ML18153A457

Monthly Operating Repts for Apr 1996 for Surry Power Station Units 1 & 2

ML18153A457
Person / Time
Site:	Surry
Issue date:	04/30/1996
From:	Bowling M, Mason D, Olsen C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-263, NUDOCS 9605200391
Download: ML18153A457 (22)

Text

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 13, 1996 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.

NO/RPC:vlh Docket Nos.

License Nos.96-263 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of April 1996.

Very truly yours, M~oi~ger Nuclear Licensing & 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 960520039i-960430 PDR ADOCK 05000280 R

PDR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 96-04 Approved:

--..J.J\\~1~-~~a~~~-- ~-- J.3.*'I-G Station Manager Date

TABLE OF CONTENTS Section tlurry Monthly Operating Report No. 96-04 Page 2 of 21 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........................................... 14 Tests and Experiments That Did Not Require NRG 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

OPERATING DATA REPORT 41urry Monthly Operating Report No. 96-04 Page 3 of 21 Docket No.:

Date:

Completed By:

50-280 5°01-96 D. Mason Telephone:

(804) 365-2459 1. Unit Name:...................................................

2.

Reporting Period:..........................................

3.

Licensed Thermal Power (MWt):.......................

4.

Nameplate Rating (Gross MWe):.......................

5.

Design Electrical Rating (Net MWe):..................

6.

Maximum Dependable Capacity (Gross MWe):....

7.

Maximum Dependable Capacity (Net MWe):........

Surry Unit 1 April, 1996 2546 847.5 788 840 801

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:

11.

Hours In Reporting Period..........................

12.

Number of Hours Reactor Was Critical..........

13.

Reactor Reserve Shutdown Hours...............

14.

Hours Generator On-Line...........................

15.

Unit Reserve Shutdown Hours.....................

16.

Gross Thermal Energy Generated (MWH)......

17.

Gross Electrical Energy Generated (MWH)....

18.

Net Electrical Energy Generated (MWH)........

19.

Unit Service Factor...................................

20.

Unit Availability Factor...............................

21.

Unit Capacity Factor (Using MDC Net)...........

22.

Unit Capacity Factor (Using DER Net)...........

23.

Unit Forced Outage Rate............................

This Month 719.0 719.0 0.0 719.0 0.0 1827763.2 609740.0 590295.0 100.0%

100.0%

102.5%

104.2%

0.0%

YTD 2903.0 2903.0 0.0 2903.0 0.0 7376250.9 2466890.0 2388051.0 100.0%

100.0%

102.7%

104.4%

0.0%

Cumulative 204743.0 140953.7 3774.5 138650.0 3736.2 323774043.4 106044073.0 100844024. 0 67.7%

69.5%

63.4%

62.5%

15.8%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25. If Shut Down at End of Report Period, Estimated Date of Start-up:

26. Unit In Test Status (Prior to Commercial Operation):

FORECAST INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED

OPERATING DATA REPORT tlurry Monthly Operating Report No. 96-04 Page 4 of 21 Docket No.:

50-281 5-01-96 D. Mason Date:

Completed By:

Telephone:

(804) 365-2459 1. Unit Name:...................................................

2.

Reporting Period:..........................................

3.

Licensed Thermal Power (MWt):.......................

4.

Nameplate Rating (Gross MWe):.......................

5.

Design Electrical Rating (Net MWe):..................

6.

Maximum Dependable Capacity (Gross MWe):....

7.

Maximum Dependable Capacity (Net MWe):........

Surry Unit 2 April, 1996 2546 847.5 788 840 801

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:

11.

Hours In Reporting Period..........................

12.

Number of Hours Reactor Was Critical..........

13.

Reactor Reserve Shutdown Hours...............

14. Hours Generator On-Line...........................

15.

Unit Reserve Shutdown Hours.....................

16.

Gross Thermal Energy Generated (MWH)......

17. Gross Electrical Energy Generated (MWH)....

18. Net Electrical Energy Generated (MWH)........

19.

Unit Service Factor...................................

20.

Unit Availability Factor...............................

21.

Unit Capacity Factor (Using MDC Net)...........

22.

Unit Capacity Factor (Using DER Net)...........

23.

Unit Forced Outage Rate............................

This Month 719.0 719.0 0.0 719.0 0.0 1829413.1 608950.0 589969.0 100.0%

100.0%

102.4%

104.1%

0.0%

YfD 2903.0 2816.8 0.0 2810.1 0.0 7088390.0 2362215.0 2287054.0 96.8%

96.8%

98.4%

100.0 %

3.2%

Cumulative 201623.0 138319.7 328.1 136366.2 0.0 319623444.0 104517859.0 99397469.0 67.6%

67.6%

63.2%

62.6%

12.8%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, May 3, 1996, 37 Days

25. If Shut Down at End of Report Period, Estimated Date of Start-up:

26. Unit In Test Status (Prior to Commercial Operation):

FORECAST INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION June 9, 1996 ACHIEVED

4lurry Monthly Operating Report No. 96-04 Page 5 of 21 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORTMONTH: April, 1996 (1)

(2)

(3)

(4)

(5)

Method Docket No.:

50-280 Unit Name:

Surry Unit 1 Date:

5-01-96 Completed by:

Craig Olsen Telephone:

(804) 365-2155 Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No.

Code Code Prevent Recurrence 4/24/96 N/A N/A (1)

F:

Forced S:

Scheduled B

(2)

REASON:

Down Rx N/A N/A A

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction TA TRB E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

(4)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

Ramp Unit from 100% to 71 %

to test the reheat/intercept valve (3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

(1) tlurry Monthly Operating Report No. 96-04 Page 6 of 21 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL TO OR GREATER THAN 20%)

REPORT MONTH: April, 1996 Docket No.:

50-281 Unit Name:

Surry Unit 2 Date:

5-01-96 Completed by:

Craig Olsen Telephone:

(804) 365-2155 (2)

(3)

(4)

(5)

Method Duration of LER No.

System Component Cause & Corrective Action to Date Type Hours Reason Shutting Code Code Prevent Recurrence (1)

F:

Forced S:

Scheduled (4)

(2)

REASON:

Down Rx None During the Reporting Period A

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

MONTH:

April, 1996 Day 2

3 4

5 6

7 8

9 10 11 12 13 14 15 16 INSTRUCTIONS e

-urry Monthly Operating Report No. 96-04 Page 7 of 21 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe-Net)

Day 825 17 825 18 825 19 825 20 823 21 823 22 823 23 825 24 825 25 825 26 822 27 822 28 825 29 826 30 825 820 Docket No.: 50-280 Unit Name:

Surry Unit 1 Date: 5-06-96 Completed by:

John D. Kilmer Telephone: (804) 365-2792 Average Daily Power Level (MWe-Net) 824 808 825 824 823 822 818 780 819 821 821 820 820 820 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.

AVERAGE DAILY UNIT POWER MONTH:

April, 1996 Average Daily Power Level Day (MWe-Net)

Day 1

816 17 2

815 18 3

824 19 4

816 20 5

826 21 6

826 22 7

828 23 8

826 24 9

824 25 10 826 26 11 826 27 12 826 28 13 824 29 14 823 30 15 824 16 821 INSTRUCTIONS LEVEL

~urry Monthly Operating Report No. 96-04 Page 8 of 21 Docket No.: 50-281 Unit Name:

Surry Unit 2 Date: 5°06-96 Completed by:

John D. Kilmer Telephone: (804) 365-2792 Average Daily Power Level (MWe - Net) 824 825 825 824 824 822 823 816 805 813 812 812 810 809 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.

~urry Monthly Operating Report No. 96-04 Page 9 of 21

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: April, 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:

4/01/96 0000 The reporting period began with the unit operating at 100% power, 850 MWe.

4/15/96 1322 During the performance of 1-IPT-RC-P-403, the enable/disable keyswitch was inadvertently placed in the enable position. This caused 1-RC-PCV-1455C to open. The lowest observed RCS pressure was 2208 psig.

4/24/96 0943 Commence ramp down to perform 1-0SP-TM-001 1030 Stop ramp at 90%, 770 MWe 1241 Commence ramp down 1418 Stop ramp at 71%, 616 MWe 1516 Commence ramp up to full power following successful completion of 1-0SP-TM-001 4/30/96 2400 The reporting period ended with the unit operating at 100% power, 850 MWe.

UNIT TWO:

4/01/96 0000 The reporting period began with the unit operating at 100% power, 835 MWe.

4/30/96 2400 The reporting period ended with the unit operating at 100% power, 835 MWe.

FS 96-09 FS 96-15 DCP 90-24

~urry Monthly Operating Report No. 96-04 Page 10 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April, 1996 Updated Final Safety Analysis Report Change (Safety Evaluation No.96-035) 4-1-96 U FSAR Change 96-09 revised Section 6.2.4.1.4, "Normal Operations," and 6.3.1.5.2, "Recirculation Spray Subsystem," to reflect that Unit 1 and Unit 2 containment recirculating spray sumps are maintained in a wet condition. This practice reduces the potential of pressure locking the LHSI pump suction MOVs 1/2-SI-MOV-1860A/B and 1/2-Sl-MOV-2860A/B.

The change is consistent with the affected system's design basis and the appropriate piping and sump lining material application. The current station practice of maintaining a water loop in these lines is an effective means of eliminating the potential for pressure locking of the LHSI valves. The amount of Primary Grade water added by this practice is negligible when compared to the RWST volume which would be added following an accident requiring safety injection. Therefore, an unreviewed safety question does not exist.

Updated Final Safety Analysis Report Change (Safety Evaluation No. 96-036A) 4-4-96 UFSAR Change 96-15 revises Section 9.5.1, "Spent Fuel Pool (SFP) Cooling - Design Basis," to maintain the SFP water temperature below 140°F during normal refueling operations commencing 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown and to maintain the SFP water temperature below 170°F during abnormal refueling operations commencing 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> after shutdown. No physical modifications to the SFP cooling system are required to meet the capability requirements described in the UFSAR change.

An evaluation was performed which shows the SFP cooling system has the capability to meet the above requirements for current operating conditions including full core offloads as a normal refueling practice.

The maximum heat loads were determined for two scenarios, back to back refuelings and non-back to back refuelings. The consequences of all the accidents considered in the design and licensing basis remain bounded by the results of the current analyses. Therefore, an unreviewed safety question does not exist.

Design Change Package (Safety Evaluation No.90-202) 4-9-96 This Design Change Package repaired ductwork and replaced dampers for fans 1-VS-F-2, 12A and 128. This work was in response to Notice of Violation IEIR 89-32. The change re-establishes radiation monitoring equipment at vent stack No. 1. An Linreviewed safety question did not exist since the change restored the service building ventilation effluent path to vent stack No. 1

TM S 1-96-006 FS 96-02 DCP 93-072-3 Rev. 3 e

Surry Monthly Operating Report FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April, 1996 Temporary Modification (Safety Evaluation No.96-038)

No. 96-04 Page 11 of 21 4-11-96 Temporary Modification (TM) S1-96-006 connects a calibrated 250 ohm resistor in series in the Boron Recovery Tank (BRT) level instrumentation loop. This will allow a chart recorder to be connected across the resistor for more precise monitoring of the BRT level during RCS draining evolutions.

The installed level indication is unaffected by this TM. The TM does not increase the probability of a malfunction of equipment important to safety or reduce the margin of safety as defined in the Technical Specifications. Therefore, an unreviewed safety question does not exist.

Updated Final Safety Analysis Report Change (Safety Evaluation No.96-039) 4-15-96 UFSAR Change 96-02 revises Section 6.2.3.12, "Combustible Gas Control in Containment," to delete references to the estimated quantities of zinc and aluminum in the containment from the text and from Table 6.15. Instead Section 6.2.3.12 will state that the inventories of zinc and aluminum in containment are controlled below maximum allowable levels.

The quantities of zinc and aluminum in containment are currently controlled by Engineering Standard STD-MAT-0006, and baseline inventories are updated annually in accordance with Technical Report MT-0002, "Inventory: Banned/Restricted Engineered Materials Installed In Containment." This change is administrative in nature and does not increase the probability of a malfunction of equipment important to safety or reduce the margin of safety as defined in the Technical Specifications. Therefore, an unreviewed safety question does not exist.

Design Change Package (Safety Evaluation No.96-040) 4-15-96 Design Change Package 93-072-3 Rev. 3 modified the non-safety related 555 Ton Containment Cooling Chiller setpoint actuation circuitry so the motor bearing temperature sensing devices will not trip the chillers, but instead will only provide local indication and control room annunciation. Presently, spurious activation of two temperature sensing modules are tripping the chillers unnecessarily.

Since the 555 Ton Containment Cooling Chillers are non-safety related and activation of the other safety setpoints are still capable of automatically tripping the chillers, an unreviewed safety question does not exist. This modification does not alter any safety related components and will eliminate spurious trips thereby reducing operator distractions and challenges.

DCP 96-004 DCP 93-033-3, Field Change 13 SE 96-044 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MoNTHNEAR: April, 1996 Design Change Package (Safety Evaluation No.96-042)

Surry Monthly Operating Report No. 96-04 Page 12 of 21 4-18-96 Design Change Package 96-004 will install new insulation on the pressurizer below the 55' 6" elevation. Currently, most insulation located in this area is the insulation that was originally supplied during construction. The insulation being replaced has deteriorated, exhibits degraded thermal performance and is creating a personnel safety hazard when sections are removed.

The new pressurizer insulation system will perform slightly better than the orginial insulation being replaced and will not increase the heat loading in the containment. The insulation system is seismically supported and will not increase the potential for containment sump blockage following a LOCA. Therefore, an unreviewed safety question does not exist.

Design Change Package (Safety Evaluation No.96-043) 4-22-96 Design Change Package 93-033-3 will provide additional restraints to the MCCs, 4160 V Switchgear and l&C cabinets ensuring that these components will remain operable during a seismic event.

Modifications will be made by following NSS Maintenance procedures. The modifications will not alter the operation of the equipment. Therefore, an unreviewed safety question does not exist.

Safety Evaluation 4-22-96 Safety Evaluation 96-044 evaluates the Unit 2 Cycle 14 reload core. This evaluation included the use of advanced alloy, ZIRLO, for cladding and most skeleton components in place of Zircaloy-4, minor dimensional changes to fuel rod assemblies due to ZlRLO. In addition, alternate mixing vane grids, in the reload batch, are no longer rotated.

Parameters affected by the reload were calculated and compared to the existing safety analysis assumptions. These parameters were shown to be either 1) explicitly bounded or 2) accommodated by existing safety analysis margins and/or conservatism. Operation of the reload core in accordance with the Technical Specifications will not violate the design basis of plant safety equipment. Thus, the probabilities and consequences of analyzed accidents and equipment malfunctions are not changed by the reload.

Therefore, an unreviewed safety question does not exist.

FS 96-20 Surry Monthly Operating Report FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1996 Updated Final Safety Analysis Report Change (Safety Evaluation No.96-053)

No. 96-04 Page 13 of 21 4-25-96 UFSAR Change 96-20 revises Section11.3.2.5, "Fuel Handling Shielding," by revising the minimum height requirement above the fuel assembly in the Spent Fuel Pool and in the Reactor Cavity during fuel movement. The minimum water height is being changed from 96 inches to 84 inches above a fuel assembly in the Spent Fuel Pool and in the Reactor Cavity during fuel movement.

A calculation was performed and determined the minimum water shielding height, which will bound actual plant refueling operations and provide sufficient shielding to maintain the surface dose rate below 50 mR/hr value specified, is 84 inches. The changes to the UFSAR will have no impact on those systems that are required to mitigate the consequences of a fuel handling accident and will not reduce the margin of safety.

Therefore, an unreviewed safety question does not exist.

1-TOP-4033 O-CSP-HRS-004 1 [2]-GOP-2.1 1 [2]-0P-RC-012 CH-93.120

~urry Monthly Operating Report No. 96-04 Page 14 of 21 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1996 Temporary Operating Procedures (Safety Evaluation No.96-036) 4-1-96 Temporary Operating Procedure, 1-TOP-4033, installs and removes a jumper. The jumper is located between 1-PG-154 and 1-RC-166 and bypasses the inoperable valve 1-RC-TV-1519A.

In the event a containment isolation signal is received, appropriate administrative controls are provided to ensure closure of 1-RC-TV-1519A within 60 seconds of notification. The inside containment isolation valve, 1-RC-160, is a check valve and will provide containment isolation until the isolation valves for the modification can be closed. The margin of safety as described in the Technical Specifications are not affected. Therefore, an unreviewed safety question does not exist.

Chemistry Surveillance Procedure (Safety Evaluation No.96-037) 4-8-96 Chemistry Surveillance Procedure O-CSP-HRS-004, "High Radiation Sampling System Waste Tank, Valve Test for Post Accident Conditions," will be re-formatted to ensure that steps establishing administrative control of containment isolation valves 1-GW-TV-102, 103 and 2-GW-TV-206, 207 are appropriately documented and in accordance with SUADM-0-26, "Administrative Control of Operational Equipment." These valves are non-automatic containment isolation valves and do not receive automatic containment isolation signal.

The specified valves are required to be closed to maintain post accident containment integrity. If they are opened during testing, administrative controls are established. The Main Control Room will notify the operator, who has assumed administrative control, to close the containment isolation valves within 40 seconds of the safety injection signal.

This revision does not change the operating mode of the subject valves or system. The margin of safety as described in the Technical Specifications are not affected. Therefore, an unreviewed safety question does not exist.

General Operating Procedure Operating Procedure Chemistry Procedure (Safety Evaluation No.96-041) 4-18-96 The procedure changes will allow addition of nitrogen gas into the Volume Control Tank (VCT) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reactor shutdown. The proposed activity is recommended by Westinghouse to reduce the RCS dissolved hydrogen inventory to~ 15 cc/Kg within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to reactor shutdown. This activity will reduce the amount of time required to degas.

RCS system chemistry will be monitored and controlled to maintain dissolved hydrogen and pH within currently approved bounds. Therefore, an unreviewed safety question does not exist.

1/2-0PT-81-022 O-MOP-VS-016 O-MOP-VS-017

~urry Monthly Operating Report No. 96-04 Page 15 of 21 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1996 Operations Periodic Test Procedure (Safety Evaluation No.96-045) 4-22-96 Operations Periodic Test Procedure, 1/2-0PT-81-022, "SI Accumulator Discharge Check Valve Test with Reactor Head Removed," will be used to verify proper operation in the open direction of the SI accumulator discharge check valves during a refueling outage by discharging the accumulator contents into the reactor cavity.

All equipment and systems involved in this activity will be operated well within their design limitations. The maximum flow rates expected to occur as a result of the accumulator discharge are well below the design flow rates of the RCS. Therefore, an unreviewed safety question does not exist.

Maintenance Operating Procedures (Safety Evaluation No.96-046) 4-25-96

_Maintenance Operating Procedures, O-MOP-VS-016, "Connecting Hard Duct for Purging Either Containment With 1-VS-F-59 and Swapping the Line Blind," and O-MOP-VS-017, "Disconnecting Hard Duct for Purging Either Containment With 1-VS-F-59 and Swapping the Line Blind," are being revised to provide instructions for the installation, operation and removal of flex connections Uumper) between the hard duct jumper and the containment purge and auxiliary building general exhaust filter 1-VS-FL-14.

Use of the jumper minimizes refueling activity impact on safety related filters by allowing containment purge to flow through a non-safety charcoal filter except when fuel is being handled inside containment.

The jumper is hard ducted and supported as directed by Engineering Transmittal 895-0230 and DCP 94-069. Areas served by the Auxiliary Building Central Exhaust System are not impacted by this jumper. Therefore, an unreviewed safety question does not exist.

1 (2)-MOP-EP-30 1 (2)-MOP-EP-31 1 (2)-MOP-EP-204 1 (2)-MOP-EP-205 1 (2)-MOP-EP-206 1 (2)-MOP-EP-207 2-0SP-SW-007 ROP-1.85 ROP-1.86 ROP-1.87 e

tlurry Monthly Operating Report No. 96-04 Page 16 of 21 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1996 Maintenance Operating Procedures (Safety Evaluation No.96-047) 4-25-96 Maintenance Operating Procedures 1 (2)-MOP-EP-30, "A Main Station Battery Remove/Return to Service," 1 (2)-MOP-EP-31, "B Main Station Battery Remove/Return to Service," 1 (2)-MOP-EP-204, "Remove "H" Emergency Bus From Service," 1 (2)-MOP-EP-205, "Remove "J" Emergency Bus From Service," 1 (2)-MOP-EP-206, "Return "H" Emergency Bus to Service," and 1 (2)-MOP-EP-207, "Return "J" Emergency Bus to Service," were evaluated for the performance of Main Station Battery (MSB) charges at a high rate during refueling outages. This evaluation was performed because the MSB must be determinated and charged for approximately 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br />. This action will be performed both when the reactor is de-fueled and fueled.

The activity does not affect the offsite power system, therefore it does not increase the probability of a loss of offsite power. The activity requires two operable trains of shutdown cooling, two operable Emergency buses, a vessel level :2'.. 16.25 ft and an operable "H" bus.

Therefore, there is no increase in the consequences of a loss of offsite power. Technical Specification 3.16 limits operation with one MSB to cold shutdown. Due to common mode failure, lack of redundancy and independence considerations, the cross-tied MSBs can be regarded as one battery. However, as an additional margin of safety, the performance of the activity is restricted to either a vessel level :2'.. 16.25 ft or a defueled vessel. The margin of safety as described in the Technical Specifications is not affected. Therefore, an unreviewed safety question does not exist.

Operations Surveillance Procedure (Safety Evaluation No.96-048) 4-26-96 Operations Surveillance Procedure 2-0SP-SW-007, "Service Water Flow Test of Recirculation Spray Heat Exchangers 2-RS-E-1 A/D," was developed to collect performance data and verify operability of the system.

This test does not constitute an unreviewed safety question since the Reactor Coolant System will be at conditions less than 350°F and 450 psig, and the Recirc Spray System is not required to be operable at these conditions.

Radwaste Operating Procedures (Safety Evaluation No.96-049) 4-29-96 Radwaste Operating Procedures ROP-1.85, "Installing Temporary Hose for Transferring Liquid Waste From the Evaporator Bottoms Tank to a Strong Tight Container," ROP-1.86, "Removing Temporary Hose for Transferring Liquid Waste From the Evaporator Bottoms Tank to a Strong Tight Container," and ROP-1.87, "Transferring Liquid Waste From the Evaporator Bottoms Tank to a Strong Tight Container were developed to allow the transfer of liquid waste from the evaporator bottoms tank to a strong tight container and liquid tight container at the Surry Radwaste Facility (SRF). This transfer is required due to a higher than anticipated conductivity of the waste water to be processed at the SRF.

The margin of safety as stated in the Technical Specifications (TS) is not affected by the modification. The material being transferred is not flammable and will not affect any fire related equipment. Therefore, an unreviewed safety question does not exist.

1-TOP-4044 2-0PT-FW-007 O-OP-SA-1 Surry Monthly Operating Report No. 96-04 Page 17 of 21 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1996 Temporary Operating Procedures (Safety Evaluation No.96-036) 4-29-96 Temporary Operating Procedure, 1-TOP-4044, will be used to apply air pressure to the Recirc Spray Heat Exchangers to assist in the draining of the heat exchangers. Use of the normal drain path would take up to 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> to drain the heat exchangers.

The unit will be at cold shutdown conditions when the Temporary Operating Procedure is performed. The procedure requires pressure to be maintained less than 20 psig, which is below the upper limit of the low pressure component of the system - a rubber expansion joint (REJ).

If a failure of the REJ does occur, the resultant volume of water (approximately 40,000 gals) is not a significant flood concern and will not create an unsafe condition. Therefore, an unreviewed safety question does not exist.

Operations Periodic Test Procedure (Safety Evaluation No.96-052) 4-29-96 Safety Evaluation 96-052 addressed 2-0PT-FW-007,"Turbine Driven AFW Pump Steam Supply Line Check Valve Test," to determine if any unreviewed safety question exists because of the degraded condition of 2-MS-120. This condition is due to the partially closed position of steam supply valve 2-MS-120 from the 'B' steam generator (S/G).

No severe impact on the SIG Tube Rupture accident assumptions exists due to the inability to fully close 2-MS-120. The basic assumption during this accident scenario is that isolation of a ruptured S/G does not occur for 30 minutes due to an assumed stuck open S/G PORV. E-3, S/G Tube Rupture, attempts to isolate a ruptured S/G by closing 2-M-120 (assuming B S/G) at step 30. If this cannot be performed, the step requires a verification of one motor driven AFW Pump being available and closes 2-MS-196, 2-FW-P-2 Steam Supply Manual Header Isolation or trips 2-FW-P-2 by manually tripping the trip and throttle valve. These alternative actions can be accomplished within the 30 minute time requirement. Therefore, an unreviewed safety question does not exist.

Operating Procedure (Safety Evaluation No.96-054) 4-30-96 A one time only PAR has been written against O-OP-SA-1 to align the Sullair diesel driven air compressor to the instrument air system and isolates the Service Air Receivers from the remainder of the Service Air System. This will allow the air dryer repairs on both units.

This alignment will provide adequate air supply to meet the station loads at an acceptable dew point. The Sullair diesel driven air compressor is equipped with its own dryer. This condition will improve the quality of the air going into the station until the dryers are repaired and reduces the volume of water entering the air system from the bypassed dryers. The Sullair diesel driven air compressor will be backed up by the Units 1 and 2 Instrument Air Compressors. This issue is discussed in UFSAR 9.8.2. and is not a Technical Specifications issue. Therefore, an unreviewed safety question does not exist.

Surry Monthly Operating Report No. 96-04 Page 18 of 21 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: April, 1996 None During the Reporting Period

Primarv Coolant Analysis Gross Radioactivity, µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml 1131, µCi/ml 113111133 HydroQen, cc/kg Lithium, ppm Boron - 10, oom*

Oxygen, (DO), ppm Chloride, ppm pH at 25 degree Celsius Boron - 10 = Total Boron x 0.196 Comments:

None CHEMISTRY REPORT MONTHNEAR: April, 1996 Unit No. 1 Max.

Min.

AvQ.

8.37E-1 5.59E-1 6.97E-1

$0.01

$0.01

$0.01 7.89E-1 7.33E-1 7.58E-1 1.38E-2 3.03E-3 4.76E-3 0.58 0.38 0.46 40.2 29.6 37.5 2.31 2.06 2.19 175.0 161.7 167.9

$0.005

$0.005

$0.005 0.006 0.002 0.005 6.72 6.40 6.54 tlurry Monthly Operating Report No. 96-04 Page 19 of 21 Unit No. 2 Max.

Min.

AVQ.

1.82E-1 1.08E-1 1.35E-1

$0.01

$0.Q1

$0.01 1.89E-1 1.51 E-1 1.73E-1 2.16E-4 7.81 E-5 1.39E-4 0.12 0.04 0.08 38.3 31.3 34.5 2.17 1.74 1.97 64.5 47.0 55.3

$0.005

$0.005

$0.005 0.004

$0.001 0.002 7.37 6.97 7.16

New or Spent Fuel Shipment Number Spent Fuel Cask CASTOR V/21 500.11-025.2 Date Stored or Received 4/02/96 e

FUEL HANDLING UNITS 1 & 2 MONTHNEAR: April, 1996 Number of Assemblies Assembly ANSI eer Shiement Number Number 21 OA2 LM04UX ON2 LM06F3 ON5 LM06GC 1B6 LM08LX 1NO LM06FC 1N4 LM06F1 201 LMOALW 2N9 LM06EU 3N1 LM06EQ 3N7 LM06F9 4N7 LM06GG 501 LMOAN4 R10 LMOOTM R12 LMOOU1 R22 LMOOUE R31 LMOOUS R42 LMOOVL R44 LMOOVG R48 LMOOVV R51 LMOOUK V02 LM041P

~urry Monthly Operating Report No. 96-04 Page 20 of 21 New or Spent Initial Fuel Shipping Enrichment Cask Activity 2.90100 3.40600 3.40600 3.21700 3.40600 3.40600 3.58880 3.40600 3.40600 3.40600 3.40600 3.60260 3.09700 3.09700 3.09700 3.09700 3.09700 3.09700 3.09700 3.09700 2.90600

lurry Monthly Operating Report No. 96-04 Page 21 of 21 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: April, 1996 None During the Reporting Period