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 A, FANGUY M J, MASON D K
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
97-586, NUDOCS 9710220016
Download: ML18153A450 (19)
v • d • e


Text

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  • VIRGINIA ELECTRIC AND POWER COMPA1SY RICHMOND~

VIRGINIA 23261 October 10~1997 United States 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. SPS Lic/JDK Docket Nos. License Nos.97-586 RO 50-280 50-281 DPR-32 DPR-37 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 97{0220016 970930 PDR ADOCK 05000280 R PDR I IIIIII IIIII IIIII IIIII IIIIII IIIII Ill llll

  • 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: Dc:(L___ /(J. S-i] Station Manager Date
  • TABLE OF CONTENTS Section
  • Surry Monthly Operating Report No. 97-09 Page 2 of 18 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

1. 2. 3. 4. 5. 6. 7. *
  • Surry Monthly Operating Report No. 97-09 Page 3 of 18 OPERATING DATA REPORT Unit Name: .......................................................

.. Reporting Period: ............................................... . Licensed Thermal Power (MWt): ........................ . Nameplate Rating (Gross MWe): ......................

.. Design Electrical Rating (Net MWe): .................. . Maximum Dependable Capacity (Gross MWe): .. . Maximum Dependable Capacity (Net MWe): ...... . Docket No.: Date: Completed By: Surry Unit 1 September, 1997 2546 847.5 788 840 801 Telephone:

50-280 10/1/97 D. K. Mason (757) 365-2459 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

1. 2. 3. 4. 5. 6. 7. e OPERATING DATA REPORT
  • Surry Monthly Operating Report Docket No.: Date: 50-281 10/01/97 No. 97-09 Page 4 of 18 Completed By: D. K Mason (757) 365-2459 Unit Name: ........................................................ . Reporting Period: ............................................... . Licensed Thermal Power (MWt): ........................ . Nameplate Rating (Gross MWe): ....................... . Design Electrical Rating (Net MWe): .................. . Maximum Dependable Capacity (Gross MWe): .. . Maximum Dependable Capacity (Net MWe): ...... . Surry Unit 2 September, 1997 2546 847.5 788 840 801 Telephone:
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):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST ACHIEVED

  • Surry Monthly Operating Report No. 97-09 Page 5 of 18 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%) REPORT MONTH: September, 1997 (1) (2) (3) (4) Method Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-03-97 Completed by: M. J. Fanguy Telephone:

(757) 365-2155 (5) Duration of LER No. System Component Cause & Corrective Action Date Type Hours (1) F: Forced S: Scheduled (4) Reason Shutting Code Down Rx None During the Reporting Period (2) REASON: 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) Code to Prevent Recurrence (3) METHOD: 1 -Manual 2 -Manual Scram 3 -Automatic Scram 4 -Other (Explain)

(5) Exhibit 1 -Same Source 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 (1) (2) (3) (4) Method Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 1 0-03-97 Completed by: M. J. Fanguy Telephone:

(757) 365-2155 (5) Duration of LER No. System Component Cause & Corrective Action Date Type Hours Reason Shutting Code (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) Code to Prevent Recurrence (3) METHOD: 1 -Manual 2 -Manual Scram 3 -Automatic Scram 4 -Other (Explain)

(5) Exhibit 1 -Same Source

  • Surry Monthly Operating Report No. 97-09 Page 7 of 18 AVERAGE DAILY UNIT POWER LEVEL MONTH: September, 1997 Average Daily Power Level Day {MWe -Net) 1 806 2 801 3 800 4 807 5 810 6 742 7 804 8 815 9 815 10 813 11 812 12 810 13 806 14 807 15 816 16 816 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-01-97 Completed by: J. D. Kilmer Telephone:
  • (757) 365-2792 Average Daily Power Level (MWe -Net) 816 815 804 814 815 816 816 815 816 819 819 819 819 819 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. 97-09 Page 8 of 18 AVERAGE DAILY UNIT POWER LEVEL MONTH: September, 1997 Average Daily Power Level Day (MWe -Net) 1 816 2 811 3 809 4 817 5 820 6 821 7 819 8 816 9 816 10 742 11 816 12 814 13 812 14 813 15 812 16 812 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-01-97 Completed by: John D. Kilmer Telephone:

(757) 365-2792 Average Daily Power Level (MWe -Net) 806 806 809 802 808 810 816 820 822 819 818 819 820 820 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.

SUMMARY

OF OPERATING EXPERIENCE MONTH/VEAR:

September, 1997

  • Surry Monthly Operating Report No. 97-09 Page 9 of 18 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 9/6/97 0000 0544 Unit 1 begins the month at 100% / 835 MWe. 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 9/1 0/97 0945 Unit 2 starts the month at 100% / 845 MWe. 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.

SE97-117 DCP 94-037 DCP 95-035 *

  • Surry Monthly Operating Report No. 97-09 Page 10 of 18 FACILITY CHANGES THAT DID Nor REQUIRE NRC APPROVAL MONTH/YEAR:

September, 1997 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. Design Change Package (Safety Evaluation 95-055) 9-5-97 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. Design Change Package (Safety Evaluation 95-184) 9-9-97 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.

FS97-037 FS97-026 FS95-039 e e Surry Monthly Operating Report No. 97-09 Page 11 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

September, 1997 Updated Final Safety Analysis Report Change (Safety Evaluation 97-118) 9-11-97 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. Updated Final Safety Analysis Report Change (Safety Evaluation 97-119) 9-11-97 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. Updated Final Safety Analysis Report Change (Safety Evaluation 97-120) 9-18-97 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.

FS95-041 SE 97-123 SE 97-124 e Surry Monthly Operating Report No. 97-09 Page 12 of 18 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

September, 1997 Updated Final Safety Analysis Report Change (Safety Evaluation 97-121) 9-22-97 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. 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. 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.

O-ECM-1509-03 O-EPM-0901-01 2-EMP-P-RT-63A 2-EMP-P-RT

-48 e e PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR:

September, 1997 Electrical Corrective Maintenance Procedure (Safety Evaluation 97-116) Surry Monthly Operating Report No. 97-09 Page 13 of 18 . 9-4-97 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. Electrical Preventive Maintenance Procedure (Safety Evaluation No.97-122) 9/22/97 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. Corrective Electrical Maintenance Procedure (Safety Evaluation No.97-125) 9-29-97. 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.

2-MOP-EP-304 O-ECM-0104-03 e PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID Nor REQUIRE NRC APPROVAL MONTH/YEAR:

September, 1997 Maintenance Operating Procedure (Safety Evaluation No.97-126) Surry Monthly Operating Report No. 97-09 Page 14 of 18 9-29-97 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. Electrical Corrective Maintenance Procedure (Safety Evaluation 97-127) 9-29-97 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

  • Primary Coolant Analvsis Gross Radioactivity, µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml 1131, µCi/ml 113111133 Hvdroaen, cc/ka Lithium, nnm Boron -10, nnm* Oxygen, (DO), ppm Chloride, ppm pH at 25 dearee Celsius

None CHEMISTRY REPORT MONTHNEAR:

September, 1997 Unit No. 1 Max. Min. Ava. 2.90E-1 2.00E-1 2.38E-1 S0.01 S0.D1 sO.Q1 6.39E-1 5.76E-1 5.90E-1 3.49E-4 2.49E-4 3.00E-4 0.08 0.06 0.07 31.6 28.3 30.3 2.34 2.06 2.20 224.8 209.3 216.2 S0.005 S0.005 S0.005 0.005 0.003 0.004 6.39 6.03 6.21 e Surry Monthly Operating Report No. 97-09 Page 16 of 18 Unit No. 2 Max. Min. Ava. 2.40E-1 1.56E-1 1.93E-1 S0.01 S0.01 <0.01 2.00E-1 1.59E-1 1.78E-1 1.75E-4 9.08E-5 1.20E-4 0.12 0.06 0.09 30.6 27.9 29.1 2.00 1.52 1.76 55.7 37.0 47.2 S0.005 s0.005 S0.005 0.002 S0.001 0.001 7.15 6.82 6.98 New Fuel Shipment or Date Stored Cask No. or Received Unit2 Batch 17 Shipment 1 9/3/97

  • FUEL HANDLING UNITS 1 & 2 MONTHNEAR:

September, 1997 Number of Assemblies Assembly ANSI per Shipment Number Number 8 05L LM159G 06L LM159H 09L LM159L 21L LM159Y 24L LM15A1 25L LM15A2 33L LM15AA 45L LM15AN e Surry Monthly Operating Report No. 97-09 Page 17 of 18 New or Spent Initial Fuel Shipping Enrichment Cask Activity 3.8995 9.94 Ci 3.9005 3.8996 3.9047 3.9002 3.9004 4.0559 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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