ML18152A549

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Monthly Operating Repts for Aug 1996 for Surry Power Station Units 1 & 2.W/960913 Ltr
ML18152A549
Person / Time
Site: Surry  Dominion icon.png
Issue date: 08/31/1996
From: Bowling M, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-479, NUDOCS 9609240301
Download: ML18152A549 (21)
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Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 13, 1996 United States Nuclear Regulatory Commission Serial No.96-479 Attention: Document Control Desk NURPC Washington, D.C. 20555 Docket Nos. 50-280 50-281 Lic~nse 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 August 1996.

If you have any questions or require additional information, please contact us.

Very truly yours, N s4 M. L. Bowling, Manager Nuclear Licensing and Operations Support 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 960924-0301 960831 PDR ADOCK 05000280 R PDR

e e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 96-08 Approved:

~ il C c.___<i -,~-9 (;

Station Manager Date

e Surry Monthly Operating Report No. 96-08 Page 2 of 20 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 ............................................................................................ 1O Procedure or Method of Operation Changes That Did Not Require NRC Approval... .............................................. 15 Tests and Experiments That Did Not Require NRC Approval .................................................................................. 17 Chemistry Report ..................................................................................................................................................... 18 Fuel Handling - Unit No. 1 ........................................................................................................................................ 19 Fuel Handling - Unit No. 2 ........................................................................................................................................ 19 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ....................................................................................................................... 20

e Surry Monthly Operating Report No. 96-08 Page 3 of 20 OPERATING DATA REPORT Docket No.: 50-280 Date: 9-04-96 Completed By: D. K. Mason Telephone: {804) 365-2459

1. Unit Name: ........................................................... Surry Unit 1
2. Reporting Period: ................................................ . August, 1996
3. Licensed Thermal Power (MWt): ......................... . 2546
4. Nameplate Rating (Gross MWe): ........................ . 847.5
5. Design Electrical Rating (Net MWe): ................... . 788
6. Maximum Dependable Capacity (Gross MWe): .. . 840
7. Maximum Dependable Capacity (Net MWe): ...... . 801
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 5855.0 207695.0
12. Number of Hours Reactor Was Critical ........... 744.0 5855.0 143905.7
13. Reactor Reserve Shutdown Hours .................. 0.0 0.0 3774.5
14. Hours Generator On-Line ................................ 744.0 5855.0 141602.0
15. Unit Reserve Shutdown Hours ........................ 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 1893735.2 14809931.3 331207723.8
17. Gross Electrical Energy Generated (MWH) ..... 623100.0 4918625.0 108495808.0
18. Net Electrical Energy Generated (MWH) ......... 600371.0 4748309.0 103204282.0
19. Unit Service Factor .......................................... 100.0% 100.0% 68.2%
20. Unit Availability Factor. .................................... 100.0% 100.0% 70.0%
21. Unit Capacity Factor (Using MDC Net) ............ 100.7% 101.2% 64.0%
22. Unit Capacity Factor (Using DER Net) ............ 100.0% 102.9% 63.1%
23. Unit Forced Outage Rate ................................ 0.0% 0.0% 15.5%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

25. If Shut Down at End of Report Period, Estimated Date of Start-up: N/A
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e .

Surry Monthly Operating Report No. 96-08 Page 4 of 20 OPERATING DATA REPORT Docket No.: 50-281 Date: 9-04-96 Completed By: D. K. Mason Telephone: (804) 365-2459

1. Unit Name: .......................................................... . Surry Unit 2
2. Reporting Period: ................................................ . August, 1996
3. Licensed Thermal Power (MWt): ......................... . 2546
4. Nameplate Rating (Gross MWe): ........................ . 847.5
5. Design Electrical Rating (Net MWe): ................... . 788
6. Maximum Dependable Capacity (Gross MWe): .. . 840
7. Maximum Dependable Capacity (Net MWe): ...... . 801
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 5855.0 204575.0
12. Number of Hours Reactor Was Critical ........... 709.6 4885.2 140388.1
13. Reactor Reserve Shutdown Hours .................. 0.0 0.0 328.1
14. Hours Generator On-Line ................................ 705.4 4863.1 138419.2
15. Unit Reserve Shutdown Hours ........................ 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ...... 1759917.6 12203484.6 324738538.6
17. Gross Electrical Energy Generated (MWH) ..... 580205.0 4043895.0 106199539.0
18. Net Electrical Energy Generated (MWH) ......... 559068.0 3908436.0 101018851.0
19. Unit Service Factor .......................................... 94.8% 83.1% 67.7%
20. Unit Availability Factor ..................................... 94.8% 83.1% 67.7%
21. Unit Capacity Factor (Using MDC Net) ............ 93.8% 83.3% 63.3%
22. Unit Capacity Factor (Using DER Net) ............ 95.4% 84.7% 62.7%
23. Unit Forced Outage Rate ................................ 5.2% 2.6% 12.7%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

25. If Shut Down at End of Report Period, Estimated Date of Start-up: N/A
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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Surry Monthly Operating Report No. 96-08 Page 5 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: August, 1996 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 9-03-96 Completed by: M. J. Fanguy Telephone: (804) 365-2155 (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 N/A N/A N/A N/A N/A N/A N/A N/A N/A (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)

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Surry Monthly Operating Report No. 96-08 Page 6 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: August, 1996 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 9-3-96 Completed by: M.J. Fanguy Teleehone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action to Date Type Hours Reason Shutting Code Code Prevent Recurrence Down Rx 8/3/96 F N/A A N/A TA V Maintenance on EHC System.

F 38.6 B 2 95-005 TG PSF Manual U2 trip due to MS turbine governor and intercept valves going closed during troubleshooting of EHC leak.

8/27/96 F N/A A N/A JE RLY Ramp down to 30% due to Hi-Hi- CLS relay failure.

New relay installed.

(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)

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Surry Monthly Operating Report No. 96-08 Page 7 of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 9-03-96 Completed by: J. D. Kilmer Telephone: (804) 365-2792 MONTH: August, 1996 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 813 17 809 2 810 18 806 3 806 19 805 4 801 20 805 5 808 21 807 6 811 22 806 7 811 23 803 8 810 24 803 9 811 25 803 10 811 26 803 11 811 27 800 12 811 28 800 13 813 29 802 14 812 30 802 15 808 31 804 16 808 INSTRUCTIONS On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.

  • e Surry Monthly Operating Report No. 96-08 Page 8 of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 9-03-96 Completed by: J. D. Kilmer Telephone: (804) 365-2792 MONTH: August, 1996 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 747 17 816 2 793 18 810 3 435 19 812 4 0 20 810 5 439 21 813 6 808 22 814 7 809 23 811 8 808 24 811 9 810 25 811 10 803 26 810 11 809 27 596 12 818 28 812 13 816 29 811 14 817 30 810 15 813 31 810 16 812 INSTRUCTIONS On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.
  • e Surry Monthly Operating Report No. 96-08 Page 9 of 20

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: August, 1996 The following 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:

8/1/96 0000 The reporting period began with the unit operating at 100% power, 840 MWe 8/31/96 2400 The reporting period ended with the unit operating at 100% power, 835 MWe UNITTWO:

8/01/96 0000 The reporting period began with the unit operating at 100% power, 825 MWe 0447 Started power reduction after removing 2-CW-E-1A for waterbox cleaning 0543 Stopped power reduction at 86%, 712 MWe 1408 Started power increase 1718 Stopped power increase at 100%, 830 MWe 8/03/96 0410 Started power reduction for 2-CW-E-1 B waterbox cleaning 0506 Stopped power reduction at 86%, 705 MWe to adjust IRPls 0550 Started power reduction to reduce governor valve oscillations 0603 Started power increase from 60%. Power reduction ineffective in reducing governor valve oscillations.

1100 Stopped power increase at 88%, 730 MWe with the #1 governor valve full open 1505 Manual Reactor Trip from 88% due to Main Steam governor and intercept valves going closed due to loss of EHC pressure 8/05/96 0150 Reactor Critical, started power increase 0542 Generator on-line 0720 Hold unit ramp at 36%, 275 MWe 0816 Continue power increase 0943 Hold unit ramp at 59%, to start 2nd main feedwater pump 1023 Continue power increase 1217 Hold unit ramp at 70% to perform calorimetric 1441 Continue power increase 2051 Unit at 100% power, 840 MWe 8/27/96 0319 Started power reduction to HSD due to Hi-Hi CLS relay failure 0650 Stopped power reduction at 30% power, 230 MWe, relay maintenance completed 1206 Started power increase after replacement of Hi-Hi CLS relay 1555 Hold power increase at 98%, 830 MWe to stabilize unit 2014 Stopped power increase at 100%, 840 MWe 8/31/96 2400 The reporting period ended with the unit operating at 100% power, 845 MWe

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Surry Monthly Operating Report No. 96-08 Page 10 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1996 NE-1053, Rev. 0 Technical Report 7/25/96 NE-1049, Rev. 0 (Safety Evaluation No.96-100)

Virginia Power performs its own reload core design analysis. Virginia Power currently performs one dimensional neutronics calculations using the NOMAD code. This method, approved by the USNRC in 1986, describes the analytical models and methods as well as the nuclear core design and safety analysis process used by Virginia Power. As part of the in-house performance of reload core design, Virginia Power is committed to improving and enhancing its methodologies and models as additional experience is obtained through their application.

The new NOMAD model is an upgrade and has been qualified by comparison to measured cycle data. No changes are being made to the relationship between systems of components and the core design/safety analysis process. Therefore system operation and component operation will be unchanged due to the use of this model. This change has been evaluated in Technical Reports NE-1049 and NE-1053 and found to provide essentially equivalent results meeting the same reliability factors as the current method.

Therefore, an unreviewed safety question does not exist.

TM S2-96-021 Temporary Modification 7-25-96 (Safety Evaluation No.96-101)

The Temporary Modification installs jumpers required to maintain train "B" of the SI logic circuit during the replacement of Test Switch 2-Sl-PC-455E-TB.

During the time of the test switch replacement, train "A" of SI will function as designed. All work will be done on train "B" of SI only. The work is a like for like switch replacement and there is no change to the design of the SI system, and no change to the existing isolation between trains and secondary plant instrument loops. Loss of the jumpers would not cause an SI signal; if the jumpers were lost the automatic SI from Pressurizer Pressure would not function. All other automatic SI signals and the manual pushbuttons would function for train "B." Both trains of SI will function as designed during the test switch replacement. Therefore, an unreviewed safety question does not exist.

DCP 91-010 Design Change Package 91-010 8-08-96 (Safety Evaluation No.94-105)

Design Change Package 91-010 replaced the in-plant 450 MHz radio system with an 850 MHz system. The new primary system unitizes "trunking" technology with six stationary repeaters. This means the repeaters are not independent, but are shared by all users.

This improves channel availability and, in conjunction with the new antenna system in the Auxiliary and Containment Buildings, improves the quality of reception for all radio units.

e Surry Monthly Operating Report No. 96-08 Page 11 pf 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1996 DCP 95-043 Design Change Package 95-043 8-08-96 (Safety Evaluation No.96-017)

Design Change Package 95-043 replaces the existing 02-CH-MOV-2115B, D valves and operators due to back leakage problems. The existing Aloyco valves were replaced with new Anchor/Darling valves.

The replacement valves are similar stainless steel material, have similar pressure/temperature ratings, have a larger flow coefficient, and are of a superior design exhibited by being leak tight at lower torques. The replacement motor operators have a torque/thrust capability equal to the replaced operators. This is considered a one tor one replacement and has no effect on any evaluated accidents in the safety analysis.

Therefore, an unreviewed safety question does not exist.

DCP 95-029 Design Change Package 95-029 8-08-96 (Safety Evaluation No.95-185 Rev 1)

Design Change Package 94-018 replaces the existing buried fuel oil lines for the Emergency Diesel Generators and the Auxiliary Boiler with 2112 inch seamless schedule 160 carbon steel piping to improve the reliability of the fuel oil system.

This fuel oil line replacement modification does not alter the current Fuel Oil System's functions. It increases reliability of the system by replacing existing questionable buried fuel oil lines with the thicker wall piping. The new piping is coated, tape wrapped, and protected by cathodic protection to protect the new fuel oil lines from external corrosion.

Therefore, an unreviewed safety question does not exist.

DCP 94-018 Design Change Package 94-018 8-08-96 (Safety Evaluation No.95-183 Rev 1)

Design Change Package 94-018 modifies the uninterruptible power supplies (UPS) by installing fuses on the Vital Bus panel feeders and replacing Vital Bus panel feeder breakers with non-automatic switches. The purpose of these modifications is to provide a quick means of isolating a Vital Bus panel from the UPS for an Appendix R event.

The Vital Bus will be de-energized during the installation of the fuses and breakers. The installation will be performed when the reactor vessel is de-fueled. Therefore, an unreviewed safety question does not exist.

1-TOP-RC-4074 Temporary Operating Procedure 8-15-96 (Safety Evaluation No.96-036 Rev 1) 1-RC-TV-1519A was declared inoperable due to erratic stroke times. This action requires the valve to be failed closed to assure containment integrity. However, this valve is the supply valve for primary grade (PG) water to the containment. A jumper hose will be installed between 1-PG-154 and 1-RC-166 to allow PG water to bypass 1-RC-TV-1519A.

The modification will be installed and managed under administrative control. When not required, the isolation valves will be closed. When open, the administrative controls will require continuous monitoring by an operator to ensure closure within 60 seconds of a Containment Isolation Signal. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 96-08 Page 12 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1996 TM 82-96-022 Temporary Modification 8-08-96 (Safety Evaluation No.96-104)

The Unit 2 "C" CW pump lower guide bearing temperature indication module is inoperable and requires replacement. Temporary Modification 82-96-022 installs and removes an electrical jumper. The jumper provides circuit continuity in order to maintain the remainder of the alarm module circuits during the replacement of the alarm module.

The jumpers and leads associated with this activity are rated for the existing voltage and current conditions. Since the components affected by this activity perform no protective or mitigating functions and are not part of the safety related ESWP controls, this activity does not effect any accidents or equipment malfunction analysis. Therefore, an unreviewed safety question does not exist.

FS 96-07 Deviation Report 8-19-96 (Safety Evaluation 96-105)

The annunicator "Rod Bank D Lo Limit" (2G-G8} does not flash when tested. UFSAR section 7.2.2.6 states "An insertion limit monitor with two alarm setpoints is provided for the control banks." Annunicator 2G-G8 does not provide a safety related alarm function and annunicator "Rod Bank D Extra Lo Limit" (2G-H8) remains operable. Alternate indication of "D" bank rods is available in the Main Control Room. No credit is taken for operator actions in the SAR, with the exception of the boron dilution event.

No compensatory measures are required due to the loss of 2G-G8. Redundant indication is available to ensure prompt response and termination of a boron dilution event.

Therefore, an unreviewed safety question does not exist.

TM 82-96-023 Temporary Modification 8-08-96 (Safety Evaluation No.96-106)

This TM installs an electrical jumper between panel 2-CP-PNL-1A and relay HC-D. The jumper maintains electrical continuity while relay AC-D is being replaced. Relay AC-D is the auto control relay for the D polisher.

Polisher 2 D will be out of service when relay AC-D is replaced. Failure of the TM will not affect flow through the polishers. The probability or consequence of an accident is not increased by the performance of this TM and the margin of safety as defined in any basis for Technical Specifications is not reduced. Therefore, an unreviewed safety question does not exist.

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Surry Monthly Operating Report No. 96-08 Page 13 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1996 TM 81-96-015 Temporary Modification 8-22-96 (Safety Evaluation No. 96-107A)

Temporary Modification 81-96-015 installed electrical jumpers to prevent Chilled Water Refrigeration Unit 1-CD-REF-1 A from tripping as a result of a spurious high bearing oil temperature indication until the chiller's sensor can be replaced. This TM removes the trip function but the sensor is still capable of being used for indication only.

1-CD-REF-1 A is not safety-related and is not used to mitigate the consequences of accidents described in the UFSAR. Automatic chiller trip functions remained operable during this activity. Double verification of jumper installation/removal and post maintenance testing were performed. Therefore, an unreviewed safety question does not exist.

TM 81-96-014 Temporary Modification 8-26-96 (Safety Evaluation No.96-108)

Crossunder safeties 1-MS-SV-1098 and 1118 have begun to lift during steady state conditions. The purpose of this TM is to temporarily gag these valves until they can be reset to the proper lift setpoint.

The crossunder safety valves are non-safety related valves that are intended for equipment protection only and have no nuclear safety significance. The 100% power steam flow rate through the high pressure turbine to the main steam reheaters is about 8,979,432 lbs/hr. This flow rate is less than the total relieving capacity available even with crossunder safeties 1-MS-SV-1098 and 1118 gagged. Therefore, an unreviewed safety question does not exist.

TM 82-96-025 Temporary Modification 8-08-96 (Safety Evaluation No.96-109)

This TM installs jumpers in the Unit 2 Train "A" Hi Hi CLS to allow the replacement of test relay 3-CLS-2AM-X.

The affected train remains in "test" during this evolution. The train "B" Hi Hi CLS is not affected during this activity and compliance with Technical Specifications will be maintained. Additionally, a valid Hi Hi CLS actuation of Train "B" will cause the train "A" system to be removed from test and actuate Hi Hi CLS. Therefore, an unreviewed safety question does not exist.

TM 81-96-016 Temporary Modification 8-27-96 (Safety Evaluation No.96-111)

This TM connects a recorder in line with the Robertshaw Fire Detection Display panel to measure the line voltage to the panel for troubleshooting purposes.

The Robertshaw panel is classified NSQ for Appendix R and is not classified as safety related. Trouble indication is maintained at the control panels in the event of loss of power, undervoltage, shorted/open circuits, or ground faults. If the recorder fails, causing a fault with the line voltage, the equipment can detect the problem and action can be taken. The fire protection indication system has a battery backup so indication is still available. Based on the above, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 96-08 Page 14 of 20 FACILITY CHANGES THAT DID Nor REQUIRE NRC APPROVAL MONTHNEAR: August, 1996 TM 82-96-026 Temporary Modification 8-29-96 (Safety Evaluation No.96-113)

This TM removes the motor stator covers for 2-RC-P-1 C to allow additional airflow through the motor. Currently, the motor stator temperature is rising and nearing the point which would require securing the motor. Test data indicates that air flow through the motor stator cooler is restricted. The removal of the motor stator cooler inspection covers will allow air to bypass the cooler, and, if the restriction is in the cooler, increase the air flow through the motor.

The removal of the motor stator cooler inspection covers will not affect the probability of any analyzed equipment malfunctions or create new malfunctions. Although the bulk air temperature in containment is expected to increase with the removal of the covers, the resulting maximum temperature will remain below the maximum analyzed temperature of 120°F. This will not result in any condition that will affect the operation of plant equipment. Based on the above, an unreviewed safety question does not exist.

Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 96-08 Page 15 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1996 OP-4.19 Operating Procedures 8-05-96 (Safety Evaluation No.96-103)

UFSAR section 9B.1.6, Movement of Heavy Loads, states "it (the irradiated sample shipping cask) is lowered into the spent fuel shipping cask area of the spent fuel pool." If this sentence is read out of context, it may be misconstrued that the UFSAR statement implies that the shipping cask is only loaded underwater. Procedure OP-4.19 will allow the cask to be loaded either underwater or above water.

The cask loading evolution is controlled by procedure (OP-4.19) and Radiation Work Permit (RWP). The cask transport crane does not allow the shipping cask to be carried above the spent fuel. The RWP specifies alarm limits, ensures radiological conditions will remain acceptable, and requires that Health Physics coverage is provided to terminate the evolution if abnormal or unexpected radiological conditions are encountered. The proposed operations do not increase the probability of occurrence or the consequences of any accident previously evaluated in the UFSAR. The margin of safety is not reduced by the proposed operation. Therefore, an unreviewed safety question does not exist.

OP-4.19 Operating Procedures 8-05-96 (Safety Evaluation No.96-103 Rev. 1)

Revision 1 of the above evaluation excludes the requirements for the fuel building to be on filtered exhaust if the cask is not carried over the fuel pool (i.e., above water loading).

1/2-MOP-36.5 Maintenance Operating Procedure 8-19-96 (Safety Evaluation No.96-107)

Maintenance Operating Procedure 1/2-MOP-36.5 "Secondary Plant Air lnleakage Inspection" will be changed to include a gas injection hose and rig to be attached to each waterbox differential pressure indicator high side vent valve. This temporary modification is procedurally controlled and will be used to inject Sulfur Hexafluoride (SF-6) during normal operation to identify condenser tube leakage.

The temporary modification will be performed when the waterbox is in-service. The gas injection pressure will be maintained below 25 psi by the injection regulator to ensure against any possible overpressurization of the circulating water lines and expansion joints. Precautions provided in 1/2-MOP-36.5 to inject tracer gas into the main condenser will ensure no increase in the consequence or possibility of an accident. No limits specified in Technical Specification are affected by this temporary modification. The margin of safety as defined by Technical Specifications will not be reduced by this activity. Therefore, an unreviewed safety question does not exist.

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Surry Monthly Operating Report No. 96-08 Page 16 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1996 0/1/2-0PT-EG-001 Operations Periodic Test Procedure (OPT) 8-27-96 1/2-0PT-EG-003 Operating Procedures (OP) 0/1/2-0PT-EG-008 (Safety Evaluation No.96-110) 0/1/2-0PT-EG-009 0/1/2-0P-EG-001 Jumpers and temporary modifications are needed to functionally verify the operation of Emergency Diesel Generator redundant start circuits, interlocks that only function in auto, and backup fuel level switches following maintenance, repairs, troubleshooting, and inspections.

Precautions provided in the procedures will ensure no increase in the consequence or possibility of an accident. No limits specified in Technical Specification are affected by this temporary modification. The margin of safety as defined by Technical Specifications will not be reduced by this activity. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 96-08 Page 17 of 20 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1996 None During the Reporting Period

e e Surry Monthly Operating Report No. 96-08 Page 18 of 20 CHEMISTRY REPORT MONTH/YEAR: August, 1996 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avq. Max. Min. Avq.

Gross Radioactivity, µCi/ml 9.34E-1 4.82E-1 6.76E-1 2.02E-1 6.30E-2 1.37E-1 Suspended Solids, ppm - - - 0.050 ~0.010 0.023 Gross Tritium, µCi/ml 5.82E-1 5.23E-1 5.51 E-1 5.46E-1 4.41E-1 4.94E-1 1131, µCi/ml 8.21 E-3 3.18E-3 5.39E-3 4.11 E-4 2.12E-5 9.02E-5 113111133 0.68 0.36 0.52 0.20 0.05 0.10 Hvdroqen, cc/kq 39.7 37.3 38.6 37.3 15.6 27.9 Lithium, ppm 2.33 2.07 2.21 2.66 2.00 2.27 Boron - 10, oom* 118.2 102.1 110.0 324.2 239.1 268.2 Oxygen, (DO), ppm ~0.005. ~0.005 ~0.005 ~0.005 ~0.005 ~Q.005 Chloride, ppm ~0.050 0.003 0.008 ~0.050 0.005 0.008 pH at 25 deqree Celsius 6.85 6.54 6.74 6.40 5.85 6.15

None

e Surry Monthly Operating Report u No. 96-08 Page 19 of 20 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: August, 1996 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity No Fuel Received or Stored During the Reporting Period

}

e Surry Monthly Operating Report No. 96-08 Page 20 of 20 DESCRIPTION OF PERIODIC TEST{S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: August, 1996 None During the Reporting Period

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