ML18153A450

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Monthly Operating Repts for Sept 1997 for Surry Power Station,Units 1 & 2.W/971010 Ltr
ML18153A450
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/30/1997
From: Christian D, Fanguy M, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
97-586, NUDOCS 9710220016
Download: ML18153A450 (19)
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VIRGINIA ELECTRIC AND POWER COMPA1SY RICHMOND~ VIRGINIA 23261 October 10~1997 United States Nuclear Regulatory Commission Serial No.97-586 Attention: Document Control Desk SPS Lic/JDK 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 September 1997 is provided in the attachment.

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

s::;rc~~

D. A. Christian, Station Manager Surry Power Station Attachment Commitments made by this letter: None 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 IIIIIII IIIII IIIII IIIII IIIIII IIIII Ill llll 97{0220016 970930

  • S S 7 2 C C
  • *Surry Monthly Operating Report No. 97-09 Page 1 of 18 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 97-09 Approved:

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Station Manager

/(J. S-i]

Date

  • TABLE OF CONTENTS
  • Surry Monthly Operating Report No. 97-09 Page 2 of 18 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. ...................................................................................... 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval ............................................. 13 Tests and Experiments That Did Not Require NRC Approval ............................................................................. 15 Chemistry Report. ............................................................................................................................................. 16 Fuel Handling - Unit Nos. 1 and 2 ...................................................................................................................... 17 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................................. 18
  • OPERATING DATA REPORT
  • Surry Monthly Operating Report No. 97-09 Page 3 of 18 Docket No.: 50-280 Date: 10/1/97 Completed By: D. K. Mason Telephone: (757) 365-2459
1. Unit Name: ......................................................... Surry Unit 1
2. Reporting Period: ............................................... . September, 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 l'vbnth , Vear-To-Date Cumulative

11. Hours in Reporting Period 720.0 6551.0 217175.0
12. Number of Hours Reactor Was Critical 720.0 4982.1 151816.8
13. Reactor Reserve Shutdown Hours 0.0 0.0 3774.5
14. Hours Generator On-Line 720.0 4859.5 149390.5
15. Unit Reserve Shutdown Hours 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) 1828415.0 11992912.5 350628356.3
17. Gross Electrical Energy Generated (MWH) 604028.0 3968773.0 114941591.0
18. Net Electrical Energy Generated (MWH) 583304.0 3828685.0 109422434.0
19. Unit Service Factor 100.0% 74.2% 68.8%
20. Unit Availability Factor 100.0% 74.2% 70.5%
21. Unit Capacity Factor (Using MDC Net) 101.1% 73.0% 64.8%
22. Unit Capacity Factor (Using DER Net) 102.8% 74.2% 63.9%
23. Unit Forced Outage Rate 0.0% 5.5% 14.9%
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 OPERATING DATA REPORT

  • Surry Monthly Operating Report No. 97-09 Page 4 of 18 Docket No.: 50-281 Date: 10/01/97 Completed By: D. K Mason Telephone: (757) 365-2459
1. Unit Name: ......................................................... Surry Unit 2
2. Reporting Period: ............................................... . September, 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 Year-To-Date Cumulative

11. Hours in Reporting Period 720.0 6551.0 214055.0
12. Number of Hours Reactor Was Critical 720.0 6487.0 149562.6
13. Reactor Reserve Shutdown Hours 0.0 0.0 328.1
14. Hours Generator On-Line 720.0 6480.1 147577.9
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1828170.6 16324465.8 347798722.6
17. Gross Electrical Energy Generated (MWH) 605160.0 5423179.0 113873978.0
18. Net Electrical Energy Generated (MWH) 584640.0 5241056.0 108432935.0
19. Unit Service Factor 100.0% 98.9% 68.9%
20. Unit Availability Factor 100.0% 98.9% 68.9%
21. Unit Capacity Factor (Using MDC Net) 101.4% 99.9% 64.8%
22. Unit Capacity Factor (Using DER Net) 103.0% 101.5% 64.3%
23. Unit Forced Outage Rate 0.0% 1.1% 12.0%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, October 6, 1997, 30 Da~s

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. 97-09 Page 5 of 18 (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: September, 1997 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-03-97 Completed by: M. J. Fanguy Telephone: (757) 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)

e Surry Monthly Operating Report No. 97-09 Page 6 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: September, 1997 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-03-97 Completed by: M. J. Fanguy Telephone: (757) 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)

AVERAGE DAILY UNIT POWER LEVEL

  • Surry Monthly Operating Report No. 97-09 Page 7 of 18 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-01-97 Completed by: J. D. Kilmer Telephone: * (757) 365-2792 MONTH: September, 1997 Average Daily Power Level Average Daily Power Level Day {MWe - Net) Day (MWe - Net) 1 806 17 816 2 801 18 815 3 800 19 804 4 807 20 814 5 810 21 815 6 742 22 816 7 804 23 816 8 815 24 815 9 815 25 816 10 813 26 819 11 812 27 819 12 810 28 819 13 806 29 819 14 807 30 819 15 816 16 816 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 AVERAGE DAILY UNIT POWER LEVEL

  • Surry Monthly Operating Report No. 97-09 Page 8 of 18 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-01-97 Completed by: John D. Kilmer Telephone: (757) 365-2792 MONTH: September, 1997 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 816 17 806 2 811 18 806 3 809 19 809 4 817 20 802 5 820 21 808 6 821 22 810 7 819 23 816 8 816 24 820 9 816 25 822 10 742 26 819 11 816 27 818 12 814 28 819 13 812 29 820 14 813 30 820 15 812 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.
  • Surry Monthly Operating Report No. 97-09 Page 9 of 18

SUMMARY

OF OPERATING EXPERIENCE MONTH/VEAR: September, 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:

9/1/97 0000 Unit 1 begins the month at 100% / 835 MWe.

9/6/97 0544 Adjusting turbine load to maintain condenser vacuum with "D" waterbox being removed from service for cleaning.

1813 Start power increase from 82% I 700 MWe after "D" waterbox is returned to service.

2100 Stop power increase at 100% / 845 MWe.

9/15/97 0936 Start power decrease per 1-GOP-2.1 due to SW leak.

0947 Stop power decrease at 99.25% / 835 MWe as SW line has been repaired, filled, and shows no indication of leakage.

1010 Start power increase 1034 Stop power increase at 100% I 845 MWe.

9/30/97 2400 Unit 1 finishes the month at 100% I 850 MWe.

UNITTwo:

9/1/97 0000 Unit 2 starts the month at 100% / 845 MWe.

9/1 0/97 0945 Adjusting turbine load to maintain condenser vacuum after 2-CW-E-1A was removed from service due to a leak in the outlet piping.

1045 Stop power decrease at 81 % / 670 MWe.

1909 Start power increase after 2-CW-E-1A outlet piping leak was repaired.

2305 Stop power increase at 100% / 845 MWe.

9/30/97 2400 Unit 2 finishes the month at 100% / 850 MWe.

FACILITY CHANGES THAT DID Nor REQUIRE NRC APPROVAL Surry Monthly Operating Report No. 97-09 Page 10 of 18 MONTH/YEAR: September, 1997 SE97-117 Safety Evaluation 9-4-97 Safety Evaluation 97-117 was performed to evaluate the Power Operated Relief Valve (PORV) which has been out of service for greater than 30 days. Each Steam Generator (S/G) has an adjustable setpoint Power Operated Relief Valve (PORV) located on the Main Steam Header outside containment. The valve is normally set to relieve pressure at 1035 psig and has a capacity of 373,00P lb/hr. Currently, Unit 1 has the 'A' SIG PORV isolated due to leakby.

The system overprotection is provided by the S/G code safety valves. These valves are fully. operable. The S/G Tube Rupture accident scenario analyzed in the UFSAR assumes the SIG PORV closest to the ruptured S/G opens and remains open for the first 30 minutes of the accident. In the event of a tube rupture on the affected SIG, the isolated S/G PORV can be unisolated for cooldown/pressure control; procedural guidance is provided by Emergency Operating Procedures. Therefore, an unreviewed safety question does not exist.

DCP 94-037 Design Change Package 9-5-97 (Safety Evaluation 95-055)

Design Change Package (DCP)94-037, installed a system* cross-connect between the Boron Recovery System and the Liquid Waste System to facilitate the transfer of liquid waste from the Boron Recovery Tanks to the Radwaste Facility for processing.

The piping is installed consistent with the existing system design and is therefore bounded by the previously analyzed accidents and equipment malfunctions. Isolating devices are provided to prevent an accident of a different type. Therefore, an unreviewed safety question does not exist.

DCP 95-035 Design Change Package 9-9-97 (Safety Evaluation 95-184)

Design Change Package (DCP)95-035, replaces the waste gas decay sample pumps 1-GW-C-4A & 48 with continuous duty diaphragm pumps, reroutes the sample return tubing from the decay tank inlet to the waste gas surge drum inlet, and installs pressure regulators to reduce pressure in the sample lines to the pumps' suction.

The modification does not change the intent or function of the waste gas decay tank oxygen sampling system. The Waste Gas system event analyzed by the Safety Analysis Report is a waste gas decay tank rupture. This change does not increase the pressure of the gases contained in the waste gas decay tank. The existing analysis of the tank rupture still bounds any release of radioactive gases. Therefore, an unreviewed safety question does not exist.

e e Surry Monthly Operating Report No. 97-09 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: September, 1997 FS97-037 Updated Final Safety Analysis Report Change 9-11-97 (Safety Evaluation 97-118)

Updated Final Safety Analysis Report (UFSAR) Change FS97-037 revises UFSAR Section 17.2, Operational Quality Assurance Program Tables 17.2.2 and 17.2.3, to correct administrative errors.

The Operational QA Program change does not affect the operation or design of the plant or any system, structure, or component. Plant equipment will not be operated in a different manner. This change merely corrects administrative (typographical) errors.

Therefore, an unreviewed safety question does not exist.

FS97-026 Updated Final Safety Analysis Report Change 9-11-97 (Safety Evaluation 97-119)

Updated Final Safety Analysis Report (UFSAR) Change FS97-026 revises UFSAR Chapter 17 to delete reference to the Nuclear Operations Department and Nuclear Operations Department Standards which are being replaced with Nuclear Business Unit and Nuclear Business Unit Standards. Additionally, the nuclear organization is updated and editorial changes are included.

The Operational QA Program change is administrative in nature and does not affect the operation or design of the plant or any system, structure, or component. Therefore, an unreviewed safety question does not exist.

FS95-039 Updated Final Safety Analysis Report Change 9-18-97 (Safety Evaluation 97-120)

Updated Final Safety Analysis Report (UFSAR) Change FS95-039 revises UFSAR Section 6.2.2.2.1, Accumulators, to ensure consistency between actual plant operations and that described in the UFSAR. Currently, the UFSAR states that 'water level is reduced by draining to the Primary Drain Transfer Tank." An existing operating procedure allows draining of the accumulators not only to the Primary Drain Transfer Tank (PDTI) but also to the Primary Drains Tank (PDT) and the Refueling Water Storage Tank (RWST) with the RWST being the preferred tank during normal operations.

The flow path used to drain to the PDT and RWST are designed to be compatible with the conditions (e.g., temperature, pressure, humidity, radiation and chemistry) that are encountered while draining the accumulator. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 97-09 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1997 FS95-041 Updated Final Safety Analysis Report Change 9-22-97 (Safety Evaluation 97-121)

Updated Final Safety Analysis Report (UFSAR) Change FS95-041 revises UFSAR Sections 11.2 and 14.4.3 to describe the modifications proposed by Chem-Nuclear. The UFSAR states that three demineralizers are in service for the reverse osmosis system.

As part of the modification, one additional demineralizer will be in service. An available demineralizer vessel will be used via rerouting qualified hoses to and from the reverse osmosis process stream and demineralizer.

The margin of safety as stated in the Technical Specifications (TS) is not affected by the modification. The TS do not address events in the Surry Radwaste Facility. The material being transferred is not flammable and will not affect any fire related equipment.

The events in the SRF will not affect the plant's ability to achieve safe shutdown.

Appropriate radiological controls will be in place during the installation of new equipment and during operation of the reverse osmosis unit. Therefore, an unreviewed safety question does not exist.

SE 97-123 Safety Evaluation 9/22/97 During the previous installation of the service water expansion joints 1/2-SW-MEJ-1A, B, C, D on the Units 1 and 2 recirculation spray cooler service water return lines, the nuts on the tie rods of the expansion joints were inadvertently installed with inadequate gaps.

The gaps provide flexibility in the service water lines to accommodate out of phase seismic anchor movements between the containment external and internal structures and the growth of the containment wall during a loss of coolant accident or a postulated main steam line break.

An evaluation (ET CEM-97-0076) was performed and confirmed that these components will maintain their structural and pressure boundary integrity. Based on the guidance of NRC Generic Letter 91-18, structural qualification of the system has been performed using allowables from Appendix F of the ASME Section Ill code for one-time operability.

Consistent with the requirements of the Generic Letter, appropriate design gap between the nuts on tie rods and the flanges of the expansion joints must be provided at the next refueling outage of each unit to restore the system to the design configuration.

Therefore, an unreviewed safety question does not exist.

SE 97-124 Safety Evaluation 9-29-97 A Safety Evaluation has been performed to determine whether an unreviewed safety question will result from the refueling and operation of Surry Unit 2 Cycle 15.

The Cycle 15 core design parameters 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 margin 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.

e e Surry Monthly Operating Report No. 97-09 Page 13 of 18 .

PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: September, 1997 O-ECM-1509-03 Electrical Corrective Maintenance Procedure 9-4-97 (Safety Evaluation 97-116)

Electrical Corrective Maintenance Procedure O-ECM-1509-03, " Votes MOV Testing for Quarter Turn Valves," incorporates a permanent change to administratively control Component Cooling Water Heat Exchanger (CCHX) Service Water (SW) Supply MOV, *1-SW-MOV-102A, to maintain the capability to isolate the non-essential Service Water flowpaths within one hour. The one hour time limit for isolating the CCHX SW Supply are assumed as part of the design basis calculations associated with the minimum initial canal level required to maintain the capability to supply adequate SW flow to the Recirculating Spray Heat Exchangers (RSHXs).

The administrative controls invoked provide acceptable contingency actions to ensure the non-essential SW isolation function can be met within the required design basis time frames assumed in calculation ME-0166. The administrative controls will be established to locally close the SW MOV. In event the MOV fails to fully close, local manual isolation of

  • the CCHX SW supply is directed by O-AP-12.01. Therefore, an unreviewed safety question does not exist.

O-EPM-0901-01 Electrical Preventive Maintenance Procedure 9/22/97 (Safety Evaluation No.97-122)

Electrical Periodic Test Procedures O-EPT-0901-01, "Mandatory Six Month Smoke and Thermal Detector Test," proceduralizes a Temporary Modification to facilitate lifting the leads to the Solenoid Operated Valve (SOV) in panel 1-FP-PNL-48. The SOV needs to be de-energized to allow testing of the fire protection system for the Condensate Polishing Building Chemistry Lab without the deluge valve charging the sprinkler header in the Chemistry Lab.

The operability of the fire detection instrumentation ensures that adequate warning is available for prompt detection of the fires. Testing of the system requires personnel to be present in the room protected by the deluge valve. This ensures that an undetected fire will not occur. Additionally, the deluge valve can be manually tripped to extinguish a fire in the area. There are no safety systems protected by the sprinkler system in the Condensate Polishing Building. A verification will be performed when the lifted leads are re-landed.

Therefore, an unreviewed safety question does not exist.

2-EMP-P-RT-63A Corrective Electrical Maintenance Procedure 9-29-97.

2-EMP-P-RT-48 (Safety Evaluation No.97-125)

Corrective Electrical Maintenance Procedures 2-EMP-P-RT-63A / 2-EMP-P-RT-48,

" Protective Relay Maintenance for Circuit Breaker 25H8/15E1 Normal Feed/Reserve Supply to Bus 2H/1 E," were revised to provide instructions for the installation and removal of procedurally controlled temporary modifications (TM).

These procedurally controlled TMs allow circuit breaker control interlocks to be functionally tested while maintaining a reliable and desirable electric plant lineup. The emergency power supplies are not affected by the installation and removal of these TMs. These procedures are performed at cold shutdown and the TMs are installed and removed by qualified individuals using double verification. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No. 97-09 Page 14 of 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID Nor REQUIRE NRC APPROVAL MONTH/YEAR: September, 1997 2-MOP-EP-304 Maintenance Operating Procedure 9-29-97 (Safety Evaluation No.97-126)

Maintenance Operating Procedure 2-MOP-EP-304, "RSS Transformer B Outage with Backfeed of Transfer Bus E and Emergency Bus 2H via Alternate AC Diesel Bus OL," was developed to provide instructions for the maintenance of Reserve Service Station Transformer 'B' while Bus 2H remains operable. This allows Bus 2H maintenance to be scheduled separately, providing greater flexibility for outage planning and decreases the unavailability of Emergency Diesel Generator 2.

The proposed change does not alter any electrical power system design or operating limit and satisfies the requirements of GDC-17 of 10CFR50 Appendix A. Existing Technical Specification requirements for electrical power system operability continue to be satisfied.

Therefore, an unreviewed safety question does not exist.

O-ECM-0104-03 Electrical Corrective Maintenance Procedure 9-29-97 (Safety Evaluation 97-127)

Electrical Corrective Maintenance Procedure O-ECM-0104-03, "Main Station and EOG Battery Freshening Charge," was temporarily changed to allow the 28 Battery Room to be isolated from the Main Control Room (MCR) envelope for battery charging. Hydrogen generated by the charging of the 28 batteries necessitates venting of the 28 battery room outside the MCR envelope.

Unit 2 will be shutdown for refueling during the 60 hour6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> charge. The 2A battery will remain operable during the interval that the 28 battery is out of service with the DC cross-tie closed as described in the UFSAR. None of the control and monitoring equipment will be rendered out of service because of the temporary modifications (TM) on the battery room supply vent and exhaust duct. However, due to the open battery room door, the 28 Battery Room Low Flow alarm will be locked in. As a result, the operators in the MCR cannot detect a 28 battery room ventilation failure. Therefore, a fire watch will be established while the 28 battery room door is open. After the TM is removed, O-OSP-VS-004, " Control Room and Relay Room Operational Pressure Test," will prove the integrity of the original MCR envelope. Therefore, an unreviewed safety question does not exist.

  • e Surry Monthly Operating Report No. 97-09 Page 15 of 18 TESTS AND EXPERIMENTS THAT DID Nor REQUIRE NRC APPROVAL MONTHNEAR: September, 1997 None During the Reporting Period
  • e Surry Monthly Operating Report No. 97-09 Page 16 of 18 CHEMISTRY REPORT MONTHNEAR: September, 1997 Unit No. 1 Unit No. 2 Primary Coolant Analvsis Max. Min. Ava. Max. Min. Ava.

Gross Radioactivity, µCi/ml 2.90E-1 2.00E-1 2.38E-1 2.40E-1 1.56E-1 1.93E-1 Suspended Solids, ppm S0.01 S0.D1 sO.Q1 S0.01 S0.01 <0.01 Gross Tritium, µCi/ml 6.39E-1 5.76E-1 5.90E-1 2.00E-1 1.59E-1 1.78E-1 1131, µCi/ml 3.49E-4 2.49E-4 3.00E-4 1.75E-4 9.08E-5 1.20E-4 113111133 0.08 0.06 0.07 0.12 0.06 0.09 Hvdroaen, cc/ka 31.6 28.3 30.3 30.6 27.9 29.1 Lithium, nnm 2.34 2.06 2.20 2.00 1.52 1.76 Boron - 10, nnm* 224.8 209.3 216.2 55.7 37.0 47.2 Oxygen, (DO), ppm S0.005 S0.005 S0.005 S0.005 s0.005 S0.005 Chloride, ppm 0.005 0.003 0.004 0.002 S0.001 0.001 pH at 25 dearee Celsius 6.39 6.03 6.21 7.15 6.82 6.98

None

  • eSurry Monthly Operating Report No. 97-09 Page 17 of 18 FUEL HANDLING UNITS 1& 2 MONTHNEAR: September, 1997 New Fuel Number of New or Spent Shipment or Date Stored Assemblies Assembly ANSI Initial Fuel Shipping Cask No. or Received per Shipment Number Number Enrichment Cask Activity Unit2 Batch 17 Shipment 1 9/3/97 8 05L LM159G 3.8995 9.94 Ci 06L LM159H 3.9005 09L LM159L 3.8996 21L LM159Y 3.9047 24L LM15A1 3.9002 25L LM15A2 3.9004 33L LM15AA 4.0559 45L LM15AN 4.0620
  • e Surry Monthly Operating Report No. 97-09 Page 18 of 18 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: SEPTEMBER, 1997 None During the Reporting Period
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