ML18152A502

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Jul 1992 for SPS Units 1 & 2.W/ 920812 Ltr
ML18152A502
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/31/1992
From: Mason D, Stewart W, Xenakis A
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-523, NUDOCS 9208190070
Download: ML18152A502 (22)
v • d • e


Text

- .

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 12, 1992 U. S. Nuclear Regulatory Commission Serial No.92-523 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 July 1992.

Very truly yours, QJ?~

~v 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. M. W. Branch NRC Senior Resident Inspector Surry Power Station

e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 92-07 Approved:

e - r r y Monthly Operating Report No. 92-07 Page 2 of 21 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 NRC Approval. .............................................................................. 11 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 16 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(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 21

.. ~ 9urry Monthly Operating Report No. 92-07 Page 3 of 21 OPERATING DATA REPORT Docket No.: 50-280 Date: 08-07-92 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . July 1992
3. Licensed Thermal Power (MWt): ...................... . 2441
4. Nameplate Rating (Gross MWe): ...................... . 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 820
7. Maximum Dependable Capacity (Net MWe): ....... . 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YID Cumulative

11. Hours In Reporting Period ......................... . 744.0 5111.0 171887.0
12. Number of Hours Reactor Was Critical ......... . 744.0 3467.8 111702.0
13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 3774.5
14. Hours Generator On-Line .......................... . 744.0 3412.6 109652.8
15. Unit Reserve Shutdown Hours ................... .. 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... . 1801047.8 7724176.0 254840852.7
17. Gross Electrical Energy Generated (MWH) ... . 587720.0 2576545.0 83091733.0
18. Net Electrical Energy Generated (MWH) ...... .. 557822.0 2443259.0 78817325.0
19. Unit Service Factor ................................. .. 100.0% 66.8% 63.8%
20. Unit Availability Factor ............................. .. 100.0% 66.8% 66.0%
21. Unit Capacity Factor (Using MDC Net) .......... . 96.0% 61.2% 59.2%
22. Unit Capacity Factor (Using DER Net) .......... . 95.1% 60.7% 58.2%
23. Unit Forced Outage Rate ........................... . 0.0% 5.0% 18.9%
24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each):
25. If Shut Down at End of Report Period Estimated Date of Start-up:
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

' ... e 9urry Monthly Operating Report No. 92-07 Page 4of 21 OPERATING DATA REPORT Docket No.: 50-281 Date: 08-07-92 Completed By: D. Mason Telephone: (804) 365-2459

1. Untt Name: .................................................. . Surry Unit 2
2. Reporting Period: ........................................ .. July 1992
3. Licensed Thermal Power (MWt): ...................... . 2441
4. Nameplate Rating (Gross MWe): ...................... . 847.5
5. Design Electrical Rating (Net MWe): ................ .. 788
6. Maximum Dependable Capacity (Gross MWe): ... . 820
7. Maximum Dependable Capacity (Net MWe): ...... .. 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe):
10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11. Hours In Reporting Period ........................ .. 744.0 5111.0 168767.0
12. Number of Hours Reactor Was Critical ........ .. 438.8 4805.8 110013.9
13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 328.1
14. Hours Generator On-Line .......................... . 430.1 4797.1 108258.0
15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) .... .. 968862.3 11538779.6 252417461.7
17. Gross Electrical Energy Generated (MWH) .. .. 309960.0 3825585.0 82259434.0
18. Net Electrical Energy Generated (MWH) ...... .. 292920.0 3637015.0 78000953.0
19. Untt Service Factor .................................. . 57.8% 93.9% 64.1%
20. Unit Availability Factor .............................. . 57.8% 93.9% 64.1%
21. Unit Capacity Factor (Using MDC Net) .......... . 50.4% 91.1% 59.3%
22. Unit Capacity Factor (Using DER Net) ......... .. 50.0% 90.3% 58.7%
23. Unit Forced Outage Rate .......................... .. 0.0% 0.0% 14.8%
24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each):
25. If Shut Down at End of Report Period Estimated Date of Start-up:
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

, *, 9urry Monthly OperatingNo.Report 92-07 Page 5 of 21 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: July 1992 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-07-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 920724 s 0 B 4 N/A TA V Reduced power to 77% in order to perform turbine valve freedom test (1-0SP-TM-001 ).

(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)

tlurry Monthly Operating Report No. 92-07 Page 6 of 21 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: July 1992 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-07-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 920706 s 313.8 B 1 NIA AB V Unit was shut down to repair leaking safety valves on the pressurizer.

920722 s 0 B 4 NIA SG COND Reduced power to 76% in order to maintain condenser vacuum while cleaning condenser waterboxes.

920728 s 0 B 4 NIA SG COND Reduced power to 79% in order to maintain condenser vacuum while hydrolasing waterboxes.

(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 (NU REG 0161)

,* "*" eurry Monthly Operating Report No. 92-07 Page ?of 21 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-07-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: July 1992 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 769 17 745 2 769 18 746 3 772 19 748 4 768 20 747 5 767 21 742 6 766 22 727 7 765 23 756 8 766 24 752 9 763 25 600 10 757 26 749 11 754 27 756 12 751 28 756 13 749 29 757 14 746 30 757 15 744 31 756 16 744 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.

I I

9urry Monthly OperatingNo.Report 92-07 Page 8 of 21 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-07-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: July 1992 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 756 17 0 2 754 18 0 3 755 19 428 4 751 20 736 5 694 21 735 6 8 22 729 7 0 23 577 8 0 24 689 9 0 25 745 10 0 26 743 11 0 27 739 12 0 28 661 13 0 29 567 14 0 30 567 15 0 31 571 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.

,... 4lurry Monthly OperatingNo.Report 92-07 Page 9 of 21

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: July 1992 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT ONE 07-01-92 0000 This reporting period started with the Unit operating at 100% power, 81 O MWe.

07-21-92 2235 Started power reduction to maintain condenser vacuum while cleaning waterboxes; 100%

power, 780 MWe.

07-22-92 0100 Stopped power reduction 88% ~wer, 665 MWe.

0510 Started ramp up; 88% power, 680 MWe.

0641 Stopped ramp; 100% power, 795 MWe.

07-24-92 2133 Started ramp down to perform 1-0SP-TM-001 (turbine valve freedom test); 100% power, 800 MWe.

07-25-92 0206 Stopped ramp; 80% p<;>wer, 630 MWe.

2119 Started ramp up; 77% power, 600 MWe.

07-26-92 0549 Stopped ramp; 100% power, 805 MWe.

07-31-92 2400 This reporting period ended with the Unit operating at 100% power, 805 MWe.

UNIT TWO 07-01-92 0000 This reporting period started with the Unit operating at 100% power, 795 MWe.

07-05-92 1933 Started Unit shutdown to repair pressurizer safety valves; 100% power, 790 MWe.

07-06-92 0138 Unit off line.

07-18-92 1914 Reactor critical.

07-19-92 0328 Unit on line and ramping up.

2052 Stopped ramp; 100% power, 770 MWe.

07-22-92 2237 Started power reduction to maintain condenser vacuum while cleaning waterboxes; 100%

power, 770 MWe.

07-23-92 0017 Stopped power reduction; 76% power, 590 MWe.

0436 Started ramp up as vacuum permitted; 76.5% power, 590 MWe.

0517 Stopped ramp while "A" waterbox remained out of service to perform maintenance on the waterbox outlet valve (2-CW-MOV-200A); 82% power, 630 MWe.

tlurry Monthly Operating Report No. 92-07 Page 10 of 21

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: July 1992

[continued]

UNIT TWO [continued]

07-24-92 0618 Started ramp up; 82% power; 660 MWe.

1115 Stopped ramp; 100% power, 78% MWe.

07-28-92 1217 Started ramp down to maintain condenser vacuum while leak check "A" waterbox; 100%

power, 775 MWe.

1430 Stopped ramp; 79% power, 610 MWe.

07-31-92 2400 This reporting period ended with the Unit operating at 79% power and 610 MWe while continuing with hydrolasing operations.

,. 't eurry Monthly OperatingNo.Report 92-07 Page 11 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July 1992 TM S2-92-12 Temporary Modifications 07-03-92 TM S2-92-13 (Safety Evaluation No.92-148)

These Temporary Modifications (TM) installed a blind flange on the Unit 2 condensate polishing (CP) vessel in place of the AOV-8 drain valves, which were removed for maintenance.

These TMs do not affect the normal operation of the nonsafety-related CP system. Therefore, an unreviewed safety question was not created.

TSR 92-055 Temporary Shielding Requests 07-07-92 (Safety Evaluation 92-150)

This Temporary Shielding Request installed temporary lead shielding on

  • pressurizer spray and pressurizer safety valve lines in the Unit 2 containment to reduce the radiation dose received by personnel while performing work in the area.

Installation of the shielding while the subject lines remained operable was determined to be acceptable through the performance of a seismic and deadweight piping analysis, but the operating conditions were not permitted to exceed 300 psi or 400° F. The shielding did not adversely affect the design functions of the affected system and was removed prior to exceeding the specified operating conditions. Therefore, an unreviewed safety question was not created.

TSR 92-056 Temporary Shielding Request 07-07-92 (Safety Evaluation 92-151)

This Temporary Shielding Request installed temporary lead shielding to the elbows of three safety injection (SI) system accumulator discharge lines in the Unit 2 containment to reduce the radiation dose received by personnel while performing work in the area.

Installation of the shielding while the subject lines remained operable was determined to be acceptable through the performance of a seismic and deadweight piping analysis. The shielding was removed prior to Unit start-up.

Therefore, an unreviewed safety question was not created.

e tlurry Monthly OperatingNo.Report 92-07 Page 12of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July 1992

[continued]

SE-92-154 Safety Evaluation 07-07-92 This Safety Evaluation was performed to evaluate the installation of an upgraded traveling water screen at the low level intake structure bay "2C".

Bay "2C" does not contain an emergency service water (ESW) pump. This change was made to improve debris removal capability and will enable various screen configurations to be tested.

The evaluation concluded that this installation was acceptable since it does not affect the ESW pumps and the traveling water screen is not required to operate in an accident. Therefore, an unreviewed safety question was not created.

SE-92-156A Safety Evaluation 07-11-92 This Safety Evaluation was performed to evaluate the venting of an unknown quantity of hydrogen gas from two Unit 2 safety injection (SI) system lines.

The hydrogen gas was routed from the vent valve on the SI piping through tubing to the ventilation vent system.

The venting was carefully controlled to ensure an explosive mixture was not released to the ventilation system. The release was also monitored constantly to ensure adherence to the radiological release requirements. In addition, the unit was at cold shutdown during this evolution and the SI system was not required to be operable. Therefore, an unreviewed safety question was not created.

TM S2-92-14 Temporary Modification 07-13-92 (Safety Evaluation No.92-157)

This Temporary Modification (TM) installed electrical jumpers to permit the replacement of Unit 2 reactor protection system (RPS) relay, FC-424-XB.

This TM was used to maintain the RPS "B" train "function" during this activity.

Double verification of the jumper installation/removal and post maintenance testing were performed. The unit was at cold shutdown with the reactor trip breakers open. The RPS "A" train logic was not affected. Therefore, an unreviewed safety question was not created.

I~

.. ~ .

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL eurry Monthly Operating Report No. 92-07 Page 13 of 21 MONTH/YEAR: July 1992

[continued]

TM S2-92-15 Temporary Modification 07-14-92 (Safety Evaluation No.92-159)

This Temporary Modification (TM) installed electrical jumpers to permit the replacement of Unit 2 reactor protection system relay (RPS), FC-424-XA.

This TM was used to maintain the RPS "A" train "function" during this activity.

Double verification of the jumper installation/removal and post maintenance testing were performed. The unit was at cold shutdown with the reactor trip breakers open. The RPS "B" train logic was not affected. Therefore, an unreviewed safety question was not created.

SE-92-161 Safety Evaluation 07-15-92 This Safety Evaluation was performed to evaluate the temporary installation of a mobile laboratory (trailer) outside of the protected area near the intake canal. The mobile lab was installed to conduct side stream sampling of service water from the intake canal. It was secured to the ground to reduce the potential of it becoming a missile hazard or falling into the intake canal.

The evaluation of this installation determined that if the mobile lab falls into the intake canal the redundant design of the high level intake structure ensures the required service water flow rates will be maintained. Therefore, an unreviewed safety question was not created.

JCO 2-92-006 Justification For Continued Operation 07-17-92 (Safety Evaluation No.92-162)

This Justification For Continued Operation (JCO) addresses the operability of the low head safety injection (LHSI) system following the discovery, during periodic testing, of the occurrence of short duration pressure spikes in the discharge piping shortly after LHSI pump start-up.

The assessment concluded that the pressure spikes will not adversely affect the integrity or function of the LHSI system piping or components. Therefore, an unreviewed safety question does not exist.

.. *. .tlurry Monthly Operating Report No. 92-07 Page 14of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: July 1992

[continued]

FS 92-08 UFSAR Change 07-21-92 (Safety Evaluation 92-164)

The Updated Final Safety Analysis Report (UFSAR) Section 14.2.7, "Excessive Heat Removal Due To Feedwater System Malfunction" was revised to reflect a reevaluation of excess feedwater and reduced feedwater temperature events in multiple loops.

The evaluation .of this change concluded that the multi-loop excess feedwater accident is essentially the same type event as its single loop counterpart and that the consequences are only slightly more adverse, in that the departure from nucleate boiling (DNB) margins are reduced by a few percent. It was determined, however, that adequate margin above the design limit exists for

  • **the multi-loop transients. Therefore, an unreviewed safety question is not created.

AC S 1-92-0724 Administrative Control 07-24-92 (Safety Evaluation No.92-168)

Administrative control of ventilation system valves 1-VS-208, 1-VS-224, 2-VS-208, and 2-VS-224 was established to enable the valves to be throttled in order to raise the main control room temperature.

The subject valves are administratively controlled in a manner such that the design flow rates can be restored within 12 minutes. This manual action ensures that the design basis bulk temperature will not be exceeded in the event of an accident. Therefore, an unreviewed safety question was not created.

TM S1-92-33 Temporary Modification 07-24-92 (Safety Evaluation No.92-167)

This Temporary Modification (TM) installed an electrical jumper to bypass the defective bearing high temperature detector on the Unit 1 chilled water (CD) system chiller, 1-CD-REF-18.

This TM will prevent the subject chiller from tripping and will not negatively affect the operation of the nonsafety-related chiller or impact any safety-related equipment. In addition, the subject chiller is not used to mitigate the consequences of any design basis accidents. Therefore, an unreviewed safety question was not created.

9urry Monthly OperatingNo.Report 92-07 Page 15of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July 1992

[continued]

TM S2-92-23 Temporary Modification 07-29-92 (Safety Evaluation No.92-169)

This Temporary Modification (TM) installed electrical jumpers across the Unit 2 lube oil conditioner variable speed controller (2-LO-P-3) , which has a damaged circuit board, to allow operation of the lube oil c.onditioner.

This TM will not negatively affect the operation of the nonsafety-related lube oil conditioner or impact any safety-related equipment. In addition, the lube oil conditioner is not used to mitigate the consequences of any design basis accidents. Therefore, an unreviewed safety question was not created.

NOV 92-13 Notice of Violation 07-30-92

-r(Safety Evaluation No.92-171)

A Safety Evaluation was performed to evaluate the operability of the recirculating spray heat exchanger (RSHX) service water (SW) system with the piping between service water motor operated valves, SW-MOV-1/203 and SW-MOV-1/204, drained or in a partially drained configuration.

The operability of the RSHX SW system in a partially drained or drained configuration was functionally tested and found to be a satisfactory method of preventing excessive biological fouling of the RSHX tubesheet. The test also demonstrated that the SW system will deliver the design basis flow during an accident condition. It was concluded that the system has been operable since June 1991 and additional procedural controls to maintain the level in the lines at equal to or greater than ten feet will be implemented. This is a conservative measure since current measures for biological control upstream have never been tested with the pipe in the drained condition. Therefore, an unreviewed safety question was not created.

tlurry Monthly Operating Report No. 92-07 Page 16 of 21 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July 1992 1-EPM-1804-24

  • Electrlcal Preventive Maintenance Procedures 07-02-92 2-EPM-1804-24 (Safety Evaluation No.92-144)

Electrical Preventive Maintenance Procedures, 1/2-EPM-1804-24, "Microflex Reset Timer Testing For Relays 2SI-A and 2SI-B" were developed to provide instructions for installing electrical jumpers which will be used during testing to simulate a start signal to the safety injection system (SI) reset timers.

These procedures require double verification of installation and removal of the jumpers and allow only one train at a time to be tested. The circuit being tested will continue to provide a correct SI signal if required and SI actuations will function from both trains. Therefore, an unreviewed safety question was not created.

HP-7.3A.31 Health Physics Procedure 07-03-92 (Safety Evaluation No.92-147)

Health Physics Procedure HP-7.3A.31, "Radioactive Gaseous Waste Sampling And Analysis," was revised to provide instructions for establishing a contaminated gas purge path from the Unit 2 pressurizer relief tank (PAT) to the process ventilation system in order to reduce the backpressure and attenuate pressurizer safety valve leakage.

The release was carefully controlled in accordance with the operating procedures. The gaseous waste was sampled and recorded prior to each release to ensure adherence to the radiological release requirements.

Therefore, an unreviewed safety question was not created.

TMOP-3006 Temporary Maintenance Operating Procedure 07-03-92 (Safety Evaluation No.92-149)

Temporary maintenance operating procedure TMOP-3006, "Unblocking Ventilation Vent RM Line," was developed to provide instructions for installing a purge supply to the downstream side of the ventilation vent isokinetic nozzle at the input of the ventilation vent radiation monitor, 1-RM-VG-109/110. This modification will enable the ventilation vent multi-ported isokinetic nozzle to be flushed with instrument air to remove a clog that prevents the radiation monitors from drawing a sample from the ventilation vent.

This modification was removed immediately following the purging operation and did not negatively impact any plant equipment. Therefore, an unreviewed safety question was not created.

9urry Monthly Operating Report No. 92-07 Page 17 of 21 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July 1992

[continued]

2-0P-5.1.5 Operating Procedure 07-07-92 (Safety Evaluation No.92-152)

Unit 2 Operating Procedure 2-0P-5.1.5, "Venting The PRT," was revised

("one-time only" change) to provide instructions for venting the pressurizer relief tank (PRT) to the sample sink hood which exhausts to the number 2 ventilation vent system stack.

The venting was carefully controlled to ensure an explosive mixture was not released to the ventilation system. The release was also monitored constantly to ensure adherence to the radiological release requirements. Therefore, an unreviewed safety question was not created.

1-PT-18.1 Operations Periodic Test Procedures 07-10-92 2-PT-18.1 (Safety Evaluation No.92-156)

Units 1 and 2 Operations Periodic Test Procedures 1/2-PT-18.1, "LHSI Pump Test," were revised ("one-time only" change) to permit the use of temporary transmitters to enable the measurement of Low Head Safety Injection Pump pressure during the few seconds following pump start.

The use of the temporary safety-related transmitters does not affect the operation of the subject pumps or the ability of the safety injection systems to perform their required safety function. Therefore, an unreviewed safety question was not created.

O-MPM-0300-01 Mechanical Preventive Maintenance Procedure 07-30-92 (Safety Evaluation No.92-170)

Mechanical Preventive Maintenance Procedure O-MPM-0300-01, "Limitorque Operator Type SB, SBD, SMB, And HBC Lubrication And Inspection," was revised to incorporate the administrative control functions (i.e. closure of certain circulating water/service water system motor operated valves) required to maintain the intake canal inventory in the event of a design basis accident or station blackout.

An evaluation of this change concluded that the functions of the circulating water/service water systems remains unchanged and that the administrative control functions can be accomplished in the required time period. Therefore, an unreviewed safety question was not created.

... 9urry Monthly Operating Report No. 92-06 Page 18 of 21 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July 1992 None during this reporting period.

,* ~

ti.my Monthly Operating Report No. 92-06 Page 19 of 21 CHEMISTRY REPORT MONTH/YEAR: July 1992 Unit No. 1 Unit No. 2 Primarv Coolant Analvsis Max. Min. Ava. Max. Min. Ava.

Gross Radioact., uCi/ml 3.35E-1 2.16E-1 2.64E-1 2.13E-1 1.61 E-2 1.15E-1 Suspended Solids, oom 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, µCi/ml 3.92E-1 3.54E-1 3.79E-1 1.41E-1 1.11E-1 1.29E-1 1131, µCi/ml 9.33E-4 3.18E-4 5.81 E-4 6.25E-4 1.67E-4 3.34E-4 113111133 0.12 0.07 0.09 0.11 0.08 0.10 HvdroQen, cc/kQ 38.1 22.9 31.2 35.9 4.3 19.9 Lithium, oom 2.39 2.07 2.20 2.89 1.43 2.17 Boron - 10, oom* 232.3 218.9 225.6 328.1 116.0 221.0 Oxvaen, (DO), oom 0.010 0.005 0.008 0.010 0.005 0.008 Chloride, oom 0.050 0.002 0.006 0.050 0.001 0.004 oH at 25 dearee Celsius 6.62 6.49 6.55 6.96 6.12 6.60 Boron - 10 = Total Boron x 0.196 Comments:

None.

\_; *~

.* ~

tlmy Monthly Operating Report No. 92-06 Page 20 of 21 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: July 1992 New or Spent Number for New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received eer Shiement Number Number Enrichment Cask Activi!}'.

CASTOR V/21

  1. 500.11-014 07-29-92 NIA OAS LM04TU 2.9 OAS LM04UF 2.9 1A2 LM04U5 2.9 1A3 LM04TR 2.9 1A5 LM04U1 2.9 1A6 LM04TV 2.9 1A7 LM04TS 2.9 085 LM08LU 3.2 087 LM08LQ 3.2 088 LM08M4 3.2 183 LM08LL 3.2 184 LM08LK 3.2 187 LMOSLW 3.2 189 LM08LY 3.2 OC7 LM08M9 3.4 1CO LM08MJ 3.4 1C2 LM08M8 3.4 1C5 LM08NF 3.4 1C7 LM08N6 3.4 1C8 LM08NG 3.4 2C2 LM08M8 3.4

eirry Monthly Operating Report No. 92-06 Page 21 of 21 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: July 1992 None During This Reporting Period.

Retrieved from "https://kanterella.com/w/index.php?title=ML18152A502&oldid=2403668"