ML18153C141
| ML18153C141 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/28/1990 |
| From: | Stewart W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 90-133, NUDOCS 9003200190 | |
| Download: ML18153C141 (26) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 16, 1990 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.
NO/RPC:vlh Docket Nos.
License Nos.90-133 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 February 1990.
Very truly yours,
~~l~fu..,~
W. L. Stewart Senior Vice President - Nuclear Enclosure cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station
/"
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT I 90-02 APPROVED:
POW 34-04
I TABLE OF CONTENTS SECTION Operating Data Report - Unit No. 1 Operating Data Report - Unit No. 2 Unit Shutdowns and Power Reductions - Unit No. 1 Unit Shutdowns and Power Reductions - Unit No. 2 Average Daily Unit Power Level
- Unit No. 1 Average Daily Unit Power Level
- Unit No. 2 Summary of Operating Experience - Unit No. 1 Summary of Operating Experience - Unit No. 2 Facility Changes That Did Not Require NRC Approval Procedure or Method of Operation Changes That Did Not Require NRC Approval Tests and Experiments That Did Not Require NRC Approval Chemistry Report Fuel Handling - Unit No. 1 Fuel Handling - Unit No. 2 Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications PAGE 1
2 3
4 5
6 7
8 10 19 20 21 22 22 23
OPERATING DATA REPORT DOCKET NO.:
DATE:
COMPLETED BY:
TELEPHONE:
OPERATING STATUS NOTES
- 1. Unit Name:
Surry Unit 1
- 2. Reporting Period: Feb 01-28, 1990
- 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 50-280 March 05, 1990 L.A. Warren (804)357-3184 x355
- 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. Reason For Restrictions, If Any: -------------------
THIS MONTH YTD CUMULATIVE
- 11. Hours In Reporting Period 672.0 1416.0 150672. 0
- 12. Number of Hours Reactor Was Critical 672.0 1416.0 94166.8
- 13. Reactor Reserve Shutdown Hours 0
0 3774. 5
- 14. Hours Generator On-Line 672.0 1416.0 92239.2
- 15. Unit Reserve Shutdown Hours 0
0 3736.2
- 16. Gross Thermal Energy Generated (MWH) 1638185.0 3427933.0 214544736.0
- 17. Gross Electrical Energy Generated (MWH) 555810. 0 1162355.0 69707758.0
- 18. Net Electrical Energy Generated (MWH) 529832.0 1107944. 0 6611887 4. 0%
- 19. Unit Service Factor 100%
100%
61.2%
- 20. Unit Availability Factor 100%
100%
63.7%
- 21. Unit Capacity Factor (Using MDC Net) 101. 0%
100.2%
56.7%
- 22. Unit Capacity Factor (Using DER Net) 100.1%
99.3%
55.7%
- 23. Unit Forced Outage Rate 0%
0%
21.4%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
NONE
- 25. If Shut Down at End of Report Period Estimated Date of Startup=---~~==--
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1
OPERATING DATA REPORT DOCKET NO.:
50-281 DATE: -M""""a_r_c,_h _,0"""5,.....,___,1,...,,9-9~0---
COMPLETED BY:
L.A. Warren TELEPHONE: --.-,(8=0"";;""4'\\"":)3=5=-7_-=3,.....1=-84,....-x=35=-=5,----
OPERATING STATUS NOTES
- 1. Unit Name:
Surry Unit 2
- 2. Reporting Period: Feb 01-28, 1990
- 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. Reason For Restrictions, If Any:
THIS MONTH YTD CUMULATIVE
- 11. Hours In Reporting Period 672.0 1416.0 147552.0
- 12. Number of Hours Reactor Was Critical 672.0 1416.0 92614.6
- 13. Reactor Reserve Shutdown Hours 0
0 328.1
- 14. Hours Generator On-Line 672.0 1416.0 91064. 9
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 1618031. 4 3312339.0 212922673.8
- 17. Gross Electrical Energy Generated (MWH) 544555.0 1116805. 0 69197404.0
- 18. Net Electrical Energy Generated (MWH) 518765.0 1063318.0 65604277. 0
- 19. Unit Service Factor 100%
100%
- 61. 7%
- 20. Unit Availability Factor 100%
100%
61.7%
- 21. Unit Capacity Factor (Using MDC Net) 98.8%
96.1%
57%
- 22. Unit Capacity Factor (Using DER Net) 98%
95.3 56.4%
- 23. Unit Forced Outage Rate 0%
0%
16%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
NONE
- 25. If Shut Down at End of Report Period Estimated Date of Startup: ---~=--
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 2
NO.
DATE (1)
F:
Forced S: Scheduled UNIT SHUTDOWN AND POWER REDUCTION (Equal to or Greater than* 20%)
REPORT MONTH:
FEBRUARY 1990 METHOD OF LICENSEE
(
DOCKET NO.:
50-280 UNIT NAME: -s=-u-r-ry--.-.On__,i,..,.t-1-.--
DATE:
03/05/90 COMPLETED BY:
L.A. Warren TELEPHONE:
804-357-3184 x355 DURATION SHUTTING EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE TYPE(l)
(HOURS)
REASON(2) DONN REACTOR(3) REPORT#
CODE(4)
CODE(5)
NONE DURING THIS REPORTING PERIOD (2)
REASON:
A - Equipment Failure (Explain)
B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain) 3 (3)
METHOD:
1 - Manual 2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain)
(4)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)
File (NUREG 0161)
(5)
Exhibit 1 - Same Source
NO.
DATE 02/05/90 02/20/90 (1)
F:
Forced S:
Scheduled UNIT SHUTDOWN AND POWER REDUCTION (Equal to or Greater than 20%)
REPORT MONTH:
FEBRUARY 1990 METHOD OF LICENSEE DOCKET NO.:
50-281
--=-----:-:------=---
UN IT NAME:
Surry Un1t 2.
DATE:
03/05/90 COMPLETED BY:
L.A. Warren TELEPHONE:
804-357-3184 x355 DURATION SHUTTING EVENT SYSTEM COMPONENT CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE TYPE(l)
(HOURS)
REASON(2) DOWN REACTOR(3) REPORT#* CODE(4)
CODE(5) s s
(2)
REASON:
0 0
B 4
B 4
A - Equipment Failure (Explain)
B - Maintenance or Test C - Refueling D - Regulatory Restriction E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain) 4 (3)
METHOD:
1 - Manual SG TA 2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain)
COND TRB Ramped down to 77%..,
maintain condenser vacuum while removing waterboxes for cleaning.
Ramped down to 75%
in preparation for 2-PT-29.1 (Turbine Control Valve Freedom Test).
(4)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER)
File (NUREG 0161)
(5)
Exhibit 1 - Same Source
AVERAGE DAILY UNIT POWER LEVEL MONTH:
February 1990 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 788 2
788 3
787 4
788 5
788 6
789 7
789 8
770 9
789 10 789 11 790 12 787 13 786 14 788 15 788 16 789 INSTRUCTIONS DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 DOCKET NO.:
50-280 UN IT NAME : --=-s u-r-ry-U~n.....-i t.,.--,,-1--
DAT E:
March 05, 1990 COMPLETED BY:
L.A. Warren TELEPHONE:(804)357-3184 x355 AVERAGE DAILY POWER LEVEL (MWe-Net) 792 791 792 791 792 791 788 788 789 791 790 786 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.
5
AVERAGE DAILY UNIT POWER LEVEL MONTH:
February 1990 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 702 2
735 3
784 4
784 5
764 6
747 7
783 8
783 9
783 10 784 11 784 12 782 13 781 14 778 15 771 16 774 INSTRUCTIONS DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 DOCKET NO.:
50-281 UN IT NAME: ~Su-r-ry__,.U..... n....-it~2--
DA TE:
March 05, 1990 COMPLETED BY:
L.A. Warren TELEPHONE:(804)357-3184 x355 AVERAGE DAILY POWER LEVEL (MWe-Net) 782 786 786 720 786 782 783 782 783 772 752 783 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.
6
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR:
FEBRUARY 1990 Listed below in chronological sequence by unit is a ~ummary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.
UNIT ONE 02/01/90 02/08/90 02/28/90 0000 This reporting period started with the Unit at 100% power, 830 MW.
1003 Started ramp down for 1-PT-29.1 performance; 100% power, 825 MW.
1120 Stopped ramp; 85% power, 700 MW.
1305 Started ramp up after completion of 1-PT-29.1; 85% power, 700 MW.
1500 Stopped ramp; 100% power, 820 MW.
2400 This reporting period ended with the Unit at 100%
- power, 825 MW.
7
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: ~-F_EB_R_UA_R_Y_l_9_90~~
e 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 TWO 02/01/90 02/02/90 02/05/90 02/06/90 0000 This reporting period started with the Unit at 89% power, 735 MW due to an inoperable main steam crossunder safety, 02-MS-SV-207A.
1718 Started ramp up; as per Westinghouse calculations, 93% power operation is permissible with 02-MS-SV-207A inoperable; 89%
power, 735 MW.
1740 Stopped ramp; 93% power, 760 MW.
2156 Started ramp down to maintain condenser vacuum during waterbox cleaning operations; 93% power, 760 MW.
2221 Stopped ramp; 88.5% power, 720 MW.
0440 Started ramp up after waterbox cleaning operations were completed; 89% power, 720 MW.
0503 Stopped ramp; 93% power, 770 MW.
1720 Started ramp up; as per Westinghouse calculations, 100%
power operation is permissible with 02-MS-SV-207A inoperable.
Allowance is based on design of th~ intercept and reheat valves.
The valves do not afford total isolation and will therefore supplement steam relief capability of remaining operable crossunder safeties.
93% power, 770 MW.
1759 Stopped ramp; 100% power, 825 MW.
2108 Started ramp down to allow for waterbox cleaning operations; 100% power, 810 MW.
2300 Stopped ramp; 77% power, 620 MW.
0322 Started ramp up after waterbox cleaning operations were completed; 76% power, 635 MW.
0455 Stopped ramp to adjust IRPis; 98.5% power, 800 MW.
0512 Started ramp up after IRPI adjustment completed; 98.5%
power, 800 MW.
0520 Stopped ramp; 100% power, 820 MW.
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SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: ___ F_E_BR_U_A_RY~1_99_0 __ ~
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 TWO 02/15/90 02/20/90 02/26/90 02/27/90 02/28/90 0744 Started ramp down for waterbox cleaning and performance of 2-PT-29.1; 100% power, 815 MW.
0846 Started ramp up; 2-PT-29.1 canceled; 91.6% power.
0943 Stopped ramp; 100% power, 825 MW.
1050 Started ramp down in preparation for 2-PT-29.1; 100%
- power, 825 MW.
1310 Stopped ramp; 75% power, 635 MW.
1819 Started ramp up after completion of 2-PT-29.1; 75% power, 635 MW.
2108 Stopped ramp; 100% power, 825 MW.
2130 Started ramp down to clean waterboxes; 100% power, 825 MW.
2330 Stopped ramp; 83.5% power, 685 MW.
0456 Started ramp up after waterboxes cleaned; 83% power, 690 MW.
0630 Stopped ramp; 100% power, 825 MW.
2400 This reporting period ended with the Unit at 100%
- power, 825 MW.
9
DC-89-15 Sl-89-2292 e
e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: ~-F_EB_R_UA_R_Y~19_9_0~
REPLACEMENT OF RADIATION MONITOR RM-SW-107 This design change installed an in-line detector in a well to detect radioactivity in the service water discharge from component cooling water heat exchanger 1D 1
This change was initiated due to maintenance problems with the existing off-line monitor, caused by river water fouling and the inability of the sample pump to draw a representative sample for monitoring.
SUMMARY
OF SAFETY ANALYSIS This modification is being done to improve the reliability of the monitor which is currently out of service. Seismic analysis of the detector well has been performed.
Emergency bus requirements have been maintained.
An unreviewed safety question does not exist since the new detector is an enhancement to the existing system.
STATION DEVIATION 02/06/90 (Safety Evaluation #90-0024)
This deviation report is to document that the possibility exists that a 900# gasket was installed in the inlet of 1-RC-SS-1558 & C in lieu of the required 1500# gasket.
Gaskets are rated by the manufacturer to match the pipe/flange ratings as a guide.
ASME specifically excludes gaskets as pressure boundary components.
Therefore, no stress analysis is applicable to the gasket itself. The physical difference between the 900# and 1500# gaskets is that approximately 2 more coils are in the 1500# gasket.
The gaskets have been seated and are pressurized.
No increased leakage has been detected during the PT-10 daily testing. The gasket design precludes a catastrophic failure.
During containment entries at normal operating pressure, no leakage from the gaskets was observed and any change would be identified via PT-10 or containment radiation monitors.
Therefore, an unreviewed safety question does not exist.
10
e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
FEBRUARY 1990 TM-S2-90-001 TEMPORARY MODIFICATION 02/08/90 (Safety Evaluation #90-0027)
This temporary modification is to install electrical jumpers in train 18 1
safeguards rack from relay Fl-YB to F3-YB to maintain continuity thru circuit while replacing relay F2-YB.
The failure of the jumper would result in the loss of continuity to 18 1 train safety injection (SI) actuation relays.
Since the 1A 1 train is unaffected and the jumper will be installed only for the time that relay F2-YB is being replaced, and 18 1
train SI relays will be unaffected unless jumper fails, an unreviewed safety question is not created.
Redundant protection is provided by the train 1A1 actuations.
Backup protection is provided by manual actions to provide the necessary actuations.
These actions are directed by the applicable ERG procedures (2-E-0, 2-ES-0, 1/2-FR-H-3).
During placement of the jumper, adequate precautions must be taken to prevent inadvertent actuation of the feedwater isolation logic and/or a
turbine/reactor trip.
Therefore, an unreviewed safety question is not created.
2-EWR-89-499 ENGINEERING WORK REQUEST 02/13/90 This Engineering Work Request is to evaluate components of the backup air supply system to 2-RC-PCV-2455C for damage due to the failure of the air regulator and subsequent pressure transient in the backup air supply system.
Redundancy provided by an additional power operated relief valve and three code safety valves ensured that no unreviewed safety question exists, and the provisions of the Technical Specifications were not violated.
SCAFFOLD REQUEST UNIT #1 (Safety Evaluation #90-0030)
This request is for the erection support the replacement of the reel handling crane 1-FH-BRDG-13 located 45 1 10 11 ), W0#076345.
02/13/90 of a temporary scaffold to and cable on the fuel in the fuel building (EL The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
11
-~
FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
FEBRUARY 1990 SCAFFOLD REQUEST UNIT #2 02/13/90 (Safety Evaluation #90-0032)
This request is for the erection of a temporary scaffold located in the Unit 2 safeguards building to support maintenance work for repairing the loose pipe hanger on line #4 11-SHP-127-601 per WO #091438.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT #1 02/13/90 (Safety Evaluation #90-0031)
This request is for the erection of a temporary scaffold to support the replacement of bearings and seals on the bridge of the drive motor for the fuel handling crane 1-FH-BRDG-13 located in the fuel building (EL-51 1 ), W0#077195.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT #2 02/13/90 (Safety Evaluation #90-0033)
This request is for the erection of a temporary scaffold to support the maintenance work to repair a packing leak on valve 2-MS-149 located in the Unit 2 safeguards building (EL-27 16 11
)
between 2-FW-P-3A and 38.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT 1 02/15/90 (Safety Evaluation #90-0036)
This change is for the erection of temporary scaffold located in Unit 1 turbine building between Cols. 7 and 9 and Y and Bat elevation 9 16 11
- The scaffold will be erected from the floor and will be supported per SUADM-ADM-07.
12
',,.~.
e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: ~-F_EB_R_U_AR_Y~19_9_0~
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function.
It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT 1 02/15/90 (Safety Evaluation #90-0037)
This change is for the erection of temporary scaffold to support installation of smoke detectors in Unit 1 cable tunnel ceiling per DCP-89-10.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT 2 02/15/90 (Safety Evaluation #90-0038)
This change is for the erection of temporary scaffold located in the Unit 2 turbine building at elevation 9 16 11 The scaffold will be erected from the floor and will be supported per SUADM-ADM-07.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT 1 02/15/90 (Safety Evaluation #90-0039)
This change is for the erection of temporary scaffold to support conduit installation and cable pulling per DCP-89-09.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT #2 02/15/90 (Safety Evaluation #90-0040)
This change is for the erection of temporary scaffold to support installation of conduit and cable pulling per EWR-89-668.
13
e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: ___
F_EB_R_UA_R_Y __
19_9_0 __
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT 2 (Safety Evaluation #90-0041) 02/15/90 This change is for the erection of temporary scaffold to support installation of smoke detectors in the Unit 2 cable tunnel ceiling per DCP 89-10.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
TM-Sl-90-05 TEMPORARY MODIFICATION (Safety Evaluation #90-0043) 02/16/90 This temporary modification is to blank the suction plenum of the non-safety related fan, 1-VS-F-98, to allow the redundant fan, 1-VS-F-9A, to operate without short circuiting the fan.
Both fans are in non-safety related ducts which are isolated by engineered safety features (ESF) actuation. All work will be performed on non-safety related equipment and will not affect operability of the safety related fans.
Therefore, an unreviewed safety question is not created.
SCAFFOLD REQUEST UNIT 1 02/20/90 (Safety Evaluation #90-0045)
This request is for the erection of temporary scaffold to rework and install new supports for the 3 11 conduit per EWR-89-616.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT 1 02/20/90 (Safety Evaluation #90-0046)
This request is for the erection of temporary scaffold to support the installation of hangers for unsupported conduits per EWR-89-616.
14
~
e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
FEBRUARY 1990 The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT 2 02/20/90 (Safety Evaluation #90-0047)
This request is for the erection of temporary scaffold to support installation of smoke detectors per DCP-89-10.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT 1 02/20/90 (Safety Evaluation #90-0048)
This request is for the erection of temporary scaffold to support replacement of check valve 1-FP-14 per work order #3800088383.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT 2 (Safety Evaluation #90-0049) 02/20/90 This request is for the erection of temporary scaffold in the Unit 2 cable vault.
The scaffold will be erected from the floor at elevation 15 1
The scaffold will be laterally supported from structural steel.
The temporary scaffold is. required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
15
FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
FEBRUARY 1990 AC-Sl-90-0221 ADMINISTRATIVE CONTROL 02/22/90 (Safety Evaluation #90-0050)
This change is to place valve l-SW-263 (Appendix R) under administrative control while it is in the manual override position due to ongoing mechanical work in the Mechanical Equipment Room (MER) #3 and the 1/2-SW-P-lOA pump room to prevent spurious valve closure due to smoke created by welding and grinding operations.
The valve can be closed by operators within two minutes of notification by firewatches.
Firewatches are located in MER
- 3 and, if the smoke detectors are inoperable, in the Service Water (SW) pump room.
If the SW pump room smoke detectors are operable, operators will be alerted by the Main Control Room annunciator. Since adequate protection is still provided to meet the safe shutdown requirements of 10CFR50, Appendix R,
an unreviewed safety question is not created.
AC-Sl-90-02218 ADMINISTRATIVE CONTROL (Safety Evaluation #90-0052) 02/22/90 This change is to place administrative control over 2-SA-60 and 2-SA-62, service air supply isolation valves to #1 containment, to ensure that containment integrity can be maintained.
Administrative Control over l-SA-60/62 in accordance with SUADM-0-26 ensures that the ability to maintain containment integrity as defined in technical specifications (TS).
The valves will be closed immediately upon notification by the Main Control Room (MCR).
In addition, control over the valves will ensure the ability to maintain the containment partial pressure within the limits established by TS-3.8.
Therefore, an unreviewed safety question is not created.
SCAFFOLD REQUEST UNIT 1 02/22/90 (Safety Evaluation #90-0054)
This request is for the erection of temporary scaffold in the Unit 1 turbine building (EL-9 16 11
)
to install conduit and supports for the component cooling radiation monitors per EWR-89-15.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function.
It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
16
FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
FEBRUARY 1990 SCAFFOLD REQUEST UNIT #1 02/22/90 (Safety Evaluation #90-0055)
This request is for the erection of temporary scaffold to install conduit and supports for the component cooling radiation monitors in the Unit 1 turbine building (EL-9 16 11 ) per EWR-89-15.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
SCAFFOLD REQUEST UNIT #1 (Safety Evaluation #90-0057) 02/23/90 This request is for the erection of temporary scaffold to perform maintenance on valve 1-CH-MOV-1267A in the Unit 1 auxiliary building charging pump 1-CH-P-lA cubicle per WO #082999.
The temporary scaffold is required for safe working.
Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function. It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
17
l/2-TOP-3034 WO# 060544 WO# 060599 WO# 080158 e
e PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR:
TEMPORARY OPERATING PROCEDURE WORK ORDER WORK ORDER WORK ORDER (Safety Evaluation #90-0023)
FEBRUARY 1990 02/05/90 02/05/90 02/05/90 02/05/90 This temporary operating procedure and work orders were to isolate the non-safety related fans, 1-VS-F-88, 9A and 98, from the vent vent system.
Fans and dampers, 1-VS-88 and 9A, need to be repaired to perform their design function.
1-VS-F-58A and B will remain available to run during blanking process.
Either 1-VS-F-58A or B will run during the outage of 1-VS-F-9A and B.
The work will be performed on non-safety related equipment and will not affect operability of the safety related fans.
Therefore, an unreviewed safety question is not created.
l/2-COP-19.0 CHEMISTRY OPERATING PROCEDURE (Safety Evaluation #90-0025) 02/08/90 l-TOP-4021 A change was made to the procedure to assign administrative control when the underground fuel oil tank access plug is removed during tank sampling operations.
Since the redundant tank will be unaffected and administrative control will exist requiring the plug to be replaced upon issuance of a tornado or hurricane watch/warning, an unreviewed safety question is not created.
TEMPORARY OPERATING PROCEDURE (Safety Evaluation #90-0026) 02/08/90 This temporary operating procedure was written to identify a possible tube leak in component cooling water (CCW) heat exchanger (HX) 1-CC-E-lA.
Helium will be injected into the shell side of the HX to pressurize it, and a helium leak detector will be used on the service water side (tube side) of the HX to identify possible leaking tubes.
The HX will be drained and removed from service during the test.
The other three CCW HXs will remain operable as required by Technical Specifications.
An unreviewed safety question does not exist because the leak check testing will be performed on an isolated HX which has been removed from service.
In addition, the pressure of the helium injected into the HX will be less than the normal operating pressure of the CCW.
18
- I
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MMP-C-G-96 PAR-900297 PAR-900298 1-PT-2.21A 2-PT-2.21A 1-PT-2.218 1-PT-2.21C 2-PT-2.21C 1-PT-18.8 2-PT-18.8 1-PT-18.8A 2-PT-18.BA e
PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
FEBRUARY 1990 MECHANICAL MAINTENANCE PROCEDURE UNITS 1&2 PROCEDURE ACTION REQUEST PROCEDURE ACTION REQUEST (Safety Evaluation #90-0056) 02/24/90 This procedure action request (PAR) is to document that the requirements of operating procedure OP-18.3 have been incorporated along with a North Anna escape lock a-ring inspection test into mechanical maintenance procedure MMP-C-G-96.
This procedure provides for inspection of the a-rings on the escape lock of the containment equipment hatch.
This procedure change ensures that containment integrity is met during the entrance into the escape lock of the hatch.
Procedural controls are such that at least one operable escape lock door will be closed during the evolution. Therefore, the health and safety of the public are not affected, and an unreviewed safety question is not created.
PERIODIC TEST (Safety Evaluation #90-0063)
(Safety Evaluation #90-0061)
(Safety Evaluation #90-0060)
(Safety Evaluation #90-0059)
(Safety Evaluation #90-0060) 02/27/90 The change in the procedure provides for administrative control over the removal of missile protection for the canal low level trip circuitry during the performance of technical specification required surveillance testing.
An unreviewed safety question does not exist since the missile shield is installed to protect the circuitry from wind generated missiles and upon removal the shield can be replaced (if severe weather is forecast or threatening) utilizing the administrative controls.
PERIODIC TEST (Safety Evaluation #90-0066)
(Safety Evaluation #90-0058)
(Safety Evaluation #90-0065)
(Safety Evaluation #90-0067) 02/27/90 This procedure change documented that the differential pressure method.of testing the check valves for the charging pump service water and charging pump component cooling water subsystems is unnecessary and is being removed from the periodic test.
An unreviewed safety question does not exist since the check valves will still be tested in the closed position to ensure system operability.
This change is in accordance with the ASME XI plan and will not affect the ability of the subject subsystems to mitigate the consequences of an accident.
19
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TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:
FEBRUARY 1990 NONE DURING THIS REPORTING PERIOD 20
e VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT MONTH/YEAR:
FEBRUARY 1990 PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAX.
MIN.
AVG.
MAX.
MIN.
Gross Radioact., µCi /ml 8.59E-1 6.33E-1 7.22E-1 2.34E-1
- 1. 87E-1 l.99E-1 4.28E-1 3.82E-1 Iodine-131, µCi/ml 6.76E-3 4.32E-4 3.90E-3 8.40E-4 1.14E-4 Iodine-131/Iodine-133 0.19 0.09 0.12 0.15 0.06 Hydrogen, cc/kg 32.7 25.3 27.5 33.8 21.8 Lithium, ppm 2.32 2.07 2.21 2.32 2.12 Boron - 10, ppm*
85.8 69.8 77.8 177.8 159.2 Oxygen, (DO), ppm 0.005 0.005 0.005 0.005 0.005 Chloride, ppm 0.007 0.003 0.005 0.007 0.003 pH@ 25 degree Celsius 7.09 6.90 7.00 6.62 6.41
UNIT TWO:
Dissolved hydrogen was out of spec for a total of 19 hours2.199074e-4 days <br />0.00528 hours <br />3.141534e-5 weeks <br />7.2295e-6 months <br /> and 10 minutes.
On 02/21/90, at 0820, the hydrogen concentration was 22.7 cc/kg.
Hydrogen VCT pressure was increased from 23 to 38 psi g, and dissolved hydrogen was back in spec at 0330 on 02/22/90, 26.4 cc/kg.
The dissolved hydrogen spec is 25-35 cc/kg.
21 AVG.
1.82E-1 0.0 4.07E-1 4.63E-4 0.10 26.7 2.22 166.4 0.005 0.005 6.56
.II
UNIT 1&2 NEW OR SPENT FUEL SHIPMENT :fl DATE SHIPPED OR RECEIVED e
FUEL HANDLING NUMBER OF ASSEMBLIES ASSEMBLY ANSI PER SHIPMENT NUMBER NUMBER e
DATE:
FEBRUARY 1990 INITIAL ENRICHMENT NEW OR SPENT FUEL SHIPPING CASK ACTIVITY LEVEL NONE DURING THIS REPORTING PERIOD 22
1-c,,.
1-S't' \\,
I DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR:
FEBRUARY 1990 NONE DURING THIS REPORTING PERIOD 23