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| number = ML18153D151
| number = ML18153D151
| issue date = 09/30/1992
| issue date = 09/30/1992
| title = Monthly Operating Repts for Sept 1992 for Sps Units 1 & 2.W/ 921012 Ltr
| title = Monthly Operating Repts for Sept 1992 for SPS Units 1 & 2.W/ 921012 Ltr
| author name = BOWLING M L, MASON D, NEGRON M A
| author name = Bowling M, Mason D, Negron M
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGiNIA 23261 October 12, 1992 U. S. Nuclear Regulatory Commission Attention:
{{#Wiki_filter:e                                 e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGiNIA 23261 October 12, 1992 U. S. Nuclear Regulatory Commission                       Serial No.      92-665 Attention: Document Control Desk                         NO/RPC:vlh Washington, D. C. 20555                                   Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:
Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of September 1992.
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No. NO/RPC:vlh Docket Nos. License Nos. 92-665 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of September 1992. Very truly yours, M. L. Bowling, Manager Nuclear Licensing  
Very truly yours, M. L. Bowling, Manager Nuclear Licensing & Programs Enclosure cc:   U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
& Programs Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station (9210150260 920930 , . \
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station (9210150260 920930                 , .\
* 1 1,, PDR
1 1,, PDR
* ADOCK 05000280 R . . PDR VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 92-09 Approved:
* ADOCK 05000280 R .       .       PDR
TABLE OF CONTENTS Section tlurry Monthly Operating Report No. 92-09 Page 2 of 17 Page Operating Data Report -Unit No. 1 .........................................................................................................
 
3 ' Operating Data Report -Unit No. 2 .........................................................................................................
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 92-09 Approved:
4 Unit Shutdowns and Power Reductions  
 
-Unit No. 1 ....................................................................................
tlurry     Monthly Operating Report No. 92-09 Page 2 of 17 TABLE OF CONTENTS Section                                                                                                                                  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 No. 1 ......................................................................................... 9 Summary of Operating Experience - Unit No. 2 ....................................................................................... 1O Facility Changes That Did Not Require NRC Approval. .............................................................................. 11 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 13 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 14 Chemistry Report ............................................................................................................................. 15 Fuel Handling - Unit No. 1 ................................................................................................................... 16 Fuel Handling - Unit No. 2 ................................................................................................................... 16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 17
5 Unit Shutdowns and Power Reductions  
 
-Unit No. 2 ....................................................................................
*'                                   e                                                     tlurry   Monthly Operating Report No. 92-09 Page 3 of 17 OPERATING DATA REPORT Docket No.:   50-280 Date:    10-07-92 Completed By:    D. Mason Telephone:     (804) 365-2459
6 Average Daily Unit Power Level -Unit No. 1 ..............................................................................................
: 1. Unit Name: .................................................. . Surry Unit 1
7 Average Daily Unit Power Level -Unit No. 2 ..............................................................................................
: 2. Reporting Period: ........................................ .. September 1992
8 Summary of Operating Experience  
: 3. Licensed Thermal Power (MWt): ...................... .             2441
-Unit No. 1 .........................................................................................
: 4. Nameplate Rating (Gross MWe): ..................... ..               847.5
9 Summary of Operating Experience  
: 5. Design Electrical Rating (Net MWe): ................ ..             788
-Unit No. 2 .......................................................................................
: 6. Maximum Dependable Capacity (Gross MWe): .. ..                       820
1 O Facility Changes That Did Not Require NRC Approval.  
: 7. Maximum Dependable Capacity (Net MWe): ...... ..                     781
..............................................................................
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
11 Procedure or Method of Operation Changes That Did Not Require NRC Approval ...........................................
: 9. Power Level To Which Restricted, If Any (Net MWe):
13 Tests and Experiments That Did Not Require NRC Approval ......................................................................
: 10. Reasons For Restrictions, If Any:
14 Chemistry Report .............................................................................................................................
This Month              YTD                Cumulative 11 . Hours In Reporting Period ........................ ..               720.0              6575.0              173351.0
15 Fuel Handling -Unit No. 1 ...................................................................................................................
: 12. Number of Hours Reactor Was Critical ........ ..                     720.0              4931.8              113166.0
16 Fuel Handling -Unit No. 2 ...................................................................................................................
: 13. Reactor Reserve Shutdown Hours .............. .                       0.0                  0.0              3774.5
16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications  
: 14. Hours Generator On-Line .......................... .                 669.6              4826.2              111066.4
...................................................................................................
: 15. Unit Reserve Shutdown Hours.................... .                     0.0                  0.0              3736.2
17 
: 16. Gross Thermal Energy Generated (MWH) ..... .                   1610768.0          11136225.0            258252901.7
*' e tlurry Monthly Operating Report No. 92-09 Page 3 of 17 OPERATING DATA REPORT Docket No.: Date: Completed By: 50-280 10-07-92 D. Mason Telephone:  
: 17. Gross Electrical Energy Generated (MWH) ... .                   530430.0          3693985.0            84209173.0
(804) 365-2459 1 . Unit Name: .................................................. . 2. Reporting Period: ........................................  
: 18. Net Electrical Energy Generated (MWH) ...... ..                 503350.0          3503091.0            79877157.0
.. 3. Licensed Thermal Power (MWt): ...................... . 4. Nameplate Rating (Gross MWe): .....................  
: 19. Unit Service Factor .................................. .             93.0%              73.4%                64.1%
.. 5. Design Electrical Rating (Net MWe): ................  
: 20. Unit Availability Factor............................. ..             93.0%              73.4%                66.2%
.. 6. Maximum Dependable Capacity (Gross MWe): .. .. 7. Maximum Dependable Capacity (Net MWe): ...... .. Surry Unit 1 September 1992 2441 847.5 788 820 781 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: 11 . Hours In Reporting Period ........................  
: 21. Unit Capacity Factor (Using MDC Net) .......... .                     89.5%              68.2%                59.4%
.. 12. Number of Hours Reactor Was Critical ........ .. 13. Reactor Reserve Shutdown Hours .............. . 14. Hours Generator On-Line .......................... . 15. Unit Reserve Shutdown Hours .................... . 16. Gross Thermal Energy Generated (MWH) ..... . 17. Gross Electrical Energy Generated (MWH) ... . 18. Net Electrical Energy Generated (MWH) ...... .. 19. Unit Service Factor .................................. . 20. Unit Availability Factor .............................  
: 22. Unit Capacity Factor (Using DER Net) ......... ..                     88.7%              67.6%                58.5%
.. 21. Unit Capacity Factor (Using MDC Net) .......... . 22. Unit Capacity Factor (Using DER Net) .........  
: 23. Unit Forced Outage Rate .......................... ..                 7.0%                4.5%                18.7%
.. 23. Unit Forced Outage Rate ..........................  
: 24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each):
.. This Month 720.0 720.0 0.0 669.6 0.0 1610768.0 530430.0 503350.0 93.0% 93.0% 89.5% 88.7% 7.0% YTD 6575.0 4931.8 0.0 4826.2 0.0 11136225.0 3693985.0 3503091.0 73.4% 73.4% 68.2% 67.6% 4.5% 24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each): 25. If Shut Down at End of Report Period Estimated Date of Start-up:  
: 25. If Shut Down at End of Report Period Estimated Date of Start-up:
: 26. Unit In Test Status (Prior to Commercial Operation):
: 26. Unit In Test Status (Prior to Commercial Operation):
Cumulative 173351.0 113166.0 3774.5 111066.4 3736.2 258252901.7 84209173.0 79877157.0 64.1% 66.2% 59.4% 58.5% 18.7% FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION e OPERATING DATA REPORT -urry Monthly Operating Report No. 92-09 Page 4of 17 Docket No.: 50-281 10-07-92 D. Mason Date: Completed By: Telephone:  
FORECAST             ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
(804) 365-2459 1. Unit Name: .................................................. . 2. Reporting Period: ........................................  
 
.. 3. Licensed Thermal Power (MWt): ...................... . 4. Nameplate Rating (Gross MWe): .....................  
e                                                     -urry Monthly Operating Report No. 92-09 Page 4of 17 OPERATING DATA REPORT Docket No.:   50-281 Date:    10-07-92 Completed By:    D. Mason Telephone:     (804) 365-2459
.. 5. Design Electrical Rating (Net MWe): ................  
: 1. Unit Name: .................................................. . Surry Unit 2
.. 6. Maximum Dependable Capacity (Gross MWe): ... . 7. Maximum Dependable Capacity (Net MWe): ...... .. Surry Unit 2 September 1992 2441 847.5 788 820 781 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 YID Cumulative  
: 2. Reporting Period: ........................................ .. September 1992
: 11. Hours In Reporting Period ..........................
: 3. Licensed Thermal Power (MWt): ...................... .             2441
720.0 6575.0 170231.0 12. Number of Hours Reactor Was Critical ..........
: 4. Nameplate Rating (Gross MWe): ..................... ..               847.5
720.0 6269.8 111477.9 13. Reactor Reserve Shutdown Hours ...............
: 5. Design Electrical Rating (Net MWe): ................ ..             788
0.0 0.0 328.1 14. Hours Generator On-Line ...........................
: 6. Maximum Dependable Capacity (Gross MWe): ... .                       820
720.0 6261.1 109722.0 15. Unit Reserve Shutdown Hours .....................
: 7. Maximum Dependable Capacity (Net MWe): ...... ..                     781
0.0 0.0 0.0 16. Gross Thermal Energy Generated (MWH) ...... 1751444.8 15073521.2 255952203.3  
: 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
: 17. Gross Electrical Energy Generated (MWH) .... 569310.0 4971195.0 83405044.0  
: 9. Power Level To Which Restricted, If Any (Net MWe):
: 18. Net Electrical Energy Generated (MWH) ........ 540142.0 4723603.0 79087541.0  
: 10. Reasons For Restrictions, If Any:
: 19. Unit Service Factor ...................................
This Month             YID               Cumulative
100.0% 95.2% 64.5% 20. Unit Availability Factor ...............................
: 11. Hours In Reporting Period ..........................                 720.0             6575.0             170231.0
100.0% 95.2% 64.5% 21. Unit Capacity Factor (Using MDC Net) ...........
: 12. Number of Hours Reactor Was Critical ..........                     720.0             6269.8             111477.9
96.1% 92.0% 59.6% 22. Unit Capacity Factor (Using DER Net) ...........
: 13. Reactor Reserve Shutdown Hours ...............                         0.0                 0.0               328.1
95.2% 91.2% 59.0% 23. Unit Forced Outage Rate ............................
: 14. Hours Generator On-Line ...........................                 720.0             6261.1             109722.0
0.0% 0.0% 14.6% 24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each): Refueling, March 6, 1993 --74 days. 25. If Shut Down at End of Report Period Estimated Date of Start-up:  
: 15. Unit Reserve Shutdown Hours.....................                       0.0                 0.0                   0.0
: 16. Gross Thermal Energy Generated (MWH) ......                     1751444.8         15073521.2           255952203.3
: 17. Gross Electrical Energy Generated (MWH) ....                     569310.0           4971195.0             83405044.0
: 18. Net Electrical Energy Generated (MWH) ........                   540142.0           4723603.0             79087541.0
: 19. Unit Service Factor ...................................             100.0%               95.2%                 64.5%
: 20. Unit Availability Factor...............................             100.0%               95.2%                 64.5%
: 21. Unit Capacity Factor (Using MDC Net) ...........                     96.1%               92.0%                 59.6%
: 22. Unit Capacity Factor (Using DER Net) ...........                     95.2%               91.2%                 59.0%
: 23. Unit Forced Outage Rate ............................                   0.0%                 0.0%               14.6%
: 24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each):
Refueling, March 6, 1993 -- 74 days.
: 25. If Shut Down at End of Report Period Estimated Date of Start-up:
: 26. Unit In Test Status (Prior to Commercial Operation):
: 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION (1) Date Type 920905 F 920908 s (1) F: Forced S: Scheduled (4) .urry Monthly Operating Report No. 92-09 Page 5of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) REPORT MONTH: September 1992 (2) (3) (4) (5) Method Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-07-92 Completed by: Anthony Xenakis Telephone:  
FORECAST             ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
(804) 365-2145 Duration of LER System Component Cause & Corrective Action to Hours 50.4 0 Reason Shutting No. Code Code Prevent Recurrence B B (2) REASON: Down Rx 4 NIA 4 NIA A -Equipment Failure (Explain)
 
B Maintenance or Test C Refueling D Regulatory Restriction EA XFMR SG COND E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)
                                                                                .urry Monthly Operating Report No. 92-09 Page 5of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
Ramped Unit off line to effect repairs to "C" Station Service Transformer.
REPORT MONTH: September 1992 Docket No.:   50-280 Unit Name:   Surry Unit 1 Date:   10-07-92 Completed by:     Anthony Xenakis Telephone:     (804) 365-2145 (1)                  (2)        (3)                (4)      (5)
The reactor remained critical at 2% power. Reduced Unit power to 75% to maintain condenser vacuum while cleaning water boxes. (3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain)  
Method Duration               of       LER     System Component Cause & Corrective Action to Date    Type      Hours     Reason   Shutting     No. Code     Code     Prevent Recurrence Down Rx 920905      F      50.4         B          4       NIA       EA     XFMR     Ramped Unit off line to effect repairs to "C" Station Service Transformer. The reactor remained critical at 2% power.
(5) Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) Exhibit 1 -Sarne Source. 
920908      s        0          B          4        NIA      SG    COND      Reduced Unit power to 75% to maintain condenser vacuum while cleaning water boxes.
.urry Monthly Operating Report No. 92-09 Page 6of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) REPORT MONTH: September 1992 (1) (2) (3) (4) (5) Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-07-92 Completed by: Anthony Xenakis Telephone:  
(1)                          (2)                                                (3)
(804) 365-2145 Duration Method of Reason Shutting Down Rx LER No. System Component Cause & Corrective Action to Date Type Hours Code Code Prevent Recurrence (1) F: Forced S: Scheduled (4) (2) REASON: No entries for this reporting period. A -Equipment Failure (Explain)
F:  Forced                  REASON:                                            METHOD:
B Maintenance or Test C Refueling D Regulatory Restriction E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)
S:  Scheduled              A - Equipment Failure (Explain)                    1 - Manual B    Maintenance or Test                          2 - Manual Scram.
Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) (3) METHOD: 1 -Manual 2 -Manual Scram; 3 -Automatic Scram. 4 -Other (Explain)  
C    Refueling                                    3 - Automatic Scram.
(5) Exhibit 1 -Same Source.
D    Regulatory Restriction                      4 - Other (Explain)
tllurry Monthly Operating Report No. 92-09 Page 7of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-07-92 Completed by: M.A. Negron Telephone:  
E    Operator Training & Licensing Examination F    Administrative G    Operational Error (Explain)
(804) 365-2795 Month: September 1992 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 707 17 763 2 735 18 764 3 760 19 764 4 756 20 765 5 374 21 765 6 0 22 762 7 129 23 766 8 706 24 772 9 693 25 775 10 757 26 775 11 760 27 774 12 758 28 773 13 767 29 774 14 767 30 778 15 768 31 16 766 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.
(4)                                                                              (5)
e tlurry Monthly Operating Report No. 92-09 Page Sot 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-07-92 Completed by: M.A. Negron Telephone:  
Exhibit G - Instructions for Preparation of Data Entry Sheets                   Exhibit 1 - Sarne Source.
(804) 365-2795 Month: September 1992 Average Daily Power Level Average Daily Power Level Day (MWe-Net) Day (MWe-Net) 746 17 748 2 740 18 741 3. 738 19 721 4 747 20 756 5 744 21 759 6 744 22 755 7 752 23 755 8 746 24 766 9 744 25 767 10 739 26 766 11 742 27 759 12 732 28 764 13 757 29 761 14 755 30 760 15 751 31 16 754 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.
for Licensee Event Report (LER) File (NUREG 0161)
e eurry Monthly Operating Report No. 92-09 Page 9 of 17  
 
                                                                                      .urry Monthly Operating Report No. 92-09 Page 6of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH:     September 1992 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-07-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (1)                (2)        (3)                  (4)        (5)
Method Duration                 of       LER     System   Component Cause & Corrective Action to Date     Type     Hours     Reason    Shutting      No.      Code         Code     Prevent Recurrence Down Rx No entries for this reporting period.
(1)                           (2)                                                      (3)
F:   Forced                 REASON:                                                METHOD:
S:   Scheduled               A - Equipment Failure (Explain)                         1 - Manual B     Maintenance or Test                               2 - Manual Scram; C     Refueling                                         3 - Automatic Scram.
D     Regulatory Restriction                           4 - Other (Explain)
E     Operator Training & Licensing Examination F     Administrative G     Operational Error (Explain)
(4)                                                                                    (5)
Exhibit G - Instructions for Preparation of Data Entry Sheets                       Exhibit 1 - Same Source.
for Licensee Event Report (LER) File (NUREG 0161)
 
tllurry   Monthly Operating Report No. 92-09 Page 7of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.:   50-280 Unit Name:   Surry Unit 1 Date: 10-07-92 Completed by:   M.A. Negron Telephone:   (804) 365-2795 Month:     September 1992 Average Daily Power Level                         Average Daily Power Level Day                     (MWe- Net)                   Day                   (MWe- Net) 707                       17                       763 2                         735                       18                       764 3                         760                       19                       764 4                         756                     20                         765 5                         374                     21                         765 6                           0                     22                         762 7                         129                     23                         766 8                         706                     24                         772 9                         693                     25                         775 10                         757                     26                         775 11                       760                     27                         774 12                       758                     28                         773 13                       767                     29                         774 14                       767                     30                         778 15                       768                     31 16                       766 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                                                   tlurry   Monthly Operating Report No. 92-09 Page Sot 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.:   50-281 Unit Name:   Surry Unit 2 Date: 10-07-92 Completed by:   M.A. Negron Telephone:   (804) 365-2795 Month:     September 1992 Average Daily Power Level                         Average Daily Power Level Day                   (MWe- Net)                   Day                   (MWe- Net) 746                       17                       748 2                         740                       18                       741
: 3.                       738                       19                       721 4                         747                       20                       756 5                         744                       21                       759 6                         744                       22                       755 7                         752                     23                         755 8                         746                       24                       766 9                         744                     25                         767 10                       739                       26                       766 11                       742                       27                       759 12                       732                       28                       764 13                         757                     29                         761 14                         755                     30                         760 15                         751                     31 16                         754 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                                                 eurry     Monthly Operating Report No. 92-09 Page 9 of 17


==SUMMARY==
==SUMMARY==
OF OPERATING EXPERIENCE MONTH/YEAR:
OF OPERATING EXPERIENCE MONTH/YEAR: September 1992 Listed below in 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.
September 1992 Listed below in 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 09-01-92       0000       This reporting period started with the Unit operating at 88% power, 670 MWe. Power reduction was under way to maintain condenser vacuum while cleaning water boxes.
UNIT ONE 09-01-92 09-02-92 09-05-92 09-07-92 09-08-92 09-09-92 09-12-92 09-13-92 09-30-92 0000 This reporting period started with the Unit operating at 88% power, 670 MWe. Power reduction was under way to maintain condenser vacuum while cleaning water boxes. 0022 Stopped power reduction; 83% power, 635 MWe. 051 O Started ramp up; 83% power, 635 MWe. 0630 Stopped ramp; 100% power, 800 MWe. 2059 Started power reduction to maintain condenser vacuum while cleaning water boxes; 100% power, 795 MWe. 2204 Stopped power reduction; 85% power, 660 MWe. 0528 Started ramp up; 88% power, 690 MWe. 0617 Stopped ramp; 100% power, 800 MWe. 0912 Started ramp down to bring the Unit off line in order to effect repairs on "C" Station Service Transformer; 100% power, 800 MWe. 1436 Unit off line. 1630 Commence ramp to 100% power following transformer repair; 5% power. 1659 Unit on line and ramping to 100% power. 0000 Unit at 100% power, 790 MWe. 1821 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100% power, 785 MWe. 2008 Stopped ramp; 75% power, 540 MWe. 0515 Started ramp up; 75% power, 595 MWe. 0700 Stopped ramp; 100% power, 795 MWe. 2235 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100% power, 770 MWe. 2255 Stopped ramp; 94.4% power, 770 MWe. 0005 Started ramp up; 94% power, 760 MWe. 0024 Stopped ramp; 100% power, 815 MWe. 2400 This reporting period ended with the Unit operating at 100% power, 815 MWe.
0022       Stopped power reduction; 83% power, 635 MWe.
UNIT TWO 09-01-92 09-02-92 09-03-92 09-12-92 09-18-92 09-19-92 09-30-92 e [continued]
051 O     Started ramp up; 83% power, 635 MWe.
9urry Monthly Operating Report No. 92-09 Page 10 of 17 0000 2114 This reporting period started with the Unit operating at 100% power, 795 MWe. Started ramp down to maintain condenser vacuum while cleaning water boxes; 100% power, 770 MWe. 2116 Stopped ramp; 95% power, 71 O MWe. 0355 Started ramp up; 93% power, 750 MWe. 0432 Stopped ramp; 100% power, 800 MWe. 0945 Started power reduction to maintain condenser vacuum while cleaning water boxes; 100% power, 770 MWe. 1518 Stopped power reduction; 94.5% power, 725 MWe. 1832 Started ramp up; 95% power, 720 MWe. 1900 Stopped ramp; 100% power, 805 MWe. 2133 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100% power 780 MWe. 2143 Stopped ramp; 96.5% power, 740 MWe. 0107 Started ramp up; 96.5% power, 740 MWe. 0121 Stopped ramp; 100% power, 790 MWe. 0847 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100% power, 790 MWe. 0955 Stopped ramp; 94% power, 750 MWe. 2030 Started ramp up; 94% power, 730 MWe. 2121 Stopped ramp; 100% power, 800 MWe. 2400 This report period ended with the Unit operating at 100% power, 780 MWe, and "D" water box out of service for cleaning.
0630       Stopped ramp; 100% power, 800 MWe.
e &rry Monthly Operating Report No. 92-09 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
2059       Started power reduction to maintain condenser vacuum while cleaning water boxes; 100%
September 1992 QLCR S91-217 QLCR R92-054 AC S 1 0906 Q-Llst Change Request (Safety Evaluation No. 92-166A) 07-23-92 This Q-List Change Request changes the classification of Unit 1 circulating water system screen wash components from "Safety-Related" (SR) to "Nonsafety-Related" (NSR). An evaluation of this change determined that the subject components do not perform a safe shutdown function and are not required for accident mitigation.
power, 795 MWe.
Furthermore, these components are not described in the UFSAR as being SR. Therefore, an unreviewed safety question is not created. Q-Llst Change Request (Safety Evaluation No. 92-193) 09-03-92 This Q-List Change Request changes the classification of the gaseous waste disposal system from "Safety-Related" (SR) to "Nonsafety-Related with Special Quality/Regulatory Requirements" (NSQ). An evaluation of this change determined that the subject system does not perform a safe shutdown function and is not required for accident mitigation.
2204       Stopped power reduction; 85% power, 660 MWe.
Therefore, an unreviewed safety question is not created. Administrative Control (Safety Evaluation No. 92-194) 09-06-92 Administrative control of Unit 1 steam generator power operated relief valves (PORV) was established to facilitate the control of reactor coolant system temperature.
09-02-92        0528       Started ramp up; 88% power, 690 MWe.
This action was necessary for a short period of time during which reactor power was less than 5 % and the generator was disconnected from the grid to enable transformer repairs. The PORVs were required to be promptly placed in the automatic control mode in the event of a main steam line break or if containment isolation was required.
0617       Stopped ramp; 100% power, 800 MWe.
09-05-92        0912       Started ramp down to bring the Unit off line in order to effect repairs on "C" Station Service Transformer; 100% power, 800 MWe.
1436       Unit off line.
09-07-92        1630       Commence ramp to 100% power following transformer repair; 5% power.
1659       Unit on line and ramping to 100% power.
09-08-92        0000       Unit at 100% power, 790 MWe.
1821       Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%
power, 785 MWe.
2008       Stopped ramp; 75% power, 540 MWe.
09-09-92        0515       Started ramp up; 75% power, 595 MWe.
0700       Stopped ramp; 100% power, 795 MWe.
09-12-92        2235       Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%
power, 770 MWe.
2255       Stopped ramp; 94.4% power, 770 MWe.
09-13-92        0005       Started ramp up; 94% power, 760 MWe.
0024       Stopped ramp; 100% power, 815 MWe.
09-30-92        2400       This reporting period ended with the Unit operating at 100% power, 815 MWe.
 
e                                                   9urry Monthly Operating Report No. 92-09 Page 10 of 17
[continued]
UNIT TWO 09-01-92 0000 This reporting period started with the Unit operating at 100% power, 795 MWe.
09-02-92 2114 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%
power, 770 MWe.
2116 Stopped ramp; 95% power, 71 O MWe.
09-03-92 0355 Started ramp up; 93% power, 750 MWe.
0432 Stopped ramp; 100% power, 800 MWe.
09-12-92 0945 Started power reduction to maintain condenser vacuum while cleaning water boxes; 100%
power, 770 MWe.
1518 Stopped power reduction; 94.5% power, 725 MWe.
1832 Started ramp up; 95% power, 720 MWe.
1900 Stopped ramp; 100% power, 805 MWe.
09-18-92 2133 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%
power 780 MWe.
2143 Stopped ramp; 96.5% power, 740 MWe.
09-19-92 0107 Started ramp up; 96.5% power, 740 MWe.
0121 Stopped ramp; 100% power, 790 MWe.
0847 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%
power, 790 MWe.
0955 Stopped ramp; 94% power, 750 MWe.
2030 Started ramp up; 94% power, 730 MWe.
2121 Stopped ramp; 100% power, 800 MWe.
09-30-92 2400 This report period ended with the Unit operating at 100% power, 780 MWe, and "D" water box out of service for cleaning.
 
e                                           &rry Monthly Operating Report No. 92-09 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1992 QLCR S91-217       Q-Llst Change Request                                             07-23-92 (Safety Evaluation No. 92-166A)
This Q-List Change Request changes the classification of Unit 1 circulating water system screen wash components from "Safety-Related" (SR) to "Nonsafety-Related" (NSR).
An evaluation of this change determined that the subject components do not perform a safe shutdown function and are not required for accident mitigation.
Furthermore, these components are not described in the UFSAR as being SR.
Therefore, an unreviewed safety question is not created.
QLCR R92-054        Q-Llst Change Request                                             09-03-92 (Safety Evaluation No. 92-193)
This Q-List Change Request changes the classification of the gaseous waste disposal system from "Safety-Related" (SR) to "Nonsafety-Related with Special Quality/Regulatory Requirements" (NSQ).
An evaluation of this change determined that the subject system does not perform a safe shutdown function and is not required for accident mitigation.
Therefore, an unreviewed safety question is not created.
AC S 1-92-0906    Administrative Control                                             09-06-92 (Safety Evaluation No. 92-194)
Administrative control of Unit 1 steam generator power operated relief valves (PORV) was established to facilitate the control of reactor coolant system temperature. This action was necessary for a short period of time during which reactor power was less than 5 % and the generator was disconnected from the grid to enable transformer repairs.
The PORVs were required to be promptly placed in the automatic control mode in the event of a main steam line break or if containment isolation was required.
This operating condition was evaluated by Engineering and determined to be acceptable since the probability of occurrence of a main steam line break is very small (4.56 E-8 in 4 hours) and the additional steam flow (with reactor power less than 5 %) has a negligible effect on the accident analysis.
This operating condition was evaluated by Engineering and determined to be acceptable since the probability of occurrence of a main steam line break is very small (4.56 E-8 in 4 hours) and the additional steam flow (with reactor power less than 5 %) has a negligible effect on the accident analysis.
Therefore, an unreviewed safety question was not created. 
-urry Monthly Operating Report No. 92-09 Page 12of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL DR S-92-0846 TM S2-92-24 AC S2-92-0807 MONTH/YEAR:
September 1992 [continued]
Deviation Report (Safety Evaluation No. 92-195) 09-08-92 This Safety Evaluation was performed to evaluate Deviation Report S-92-0846 concerning Unit 1 operation with a body-to-bonnet leak on pressurizer vapor space sample trip valve 1-SS-TV-1018 and seat leakage on redundant valve 1-SS-TV-101 A. Isolation valve 1-RC-133 is being maintained closed in order to isolate the penetration.
Closure of this valve also isolates the discharge flow path of the pressurizer vent system. The evaluation determined that this operating condition is acceptable since the affected trip valves are in their fail-safe position (closed), ensuring containment integrity.
The pressurizer vent system vent valves are not identified as accident mitigation equipment or required to be operable by Technical Specifications.
Therefore, an unreviewed safety question is not created. Temporary Modification (Safety Evaluation No. 92-197) 09-18-92 This Temporary Modification (TM) installed an electrical jumper to permit the replacement of Unit 2 reactor protection system (RPS) relay, 28/AFP. This TM was used to maintain the auxiliary feedwater (AFW) train "B" start circuit continuity during this activity.
Double verification of the jumper installation/removal and post maintenance testing were performed.
The motor-driven AFW pumps remained operable and the turbine-driven AFW pump was secured during this activity.
The AFW train "A" logic was not affected.
Therefore, an unreviewed safety question was not created. Administrative Control (Safety Evaluation No. 92-1738) 09-24-92 Administrative control of Unit 2 main feedwater regulating valves was established (one at a time) in order to close the valves in the event of a reactor trip or safety injection signal. Administrative control of these valves was required while they were jacked open (preventing performance of their automatic safety function) to facilitate troubleshooting and repair of valve controllers and operators.
This activity did not affect the operation of other systems or components.
The subject valves were controlled by a licensed operator who was capable of closing the valve (from the control room) within 30 seconds following a feedwater isolation signal. This capability ensured that the activity was bounded by the main steam line break accident analysis.
Therefore, an unreviewed safety question was not created.
Therefore, an unreviewed safety question was not created.
O-TOP-4019 O-TOP-4020 TSl-010 tlurry Monthly Operating Report No. 92-09 Page 13 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
 
September 1992 Temporary Operating Procedures (Safety Evaluation No. 92-192) 09-03-92 Temporary Operating Procedures (TOP) O-TOP-4019, "Blend System Resin Transfer Using [Transfer Pump 1-LW-P-13)", and O-TOP-4020, "Blend System Resin Transfer Using [Transfer Pump 1-LW-P-12]" were developed to provide instructions for spent resin transfer within the catch and blend tank system and from the spent resin blend tank to a high integrity container.
                                                                      -urry Monthly Operating Report No. 92-09 Page 12of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1992
The operations addressed by these TOPs are controlled by Operating Procedure O-OP-22.9.21, "Spent Resin Catch Tank And Blend Tank Transfer System Operation".
[continued]
The TOPs were issued to sequence the operations and to incorporate requirements for infrequently conducted or complex tests or evolutions.
DR S-92-0846      Deviation Report                                                    09-08-92 (Safety Evaluation No. 92-195)
The spent resin piping will be operated well below its design pressure rating and is located in an area with no safety-related equipment.
This Safety Evaluation was performed to evaluate Deviation Report S-92-0846 concerning Unit 1 operation with a body-to-bonnet leak on pressurizer vapor space sample trip valve 1-SS-TV-1018 and seat leakage on redundant valve 1-SS-TV-101 A. Isolation valve 1-RC-133 is being maintained closed in order to isolate the penetration. Closure of this valve also isolates the discharge flow path of the pressurizer vent system.
Therefore, an unreviewed safety question is not created. Technical Specification Interpretation (Safety Evaluation No. 92-196) 09-15-92 Technical Specification Interpretation TSl-01 O was developed to clarify the operability requirements, specified in Technical Specification (TS) 3.23.C.2, for the main control room and emergency switch gear room air handling units (AHU) while Unit 1 /Unit 2 are at cold shutdown or refueling shutdown.
The evaluation determined that this operating condition is acceptable since the affected trip valves are in their fail-safe position (closed), ensuring containment integrity. The pressurizer vent system vent valves are not identified as accident mitigation equipment or required to be operable by Technical Specifications. Therefore, an unreviewed safety question is not created.
TM S2-92-24      Temporary Modification                                                09-18-92 (Safety Evaluation No. 92-197)
This Temporary Modification (TM) installed an electrical jumper to permit the replacement of Unit 2 reactor protection system (RPS) relay, 28/AFP.
This TM was used to maintain the auxiliary feedwater (AFW) train "B" start circuit continuity during this activity. Double verification of the jumper installation/removal and post maintenance testing were performed. The motor-driven AFW pumps remained operable and the turbine-driven AFW pump was secured during this activity. The AFW train "A" logic was not affected.
Therefore, an unreviewed safety question was not created.
AC S2-92-0807      Administrative Control                                              09-24-92 (Safety Evaluation No. 92-1738)
Administrative control of Unit 2 main feedwater regulating valves was established (one at a time) in order to close the valves in the event of a reactor trip or safety injection signal. Administrative control of these valves was required while they were jacked open (preventing performance of their automatic safety function) to facilitate troubleshooting and repair of valve controllers and operators.
This activity did not affect the operation of other systems or components. The subject valves were controlled by a licensed operator who was capable of closing the valve (from the control room) within 30 seconds following a feedwater isolation signal. This capability ensured that the activity was bounded by the main steam line break accident analysis. Therefore, an unreviewed safety question was not created.
 
tlurry Monthly Operating Report No. 92-09 Page 13 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1992 O-TOP-4019    Temporary Operating Procedures                                     09-03-92 O-TOP-4020    (Safety Evaluation No. 92-192)
Temporary Operating Procedures (TOP) O-TOP-4019, "Blend System Resin Transfer Using [Transfer Pump 1-LW-P-13)", and O-TOP-4020, "Blend System Resin Transfer Using [Transfer Pump 1-LW-P-12]" were developed to provide instructions for spent resin transfer within the catch and blend tank system and from the spent resin blend tank to a high integrity container.
The operations addressed by these TOPs are controlled by Operating Procedure O-OP-22.9.21, "Spent Resin Catch Tank And Blend Tank Transfer System Operation". The TOPs were issued to sequence the operations and to incorporate requirements for infrequently conducted or complex tests or evolutions. The spent resin piping will be operated well below its design pressure rating and is located in an area with no safety-related equipment.
Therefore, an unreviewed safety question is not created.
TSl-010      Technical Specification Interpretation                             09-15-92 (Safety Evaluation No. 92-196)
Technical Specification Interpretation TSl-01 O was developed to clarify the operability requirements, specified in Technical Specification (TS) 3.23.C.2, for the main control room and emergency switch gear room air handling units (AHU) while Unit 1/Unit 2 are at cold shutdown or refueling shutdown.
An evaluation of the requirements specified in TSl-010 (i.e., limiting conditions for operation) determined that the subject AHUs will continue to be operated in accordance with TS requirements and applicable operating procedures.
An evaluation of the requirements specified in TSl-010 (i.e., limiting conditions for operation) determined that the subject AHUs will continue to be operated in accordance with TS requirements and applicable operating procedures.
Therefore, an unreviewed safety question is not created.
Therefore, an unreviewed safety question is not created.
e -urry Monthly Operating Report No. 92-09 Page 14of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
 
September 1992 None during this reporting period.
e                                     -urry Monthly Operating Report No. 92-09 Page 14of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1992 None during this reporting period.
CHEMISTRY REPORT MONTH/YEAR:
 
September 1992 Unit No. 1 Primarv Coolant Analvsis Max. Min. Avg. Gross Radioact., uCi/ml 3.87E-1 1.88E-2 2.69E-1 Suspended Solids, com < 0.1 < 0.1 < 0.1 Gross Tritium, uCi/ml 3.88E-1 2.55E-1 2.99E-1 1131, uCi/ml 8.19E-4 1.69E-4 5.53E-4 1131/1133 0.11 0.06 0.09 Hvdroaen, cc/ka 44.5 26.5 31.8 Lithium, oom 2.41 1.98 2.21 Boron -10, oom* 284.0 198.5 213.2 Oxvaen, (DO), oom < 0.005 < 0.005 < 0.005 Chloride, com 0.008 0.003 0.006 pH at 25 decree Celsius 6.63 5.96 6.54
9urry Monthly Operating Report No. 92-09 Page 15of 17 CHEMISTRY REPORT MONTH/YEAR: September 1992 Unit No. 1                   Unit No. 2 Primarv Coolant Analvsis         Max.      Min.      Avg. Max.     Min.         Avg.
* Boron -1 O = Total Boron x 0.196 Comments:
Gross Radioact., uCi/ml               3.87E-1   1.88E-2   2.69E-1  2.35E-1  1.14E-1      1.70E-1 Suspended Solids, com                 < 0.1     < 0.1     < 0.1    < 0.1    < 0.1        < 0.1 Gross Tritium, uCi/ml                 3.88E-1   2.55E-1   2.99E-1  2.94E-1  2.42E-1    2.63E-1 1131, uCi/ml                         8.19E-4   1.69E-4   5.53E-4  4.50E-4  1.80E-4    3.24E-4 1131/1133                               0.11     0.06     0.09    0.13      0.06        0.09 Hvdroaen, cc/ka                         44.5     26.5     31.8     43.6      26.1        34.3 Lithium, oom                           2.41     1.98     2.21     2.34      2.10        2.20 Boron - 10, oom*                       284.0     198.5     213.2     96.4      78.6        87.3 Oxvaen, (DO), oom                     < 0.005  < 0.005  < 0.005 < 0.005   < 0.005      < 0.005 Chloride, com                         0.008     0.003     0.006   0.003    < 0.001      0.002 pH at 25 decree Celsius                 6.63     5.96     6.54     7.15      6.90        7.05
None. 9urry Monthly Operating Report No. 92-09 Page 15of 17 Unit No. 2 Max. Min. Avg. 2.35E-1 1.14E-1 1.70E-1 < 0.1 < 0.1 < 0.1 2.94E-1 2.42E-1 2.63E-1 4.50E-4 1.80E-4 3.24E-4 0.13 0.06 0.09 43.6 26.1 34.3 2.34 2.10 2.20 96.4 78.6 87.3 < 0.005 < 0.005 < 0.005 0.003 < 0.001 0.002 7.15 6.90 7.05 New or Spent Fuel Shipment Date Stored or Number Received FUEL HANDLING UNITS 1 & 2 MONTH/YEAR:
* Boron - 1O = Total Boron x 0.196 Comments:
September 1992 Number for Assemblies per Shipment Assembly Number ANSI Number 9urry Monthly Operating Report No. 92-09 Page 16of 17 Initial Enrichment New or Spent Fuel Shipping Cask Activity No fuel received or stored during this report period.
None.
* tlurry Monthly Operating Report No. 92-09 Page 17of 17 DESCRIPTION OF PERIODIC TEST(S} WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR:
 
September 1992 None During This Reporting Period.}}
9urry   Monthly Operating Report No. 92-09 Page 16of 17 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: September 1992 New or Spent                  Number for                                                         New or Spent Fuel Shipment Date Stored or  Assemblies       Assembly            ANSI            Initial      Fuel Shipping Number      Received      per Shipment       Number           Number         Enrichment     Cask Activity No fuel received or stored during this report period.
* tlurry DESCRIPTION OF PERIODIC TEST(S} WHICH WERE NOT COMPLETED Monthly Operating Report No. 92-09 Page 17of 17 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: September 1992 None During This Reporting Period.}}

Latest revision as of 21:33, 2 February 2020

Monthly Operating Repts for Sept 1992 for SPS Units 1 & 2.W/ 921012 Ltr
ML18153D151
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/30/1992
From: Bowling M, Mason D, Negron M
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-665, NUDOCS 9210150260
Download: ML18153D151 (18)
v • d • e


Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGiNIA 23261 October 12, 1992 U. S. Nuclear Regulatory Commission Serial No.92-665 Attention: Document Control Desk NO/RPC:vlh Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of September 1992.

Very truly yours, M. L. Bowling, Manager Nuclear Licensing & Programs Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station (9210150260 920930 , .\

1 1,, PDR

  • ADOCK 05000280 R . . PDR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 92-09 Approved:

tlurry Monthly Operating Report No. 92-09 Page 2 of 17 TABLE OF CONTENTS Section 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 No. 1 ......................................................................................... 9 Summary of Operating Experience - Unit No. 2 ....................................................................................... 1O Facility Changes That Did Not Require NRC Approval. .............................................................................. 11 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 13 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 14 Chemistry Report ............................................................................................................................. 15 Fuel Handling - Unit No. 1 ................................................................................................................... 16 Fuel Handling - Unit No. 2 ................................................................................................................... 16 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 17

  • ' e tlurry Monthly Operating Report No. 92-09 Page 3 of 17 OPERATING DATA REPORT Docket No.: 50-280 Date: 10-07-92 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ........................................ .. September 1992
3. Licensed Thermal Power (MWt): ...................... . 2441
4. Nameplate Rating (Gross MWe): ..................... .. 847.5
5. Design Electrical Rating (Net MWe): ................ .. 788
6. Maximum Dependable Capacity (Gross MWe): .. .. 820
7. Maximum Dependable Capacity (Net MWe): ...... .. 781
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 YTD Cumulative 11 . Hours In Reporting Period ........................ .. 720.0 6575.0 173351.0

12. Number of Hours Reactor Was Critical ........ .. 720.0 4931.8 113166.0
13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 3774.5
14. Hours Generator On-Line .......................... . 669.6 4826.2 111066.4
15. Unit Reserve Shutdown Hours.................... . 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... . 1610768.0 11136225.0 258252901.7
17. Gross Electrical Energy Generated (MWH) ... . 530430.0 3693985.0 84209173.0
18. Net Electrical Energy Generated (MWH) ...... .. 503350.0 3503091.0 79877157.0
19. Unit Service Factor .................................. . 93.0% 73.4% 64.1%
20. Unit Availability Factor............................. .. 93.0% 73.4% 66.2%
21. Unit Capacity Factor (Using MDC Net) .......... . 89.5% 68.2% 59.4%
22. Unit Capacity Factor (Using DER Net) ......... .. 88.7% 67.6% 58.5%
23. Unit Forced Outage Rate .......................... .. 7.0% 4.5% 18.7%
24. Shutdowns Schedule 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 ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e -urry Monthly Operating Report No. 92-09 Page 4of 17 OPERATING DATA REPORT Docket No.: 50-281 Date: 10-07-92 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ........................................ .. September 1992
3. Licensed Thermal Power (MWt): ...................... . 2441
4. Nameplate Rating (Gross MWe): ..................... .. 847.5
5. Design Electrical Rating (Net MWe): ................ .. 788
6. Maximum Dependable Capacity (Gross MWe): ... . 820
7. Maximum Dependable Capacity (Net MWe): ...... .. 781
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 YID Cumulative

11. Hours In Reporting Period .......................... 720.0 6575.0 170231.0
12. Number of Hours Reactor Was Critical .......... 720.0 6269.8 111477.9
13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 328.1
14. Hours Generator On-Line ........................... 720.0 6261.1 109722.0
15. Unit Reserve Shutdown Hours..................... 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ...... 1751444.8 15073521.2 255952203.3
17. Gross Electrical Energy Generated (MWH) .... 569310.0 4971195.0 83405044.0
18. Net Electrical Energy Generated (MWH) ........ 540142.0 4723603.0 79087541.0
19. Unit Service Factor ................................... 100.0% 95.2% 64.5%
20. Unit Availability Factor............................... 100.0% 95.2% 64.5%
21. Unit Capacity Factor (Using MDC Net) ........... 96.1% 92.0% 59.6%
22. Unit Capacity Factor (Using DER Net) ........... 95.2% 91.2% 59.0%
23. Unit Forced Outage Rate ............................ 0.0% 0.0% 14.6%
24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, March 6, 1993 -- 74 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 ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

.urry Monthly Operating Report No. 92-09 Page 5of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: September 1992 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-07-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 920905 F 50.4 B 4 NIA EA XFMR Ramped Unit off line to effect repairs to "C" Station Service Transformer. The reactor remained critical at 2% power.

920908 s 0 B 4 NIA SG COND Reduced Unit power to 75% to maintain condenser vacuum while cleaning water boxes.

(1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Sarne Source.

for Licensee Event Report (LER) File (NUREG 0161)

.urry Monthly Operating Report No. 92-09 Page 6of 17 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: September 1992 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-07-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx No entries for this reporting period.

(1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram; C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

tllurry Monthly Operating Report No. 92-09 Page 7of 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-07-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: September 1992 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 707 17 763 2 735 18 764 3 760 19 764 4 756 20 765 5 374 21 765 6 0 22 762 7 129 23 766 8 706 24 772 9 693 25 775 10 757 26 775 11 760 27 774 12 758 28 773 13 767 29 774 14 767 30 778 15 768 31 16 766 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 tlurry Monthly Operating Report No. 92-09 Page Sot 17 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-07-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: September 1992 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 746 17 748 2 740 18 741

3. 738 19 721 4 747 20 756 5 744 21 759 6 744 22 755 7 752 23 755 8 746 24 766 9 744 25 767 10 739 26 766 11 742 27 759 12 732 28 764 13 757 29 761 14 755 30 760 15 751 31 16 754 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 eurry Monthly Operating Report No. 92-09 Page 9 of 17

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: September 1992 Listed below in 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 09-01-92 0000 This reporting period started with the Unit operating at 88% power, 670 MWe. Power reduction was under way to maintain condenser vacuum while cleaning water boxes.

0022 Stopped power reduction; 83% power, 635 MWe.

051 O Started ramp up; 83% power, 635 MWe.

0630 Stopped ramp; 100% power, 800 MWe.

2059 Started power reduction to maintain condenser vacuum while cleaning water boxes; 100%

power, 795 MWe.

2204 Stopped power reduction; 85% power, 660 MWe.

09-02-92 0528 Started ramp up; 88% power, 690 MWe.

0617 Stopped ramp; 100% power, 800 MWe.

09-05-92 0912 Started ramp down to bring the Unit off line in order to effect repairs on "C" Station Service Transformer; 100% power, 800 MWe.

1436 Unit off line.

09-07-92 1630 Commence ramp to 100% power following transformer repair; 5% power.

1659 Unit on line and ramping to 100% power.

09-08-92 0000 Unit at 100% power, 790 MWe.

1821 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%

power, 785 MWe.

2008 Stopped ramp; 75% power, 540 MWe.

09-09-92 0515 Started ramp up; 75% power, 595 MWe.

0700 Stopped ramp; 100% power, 795 MWe.

09-12-92 2235 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%

power, 770 MWe.

2255 Stopped ramp; 94.4% power, 770 MWe.

09-13-92 0005 Started ramp up; 94% power, 760 MWe.

0024 Stopped ramp; 100% power, 815 MWe.

09-30-92 2400 This reporting period ended with the Unit operating at 100% power, 815 MWe.

e 9urry Monthly Operating Report No. 92-09 Page 10 of 17

[continued]

UNIT TWO 09-01-92 0000 This reporting period started with the Unit operating at 100% power, 795 MWe.

09-02-92 2114 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%

power, 770 MWe.

2116 Stopped ramp; 95% power, 71 O MWe.

09-03-92 0355 Started ramp up; 93% power, 750 MWe.

0432 Stopped ramp; 100% power, 800 MWe.

09-12-92 0945 Started power reduction to maintain condenser vacuum while cleaning water boxes; 100%

power, 770 MWe.

1518 Stopped power reduction; 94.5% power, 725 MWe.

1832 Started ramp up; 95% power, 720 MWe.

1900 Stopped ramp; 100% power, 805 MWe.

09-18-92 2133 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%

power 780 MWe.

2143 Stopped ramp; 96.5% power, 740 MWe.

09-19-92 0107 Started ramp up; 96.5% power, 740 MWe.

0121 Stopped ramp; 100% power, 790 MWe.

0847 Started ramp down to maintain condenser vacuum while cleaning water boxes; 100%

power, 790 MWe.

0955 Stopped ramp; 94% power, 750 MWe.

2030 Started ramp up; 94% power, 730 MWe.

2121 Stopped ramp; 100% power, 800 MWe.

09-30-92 2400 This report period ended with the Unit operating at 100% power, 780 MWe, and "D" water box out of service for cleaning.

e &rry Monthly Operating Report No. 92-09 Page 11 of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1992 QLCR S91-217 Q-Llst Change Request 07-23-92 (Safety Evaluation No. 92-166A)

This Q-List Change Request changes the classification of Unit 1 circulating water system screen wash components from "Safety-Related" (SR) to "Nonsafety-Related" (NSR).

An evaluation of this change determined that the subject components do not perform a safe shutdown function and are not required for accident mitigation.

Furthermore, these components are not described in the UFSAR as being SR.

Therefore, an unreviewed safety question is not created.

QLCR R92-054 Q-Llst Change Request 09-03-92 (Safety Evaluation No.92-193)

This Q-List Change Request changes the classification of the gaseous waste disposal system from "Safety-Related" (SR) to "Nonsafety-Related with Special Quality/Regulatory Requirements" (NSQ).

An evaluation of this change determined that the subject system does not perform a safe shutdown function and is not required for accident mitigation.

Therefore, an unreviewed safety question is not created.

AC S 1-92-0906 Administrative Control 09-06-92 (Safety Evaluation No.92-194)

Administrative control of Unit 1 steam generator power operated relief valves (PORV) was established to facilitate the control of reactor coolant system temperature. This action was necessary for a short period of time during which reactor power was less than 5 % and the generator was disconnected from the grid to enable transformer repairs.

The PORVs were required to be promptly placed in the automatic control mode in the event of a main steam line break or if containment isolation was required.

This operating condition was evaluated by Engineering and determined to be acceptable since the probability of occurrence of a main steam line break is very small (4.56 E-8 in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) and the additional steam flow (with reactor power less than 5 %) has a negligible effect on the accident analysis.

Therefore, an unreviewed safety question was not created.

-urry Monthly Operating Report No. 92-09 Page 12of 17 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1992

[continued]

DR S-92-0846 Deviation Report 09-08-92 (Safety Evaluation No.92-195)

This Safety Evaluation was performed to evaluate Deviation Report S-92-0846 concerning Unit 1 operation with a body-to-bonnet leak on pressurizer vapor space sample trip valve 1-SS-TV-1018 and seat leakage on redundant valve 1-SS-TV-101 A. Isolation valve 1-RC-133 is being maintained closed in order to isolate the penetration. Closure of this valve also isolates the discharge flow path of the pressurizer vent system.

The evaluation determined that this operating condition is acceptable since the affected trip valves are in their fail-safe position (closed), ensuring containment integrity. The pressurizer vent system vent valves are not identified as accident mitigation equipment or required to be operable by Technical Specifications. Therefore, an unreviewed safety question is not created.

TM S2-92-24 Temporary Modification 09-18-92 (Safety Evaluation No.92-197)

This Temporary Modification (TM) installed an electrical jumper to permit the replacement of Unit 2 reactor protection system (RPS) relay, 28/AFP.

This TM was used to maintain the auxiliary feedwater (AFW) train "B" start circuit continuity during this activity. Double verification of the jumper installation/removal and post maintenance testing were performed. The motor-driven AFW pumps remained operable and the turbine-driven AFW pump was secured during this activity. The AFW train "A" logic was not affected.

Therefore, an unreviewed safety question was not created.

AC S2-92-0807 Administrative Control 09-24-92 (Safety Evaluation No. 92-1738)

Administrative control of Unit 2 main feedwater regulating valves was established (one at a time) in order to close the valves in the event of a reactor trip or safety injection signal. Administrative control of these valves was required while they were jacked open (preventing performance of their automatic safety function) to facilitate troubleshooting and repair of valve controllers and operators.

This activity did not affect the operation of other systems or components. The subject valves were controlled by a licensed operator who was capable of closing the valve (from the control room) within 30 seconds following a feedwater isolation signal. This capability ensured that the activity was bounded by the main steam line break accident analysis. Therefore, an unreviewed safety question was not created.

tlurry Monthly Operating Report No. 92-09 Page 13 of 17 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1992 O-TOP-4019 Temporary Operating Procedures 09-03-92 O-TOP-4020 (Safety Evaluation No.92-192)

Temporary Operating Procedures (TOP) O-TOP-4019, "Blend System Resin Transfer Using [Transfer Pump 1-LW-P-13)", and O-TOP-4020, "Blend System Resin Transfer Using [Transfer Pump 1-LW-P-12]" were developed to provide instructions for spent resin transfer within the catch and blend tank system and from the spent resin blend tank to a high integrity container.

The operations addressed by these TOPs are controlled by Operating Procedure O-OP-22.9.21, "Spent Resin Catch Tank And Blend Tank Transfer System Operation". The TOPs were issued to sequence the operations and to incorporate requirements for infrequently conducted or complex tests or evolutions. The spent resin piping will be operated well below its design pressure rating and is located in an area with no safety-related equipment.

Therefore, an unreviewed safety question is not created.

TSl-010 Technical Specification Interpretation 09-15-92 (Safety Evaluation No.92-196)

Technical Specification Interpretation TSl-01 O was developed to clarify the operability requirements, specified in Technical Specification (TS) 3.23.C.2, for the main control room and emergency switch gear room air handling units (AHU) while Unit 1/Unit 2 are at cold shutdown or refueling shutdown.

An evaluation of the requirements specified in TSl-010 (i.e., limiting conditions for operation) determined that the subject AHUs will continue to be operated in accordance with TS requirements and applicable operating procedures.

Therefore, an unreviewed safety question is not created.

e -urry Monthly Operating Report No. 92-09 Page 14of 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1992 None during this reporting period.

9urry Monthly Operating Report No. 92-09 Page 15of 17 CHEMISTRY REPORT MONTH/YEAR: September 1992 Unit No. 1 Unit No. 2 Primarv Coolant Analvsis Max. Min. Avg. Max. Min. Avg.

Gross Radioact., uCi/ml 3.87E-1 1.88E-2 2.69E-1 2.35E-1 1.14E-1 1.70E-1 Suspended Solids, com < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 < 0.1 Gross Tritium, uCi/ml 3.88E-1 2.55E-1 2.99E-1 2.94E-1 2.42E-1 2.63E-1 1131, uCi/ml 8.19E-4 1.69E-4 5.53E-4 4.50E-4 1.80E-4 3.24E-4 1131/1133 0.11 0.06 0.09 0.13 0.06 0.09 Hvdroaen, cc/ka 44.5 26.5 31.8 43.6 26.1 34.3 Lithium, oom 2.41 1.98 2.21 2.34 2.10 2.20 Boron - 10, oom* 284.0 198.5 213.2 96.4 78.6 87.3 Oxvaen, (DO), oom < 0.005 < 0.005 < 0.005 < 0.005 < 0.005 < 0.005 Chloride, com 0.008 0.003 0.006 0.003 < 0.001 0.002 pH at 25 decree Celsius 6.63 5.96 6.54 7.15 6.90 7.05

None.

9urry Monthly Operating Report No. 92-09 Page 16of 17 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: September 1992 New or Spent Number for New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity No fuel received or stored during this report period.

  • tlurry DESCRIPTION OF PERIODIC TEST(S} WHICH WERE NOT COMPLETED Monthly Operating Report No. 92-09 Page 17of 17 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: September 1992 None During This Reporting Period.
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