ML18152A317

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Monthly Operating Repts for Apr 1991 for Surry Power Station Units 1 & 2.W/910515 Ltr
ML18152A317
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/30/1991
From: Negron M, Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
91-276, NUDOCS 9105210301
Download: ML18152A317 (26)
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, e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 15, 1991 U. S. Nuclear Regulatory Commission Serial No.91-276 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 April 1991. *

  • Very truly yours, r/"'7 'u /* 0 .1 o
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  • !.~~~ 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 NO. 91-04 Approved:

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... -Surry Monthly Operating Report No. 91-04 Page 2 of 25 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 ......................................................................................... 9 Facility Changes That Did Not Require NRG Approval ............................................................................... 10 Procedure or Method of Operation Changes That Did Not Require NRG Approval ........................................... 20 Tests and Experiments That Did Not Require NRG Approval ...................................................................... 22 Chemistry Report ............................................................................................................................. 23 Fuel Handling - Unit No. 1 ................................................................................................................... 24 Fuel Handling - Unit No. 2 ................................................................................................................... 24 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 25

  • OPERATING DATA REPORT

&urry Monthly Operating Report No. 91-04 Page 3 of 25 Docket No.: 50-280 Date: 05-06-91 Completed By: M.A. Negron Telephone: 804-365-2795

1. Unn Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . April 1991
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 .................................... 719.0 2879.0 160895.0
12. Number of Hours Reactor Was Critical .......... 719.0 2879.0 102353.2
13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 3774.5
14. Hours Generator On-Line ........................... 719.0 2879.0 100359.2
15. Unit Reserve Shutdown Hours ..................... 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 1752325.3 6984865.3 233204775.6
17. Gross Electrical Energy Generated (MWH) .... 586090.0 2355540.0 75932363.0
18. Net Electrical Energy Generated (MWH) ........ 558932.0 2244323.0 72027452.0
19. Unit Service Factor ................................... 100.0% 100.0% 62.4%
20. Unit Availability Factor............................... 100.0% 100.0% 64.7%
21. Unit Capacity Factor (Using MDC Net) ........... 99.5% 99.8% 57.8%
22. Unit Capacity Factor (Using DER Net) ........... 98.7% 98.9% 56.8%
23. Unit Forced Outage Rate ............................ 0.0% 0.0% 20.2%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25. If Shut Down at End of Report Period Estimated Date of Start-up:
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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&urry Monthly Operating Report No. 91-04 Page 4 of 25 OPERATING DATA REPORT Docket No.: 50-281 Date: 05-06-91 Completed By: M.A. Negron Telephone: 804-365-2795

1. Un~ Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . April 1991
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):

1 0. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting .................................... 719.0 2879.0 157775.0
12. Number of Hours Reactor Was Critical .......... 0.0 2136.0 101308.3
13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 328.1
14. Hours Generator On-Line ........................... 0.0 2114.8 99685.4
15. Unit Reserve Shutdown Hours ..................... 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ...... 0.0 4493943.2 232629411 .5
17. Gross Electrical Energy Generated (MWH) .... 0.0 1510315.0 75740429.0
18. Net Electrical Energy Generated (MWH) ........ 0.0 1432860.0 71811585.0
19. Unit Service Factor ................................... 0.0% 73.5% 63.2%
20. Unit Availability Factor ............................... 0.0% 73.5% 63.2%
21. Unit Capacity Factor (Using MDC Net) ........... 0.0% 63.7% 58.4%
22. Unit Capacity Factor (Using DER Net) ........... 0.0% 63.2% 57.8%
23. Unit Forced Outage Rate ............................ 0.0% 0.0% 15.0%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling 29 67 days

25. If Shut Down at End of Report Period Estimated Date of Start-up: 06-05-91
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

-urry Monthly Operating Report No. 91-04 Page 5 of 25 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: April 1991 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 05-06-91 Completed by: M. A. Negron Telephone: 804-365-2795 (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 04-05-91 s 0 B 4 NIA TA V Ramped unit to 75% to perform 1-PT-29.1 (Turbine Valve Freedom Test).

04-26-91 F 0 D 4 1 UC CHU Technical Specifications 008-00 required shutdown commenced due to two of three chillers inoperable per Tech Spec 3.23 and 3.0.2. Unit ramp stopped at 78%, 635 MWe when a relay was replaced and the necessary chillers were returned to service.

(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 (LEA) File (NUREG 0161)

UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

eurry Monthly Operating Report No. 91-04 Page 6 of 25 REPORT MONTH: April 1991 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 05-06-91 Completed by: M. A. Negron Telephone: 804-365-2795 (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 04-01-91 s 719 C NIA NIA NIA Scheduled Refueling Outage.

(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)

AVERAGE DAILY UNIT POWER LEVEL eurry Monthly Operating Report No. 91-04 Page 7 of 25 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 05-06-91 Completed by: M.A. Negron Telephone: 804-365-2795 Month: April 1991 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 787 17 784 2 789 18 773 3 788 19 780 4 786 20 775 5 761 21 776 6 785 22 775 7 751 23 772 8 779 24 771 9 784 25 771 10 784 26 756 11 787 27 764 12 787 28 763 13 788 29 761 14 787 30 756 15 786 31 16 784 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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eurry Monthly Operating Report No. 91-04 Page 8 of 25 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 05-06-91 Completed by: M.A. Negron Telephone: 804-365-2795 Month: April 1991 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (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 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 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

-urry Monthly Operating Report No. 91-04 Page 9 of 25 MONTH/YEAR: April 1991 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 04-01-91 0000 This reporting period started with the Unit operating at 100% power and 825 MWe.

04-05-91 1220 Started ramp down to perform 1-PT-29.1; 100% power, 825 MWe.

1410 Stopped ramp; 75% power, 615 MWe.

1515 Started ramp up after completion of 1-PT-29.1; 75% power, 615 MWe.

1700 Stopped ramp; 100 % power, 825 MWe.

04-26-91 0115 Started Technical Specification required shutdown due to two (2) of three (3) control room chillers inoperable.

Reference:

Technical Specification 3.23 and 3.0.2; 100% power, 805 MWe.

0222 Stopped ramp; 78% power, 635 Mwe.

0236 Started ramp up after one (1) control room chiller repaired; 78% power, 635 MWe.

0425 Stopped ramp; 100% power, 795 MWe.

04-30-91 2400 This report period ended with the Unit operating at 100% power, 795 MWe.

UNIT TWO 04-01-91 0000 This report period started with the Unit at Cold Shutdown with Refueling scheduled.

04-30-91 2400 This report period ended with the Unit at Refueling Shutdown.

  • eurry Monthly Operating Report No. 91-04 Page 10 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991 TM S2-91-03 Temporary Modification 04-02-91 (Safety Evaluation No.91-075)

This Temporary Modification (TM) installs roughing filters upstream of fans 2-VS-E-2A, B, and C on the Containment Recirculation Fan System to reduce the spread of contaminated dust during the Unit 2 Cycle 1O refueling outage.

This TM will be installed on the non-safety related Containment Recirculation Fan System, will be in place only during Cold Shutdown, and will not affect fuel handling accident mitigation systems. Therefore, an unreviewed safety question does not exist.

TSR 91-014 Temporary Shielding Requests 04-02-91 TSR 91-053 (Safety Evaluation No.91-076)

These Temporary Shielding Requests (TSR) install temporary lead shielding on the Residual Heat Removal (RHR) system piping in the vicinity of the RHR pumps to reduce the radiation dose received by personnel performing work on or in the area of the RHR pumps during the Unit 2 Cycle 1O refueling outage.

Installation of the shielding while the RHR system is operable (per TSR 91-014) was determined to be acceptable through the performance of a seismic piping analysis. Additional shielding (per TSR 91-053) will be installed when the RHR system in inoperable and will be reviewed for dead weight concerns. This shielding will be removed prior to Unit startup. Therefore, an unreviewed safety question does not exist.

TM S2-91-04 Temporary Modification 04-04-91 (Safety Evaluation No.91-077)

This Temporary Modification (TM) splices in a cable to connect the normal power supply leads to Main Steam Non Return Valve (MS NRV) 2-MS-MOV-201 B to MS NRVs "A" and "C" to allow the removal and installation of motor operators. In addition, a local control switch will be connected to the 2-MS-MOV-201 B limit switch/torque switch assembly to prevent limit and torque switch actuation while removing the motor operator from the stem of the valve.

This TM will only be installed while the Unit is at Cold Shutdown and affects only the MS NRVs and associated power supplies. At this condition the MS NRVs play no role in accident mitigation. Therefore, an unreviewed safety question does not exist.

  • eurry Monthly Operating Report No. 91-04 Page 11 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991

[continued)

TSR 91-056 Temporary Shielding Request 04-04-91 (Safety Evaluation No.91-078)

This Temporary Shielding Request (TSR) installs temporary lead shielding on Safety Injection (SI) system piping (1 O"-Sl-206-153) located in the Unit 2 Safeguards building basement to reduce the radiation dose received by personnel performing Auxiliary Feedwater piping modification work.

Installation of the shielding while the SI system remains operable was determined to be acceptable through the performance of a seismic piping analysis. This TSR will not affect the design functions of the SI or other systems and the shielding will be removed prior to Unit startup. Therefore, an unreviewed safety question does not exist.

TSR 91-020 Temporary Shielding Requests 04-04-91 TSR 91-021 (Safety Evaluation No.91-079)

TSR 91-031 TSR 91-032 . These Temporary Shielding Requests (TSR) install temporary lead shielding on Pressurizer Spray, Auxiliary Pressurizer Spray, and Pressurizer Safety Valve piping in the Unit 2 Containment building to reduce the radiation dose received by personnel while performing various work activities in the area.

The shielding will be installed while the Unit is at Cold Shutdown and the affected piping is inoperable. A dead weight analysis was performed for the additional loading on the piping and was determined to be acceptable. These TSRs will not affect the design functions of the affected systems and the shielding will be removed prior returning the piping to service. Therefore, an unreviewed safety question does not exist.

SE 91-080 Safety Evaluation No.91-080 04-05-91 This Safety Evaluation was performed to evaluate the implementation of the new Radwaste Facility. The facility was designed to 1) treat liquid, laundry, and solid wastes, 2) provide decontamination services, 3) provide a hot machine shop, and 4) provide storage for packaged waste prior to shipment for off-site disposal.

Radiation monitoring will be in accordance with the Technical Specifications (TS). Liquid wastes will be processed using acceptable methods described in the FSAR. Solid wastes will be processed using an approved Process Control Program in accordance with TS and government regulations. Handling and transport of waste packages will be in accordance with federal, state, and local regulations using only containers evaluated and approved for their intended use.

Therefore, an unreviewed safety question does not exist.

  • tlurry Monthly Operating Report No. 91-04 Page 12 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991

[continued]

TM S1-91-05 Temporary Modification 04-06-91 TM S2-91-05 (Safety Evaluation No.91-081)

This Temporary Modification (TM) places the Unit 1 and Unit 2 discharge tunnel vacuum breaker valves (1-CW-117,2-CW-117) in the full open position to ensure the proper operation of the Recirculation Spray Heat Exchanger (RSHX)

Service Water (SW) Radiation Monitoring Pumps 1-SW-P-SA, B, C, D and 2-SW-P-SA, B, C, D.

The TM was initiated in response to the failure of RSHX SW Radiation Monitoring Pumps 2-SW-P-58 and 2-SW-P-SC to develop adequate flow and discharge pressure during functional testing while performing RSHX flow test (ST-301 ). The failure was attributed to insufficient pump suction pressure due to discharge tunnel vacuum. The pumps were retested and performed satisfactorily with the tunnel at atmospheric pressure.

Based on previous RSHX and Component Cooling Heat Exchanger flow tests, design basis flow rates have been demonstrated with the discharge tunnels operating at atmospheric pressure. Operating the tunnels at atmospheric pressure is also consistent with canal inventory calculation assumptions.

Consequently, this change does not create an unanalyzed condition and does not alter the licensing basis. Therefore, an unreviewed safety question does not exist.

  • tlurry Monthly Operating Report No. 91-04 Page 13 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991

[continued]

AC S1 0407 Administrative Control 04-07-91 JCO 91-1-2 Justification For Continued Operation (Safety Evaluation No.91-082)

The Unit 1 discharge tunnel vacuum breaker valve 1-CW-117 was placed under administrative control with an operator stationed at the valve to open it, thereby breaking tunnel vacuum, upon notification of a Hi Hi Consequence Limiting Safeguards signal. This action was required to ensure the proper operation of the Recirculation Spray Heat Exchanger (RSHX) Service Water (SW) Radiation Monitoring Pumps (1-SW-P-5A, B, C,D) following the failure of pumps 2-SW-P-5B and 2-SW-P-5C to develop adequate flow and discharge pressure during functional testing while performing RSHX flow test (ST-301 ).

The failure was attributed to insufficient pump suction pressure due to discharge tunnel vacuum. The pumps were retested and performed satisfactorily with the tunnel at atmospheric pressure. The compensatory action will continue while the design basis of the RSHX SW Radiation Monitoring System is investigated and an alternate means of ensuring pump operability is implemented.

Based on previous RSHX and Component Cooling Heat Exchanger flow tests, design basis flow rates have been demonstrated with the discharge tunnels operating at atmospheric pressure. Operating the tunnels at atmospheric pressure is also consistent with canal inventory calculation assumptions.

Consequently, this change does not create an unanalyzed condition and does not alter the licensing basis. Therefore, an unreviewed safety question does not exist.

EWR 91-035 Engineering Work Request 04-09-91 (Safety Evaluation No.90-056)

This Engineering Work Request modified the starting circuitry of the Diesel Driven Emergency Service Water Pumps (1-SW-P-1 A, 1B, 1C) to replace the automatic start functions with manual start capability.

The automatic start circuitry, utilized when the pumps could be started from the Main Control Room, is no longer used. The relays of this circuitry have proven unreliable and were bypassed to provide direct operator control over starter engagement, thus reducing the probability of start failure. This modification does not affect the design basis function of the Emergency Service Water Pumps. Therefore, an unreviewed safety question does not exist.

  • eurry Monthly Operating Report No. 91-04 Page 14of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991

[continued]

TM S2-91-06 Temporary Modification 04-11-91 (Safety Evaluation No.91-084)

This Temporary Modification (TM) installs a temporary hose on the existing distillate transfer pump (2-WT-P-106A) discharge drain valve (2-WT-2025) to supply system flushing water to the new radwaste facility.

Once in service, the hoses and connections will be periodically inspected to identify and correct excessive leakage or flooding. Potential flooding, due to a hose or connection failure, would be contained by the Condensate Polishing building sumps, drains, and dikes. This TM will not affect any equipment or systems important to safety or the UFSAR accident analyses. Therefore, an unreviewed safety question does not exist.

SE 91-086 Safety Evaluation No.91-086 04-11-91 This Safety Evaluation was performed to evaluate the Unit 2 Cycle 11 reload core, including installation of a new burnable poison rod assembly design, enhanced performance rod cluster control assemblies, and modified new fuel assemblies that incorporate debris filter bottom nozzles and longer fuel rod bottom end plugs. This evaluation also assumed operation of the Unit in accordance with the recently approved Technical Specification change to increase the boron concentration.

UFSAR Chapter 14 accidents were considered in this evaluation. The boron dilution event, impacted by the boron increase, was the only one affected.

This event was reanalyzed and considered in the safety analysis of the reload core. Therefore, an unreviewed safety question does not exist.

TM S1-91-07 Temporary Modification 04-11-91 (Safety Evaluation No.91-087)

This Temporary Modification (TM) installs electrical jumpers to bypass the test switch on the Loop 2, Train "A" Feedwater (FW) isolation circuitry to allow its replacement without rendering the circuits inoperable.

This TM continues to allow Loop 2, Train "A" FW isolation actuation on a valid signal and does not affect the other loops and trains, thus maintaining the design FW isolation functions. Therefore, an unreviewed safety question does not exist.

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  • 9irry Monthly Operating Report No. 91-04 Page 15 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991

[continued]

TM S2-91-07 Temporary Modification 04-14-91

. (Safety Evaluation No.91-089)

This Temporary Modification (TM) blocks valve, 2-CH-MOV-2287C , in the open position to allow maintenance to be performed on the motor operator.

This TM will maintain the subject valve in its normal (open) configuration using a blocking device that has been seismically evaluated and determined to be acceptable. The system integrity and pressure boundary will not be affected and the design functions of providing boration flowpath and charging cross-tie capability will be maintained. Therefore, an unreviewed safety question does not exist.

TM S2-91-08 Temporary Modification 04-15-91 (Safety Evaluation No.91-090)

This Temporary Modification (TM) installs an electrical jumper in the Emergency Switch Gear Room to permit the use of existing spare telephone lines to establish sound powered telephone communications between the Unit 2 Control Room and Containment building during the Unit 2, Cycle 10 refueling outage.

This TM will not negatively impact the operation of the sound powered telephone system or other plant communications systems as described in the UFSAR. Alternate means of communication will also be available, if needed.

Therefore, an unreviewed safety question does not exist.

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FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL 9my Monthly Operating Report No. 91-04 Page 16 of 25 MONTH/YEAR: April 1991

[continued]

TM S2-91-09 Temporary Modification 04-17-91 (Safety Evaluation No.91-092)

This Temporary Modification (TM) replaces a cracked end cap on the Containment Purge Air Operated Damper (AOD-VS-1118) actuator with a manufactured end cap to ensure proper operation of the damper while waiting for a replacement part.

The temporary replacement end cap will be manufactured using a stronger material than the original part and will have no affect on the operation of the actuator for any design plant conditions. This TM will also not affect the redundant damper's ability to isolate the Containment Purge system.

Therefore, an unreviewed safety question does not exist.

EWR 89-477 Engineering Work Request 04-18-91 (Safety Evaluation No.90-140)

This Engineering Work Request modified the Emergency Diesel* Generator's (EOG) Radiator Louver Control circuits, replacing the function of the Louver Control Relays (LCR) by using the Engine Start Relays (ESR).

This modification enhances the operation of the Louver Control circuits by eliminating the failure prone LCRs. The ESRs are utilized to operate the louvers while the EDGs are running. No new failure modes will be introduced by this change and this change will have no effect on the ability of the EDGs to start.

Therefore, an unreviewed safety question does exist.

DC-88-02-2 Design Change 04-19-91 This Design Change installed recirculation test piping to permit periodic full flow testing of the Inside Recirculation Spray (IRS) pumps.

This modification does not affect the operation of the IRS pumps or the design basis of the of the IRS system to perform its safety functions. Testing will be performed during plant shutdown conditions only and the recirculation piping will be physically disconnected (using spool pieces) from the IRS system piping after testing. Therefore, an unreviewed safety question does exist.

  • esurry Monthly Operating Report No. 91-04 Page 17of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991

[continued]

TSR 91-048 Temporary Shielding Requests 04-19-91 TSR 91-049 (Safety Evaluation No.91-094)

TSR 91-050 These Temporary Shielding Requests (TSR) install temporary lead shielding on the Reactor Coolant "A", "B", and "C" loop bypass piping (8"-RC-311/312/

313-250IR) and valves (2-RC-MOV-2585, 2586, 2587) in the Unit 2 Reactor Coolant Pump (RCP) cubicles to reduce the radiation dose received by personnel while performing work on the valve motor operators and limitorques.

The shielding will be installed while the Unit is at Cold Shutdown and the affected piping is inoperable. A dead weight analysis was performed for the additional loading on the piping and was determined to be acceptable. These TSRs will not affect other systems and the shielding will be removed prior to returning the piping to service. Therefore, an unreviewed safety question does not exist.

JCO 1-91-3 Justification For Continued Operation 04/19/91 (Safety Evaluation No.91-096)

This Justification For Continued Operation (JCO) permits the replacement of the failed existing 70 amp, 3 phase breakers in the Unit 1 Pressurizer Heater Panels with new 70 amp, 3 phase breakers.

The new breakers are a one-for0 one replacement of the existing breakers and will not affect the normal operation of the system. The compensatory measures identified in the JCO are designed to provide ambient temperatures in the motor control center room consistent with the specified ambient temperatures for the breakers. They will provide for reliable service and protection of the Pressurizer Heater system until a new, enhanced breaker system can be procured and installed. Therefore, an unreviewed safety question does not exist.

TM S2-91-12 Temporary Modification 04-22-91 (Safety Evaluation No.91-097)

This Temporary Modification (TM) relocates the Unit 2 Containment Sump Pump (2-DA-P-4A) to the Containment trough to permit the pumping of Containment drains to the low level waste header while the Containment sump is being used to support the performance of Inside Recirculation Spray Pump flow testing.

This TM will be implemented while the Unit is at Cold Shutdown (CSD) and will not affect any safety related system or component. It will also not affect the design function of the pump. In addition, this pump is not required to mitigate an accident with the Unit at CSD. Therefore, an unreviewed safety question does not exist.

'i..

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  • emy Monthly Operating Report No. 91-04 Page 18 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991

[continued]

TM S2-91-11 Temporary Modification 04-22-91 (Safety Evaluation No.91-098)

This Temporary Modification (TM) removes Containment Sump Trip Valve 2-DA-TV-200A for maintenance and installs a spool piece to maintain an operable flow path from Containment Sump Pumps 2-DA-P-4A and 48.

The Unit will be at Cold Shutdown while this TM is in place. The Containment Sump Trip Valve closure interlocks, which would shut off pumps 2-DA-P-4A and 48, will be defeated to allow pump operation to continue as needed. The pump interlocks of the redundant valve 2-DA-TV-2008 will remain operable or the valve will be tagged closed. In addition, personnel will be alerted to this abnormal configuration. Therefore, an unreviewed safety question does not exist.

TSR 91-020 Temporary Shieldlng Requests 04-23-91 TSR 91-021 (Safety Evaluation No.91-095, Revision 1)

TSR 91-031 These Temporary Shielding Requests (TSR) install temporary lead shielding on Pressurizer Spray and Pressurizer Safety Valve piping in the Unit 2 Containment building to reduce the radiation dose received by personnel while performing various work activities in the area.

The shielding will be installed while the Unit is at Cold Shutdown and the affected piping, although considered operable, will not be pressurized or exceed 140 degrees F. A seismic and dead weight analysis was performed for the additional loading on the piping and determined to be acceptable. These TSRs will not affect other systems and the shielding will be removed prior to the affected system piping being pressurized or exceeding 140 degrees F.

Therefore, an unreviewed safety question does not exist.

TSR 91-059 Temporary Shleldlng Request 04-25-91 (Safety Evaluation No.91-105)

This Temporary Shielding Request (TSR) installs temporary lead shielding on Reactor Cavity Purification system piping (3"-RL-101-152) located in the Unit 2 Auxiliary building (Elevation 4'-0") to reduce the radiation dose received by personnel performing work in the area.

Installation of the shielding while the piping remains operable was determined to be acceptable through the performance of a seismic piping analysis. The shielding will not affect the design functions of the Reactor Cavity Purification system piping or other systems and will only be in place while the Unit is at Cold Shutdown. Therefore, an unreviewed safety question does not exist.

  • .~ . ' [.

1**

erry Monthly Operating Report No. 91-04 Page 19 of 25 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991

[continued]

TM S1-91-08 Temporary Modification 04-26-91 (Safety Evaluation No.91-106)

This Temporary* Modification (TM) removes the Reset Relay (for oil pressure/

overload lock-out) from the inoperable Main Control Room "B" Chiller to replace the failed Reset Relay in the "A" Chiller.

This TM involves a one-for-one component replacement that will render the "A" Chiller operable. Two chillers ("A" and "C"), including emergency power supplies, will then be available and the applicable Technical Specifications action statement will be implemented. No other systems are affected by this modification. Therefore, an unreviewed safety question does not exist.

TM S2-91-13 Temporary Modification 04-26-91 (Safety Evaluation No.91-108)

This Temporary Modification (TM) involves a one-for-one component replacement of a damaged Safety Injection (SI) system relay (F3-XB) with a new relay.

During the implementation of this TM, a jumper will be installed to maintain the other SI relays energized to prevent spurious actuation of the system. In addition, the Unit will be at Cold Shutdown, a condition that does not require the SI system. Therefore, an unreviewed safety question does not exist.

TM S2-91-14 Temporary Modification 04-28-91 (Safety Evaluation No.91-109)

This Temporary Modification (TM) installs temporary cables to transfer the electrical load from failed Load Center Transformer "2J1" to "2J" until repairs can be made.

Transferring the load from Transformer "2J1" to "2J" was determined to acceptable since Unit 2 is at Cold Shutdown in a refueling outage and "2J1

  • is lightly loaded, as a result. Previous load readings indicate that load demands on "2J" will be within design parameters. In addition, a spare circuit breaker in "2J" will provide circuit protection. Therefore, an unreviewed safety question does not exist.

)

}

PROCEDURE OR METHOD OF OPERATION CHANGES tlurry Monthly Operating Report No. 91-04 Page 20of 25 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991 2-TOP-3051 Temporary Operating Procedure 04-06-91 (Safety Evaluation No.91-081 A)

Temporary Operating Procedure, 2-TOP-3051, was developed to provide instructions for processing Primary Drains Transfer Tank inventory to the Volume Control Tank and back to the Reactor Coolant System (RCS) during Cold Shutdown conditions to provide RCS inventory control and to minimize liquid waste generation and RCS make-up.

The procedure provides the necessary steps and precautions to avoid undetected and uncontrolled boron dilution conditions through proper valve alignment, minimizing primary grade water flow paths, and valve leakage testing .. In addition, monitoring will continue to be performed using the Nuclear Instrumentation system. Any potential dilution of the RCS would occur very slowly. Thus, a loss of shutdown margin could be anticipated and prevented.

Therefore, an unreviewed safety question does not exist.

2-TOP-3051 Temporary Operating Procedure 04-16-91 (Safety Evaluation No.91-081 A, Revision 1)

Temporary Operating Procedure 2-TOP-3051 .was developed to provide instructions for flowing Reactor Coolant system (RCS) water from the Primary Drains Transfer Tank through approximately 70 feet of hose to the Safety Injection (SI) system cold leg piping and back to the RCS. This flow path will be used when Unit 2 is at Cold Shutdown and will allow the Volume Control Tank to be tagged out for maintenance.

The SI system will remain operable and capable of performing its intended safety function. It will also be available to maintain RCS volume. The hose connections will be isolable on both ends and will be checked for leaks once per shift upon initiation of the procedure. Therefore, an unreviewed safety question does not exist.

i ) -

tlurry Monthly Operating Report No. 91-04 Page 21 of 25 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1991

[continued]

2-TOP-4006 Temporary Operating Procedure 04-17-91 (Safety Evaluation No.91-091)

Temporary Operating Procedure, 2-TOP-4006, was developed to provide instructions for flowing Reactor Coolant system (RCS) water from the Primary Drains Transfer Tank through approximately 70 feet of hose to the Safety Injection (SI) system cold leg piping and back to the RCS. This flow path will be used when Unit 2 is at Cold Shutdown and will allow the Volume Control Tank to be tagged out for maintenance.

The SI system will remain operable and capable of performing its intended safety function. It will also be available to maintain RCS volume. The hose connections will be isolable on both ends and will be checked for leaks once per shift upon initiation of the procedure. Therefore, an unreviewed safety question does not exist.

1-PT-17.6 Periodic Test Procedure 04-26-91 2-PT-17.6 (Safety Evaluation No.91-107)

Periodic Test (PT) Procedure 1/2-PT-17.6 was revised to provide instructions for performing the Containment Spray (CS) system nozzle flow test using a thermographic imager for verification of flow through the nozzles.

This test will be conducted with the Unit at Cold Shutdown using 180 degree F temperature air for the flow test. This type of testing is addressed in the Technical Specifications and has also been determined, through an Engineering evaluation, to have no adverse effect on the CS system. Therefore, an unreviewed safety question does not exist.

'l' l -~*

'..... * -urry Monthly Operating Report TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL No. 91-04 Page 22 of 25 MONTH/VEAR: April 1991 None During This Reporting Period.

1' -urry Monthly Operating Report

'..... No. 91-04 Page 23 of 25 CHEMISTRY REPORT MONTH/YEAR: April 1991 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avr;i. Max. Min. Avr;i.

Gross Radioact., µ.Ci/ml 7.72E-1 3.29E-1 5.18E-1 2.14E-1 1.23E-3 2.20E-2 Suspended Solids, oom 0.0 0.0 0.0 400 0.0 107 Gross Tritium, µ.Ci/ml 3.73E-1 3.18E-1 3.52E-1 ------- ------- -------

1131, uCi/ml 3.59E-3 1.51 E-3 1.99E-3 ------- ------- -------

113111133 0.13 0.08 0.10 ------- ------- -------

Hydror;ien, cc/kr;i 40.9 30.8 35.2 ------- ------- -------

Lithium, oom 2.33 2.06 2.20 ------- ------- -------

Boron - 1o, oom* 144 129 136 192 1.9 125 Oxyr;ien, (DO), oom <0.005 <0.005 <0.005 7.0 <0.005 1.99 Chloride, oom 0.010 0.002 0.004 0.020 0.002 0.006 pH at 25 der;iree Celsius 6.88 6.59 6.73 5.92 4.87 5.22 Boron - 1 O = Total Boron x 0.196 Comments:

Unit 2: Shutdown for Refueling.

., . ~...-

  • FUEL HANDLING 4lurry Monthly Operating Report No. 91-04 Page 24 of 25 UNITS 1 & 2 MONTH/YEAR: April 1991 Units One and Two Number for Nominal New or Spent Assemblies Assembly ANSI Initial Fuel Shipping Cask Stored per Shipment Number Number Enrichment Cask Activity None during this reporting period.

eurry Monthly Operating Report No. 91-04 Page 25 of 25 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: April 1991 None During This Reporting Period.

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