ML18153A429

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Monthly Operating Repts for Jul 1997 for Surry Power Station,Units 1 & 2.W/970812 Ltr
ML18153A429
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/31/1997
From: Fanguy M, Kilmer J, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
97-465, NUDOCS 9708190026
Download: ML18153A429 (21)
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Text

4 e* e VIRGINIA ELECTRIC AND PowER COMPANY RICHMOND, VIRGINIA 23261 August 12, 1997 United States Nuclear Regulatory Commission Serial No.97-465 Attention: Document Control Desk NUJDK/GDM RO 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 The Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of July 1997 is provided in the attachment.

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

Very truly yours, Attachment cc: U. S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth Street, S. W.

Suite 23T85 Atlanta, Georgia 30303 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

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e eSurry Monthly Operating Report No. 97-07 Page 1 of20 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 97-07 Approved: ~S2(_~_y Station Manager

.. 1'L_'=t7 Date

e Surry Monthly Operating Report No. 97-07 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 Nos. 1 and 2 ............................................................................................. 9 Facility Changes That Did Not Require NRC Approval ............................................................................................ 11 Procedure or Method of Operation Changes That Did Not Require NRC Approval. ................................................ 14 Tests and Experiments That Did Not Require NRC Approval .................................................................................. 16 Chemistry Report ..................................................................................................................................................... 17 Fuel Handling - Unit Nos. 1 and 2 ............................................................................................................................ 18 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ....................................................................................................................... 20

e Surry Monthly Operating Report No. 97-07 Page 3 of 20 OPERATING DATA REPORT Docket No.: 50-280 Date: 08/1/97 Completed By: D. K. Mason Telephone: (804) 365-2459

1. Unit Name: ............................................................ Surry Unit 1
2. Reporting Period: ................................................. . July, 1997
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 5087.0 215711.0
12. Number of Hours Reactor Was Critical. ......... 744.0 3518.1 150352.8
13. Reactor Reserve Shutdown Hours .................. 0.0 0.0 3774.5
14. Hours Generator On-Line .................................. 744.0 3395.5 147926.5
15. Unit Reserve Shutdown Hours ......................... 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ..... 1887869.2 8286649.3 346922093.1
17. Gross Electrical Energy Generated (MWH) .... 617948.0 2747203.0 113720021 .0
18. Net Electrical Energy Generated ...................... 595390.0 2649574.0 108243323.0
19. Unit Service Factor.............................................. 100.0% 66.7% 68.6%
20. Unit Availability Factor......................................... 100.0% 66.7% 70.3%
21. Unit Capacity Factor (Using MDC Net) ............ 99.9% 65.0% 64.5%
22. Unit Capacity Factor (Using DER Net) ............ 101.6% 66.1% 63.7%
23. Unit Forced Outage Rate ................................... 0.0% 7.8% 15.1%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
25. If Shut Down at End of Report Period, Estimated Date of Start-up:
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 97-07 Page 4 of 20 OPERATING DATA REPORT Docket No.: 50-281 Date: 08/01/97 Completed By: D. K. Mason Telephone: (804) 365-2459

1. Unit Name: ........................................................... . Surry Unit 2
2. Reporting Period: ................................................. . July, 1997
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 5087.0 212591.0
12. Number of Hours Reactor Was Critical .......... 744.0 5023.0 148098.6
13. Reactor Reserve Shutdown Hours .................. 0.0 0.0 328.1 -
14. Hours Generator On-Line .................................. 744.0 5016.1 146113.9
15. Unit Reserve Shutdown Hours ......................... 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ..... 1802262.7 12605676.3 344079933.1
17. Gross Electrical Energy Generated (MWH) .... 585070.0 4196690.0 112647489.0
18. Net Electrical Energy Generated ...................... 563718.0 4056836.0 107248715.0
19. Unit Service Factor.............................................. 100.0% 98.6% 68.7%
20. Unit Availability Factor......................................... 100.0% 98.6% 68.7%
21. Unit Capacity Factor (Using MDC Net) ............ 94.6% 99.6% 64.6%
22. Unit Capacity Factor (Using DER Net) ............ 96.2% 101.2% 64.0%
23. Unit Forced Outage Rate ................................... 0.0% 1.4% 12.1%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, October 4, 1997, 30 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 ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

UNIT SHUTDOWN AND POWER REDUCTION

-Surry Monthly Operating Report No. 97-07 Page 5 of 20 (EQUAL To OR GREATER THAN 20%}

REPORT MONTH: July, 1997 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 07-03-97 Completed by: M. J. Fanguy Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to Prevent Recurrence Down Rx None During the Reporting Period (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)

Surry Monthly Operating Report No. 97-07 Page 6 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%}

REPORT MONTH: July, 1997 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 07-03-97 Completed by: M. J. Fanguy Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code Code to Prevent Recurrence Down Rx 07/02/97 s NA B NA NA TA V Ramp due to 2-MS-IV-2 drifting closed.

07/09/97 s NA B NA NA SI COND Ramp down to maintain condenser vacuum while 2-CW-E-1C OOS.

07/20/97 s NA B NA NA SI COND Ramp down to maintain condenser vacuum while 2-CW-E-1 B OOS.

07/24/97 F NA B NA NA SJ p Ramp down for repairs to 2-FW-P-1B.

(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)

e e Surry Monthly Operating Report No. 97-07 Page 7 of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 08-06-97 Completed by: J. D. Kilmer Telephone: (804) 365-2792 MONTH: July, 1997 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 813 17 796 2 812 18 794 3 811 19 796 4 810 20 797 5 810 21 797 6 811 22 795 7 808 23 799 8 802 24 798 9 806 25 801 10 807 26 750 11 806 27 756 12 805 28 807 13 803 29 805 14 801 30 808 15 800 31 809 16 797 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. 97-07 Page 8 of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 08-06-97 Completed by: John D. Kilmer Telephone: (804) 365-2792 MONTH: July, 1997 Average Daily Power Level . Average Daily Power Level Day {MWe - Net) Day {MWe - Net) 796 17 790 2 765 18 789 3 792 19 789 4 788 20 681 5 788 21 807 6 789 22 806 7 715 23 808 8 787 24 535 9 669 25 504 10 675 26 568 11 802 27 815 12 798 28 812 13 796 29 813 14 794 30 816 15 794 31 816 16 789 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.

eSurry Monthly Operating Report No. 97-07 Page 9 of 20

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: July, 1997 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:

07/01/97 0000 Unit 1 begins the month at 100% / 845 MWe.

07/26/97 0603 Start power decrease from 100% I 810 MWe to maintain condenser vacuum after removing 1-CW-E-1A from service.

1400 Stop power decrease at 87% I 734 MWe.

2005 Start power increase from 87% I 734 MWe to 100% after returning 1-CW-E-1A to service.

2130 Stop power increase at 100% / 830 MWe.

07/27/97 0605 Start power decrease to maintain condenser vacuum after removing 1-CW-E-1 D from service.

1800 Stop power decrease at 87% / 700 MWe.

1820 Start power increase from 87% / 700 MWe to 100% after returning 1.-CW-E-1D to service.

1915 Stop power increase at 100% / 830 MWe.

7/31/97 2400 Unit 1 finishes the month at 100% / 840 MWe.

UNIT Two:

07/01/97 0000 Unit 2 begins the month at 100% / 830 MWe.

07/02/97 0949 Start power decrease from 100% / 820 MWe due to 2-MS-IV-2 drifting closed.

1026 Stop power decrease at 92% / 745 MWe to place second letdown orifice in service.

1030 Start power decrease.

1154 Stop power decrease at 71 % / 600 MWe.

1246 Start power increase from 73% / 625 MWe to 100% after successfully performing 2-0SP0TM-001 stroke test on 2-MS-IV-21L.

1800 Stop power increase at 100% / 825 MWe.

07/07/97 0405 Start power decrease from 100% I 815 MWe to maintain condenser vacuum after removing 2-CW-E-1C from service.

0615 Stop power d_ecrease at 84% / 680 MWe.

1636 Start power increase from 87% / 717 MWe to 100%.

1903 Stop power increase at 100% / 818 MWe.

e Surry Monthly Operating Report No. 97-07 Page 10 of 20

SUMMARY

OF OPERATING EXPERIENCE (CONTINUED) 07/09/97 0350 Start power decrease from 100% / 820 MWe to maintain condenser vacuum after removing 2-CW-E-10 from service.

0930 Stop power decrease at 77% I 615 MWe.

1746 Start power increase from 73.5% I 610 MWe after returning 2-CW-E-1 D to service.

2031 Stop power increase at 100% I 821 MWe.

07/10/97 0230 Start power decrease from 100% / 820 MWe to maintain condenser vacuum after removing 2-CW-E-2C from service.

0432 Stop power decrease at 83.5% / 675 MWe.

1303 Start power decrease to maintain condenser vacuum.

1345 Stop power decrease at 82% I 660 MWe.

2108 Start power increase from 83% / 702 to 100% after returning 2-CW-E-2C to service.

2318 Stop power increase at 100% / 836 MWe.

07/20/97 0315 Start power decrease from 100% I 820 MWe to maintain condenser vacuum after removing 2-CW-E-1 B from service.

0514 Stop power decrease at 77% I 630 MWe.

1756 Start power increase from 85% / 730 MWe to 100% after returning 2-CW-E-1 B to service.

1918 Stop power increase at 100% / 840 MWe.

07/24/97 0200 Start power decrease from 100% I 840 MWe for 2-FW-P-1 B repairs.

0458 Stop power decrease at 60% I 495 MWe.

07/26/97 1725 Start power increase from 64% / 545 MWe to 100%.

2343 Stop power increase at 100% / 848 MWe.

07/31/97 2400 Unit 2 finishes the month at 100% / 845 MWe.

e Surry Monthly Operating Report No. 97-07 Page 11 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1997 SE 97-085 Safety Evaluation 7-3-97 Safety Evaluation 97-085 was performed to evaluate the the best method for stabilizing the sample flow rate through the Waste Gas Decay Tank (WGDT) oxygen analyzer 1-GW-AIT-150A. This will be performed using a Supplemental Work Instruction (SWI).

Performance of the SWI will ensure that the oxygen analyzer will not be operated outside of its design capabilities and will not change the concentration, pressure or radioactivity level of the waste gas stored in the system. Additionally, performance of the SWI will not affect the ability to obtain grab samples of the gas stored in the Waste Gas System.

Therefore, an unreviewed safety question does not exist.

SE 97-086 Safety Evaluation 7-7-97 Safety Evaluation 97-086 was performed to evaluate the contamination of the Primary Grade Water (PG) System originally assumed to be uncontaminated. IE Bulletin 80-10 contained provisions to allow continued operation with contaminated non-radioactive systems provided a 10CFR50.59 Safety Evaluation was performed.

The evaluation concluded that with a stuck open relief valve dumping the contents of a PG tank to the storm drains with only minimal Circulating Water/Service Water flowrate, the highest radionuclide activity concentration would be diluted far below the maximum ODCM release levels and the isotopic activity concentrations in the discharge canal would be lower than the 10CFR20 allowable limits. Therefore, an unreviewed safety question does not exist.

JCO 82-97-001, Rev. 3 Justification For Continued Operation 7-7-97 (Safety Evaluation No.97-002 Rev. 3)

This revision to the Justification for Continued Operation (JCO) discusses the Unit 2 letdown weld failure on June 24, 1997 and subsequent repair. Subsequent analysis in accordance with NRG Generic Letter 91-18 requirements have determined that additional interim support is required on the letdown line.

This degraded and non-conforming condition has been reviewed and analyzed. The previous letdown operational restrictions and support modifications made provide reasonable assurance that the letdown piping system and supports meet the structural integrity requirements outlined in Generic Letter 91-18 Section 6.13. Therefore, an unreviewed safety question does not exist.

FS95-043 Updated Final Safety Analysis Report Change 7-10-97 (Safety Evaluation 97-087)

Updated Final Safety Analysis Report Change FS95-043 reformats and revises Section 9.6, Sampling System, to correct/clarify operation and description of the normal and post-accident sampling systems in use at the station.

These changes are administrative in nature and made to accurately reflect the current plant condition. None of the changes to the UFSAR increases the probability of occurrence or increases the consequence of an accident. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 97-07 Page 12 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1997 TM S2-97-005 Temporary Modification 7-14-97 (Safety Evaluation No.97-083 Rev. 1)

This Temporary Modification (TM) decreases the low charging flow setpoint for Annunciator 20-E-5 (CHRG PP TO REGEN HX HI-LO FLOW). This was performed to eliminate a distraction to the Unit 2 Operations Staff due to the annunciator alarming frequently as a result of reduced charging flow conditions operating with only 2-CH-HCV-2200A Letdown Flow Orifice in service.

The charging low flow setpoint for this annunciator is being decreased by this TM, but the high flow alarm capabilities will be maintained at its normal setpoint. Annunciator 20-F-3, REGEN HX LTDN LINE HI TEMP, will be functional to provide alternate indications for low charging flow. This condition does not affect accidents previously evaluated, does not create the potential for an accident not previously identified, and Technical Specification compliance is maintained. Therefore, an unreviewed safety question does not exist.

TM S2-97-006 Temporary Modification 7-15-97 (Safety Evaluation No.97-089)

This Temporary Modification (TM) connects a Dranetz Power Supply Monitor recorder.

This will allow the troubleshooting of the NRG Monitor power supplies to the Radiation Monitoring Cabinet O-RM-CAB-100.

The Radiation Monitoring System for secondary and ProcessNent Vent Systems utilizes redundant indications. The installed radiation monitoring indications and alarm functions will be unaffected by this TM. Therefore, an unreviewed safety question does not exist.

SE 97-0041 Safety Evaluation 7-17-97 Safety Evaluation 97-0041 was performed to evaluate the effect of losing three threads in one of the lid bolt holes in TN-32 Cask No. 3.

While the bolt threads are not specifically mentioned in the TN-32 Topical Safety Analysis Report (TSAR), the strength of the lid bolt engagement is discussed in various chapters of the TSAR. Transnuclear, Inc. has determined that 1.52 inches of threaded bolt shank are required to be engaged in the bolt hole threads to maintain the full strength of the bolt.

Even if three threads in the hole are damaged, 1.56 inches of thread bolt shank will be engaged (this assumes the worst case design tolerances). Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 97-07 Page 13 of 20 FACILITY CHANGES THAT DID Nor REQUIRE NRC APPROVAL MONTH/YEAR: July, 1997 JCO 81-97-002, Rev. 0 Justification For Continued Operation 7-25-97 (Safety Evaluation No.97-091)

This Justification For Continued Operation evaluates the impact of elevated levels of hydrogen in the containment atmosphere and supports the interim hydrogen concentration limit of 0.8%. The evaluation supports the 0.8% hydrogen concentration with the following limiting conditions: 1) continued operation of the containment upper dome air fan and pressurizer cubicle ventilation while at power and 2) hydrogen sampling program confirms bulk concentrations do not exceed the 0.8% limit.

The initial presence of 0.8% hydrogen in containment will have a negligible impact on the containment peak pressure, depressurization and pump NPSH analyses. The self-imposed administrative limit of 0.8% is bounded by the conservatism assumed in the post-LOCA hydrogen analysis which include the one day hydrogen recombiner start time and the 50 scfm flowrate through the recombiner. Therefore, an unreviewed safety question does not exist.

JCO C-97-004, Rev. 0 Justification For Continued Operation 7-31-97 (Safety Evaluation No.97-094)

A review of the Appendix R fire safe shutdown Fire Contingency Action (FCA) procedures determined that the methodology for ensuring the proper ventilation alignment did not fully meet 10CFR50 Appendix R criteria. To provide the proper ventilation line up to support cooling of the Charging Pumps during an Appendix R event, a PAR to the Fire Contingency Action (FCA) Ventilation Attachment procedures was written as a compensatory measure.

The PAR written to the FCA Ventilation Attachment procedures allows the proper ventilation line up to support cooling of the Charging Pumps during an Appendix R event.

Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 97-07 Page 14 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: July, 1997 1-IPT-CC-RC-L-459 Instrument Periodic Test Procedure 7-11-97 (Safety Evaluation 97-088)

Instrument Periodic Test Procedures 1-IPT-CC-RC-L-459, "Pressurizer Level Protection Loop L-1-459 Channel Calibration," One Time Only PAR allows required on-line corrective maintenance/testing of the pressurizer level control circuit following comparator LC-1-4590 replacement without an unnecessary system actuation. This maintenance is needed to restore the pressurizer level control loop to its designed configuration and function.

Letdown isolation 1-CH-LCV-1460A will be temporarily rendered inoperable by this activity.

However, the in-series valve 1-CH-LCV-1460B will remain fully functional. Additionally, the Safety Injection (SI) signal (unaffected by this activity) will. automatically close letdown isolation trip valves 1-CH-TV-120A/B. As an added measure of protection, AP-16.0, "Excessive RCS Leakage," will verify the isolation function. Therefore, an unreviewed safety question does not exist.

1-TOP-4081 Temporary Operating Procedure 7-21-97 (Safety Evaluation 96-036 Rev. 2) 1-RC-TV-1519A was declared inoperable due to erratic stroke times. This action requires the valve to fail 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 who will close 1-RC-166 within 40 seconds of notification to ensure closure within 60 seconds of a Containment Isolation Signal.

Therefore, an unreviewed safety question does not exist.

1-IPT-CC-RC-L-459 Instrument Periodic Test Procedure 7-24-97 (Safety Evaluation 97-092)

Instrument Periodic Test Procedures 1-IPT-CC-RC-L-459, "Pressurizer Level Protection Loop L-1-459 Channel Calibration," One Time Only PAR allows required on-line corrective maintenance/testing of the pressurizer level control circuit following corrective maintenance without an unnecessary system actuation. This maintenance is needed to restore the pressurizer level control loop to its designed configuration and function.

Letdown isolation 1-CH-LCV-1460A will be temporarily rendered inoperable by this activity.

However, the in-series valve 1-CH-LCV-1460B will remain fully functional. Additionally, the Safety Injection (SI) signal (unaffected by this activity) will automatically close letdown isolation trip valves 1-CH-TV-120A/B. As an added measure of protection, AP-16.0, "Excessive RCS Leakage," will verify the isolation function. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 97-07 Page 15 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: July, 1997 O-FCA-1.00 Fire Contingency Action Procedure 7-31-97 1/2-FCA-3.00 Operations Surveillance Procedure 1/2-FCA-4.00 Abnormal Procedure 1/2-FCA-6.00 (Safety Evaluation 97-093) 1/2-FCA-18.00 O-OSP-FP-011 O-AP-48.00 Two separate areas of Appendix R non-compliance have been identified with respect to the O-AP-48.00 120 Volt Vital Bus System. The first issue deals with a fire in the main control room with no means to isolate the affected Vital Bus panel from the associated Uninterruptable Power Supplies (UPS). This postulated event could potentially affect the associated UPS and, therefore, affect the downstream Appendix R Panel which could affect the Remote Monitoring Panel, the Emergency Diesel Generator Isolation Panels and Vital Bus Panels feeding Appendix R communications equipment. Secondly, Chapter 9 of the Appendix R Report indicates that proper selective tripping is required for faults on Vital Bus branch circuits. A high fault current could result in the main breaker tripping simultaneously with, or in lieu of, the branch circuit breaker. All Vital Bus Panels are potentially affected by this issue. Compensatory measures implemented in the FCAs will a) disconnect the feeder conductors routed to the control room at UPSs 1A1, 1A2, 2A1, and 2A2 for a main control room fire to ensure the availability of distribution panels located in the ESGR 1 and 2 fire areas and b) restore Control Room or ESGR Vital Bus distribution panels lost as a result of fire induced hot shorts and mis-coordination between the main and branch circuit breakers as needed to accomplish safe shutdown. These compensatory measures do not adversely impact the Class 1E electrical distribution system. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 97-07 Page 16 of 20 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL

  • MONTH/YEAR: July, 1997 None During the Reporting Period

e Surry Monthly Operating Report No. 97-07 Page 17 of 20 CHEMISTRY REPORT MONTH/YEAR: July, 1997 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. Avq. Max. Min. Avq.

Gross Radioactivity, µCi/ml 3.23E-1 2.31 E-1 2.75E-1 2.96E-1 1.70E-1 2.29E-1 Suspended Solids, ppm - - - - - -

Gross Tritium, µCi/ml 5.53E-1 4.63E-1 5.18E-1 2.96E-1 1.38E-1 2.10E-1 1131, µCi/ml 7.89E-4 2.22E-4 3.01 E-4 3.23E-4 6.34E-5 1.18E-4 113111133 0.09 0.06 0.07 0.13 0.05 0.09 Hvdroqen, cc/kq 29.4 27.2 28.2 31.6 18.2 24.7 Lithium, ppm 2.40 2.14 2.26 2.34 2.05 2.19 Boron - 10, oom* 249.9 240.9 245.7 101.1 76.2 88.7 Oxygen, (DO), ppm  :-:;0.005  :-:;0.005  :-:;0.005 :-:;0.005  :-:;0.005  :-:;0.005 Chloride, ppm 0.005 0.003 0.004 0.003  :-:;0.001 0.002 pH at 25 deqree Celsius 6.17 5.85 5.98 6.97 6.52 6.69 Boron - 10 = Total Boron x 0.196 Comments:

None

  • e Surry Monthly Operating Report No. 97-07 Page 18 of 20 FUEL HANDLING UNITS 1 &2 MONTHNEAR: July, 1997 New Fuel Number of New or Spent Shipment or Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Cask No. Received per Shipment Number Number Enrichment Cask Activity TN 32-03 07/23/97 32 OE1 LMODEM 3.6057 N/A OE4 LMODFR 3.6007 OE5 LMODFK 3.5982 OE6 LMODEL 3.6049 086 LMOESC 3.5962 1EO LMODFV 3.6009 1E6 LMODFU 3.5990 1E7 LMODEE 3.6034 3E1 LMODFN 3.6050 3E3 LMODEZ 3.6053 3E7 LM0DF2 3.6022 381 LMOES9 3.6033 382 LMOES6 3.5963 4EO LMODEW 3.6039 4E1 LM0DF7 3.5940 4E2 LMODEK 3.6036 4E3 LMODFQ 3.6010 4E4 LMODEF 3.6059 4E5 LMODEC 3.6055 6R5 LMOBDJ 3.5844 R20 LMOOUB 3.0970 R21 LMOOU7 3.0970 R23 LMOOU8 3.0970 R24 LMOOUD 3.0970 R25 LMOOUQ 3.0970 R26 LMOOUN 3.0970 R27 LMOOUH 3.0970

Surry Monthly Operating Report No. 97-07 Page 19 of 20 I

FUEL HANDLING UNITS 1 &2

' MONTH/YEAR: July, 1997 New Fuel Number of New or Spent Shipment or Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Cask No. Received per Shipment Number Number Enrichment Cask Activity R28 LMOOUU 3.0970 (continued) R29 LMOOV2 3.0970 R30 LMOOUV 3.0970 R32 LMOOUP 3.0970 R33 LMOOUR 3.0970

I

  • e Surry Monthly Operating Report No. 97-07 Page 20 of 20 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: JULY, 1997 None During the Reporting Period
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