ML18153C028
| ML18153C028 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/30/1989 |
| From: | Stewart W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 89-851, NUDOCS 9001030006 | |
| Download: ML18153C028 (24) | |
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- e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 15, 1989 U. S. Nuclear Regulatory Commission Serial No.89-851 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 November 1989.
Very truly yours, 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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POW 34-04 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT # 89-11 APPROVED: ~~ Station Manager
TABLE OF CONTENTS SECTION PAGE Operating Data Report - Unit No. 1 1 Operating Data Report - Unit No. 2 2 Unit Shutdowns and Power Reductions - Unit No. 1 3 Unit Shutdowns and Power Reductions - Unit No. 2 4 Average Daily Unit Power Level - Unit No. 1 5 Average Daily Unit Power Level - Unit No. 2 6 Summary of Operating Experience - Unit No. 1 7 Summary of Operating Experience - Unit No. 2 8 - 9 Facility Changes Requiring NRC Approval 10 Facility Changes That Did Not Require NRC Approval 11 - 14 Procedure or Method of Operation Changes Requiring NRC Approval 15 Procedure or Method of Operation Changes that Did Not Require NRC Approval 16 Tests and Experiments Requiring NRC Approval 17 Tests and Experiments That Did Not Require NRC Approval 18 Chemistry Report 19 Fuel Handling - Unit No. 1 20 Fuel Handling - Unit No. 2 20 Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications 21
OPERATING DATA REPORT DOCKET NO.: 50-280 PATE: 12/05/89 COMPLETED BY: L.A. Warren TELEPHONE: (804)357-3184 x355 OPERATING STATUS NOTES
- 1. Unit Name: Surry Unit 1
- 2. Reporting Period: NOV 01-30, 1989
- 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 720.0 8016.0 148512.0
- 12. Number of Hours Reactor Was Critical 720.0 3553.0 92031. 6
- 13. Reactor Reserve Shutdown Hours 0 0 3774.5
- 14. Hours Generator On-Line 720.0 3501.7 90107.1
- 15. Unit Reserve Shutdown Hours 0 0 3736.2
- 16. Gross Thermal Energy Generated (MWH) 1730947.0 8212036.0 209383303.0
- 17. Gross Electrical Energy Generated (MWH) 588890.0 2754080.0 67957753.0
- 18. Net Electrical Energy Generated (MWH) 560503.0 2610344.0 64450747.0
- 19. Unit Service Factor 100% 43.7% 60.7%
- 20. Unit Available Factor 100% 43.7% 63.2%
- 21. Unit Capacity Factor (Using MDC Net) 99.7% 41. 7% 56.1%
- 22. Unit Capacity Factor (Using DER Net) 98.8% 41.3% 55.1%
- 23. Unit Forced Outage Rate 0 56.3% 21. 7%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down at End of Report Period Estimated Date of Startup:
--....,....,,.=-==--
- 26. Unit In Test Status (Prior to CoI!llllercial Operation): FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1
OPERATING DATA REPORT DOCKET NO.: 50-281 DATE: 12/05/89 COMPLETED BY: L.A. Warren TELEPHONE: (804)357-3184 x355 OPERATING STATUS NOTES
- 1. Unit Name: Surry Unit 2
- 2. Reporting Period: NOV 01-30, 1989
- 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 720.0 8016.0 145392.0
- 12. Number of Hours Reactor Was Critical 157.9 760.3 90454.6
- 13. Reactor Reserve Shutdown Hours 0 0 328.1
- 14. Hours Generator On-Line 152.2 611.9 88904.9
- 15. Unit Reserve Shutdown Hours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 341996.3 7725110.3 207820743.8
- 17. Gross Electrical Energy Generated (MWH) 114585. 0 341735.0 67477979. 0
- 18. Net Electrical Energy Generated (MWH) 108802.0 320497.0 63967875.0
- 19. Unit Service Factor 21.1% 7.6% 61.1%
- 20. Unit Available Factor 21.1% 7.6% 61.1%
- 21. Unit Capacity Factor (Using MDC Net) 19.3% 5.1% 56.5%
- 22. Unit Capacity Factor (Using DER Net) 19.2% 5.1% 55.8%
- 23. Unit Forced Outage Rate 78.9% 63.4% 15.8%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down at End of Report Period Estimated Date of Startup:
- 26. Unit In Test Status (Prior to Commercial Operation): FORECAST---------
ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 2
DOCKET NO.: 50-280 UNIT SHUTDOWN AND POWER REDUCTION UNIT NAME: --=su_r_ry_"""u,....n-=-i-t...,1==----
DATE: 12/05/89 COMPLETED BY: ---L-.A.,--.__W:__a_r_r-en _ _ __
REPORT MONTH: NOVEMBER 1989 TELEPHONE: 804-357-3184 x355 METHOD OF LICENSEE CAUSE & CORRECTIVE DURATION SHU1'TING EVENT SYSTEM COMPONENT ACTION TO PREVENT NO. DATE TYPE{l) (HOURS) REASON(2) DOWN REACTOR(3) REPORT# CODE(4) CODE(5) RECURRENCE 11/16/89 S 0 B 4 TA TRB Ramped Unit to 73% p ~
for 1-PT-29.1 Main Turbine Valve Testing and Clean Waterboxes. Load reduced to 600 MWE.
11/28/89 S 0 B 4 SG COND Ramped down to 80% power 600 MWE to clean water-boxes.
(1) (2) (3) (4)
F: Forced REASON: METHOD:
S: Scheduled A - Equipment Failure (Explain) 1 - Manual Exhibit G - Instructions for B - Maintenance or Test 2 - Manual Scram~ Preparation of Data Entry Sheets C - Refueling 3 - Automatic Scram. for Licensee Event Report (LER)
D - Regulatory Restriction 4 - Other (Explain) File (NUREG 0161)
E - Operator Training & License Examination F - Administrative (5)
G - Operational Error .(Explain)
H ~ Other (Explain) 3 Exhibit 1 - Same Source
DOCKET NO.: 50-281 UNIT SHUTDOWN AND POWER REDUCTION UNIT NAME: --=su_r_ry--=u=-n-=-i-t-2=----
DATE: 12/05/89 COMPLETED BY: --=-L-.A~.--=w--a_r_r-en_ _ __
REPORT MONTH: NOVEMBER 1989 TELEPHONE: 804-357-3184 x355 METHOD OF LICENSEE CAUSE & CORRECTIVE DURATION SHUTTING EVENT SYSTEM COMPONENT ACTION TO PREVENT NO. DATE TYPE{l) (HOURS) REASON(2) DOWN REACTOR(3) REPORT# CODE(4) CODE(5) RECURRENCE C-10-3 11/01/89 F I
567.8 A 1 AB RV Pressurizer safety 2-RC-SV-2551B leaking by its seat.
e (1) (2) (3) (4)
F: Forced REASON: METHOD:
S: Scheduled A - Equipment Failure (Explain) 1 - Manual Exhibit G - Instructions for B - Maintenance or Test 2 - Manual Scram. Preparation of Data Entry Sheets C - Refueling 3 - Automatic Scram. for Licensee Event Report (LER)
D - Regulatory Restriction 4 - Other (Explain) File (NUREG 0161)
E - Operator Training & License Examination F - Administrative (5)
G - Operational Error (Explain)
- H - Other (Explain) 4 Exhibit 1 - Same Source
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 50-280 UNIT NAME: Surry Unit 1 DATE: 12/05/89 COMPLETED BY: L.A. Warren TELEPHONE:(804)357-3184 x355 MONTH: NOVEMBER 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 783 17 786 2 783 18 787 3 781 19 785 4 782 20 785 5 783 21 788 6 781 22 789 7 783 23 786 8 783 24 786 9 783 25 789 10 783 26 792 11 783 27 790 12 783 28 769 13 785 29 662 14 785 30 791 15 784 31 16 782 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.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 50-281 UNIT NAME: Surry Unit 2 DATE: 12/05/89 COMPLETED BY: L.A. Warren TELEPHONE:(804)357-3184 x355 MONTH: NOVEMBER 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 24 157 9 0 25 588 10 0 26 780 11 0 27 772 12 0 28 769 13 0 29 767 14 0 30 767 15 0 31 16 0 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.
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SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: NOVEMBER 1989 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 11/01/89 0000 This reporting period begins with the Unit at 100% power.
11/16/89 0916 Started ramping down to perform PT-29.1. 100% power, 820 MWe.
1109 Stopped ramp at 73% power, 600 MWe.
1530 Started ramping up following PT-29.1, 590 MWe.
1553 Stopped ramp for turnover, 640 MWe, 78% power.
1625 Started ramp up.
1816 Stopped ramp at 100% power, 815 MWe.
11/28/89 2021 Commenced ramp down to 660 MWe, 100% power, 825 MWe to clean all four waterboxes.
2144 Stopped ramp, 79.8% power, 665 MWe.
11/29/89 1735 Commenced Unit ramp to 100% power; 80% power, 670 MWe.
1842 Stopped ramp at 96% power, 800 MWe, 572°F Tavg. to stabilize and verify NIS and reactor power to match prior to approaching 100%.
2023 Unit at 100%, 830 MWe, 575°F Tavg.
11/30/89 2400 This reporting period ends with the Unit at 100% power.
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SUMMARY
OF OPER1\TING EXPERIENCE MONTH/YEAR: NOVEMBER 1989 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.
lJJNIT TWO 11/01/89 0000 This reporting period begins with the Unit at cold shutdown due to leakage of 2-RC-SV-2551B.
11/05/89 2105 RCS temp. )200°F.
11/06/89 0555 RCS temp. )350°F.
11/07 /89 0132 Inserted shutdown banks due to SV-2551C inoperable due to setpoint exceeding 1% tolerance-commenced cooldown and declared unusual event.
1416 Unit 2 <350°F, 450 PSIG.
2230 RCS temperature indication <200°F. Unit at CSD, N.O.U.E.
terminated.
11/20/89 1229 RCS AT 200°F and heating up.
2256 Unit at 350°F, 450 PSIG.
0345 RCS <1000 PSIG, hold temperature and pressure 470°F and 960 PSIG.
2007 Inserted shutdown banks.
11/22/89 0515 Unit at 1800 PSIG due to leakage of pressurizer safety valves.
0655 Started pressure increase from 1800 - 2000 PSIG.
11/24/89 0743 Reactor start up commencing, pulling control rods.
0953 Reactor critical; increasing to amps in the intermediate range.
1548 Unit on line.
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SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: __N_O_VEMB
__ ER_l_9_8_9_ _
Listed below in chronological sequence by unit is a sunnnary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.
UNIT TWO 11/25/89 0517 Commenced ramp-up reactor power 41%, 350 MWe.
0530 Stopped ramp due to 'B' main feed regulating valve dropped
'B' S/G level to 32%.
0538 'B' main feed regulating valve back in auto; connnenced ramp up.
0616 Stopped ramp at 60%, 475 MWe to start 2-FW-P-lB.
0653 Started ramp to 70% reactor power, 60% and 480 MWe.
0726 Stopped ramp at 70%, 550 MWe. for calorimetric.
1212 Holding ramp at 84% reactor power, Techs adjusting IRPis; 680 MWe.
1303 IRPI adjustments completed, connnenced ramp up.
1415 Reactor at 100% power, 820 MWe.
11/26/89 2148 Reduced reactor power to 98% due to 'B' loop protection differential temperature reading high.
11/30/89 2400 This reporting period ended with the Unit at 98% power.
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FACILITY CHANGES REQUIRING NRC APPROVAL MONTH/YEAR: NOVEMBER 1989 NONE DURING THIS REPORTING PERIOD 10
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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: NOVEMBER 1989 l-EWR-89-702 ENGINEERING WORK REQUEST 11/05/89 This work request was for the interim removal of drain valve l-CH-427 and its associated piping and cap; also, to install a pipe plug in the 2" x 211 x 3/4" tee on line 2 11 CH-6-602.
Implementation of this activity will return the system and containment pressure boundaries to an acceptable state. The drain. line removal will have no impact on continued operation of the charging system. An unreviewed safety question does not exist because the consequences of failure of the activity are bounded by the Design Basis Accident analysis in the UFSAR, section 14.5 and are in comparison, insignificant. This interim modification is necessary until an acceptable technical solution is implemented to reduce fatigue on the drain line assembly.
UFSAR UPDATED FINAL SAFETY ANALYSIS REVIEW - UNITS 1&2 11/07 /89 Sec.14.2.9 (SAFETY EVALUATION #N89-0022)
An Updated Final Safety Analysis Report (UFSAR) change was written to correct a calculational error in SM-457 that led to a non-conservative value for peak clad temperature (PCT) following a locked rotor event. This value was reported to USNRC in support of operation with Surry Improved Fuel.
This is a correction of the error that led to an increase in PCT from 1654°F to 1795°F. This evaluation demonstrates that an unreviewed safety question does not exist because the design acceptance criteria for PCT of 2700°F is still met. The NRC was formally informed of this correction by a letter (Serial No.89-716) dated November 14, 1989.
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e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: NOVEMBER 1989 SCAFFOLD REQUEST - UNIT 2 11/13/89 (SAFETY EVALUATION #N89-0027)
This scaffold request is for the erection of temporary scaffold to support painting of Unit 2 turbine building per Work Order #3800083521.
This temporary scaffold was required for safe working. Scaffolds erected per SUADM-ADM-07 have a high confidence factor against failure and it was reviewed for effects on accident analysis and equipment operability. In view of this, it was concluded that the assumptions and probabilities of accident analysis and equipment malfunctions are not significantly affected by this scaffold.
TM-S2-89-139 TEMPORARY MODIFICATION 11/16/89 (SAFETY EVALUATION #N89-0030)
TM-S2-89-140 TEMPORARY MODIFICATION 11/16/89 (SAFETY EVALUATION #N89-0033)
TM-S2-89-141 TEMPORARY MODIFICATION 11/16/89 (SAFETY EVALUATION #N89-0032)
Each temporary modification allowed starting a reactor coolant pump (RCP) with normal cold reactor coolant system (RCS) starting amps expected.
Since RCPs are not used for safety related functions outside of their RCS pressure retaining capacity and Operators are instructed to stop a RCP within 10 seconds if no flow is indicated after pump start, an unreviewed safety question is not created by the temporary removal of the RCP speed sensing relay.
TM-S2-89-136 TEMPORARY MODIFICATION 11/16/89 (SAFETY EVALUATION #N89-0031)
TM-S2-89-137 TEMPORARY MODIFICATION 11/16/89 (SAFETY EVALUATION #N89-0035)
TM-S2-89-138 TEMPORARY MODIFICATION 11/16/89 (SAFETY EVALUATION #N89-0034)
Each temporary modification allowed normal running of a RCP with bearing lift oil to lower shoes at low reactor coolant system pressures.
Since RCPs are not assumed in accident analyses and this change does not affect RCS pressure retaining portion of RCPs, an unreviewed safety question is not created.
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e e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: NOVEMBER 1989 TM-S2-89-147 TEMPORARY MODIFICATION (SAFETY EVALUATION #N89-044) 11/30/89 This modification was written to energize relay 33YBV595 (the relay should be energized when 2-RC-MOV-2595 is open, as it will be throughout the time this change is in effect) to enable restarting 'C' reactor coolant pump should it trip and be required/desired to be restarted.
Since 'C' loop cold leg loop stop valve will remain open and de-energized while change is in effect, the bypassing of .the interlock to prevent starting 'C' RCP with cold leg loop stop valve closed has no effect.
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PROCEDURE OR METHOD OF OPERATION CHANGES REQUIRING NRC APPROVAL MONTH/YEAR: NOVEMBER 1989 NONE DURING THIS REPORTING PERIOD 15
PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: NOVEMBER 1989 l-TOP-40,20 TEMPORARY OPERATING PROCEDURE 11/04/89 (SAFETY EVALUATION #N89-0021)
This procedure allows filling and placing in service the normal letdown following maintenance of l-CH-427.
During the performance of this procedure the letdown line will remain isolated from the RCS. Also, primary grade water that is used will be diverted to the primary drains tank prior to placing letdown in service. Assumptions used in the accident analysis will not be altered during the performance of this procedure.
Therefore, an unreviewed safety question does not exist.
l-TOP-2148 TEMPORARY OPERATING PROCEDURE 11/10/89 (SAFETY EVALUATION #N89-0024)
This procedure was written to allow adjusting 01-FW-E-lB level.
This procedure included disabling the high level alarm.
Since this procedure only affects the condensate and main feedwater systems and is bounded by the previously analyzed loss of feedwater accident, an unreviewed safety question does not exist.
l/2-PT-18.8 PERIODIC TEST PROCEDURE DEVIATION 11/22/89 (SAFETY EVALUATION #N89-0037/38)
This deviation deleted the differential pressure method of testing check valves in the closed position for 1/2-SW-P-lOA/B, and 2-CC-P-ZA,B.
An unreviewed safety question is not created 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 inservice inspection plan and will not affect the ability of the charging pump service water and component cooling subsystems to mitigate the consequences of an accident.
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e TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH/YEAR: NOVEMBER 1989 NONE DURING THIS REPORTING PERIOD 17
TESTS AND EXPERIMENTS THAT DID NOT REQUIRE MRC APPROVAL MONTH/YEAR: NOVEMBER 1989 NONE DURING THIS REPORTING PERIOD 18
... :;. }
- VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT MONTH/YEAR: NOVEMBER 1989 PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAX. MIN. AVG.* MAX. MIN. AVG.
Gross Radioact., µCi/ml 8.05E-l 5.28E-l 6.65E-l 3.39E-l 9.40E-4 2.89E-2 Suspended Solids, ppm 0.0 0.0 0.0 0.0 o.o 0.0 Gross Tritium, µCi/ml 2.97E-l 2.81E-l 2.87E-l 4.27E-2 7.34E-3 l.93E-2 Iodine-131, µCi/ml 3.24E-2 2.29E-3 1. 15E-2 5.0lE-4 4. 81E-5 2 .13E-4 Iodine-131/Iodine-133 0.24 0.07 0.15 0.14 0.10 0.12 Hydrogen, cc/kg 32.9 15.3 22.3 33.5 3.7 18.7 Lithium, ppm 2.33 2.05 2.18 2.95 0.87 1. 82 Boron - 10, ppm* 130.3 115. 4 122.8 469.8 196.6 394.6 Oxygen, (DO), ppm 0.005 0.005 0.005 3.0 <0.005 0.400 Chloride, ppm 0.009 0.006 0.007 0.012 0.004 0.007 pH@ 25 degree Celsius 6.89 6.69 6.83 6.54 5.48 5.80
UNIT ONE The month began with the unit at 100% power with letdown secured due to a leak on the non-regenerative heat exchanger causing RCS dissolved hydrogen concentration to exceed the lower specification limit at 2055 on 10/01/89. On 11/05/89 at 0555, B Mixed Bed was placed back in service and the dissolved hydrogen concentration returned to within normal limits at 1230. A 165 gm lithium addition was also made on 11/05/89. A 320 gm lithium addition was made on 11/17/89. A 420 gm lithium addition was made on 11/29/89.
UNIT TWO The month began with the unit at cold shutdown with BMB inservice. On 11/04/89 a total of 2.5 gallons of hydrazine were added to the RCS. A 1500 gm. lithium addition was also made on 11/04/89. On 11/23/89, 2822 gm of lithium were added to the RCS.
The reactor went critical at 0955 on 11/24/89. A lithium addition of 275 gm to the RCS was made on 11/26/89. The cation bed was placed inservice on 11/28/89 for lithium removal.
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....\, ,*
UNIT 1&2 FUEL HANDLING
- DATE: NOV 1989 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED ASSEMBLIES ASSEMBLY ANSI. INITIAL FUEL SHIPPING SHIPMENT II OR RECEIVED PER SHIPMENT NUMBER NUMBER ENRICHMENT' CASK ACTIVITY LEVEL NONE DURING THIS REPORTING PERIOD 20
DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: NOVEMBER 1989 NONE DURING THIS REPORTING PERIOD 21
FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: NOVEMBER 1989 AC-Sl-89-1106 ADMINISTRATIVE CONTROL (SAFETY EVALUATION #N89-0040) 11/27/89 This administrative control ensures that the main control room (MCR) pressure envelope can be maintained. The service air supply valve to the #2 emergency switch gear room (ESGR)
(l-SA-226) must be maintained under administrative control when the valve is open.
Administrative control over l-SA-226 in accordance with SUADM-0-26 ensures the ability to maintain the MCR/ESGR pressure boundary in the event of a radioactive release. The valve will be closed immediately upon notification by the MCR. In addition, control over the valve will ensure the ability to maintain the pressure boundary thus maintaining operability of the MCR air bottle dump system. Therefore, an unreviewed safety question is not created.
SCAFFOLD REQUEST - UNIT 1 11/27/89 (SAFETY EVALUATION #N89-0041)
This request was written to erect scaffolds to support the replacement of component cooling heat exchangers in Unit 1 turbine basement per Design Change 87-29.
The temporary scaffold was 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.
l-EWR-87-312 ENGINEERING WORK REQUEST 11-29/89 This request was to replace the turbine lube oil and to improve its quality and to reduce the maintenance time spent on the system's upkeep.
The Lube Oil System is an enhancement by design, as it is used to purify the turbine lube oil. Its operability is not required during safe shutdown nor has any effect on safety related equipment. Therefore, an unreviewed safety question is not created.
EWR-89-462 ENGINEERING WORK REQUEST - UNITS 1&2 11/29/89 This request is for the installation of additional air bottles in the compressed dry air system. The bottled air system serving the control room and the emergency switchgear room has marginal capacity to maintain the required positive pressure; the additional bottles will improve system performance.
The consequences or probability of an accident has not been increased due to the addition of air bottles to the control room compressed breathing air system.
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