0.0 3774.5
- 14.
Hours Generator On-Line 744.0 7068.5 151599.5
- 15.
Unit Reserve Shutdown Hours 0.0 0.0 3736.2
- 16.
Gross Thermal Energy Generated (MWH) 1894162.9 17609571.8 356245015.6
- 17.
Gross Electrical Energy Generated (MWH) 634447.0 5842936.0 116815754.0
- 18.
Net Electrical Energy Generated (MWH) 614197.0 5640472.0 111234221.0
- 19.
Unit Service Factor 100.0%
80.7%
69.1%
- 20.
Unit Availability Factor 100.0%
80.7%
70.8%
- 21.
Unit Capacity Factor (Using MDC Net) 103.1%
80.4%
65.2%
- 22.
Unit Capacity Factor (Using DER Net) 104.8%
81.7%
64.3%
- 23.
Unit Forced Outage Rate 0.0%
3.9%
14.8%
- 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):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED
- 1.
- 2.
- 4.
- 5.
- 6.
- 7.
OPERATING DATA REPORT e
Surry Monthly Operating Report No. 97-12 Page 4 of 17 Docket No.:
Date:
50-281 01/05/98 Completed By:
D. K. Mason (757) 365-2459 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 December, 1997 2546 847.5 788 840 801 Telephone:
- 8.
If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9.
Pow,2r 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 8760.0 216264.0
- 12.
Hours Reactor Was Critical 710.8 8074.7 151150.3
- 13.
Reactor Reserve Shutdown Hours 0.0 0.0 328.1
- 14.
Hours Generator On-Line 705.8 8035.6 149133.4
- 15.
Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16.
Gross Thermal Energy Generated (MWH) 1684576.2 20059310.5 351533567.3
- 17.
Gross Electrical Energy Generated (MWH) 564360.0 6674809.0 115125608.0
- 18.
Net Electrical Energy Generated (MWH) 546098.0 6451272.0 109643151. 0
- 19.
Unit Service Factor 94.9%
91.7%
69.0%
- 20.
Unit Availability Factor 94.9%
91.7%
69.0%
- 21.
Unit Capacity Factor (Using MDC Net) 91.6%
91.9%
64.9%
- 22.
Unit Capacity Factor (Using DER Net) 93.1%
93.5%
64.3%
- 23.
Unit Forced Outage Rate 5.1%
1.3%
11.9%
- 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):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED
(1)
Date Type (1)
F:
Forced S:
Scheduled (4)
UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: DECEMBER, 1997 e
Surry Monthly Operating Report No. 97-12 Page 5 of 17 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 01/05/98 Completed by:
G. N. Marshall Telephone: (757) 365-2465 (2)
(3)
Method of Shutting Down Rx (4)
(5)
Duration Hours Reason LER No.
System Code Component Code Cause & Corrective Action to Prevent Recurrence 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)
(3)
METHOD:
1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File {NUREG 0161)
Exhibit 1 - Same Source
Date Type 12/2/97 F
(1)
F:
Forced S:
Scheduled (4) e UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: DECEMBER, 1997 Surry Monthly Operating Report No. 97-12 Page 6 of 17 Docket No.:
50-281 Unit Name:
Surry Unit 2 Date:
01/05/98 Completed by:
G. N. Marshall Telephone:
(757) 365-2465 (2)
(3)
(5)
Duration Hours Method of Reason Shutting Down Rx (4)
LER No.
System Code Component Code Cause & Corrective Action to Prevent Recurrence 38.2 A
(2)
REASON:
97-004 A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction SB E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
ZI Invalid Main Steam Trip Valve (MSTV) indication resulted in manual trip.
MSTV actuator arm was relocated closer to the valve position bar to provide additional overlap.
(3)
METHOD:
1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee.Event Report (LER) File (NUREG 0161)
Exhibit 1 - Same Source
e Surry Monthly Operating Report No. 97-12 Page 7 of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name:
Surry Unit 1 Date: 01/05/98 Completed by: J. D. Kilmer Telephone: (757) 365-2792 MONTH:
DECEMBER, 1997 Average Daily Power Level Average Daily Power Level Day (MWe - Net)
Day (MWe - Net) 824 17 825 2
811 18 826 3
824 19 827 4
825 20 828 5
825 21 828 6
825 22 828 7
827 23 826 8
828 24 826 9
828 25 827 10 828 26 826 11 828 27 825 12 828 28 825 13 828 29 824 14 828 30 821 15 827 31 821
-is 827 INSTRUCTIONS 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.
e e
Surry Monthly Operating Report No. 97-12 Page 8 of 17 AVERAGE DAILY UNIT POWER LEVEL MONTH:
DECEMBER, 1997 Average Daily Power Level Day (MWe - Net}
1 831 2
327 3
0 4
214 5
216 6
482 7
827 8
827 9
828 10 828 11 827 12 828 13 828 14 828
- ,5 828 16 827 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 Docket No.: 50-281 Unit Name:
Surry Unit 2 Date: 01/05/98 Completed by:
John D. Kilmer Telephone: (757) 365-2792 Average Daily Power Level (MWe - Net}
827 828 827 826 827 828 828 826 827 825 826 826 827 829 830 On this format, !ist 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: DECEMBER, 1997 e
Surry Monthly Operating Report No. 97-12 Page 9 of 17 The following chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.
UNIT ONE:
12/01/97 0000 12/31/97 2400 UNITTwO:
12/01/97 0000 12/02/97 0930 12/03/97 1744 1843 2342 12/04/97 0021 12/06/97 0926 2223 12/31/97 2400 Unit 1 starts the month at 100% / 854 MWe.
Unit 1 finishes the month at 100% / 854 MWe.
Unit 2 starts the month at 100% / 854 MWe.
Manual reactor trip due to the "A" Main Steam Trip Valve indicating intermediate position.
Commence reactor startup.
Reactor critical.
Unit on line and Starting power increase.
Stop power increase at 30% / 220 MWe.
Start power increase.
Stop power increase at 100% / 850 MWe.
Unit 2 finishes the month at 100% / 855 MWe.
Appendix R Report TM S1-97-020 SE 97-0081 DCP 93-072 e
Surry Monthly Operating Report No. 97-12 Page 10 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: DECEMBER, 1997 Technical Report 12/01/97 (Safety Evaluation No.97-154)
This evaluation is being performed to assess the annual update of the Surry 10CFR50 Appendix R Report for 1997.
It incorporates previously approved Design Change Packages completed during 1996 through September 1997, as well as information concerning other station changes as they pertain to Appendix R. Engineering evaluations were revised to address changes to fire doors.
Changes to Appendix R exemption requests were performed to reflect current plant configurations.
The level of fire protection for the station is not being diminished, and the changes will not adversely affect the capacity to achieve and maintain safe shutdown in the event of a fire.
Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.97-156) 12/05/97 This Temporary Modification (TM) installs a jumper hose to provide an alternate water supply (Fish Screens system) to the Low Level Intake Structure Vacuum Priming (VP) system until the normal well water supply pump is returned to service.
This TM will enable the non-safety-related VP system to operate normally with the alternate water supply. Therefore, an unreviewed safety question does not exist.
f>afety Evaluation 12/17/97 Safety Evaluation 97-0081 was performed for the Surry ISFSI Safety Analysis Report. The.
TN-32 cask Topical Safety Analysis Report drawing 1049-70-2, rev. 2 shows a 30 degree angle for the trunnion. This is the weld prep angle for the trunnion to the gamma shield shell. The fabrication drawings show a 45 to 50 degree trunnion weld prep angle. The increase in the weld prep angle allows better access to perform the weld. The 45 to 50 degree angle has been used on all TN-32 trunnions, and was initiated at the start of the TN-32 purchase order. The ISFSI SAR will be amended to note the actual weld prep angle.
Changing a trunnion weld prep angle from 30 degrees to 45 - 50 degrees has no impact on the structural functions of the trunnions. The trunnion analyses presented in Chapter 3 of the TN-32 TSAR are not affected by the change in weld prep angle. Therefore, an unreviewed safety question does not exist.
Design Change Package (Safety Evaluation 96-131) 12/22/97 Design Change Package (DCP)93-072, removes the motor and bearing temperature sensors from the trip circuitry of the 555 ton chiller and uses them for indication only.
The 555 ton containment cooling chillers are non-safety related, and activation of the other safety cutouts will still automatically trip the chillers. This modification does not aiter any safety related components and will eliminate spurious trips thereby reducing operator distractions and challenges. Therefore, an unreviewed safety question does not exist.
JCO C-93-001 Rev. 3 e
Surry Monthly Operating Report No. 97-12 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: DECEMBER, 1997 Justification For Continued Operation (Safety Evaluation No.97-160) 12/23/97 This Safey Evaluation provides approval of an extension to the Justification for Continued Operation (JCO) C-93-001, Rev 3 until completion of Design Change Package 96-024 to achieve full compliance with Appendix R. Compensatory measures are in place to provide an hourly fire watch in the Unit 2 Emergency Switch Gear Room (ESGR) with operable Robert Shaw detection and Halon suppression systems. Should either of these systems become inoperable, a continuous fire watch would be initiated.
The compensatory measure will remain in effect until the closeout of the JCO.
The compensatory measures currently in effect provides a level of protection necessary for safe shutdown and is allowed by NRC regulations. The compensatory measure will remain in effect until compliance with 10 CFR 50 Appendix R can be met as described in the UFSAR. Therefore, an unreviewed safety question does not exist.
1
CAL-817 PT-26.GV IMP-C-RM-36 O-IPM-RM-G-001 O-IPM-RM-G-002 O-IPM-RM-G-003 ARP 1C-D7 1-CAL-442 1-FT-36 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: DECEMBER, 1997 Calibration Procedure Instrumentation Periodic Test Procedure Instrument Maintenance Procedure Instrument Preventive Maintenance Procedures (Safety Evaluation No.96-075 Rev 1)
Surry Monthly Operating Report No. 97-12 Page 12 of 17 12/01/97 Calibration Procedure CAL-817, "Model 942 Log Ratemeter Scintillation Detector Source Calibration," Instrumentation Periodic Test Procedure PT-26.SV, "Victoreen Radiation Monitoring Equipment Background, Heat Trace, Flow Fault Checks and Filter Replacement," Instrument Maintenance Procedure IMP-C-RM-36, "Checking, Repairing or Replacing a Component in the Radiation Monitoring System, and Instrument Preventive Maintenance Procedures O-IPM-RM-G-001, "Digital Ratemeter Model 9428 Process Monitor Calibration," O-IPM-RM-G-002, "9458 Series Area Monitor Ratemeter and Detector Calibration," and O-IPM-RM-G-003, "Model 943-5 GM Tube Detector Calibration," were revised to provide instructions to install/remove temporary modifications in the main control room radiation monitor cabinets to prevent various control functions from occurring while the digital ratemeters are removed from service for testing, repair, or calibration.
These activities will not alter the performance characteristics of any safety related systems or components. Only one ratemeter, that involves a control function, will be removed from service at a time. Therefore, an unreviewed safety question does not exist.
.Annunciator Response Procedure Calibration Procedure instrumentation Periodic Test Procedure (Safety Evaluation No.96-095 Rev. 7) 12/17/97 Annunciator Response Procedure 1 C-D7, "Pressurizer Power Relief Line Hi Temp,"
Calibration Procedure 1-CAL-442, "T-1-463 Pressurizer Power Relief Line Temperature,"
and Instrumentation Periodic Test Procedure 1-PT-36, "Instrument Surveillance," were revised to change the PORV high tailpipe temperature alarm setpoint from 220 °F to 225 °F. The alarm setpoint is set to correspond to Tsat for the normal operating pressure in the Pressurizer Relief Tank (PRT).
Since Temporary Modification S1-97-15 allows 0peration of the PRT on continuous vent to the Overhead Gas System which operates at pressures higher than the PRT, the PORV tailpipe temperature setpoint needs to be raised to match the new operating conditions.
This change involves an improvement in the monitoring of tailpipe temperature by clearing alarm 1 C-D7, PRZR PWR RELIEF LINE HI TEMP and re-establishing this annunciator as a tool in the diagnosis of increased PORV leakage.
Therefore, an unreviewed safety question does not exist.
e e
Surry Monthly Operating Report No. 97-12 Page 13 of 17 TESTS AND EXPERIMENTS THAT DID Nor REQUIRE NRC APPROVAL l\\t'IIONTHNEAR: DECEMBER, 1997 None During the Reporting Period
e CHEMISTRY REPORT MONTHNEAR: DECEMBER, 1997 Unit No. 1 Primary Coolant Analvsis Max.
Min.
Avg.
Gross Radioactivity, µCi/ml 3.85E-1 2.52E-1 3.14E-1 Suspended Solids, ppm so.010 so.010 so.010 Gross Tritium, 1,tCi/ml 6.40E-1 5.96E-1 6.24E-1 1131, 1-iCi/m!
3.93E-3 5.46E-4 1.62E-3 113111133 0.60 0.09 0.26 Hydrogen, cc/kQ 31.7 29.3 30.3 Lithium, ppm 2.33 2.06 2.19 Boron - 10, ppm*
175.8 158.0 167.4 Oxygen, (DO), pprn s0.005 s0.005 s0.005 Chloride, oom 0.004 0.002 0.003 pH at 25 deqre0 Celsius 6.77 6.67 6.72 Boron - 10 = Total Boron x 0:196 Comments:
None e
Surry Monthly Operating Report No. 97-12 Page 14 of 17 Unit No. 2 Max.
Min.
Avg.
2.07E-1 9.56E-2 1.51 E-1 so.010
- 0,010
- 0.010 4.29E-1 2.48E-1 3.29E-1 1.14E-4 1.17E-5 5.65E-5 0.11 0.07 0.09 38.1 32.7 35.8 2.94 2.11 2.37 325.9 237.2 268.1
- 0.005
- 0,005
- 0.005 0.004 0.003 0.003 6.49 6.26 6.38
New Fuel Shipment or Date Stored Cask No.
or Received DRY STORAGE CASK TN 32-05 12/16/97 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: DECEMBER, 1997 Number of Assemblies Assembly ANSI per Shipment Number Number 32 OP3 LM05YE OP4 LM05Y8 OS3 LMOES1 OS5 LMOESA OS7 LMOET4 1P3 LM05XE 1S1 LMOESN 1S6 LMOESQ 1S7 LMOESX 1S8 LMOES2 2P5 LM05YQ 2P9 LM05YO 2SO LMOERN 2S3 LMOESE 2S4 LMOES7 2S5 LMOET2 2S6 LMOESM 2S7 LMOES4 3P3 LM05YA 3P9 LM05XL 3SO LMOES5 3S3 LMOET9 3S8 LMOERT 3S9 LMOERW 4P7.
LM09PF 4S1 LMOESB t!urry Monthly Operating Report No. 97-12 Page 15 of 17 New or Spent Initial Fuel Shipping Enrichment Cask Activity 3.6070 N/A 3.6070 3.5897 3.6022 3.5993 3.6070 3.5994 3.5962 3.5983 3.5927 3.6070 3.6070 3.6018 3.5992 3.5952 3.5923 3.5985 3.5965 3.6070 3.6070 3.6015 3.6014 3.5876 3.5975 3.6070 3.6006
New Fuel Shipment or Date Stored Cask No.
or Received e
FUEL HANDLING UNITS 1 & 2 MONTHNEAR: DECEMBER, 1997 Number of Assemblies Assembly ANSI per Shipment Number Number 483 LMOERS 488 LMOESH 5P6 LM09PD 580 LMOESF 6PO LM05YK 6P1 LM05Y2 tlurry Monthly Operating Report No. 97-12 Page 16 of 17 New or Spent Initial Fuel Shipping Enrichment Cask Activity 3.5815 N/A 3.5986 3.6070 3.5924 3.6070 3.6070
~urry Monthly Operating Report No. 97-12 Page 17 of 17 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: DECEMBER, 1997 None During the Reporting Period