ML18153A762

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Monthly Operating Repts for Aug 1995 for Surry Power Station Units 1 & 2.W/950912 Ltr
ML18153A762
Person / Time
Site: Surry  Dominion icon.png
Issue date: 08/31/1995
From: Bowling M, Mason D
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-471, NUDOCS 9509190183
Download: ML18153A762 (21)
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Text

g; VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 12, 1995 U.S. Nuclear Regulatory Commission Serial No.95-471 Attention: Document Control Desk NO/RPC:vlh 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 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of August 1995.

Very truly yours,

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M. L. Bowling, Manager 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

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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 95-08 Approved:

Station Manager Date

Surry Monthly Operating Report No. 95-08 Page 2 of 20 TABLE OF CONTENTS Section Page Operating Data Report - Unit No. 1 ......................................................................................................... 3 Operating Data Report - Unit No. 2 ........................................................................................................ .4 Unit Shutdowns and Power Reductions - Unit No. 1.................................................................................... 5 Unit Shutdowns and Power Reductions - Unit No. 2 .................................................................................... 6 Average Daily Unit Power Level - Unit No. 1.............................................................................................. 7 Average Daily Unit Power Level - Unit No. 2 .............................................................................................. 8 Summary of Operating Experience - Unit No. 1 ......................................................................................... 9 Summary of Operating Experience - Unit No. 2 ......................................................................................... 9 Facility Changes That Did Not Require NRC Approval. .............................................................................. 10 Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 14 Tests and Experiments That Did Not Require NRC Approval ...................................................................... 17 Chemistry Report .................................. *: ......................................................................................... 18 Fuel Handling - Unit No. 1 ................................................................................................................... 19 Fuel Handling - Unit No. 2 ................................................................................................................... 19 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 20

Surry Monthly Operating Report No. 95-08 Page 3 of 20 OPERATING DATA REPORT Docket No.: 50-280 Date: 09-05-95 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . August, 1995
3. Licensed Thermal Power (MWt): ...................... . 2441
4. Nameplate Rating (Gross MWe): ...................... . 847.5
5. Design Electrical Rating (Net MWe): ................. . 788
6. Maximum Dependable Capacity (Gross MWe): ... . 820
7. Maximum Dependable Capacity (Net MWe): ....... . 781
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 5831.0 198911.0
12. Number of Hours Reactor Was Critical .......... 744.0 5651.7 136121.4
13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5
14. Hours Generator On-Line ........................... 744.0 5617.2 133858.2
15. Unit Reserve Shutdown Hours ..................... 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 1648319.6 13449323.9 311903063.1
17. Gross Electrical Energy Generated (MWH) .... 524795.0 4471760.0 102085593.0
18. Net Electrical Energy Generated (MWH) ........ 503061.0 4305902.0 97014925.0
19. Unit Service Factor ................................... 100.0% 96.3% 67.3%
20. Unit Availability Factor ............................... 100.0% 96.3% 69.2%
21. Unit Capacity Factor (Using MDC Net) ........... 86.6% 94.6% 62.9%
22. Unit Capacity Factor (Using DER Net) ........... 85.8% 93.7% 61.9%
23. Unit Forced Outage Rate ............................ 0.0% 3.7% 16.2%
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, September 7, 1995, 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 ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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(' Surry Monthly Operating Report No. 95-08 Page 4 of 20 OPERATING DATA REPORT Docket No.: 50-281 Date: 09-05-95 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . August, 1995
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): .. .. 820
7. Maximum Dependable Capacity (Net MWe): ....... . 781
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

Amendment 203 to Facility Operating License DPR-37 was issued August 3, 1995. Amendment 203 revised the Facility Operating License to permit operation at steady state reactor core power levels not in excess of 2546 megawatts (thermal).

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 5831.0 195791.0
12. Number of Hours Reactor Was Critical .......... 744.0 4586.6 132924.1
13. Reactor Reserve Shutdown Hours ............... 0 0 328.1
14. Hours Generator On-Line ........................... 744.0 4516.7 130983.8
15. Unit Reserve Shutdown Hours ..................... 0 0 0
16. Gross Thermal Energy Generated (MWH) ...... 1778291.1 10753320.8 306021785.1
17. Gross Electrical Energy Generated (MWH); ... 578755.0 3558165.0 100000459.0
18. Net Electrical Energy Generated (MWH) ........ 557122.0 3428916.0 95021952.0
19. Unit Service Factor ................................... 100.0% 77.5% 66.9%
20. Unit Availability Factor ............................... 100.0% 77.5% 66.9%
21. Unit Capacity Factor (Using MDC Net) ........... 95.9% 75.3% 62.2%
22. Unit Capacity Factor (Using DER Net) ........... 95.0% 74.6% 61.6%
23. Unit Forced Outage Rate ............................ 0.0% 4.4% 13.0%
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

Surry Monthly Operating Report No. 95-08 Page 5 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: August, 1995 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 09-04-95 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 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 (NU REG 0161)

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Surry Monthly Operating Report No. 95-08 Page 6 of 20 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL TO OR GREATER THAN 20%)

REPORT MONTH: August, 1995 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 09-04-95 Completed by: Craig Olsen Telephone: (804) 365-2155 (1) (2) (3) (4) (5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No. Code Code Prevent Recurrence Down Rx 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 (NU REG 0161)

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Surry Monthly Operating Report No. 95-08 Page 7 of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 09-06-95 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: August, 1995 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 1 753 17 672 2 750 18 663 3 745 19 662 4 727 20 655 5 731 21 648 6 729 22 639 7 730 23 636 8 729 24 631 9 724 25 622 10 717 26 625 11 709 27 619 12 701 28 611 13 691 29 609 14 685 30 599 15 682 31 585 16 679 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.

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  • j Surry Monthly Operating Report No. 95-08 Page 8 of 20 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 09-06-95 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: August, 1995 Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe - Net) 1 761 17 773 2 759 18 771 3 756 19 772 4 756 20 772 5 752 21 767 6 746 22 764 7 759 23 761 8 759 24 759 9 767 25 731 10 766 26 740 11 758 27 637 12 663 28 679 13 732 29 688 14 771 30 753 15 771 31 799 16 772 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.
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Surry Monthly Operating Report No. 95-08 Page 9 of 20

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: August, 1995 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:

08/01/95 0000 The reporting period began with the unit operating at 100% power, 790 MWe.

08/31/95 2400 The reporting period ended with the unit operating at 79.5% power, 590 MWe, in a power coastdown due to fuel depletion.

UNIT Two:

08/01/95 0000 The reporting period began with the unit operating at 100% power, 795 MWe.

08/11/95 2150 Started power reduction to maintain condenser vacuum while cleaning the "B" waterbox.

2325. Stopped power reduction at 91 %, 715 MWe.

08/13/95 0944 Started power increase following "B" waterbox maintenance.

1036 Stopped power increase at 100%, 810 MWe.

08/25/95 0454 Started power reduction to maintain condenser vacuum while cleaning the "D" waterbox.

0705 Stopped power reduction at 93%, 717 MWe.

1425 Started power increase following "D" waterbox maintenance.

1515 Stopped power increase at 100%, 805 MWe.

08/26/95 2031 Started power reduction to perform Main Control Room instrument scaling activities associated with the implementation of the uprated core power level of 2546 MWt.

2130 Stopped power reduction at 90%, 700 MWe.

08/28/95 0124 New power level established at 85.5%, 700 MWe.

08/29/95 2118 Started power increase.

2204 Stopped power increase at 92.4%, 785 MWe, to resolve power indication disparity.

08/30/95 1852 Started power increase to new uprated core full power level.

1930 Stopped power increase at 96%, 815 MWe, for two hour thermal soak.

2134 Started power increase.

08/31/95 1230 Stopped power increase at 100%, 840 MWe.

2400 The reporting period ended with the unit operating at 100% power, 845 MWe.

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Surry Monthly Operating Report No. 95-08 Page 10 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MoNTHNEAR: August, 1995 FS 95-26 Updated Final Safety Analysis Report Change 8-01-95 (Safety Evaluation No.95-086)

UFSAR Change 95-26 revised Section 14.3.2, "Rupture of a Main Steam Pipe," to reflect a revised Main Steamline Break (MSLB) accident analysis for Units 1 and 2.

The new analysis was performed, utilizing improved analysis techniques, to provide additional design and operational flexibility by eliminating unnecessary analysis conservatism. The requirements for the MSLB analysis acceptance criteria and the methodology for analyzing the transient remain unchanged. Therefore, an unreviewed safety question does not exist.

DCP 93-054-3 Design Change Package 8-03-95 (Safety Evaluation No.93-203)

Design Change Package 93-054-3 implemented various outage related modifications to correct control room design deficiencies identified by the Control Room Design Review Reassessment Report including: 1) engraving and grouping some annunciator windows, 2) rescaling charging line flow indicators, 3) separating safety injection "A" and "B" alarms, 4) relocating annunciator pushbutton controls away from reactor trip pushbuttons, 5) installing digital auxiliary feedwater flow indicators, 6) adding engineering units to indicator scales, 7) changing the scale on the chemical addition tank, and 8) labeling emergency diesel generator No. 3 watts and VARs indicators.

These modifications, which enhance operator response capability, affect indication and annunciator control only. The operation of safety-related equipment or availability of safety-related power sources is not affected. Therefore, an unreviewed safety question does not exist.

FS 94-20 Updated Final Safety Analysis Report Change 8-03-95 (Safety Evaluation No.95-087)

UFSAR Change 94-20 revised Section 8.3, "[Electrical] System Interconnections," to remove outdated information regarding short term voltage relays that were designed to protect the main transformers from overexcitation.

This was an editorial change, unrelated to nuclear safety, and did not involve any physical plant modifications. Therefore, an unreviewed safety question does not exist.

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Surry Monthly Operating Report No. 95-08 Page 11 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1995 SE 95-094 Safety Evaluation 8-08-95 Safety Evaluation 95-094 was performed to evaluate the operation of Unit 2 at the uprated core power of up to 2546 MWt for the remainder of Cycle 13. Operation at 2546 MWt was recently approved by the NRC through the issuance of Technical Specification Amendment No. 203.

The Cycle 13 core design parameters were calculated for uprated conditions and compared to the applicable 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 Cycle 13 core in accordance with the new Technical Specifications thermal power level will not violate the design basis of plant safety equipment. Thus, the probabilities and consequences of analyzed accidents and equipment malfunctions are not changed. Therefore, an unreviewed safety question does not exist.

DCP 87-013-2 Design Change Package 8-10-95 (Safety Evaluation No.91-020)

Design Change Package (DCP) 87-013-2 replaced the Unit 2 first and second point feedwater heaters, the fifth point external drain coolers, and the feedwater inlet isolation valve for each first point feedwater heater. The DCP also added a n'itrogen purging piping system to the first through sixth point feedwater heaters and fifth point drain coolers to facilitate nitrogen blanketing during extended lay-up periods.

The new heaters and drain coolers utilize stainless steel tubes which eliminate the copper carryover to the steam generators that was associated with the previous equipment. The replacement components were essentially one-for-one replacements of an enhanced design. The modifications did not affect the operation of equipment important to safety or its safety function capability. Therefore, an unreviewed safety question does not exist.

DCP 87-029-2 Design Change Package 8-14-95 Design Change Package (DCP) 87-029-2 replaced the Unit 2 Component Cooling Heat Exchangers 1-CC-E-1 C and 1-CC-E-10.

The new heat exchangers and the originals are of like design with similar duty and pressure drop characteristics. The material composition of the new heat exchangers is superior to that of the originals. The performance characteristics of the Component Cooling system were not altered by this DCP. Therefore, an unreviewed safety question does not exist.

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Surry Monthly Operating Report No. 95-08 Page 12 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MoNTHNEAR: August, 1995 TM S1-95-12 Temporary Modification 8-15-95 (Safety Evaluation No.95-097)

Temporary Modification (TM) S1-95-12 will install an electrical jumper to maintain Unit 2 indication from three component cooling instrument loops in main board rack No. 5 during the replacement of a magnetic amplifier.

The TM will be implemented while Unit 1 is at cold shutdown. This activity will not affect any protection instrument loop or output and will not impact the separation between control and protection loops or instrument racks. Therefore, an unreviewed safety question does not exist.

TM S2-95-11 Temporary Modification 8-23-95 (Safety Evaluation No.95-099)

Temporary Modification (TM) S2-95-11 installed an electrical jumper to maintain power to downstream relays during the replacement of failed relay PC-455E-XB.

The TM allowed the high steam line ~p instrument loops 1, 2, and 3 to function, if required.

This activity did not affect Safety Injection (SI) Train "A" and enabled SI Train "B" to provide its safety function. Double verification of jumper installation/removal and post-maintenance testing were performed. Therefore, an unreviewed safety question did not exist.

TM S1-95-14 Temporary Modification 8-28-95 (Safety Evaluation No.95-103)

Temporary Modification (TM) S1-95-14 rewired three pressurizer heaters from the "C" group to the "A" group in order to maintain 125 kW of heater capacity in the "A" group. This modification was implemented due to failures of Unit 1 "A" group pressurizer heaters and maintains compliance with Virginia Power's response to NUREG-0737, Item 11.E.3.1 which indicated that at least 125 kW of pressurizer heater capacity will be available on each emergency bus.

The TM shifts existing pressurizer heater capacity from one group to another. Total pressurizer heater capacity remains unchanged and the total heater capacity on any emergency bus remains within design limits. Therefore, an unreviewed safety question does not exist.

DCP 95-014-3 Design Change Package 8-30-95 (Safety Evaluation No.95-036)

Design Change Package (DCP) 95-014-3 installed a 3/4 inch test connection and ball valve to facilitate seal leak testing of existing Safety Injection (SI) System valves in the flowpath from the refueling water storage tank to the charging pump suction header.

The new nonsafety-related test connection and valve are isolated from and do not affect the adjacent SI System piping. When not being used for testing, the ball valve will be closed and the test connection will be capped. Therefore, an unreviewed safety question does not exist.

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Surry Monthly Operating Report No. 95-08 Page 19 of 20 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: August, 1995 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received eer Shiement Number Number Enrichment Cask Activit~

Spent Fuel Cask CASTOR V/21 500.11-022.2 8/30/95 21 C28 NOANSI 3.1170 N/A S10 LMOOTR 2.6060 S13 LMOOV1 2.6060 C07 NOANSI' 3.1170 4A2 LM04TN 3.3930 4A7 LM04U9 3.3930 1RO LMOC2J 3.5974 S22 LMOOV5 2.6060 C25 NOANSI 3.1170 4A3 LM04U6 3.3930 5A5 LM04V7 3.3930 1R6 LMOC1S 3.5923 3R3 LMOC1J 3.5886 C26 NOANSI 3.1170 4A6 LM04U6 ;3.3930 5A6 LM04UO 3.3930 2R3 LMOC1A 3.5932 S30 LMOOVK 2.6060 C37 NOANSI 3.1170 S12 LMOOV4 2.6060 S14 LMOOV6 2.6060

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Surry Monthly Operating Report No. 95-08 Page 13 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1995 WO 318998-02 Work Order 8-30-95 (Safety Evaluation No.95-104)

Safety Evaluation No.95-104 evaluated Work Order 318998-02, which was initiated to install plugs in two tubes of the Main Control Room chiller condenser, 1-VS-E-4D. Minor through wall leaks were identified in the affected tubes.

The evaluation concluded that plugging two tubes is acceptable. The capacity of the chiller will continue to exceed the required design basis capacity and the pressure rating of the safety-related class plugs exceeds the maximum chiller operating differential pressure. Therefore, an unreviewed safety question does not exist.

TM 81-95-15 Temporary Modification 8-31-95 (Safety Evaluation No.95-105)

Temporary Modification (TM) S 1-95-15 installed temporary seals on the damaged Unit 1 No. 2 Low Pressure (LP) Turbine rupture discs. The temporary seals will help to maintain condenser vacuum by sealing holes in the rupture discs until they can be replaced during a future unit outage.

The temporary seals will be held in place only by condenser vacuum and will not affect the ability of the rupture discs to perform their intended function (condenser overpressure protection). In addition, a lanyard will be attached to each temporary seal to preclude it from becoming a missile hazard in the event the rupture disc is breached due to an overpressure condition. Therefore, an unreviewed safety question does not exist.

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Surry Monthly Operating Report No. 95-08 Page 15 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: August, 1995 1[2]-GOP-2.5 General Operating Procedures 8-08-95 1[2]-GOP-2.6 (Safety Evaluation No.95-092)

General Operating Procedures 1[2]-GOP-2.5, "Unit Cooldown, 351 °F to 201 °F," and 1[2]-

GOP-2.6, "Unit Shutdown, 201 °F to Ambient," were revised to provide instructions for implementing an alternate unit shutdown method. The new method will enhance control of pressurizer heatup and cooldown rates during plant shutdown and will place the plant in a condition in which hydrogen peroxide can be injected into the Reactor Coolant System (RCS). Hydrogen peroxide reacts with and reduces dissolved hydrogen in the RCS.

Hydrogen peroxide also changes the RCS chemistry to an acid oxidizing state to control the dissolution of activated cobalt species.

Implementation of the new shutdown method requires adherence to the following conditions and limitations: 1) At least one reactor coolant pump must be running while filling the pressurizer and collapsing the bubble, 2) The safety injection accumulators must be depressurized and/or isolated, 3) The pressurizer power operated relief valves must be operable, 4) Reactor Operators tasked with RCS pressure control during this evolution must have received related simulator training, 5) No more than one charging pump can be in operation while the RCS is water solid, 6) Isolation of charging flow to the reactor core is prohibited, 7) Both residual heat removal trains must be filled and vented before making the RCS water solid, and 8) RCS pressure and temperature must be < 365 psig and 350 °F, respectively, while the RCS is solid. These measures will ensure that affected plant equipment is operated within design temperature and pressure limits and in accordance with the Technical Specifications. Therefore, an unreviewed safety question does not exist.

1[2]-GOP-2.5 General Operating Procedures 8-08-95 1(2]-GOP-2.6 Chemistry Procedure CH-93.120 (Safety Evaluation No.95-092)

General Operating Procedures 1[2]-GOP-2.5, "Unit Cooldown, 351 °F to 201 °F,"

1[2]-GOP-2.6, "Unit Shutdown, 201 °F to Ambient," and Chemistry Procedure CH-93.120, "Primary Coolant Chemistry Controls: Refueling Outage" were revised to provide instructions for implementing an alternate hydrogen peroxide addition method to expedite the removal of dissolved hydrogen from the Reactor Coolant System (RCS).

The new method requires the RCS to be water solid and Tave to be :::; 180 °F before the hydrogen peroxide is injected into the RCS. Monitoring of gas spaces open to the RCS is required to ensure potentially explosive mixtures of hydrogen and oxygen are not formed.

This change will not decrease the Technical Specifications margin of safety since it does not change or cause chemistry related Technical Specification parameters to be exceeded. Therefore, an unreviewed safety question does not exist.

  • .I Surry Monthly Operating Report No. 95-08 Page 14 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1995 2-MOP-EP-009 Maintenance Operating Procedure 8-03-95 (Safety Evaluation No.95-090)

Maintenance Operating Procedure 2-MOP-EP-009, "Removal from Service and Return to Service of Breaker 2H1-1-1 A 1," was developed to provide instructions for the installation and removal of temporary modifications that provide alternate power supplies for fire detection equipment while performing preventive maintenance on 480 volt electrical breaker 2-EP-BKR-2H1-1-1 A 1.

This procedure includes steps to verify that the fire detection equipment is operable after both the installation and the removal of the temporary modifications. Therefore, an unreviewed safety question does not exist.

1[2]-GOP-2.4 General Operating Procedures 8-08-95 1[2]-GOP-2.5 (Safety Evaluation No.95-093) 1[2]-GOP-2.6 General Operating Procedures 1[2]-GOP-2.4, "Unit Cooldown, HSD to 351 °F," 1[2]-GOP-2.5, "Unit Cooldown, 351 °F to 201 °F," and 1[2]-GOP-2.6, "Unit Shutdown, 201 °F to Ambient," were revised to provide instructions for the installation and removal of temporary modifications that realign instrument air from the Turbine Building to the Containment Building.

The subject instrument air alignment will be used when a unit is shutdown and containment integrity is required. The pressurizer power operated relief valves are required to be operable while the TMs are in place to ensure overpressure mitigation is available.

Instrument air is a nonsafety-related, nonseismic system that has no impact on the margin of safety as described in the Technical Specification. Therefore, an unreviewed safety question does not exist.

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Surry Monthly Operating Report No. 95-08 Page 16 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1995 1[2]-IPT-FT-MS-P-446 Instrument Periodic Test Procedures 8-10-95 1[2]-1 PT-FT-MS-P-447 (Safety Evaluation No.95-095) 1[2]-IPT-CC-MS-P-446 1[2]-IPT-CC-MS-P-447 Instrument Periodic Test Procedures 1[2]-IPT-FT-MS-P-446, "Turbine Load Loop P-2-446 Functional Test," 1 [2]-IPT-FT-MS-P-447, "Turbine Load Loop P-2-447 Functional Test,"

1(2]-IPT-CC-MS-P-446, "Turbine Load Loop P-2446 Channel Calibration," and 1(2]-

IPT-CC-MS-P-447, "Turbine Load Loop P-2447 Channel Calibration," are being developed to provide instructions for temporarily removing power fuses for the respective instrument loop's signal summator. Removal of the fuses prevents a spurious safety injection initiation under certain test conditions (i.e., Low Tave or Low Main Steam Line Pressure),

during the performance of channel calibration or functional tests.

Only one steam flow protection channel at a time is removed from service for testing as allowed by Technical Specifications. In addition, adequate procedural guidance is provided to assure the restoration of the initial conditions, including requirements for independent verification. Therefore, an unreviewed safety question does not exist.

O-TMOP-3034 Temporary Maintenance Operating Procedure 8-23-95 (Safety Evaluation No.95-100)

Temporary Maintenance Operating Procedure O-TMOP-3034, "Unblocking Ventilation Vent RM Nozzle," was developed to provide instructions for installing a purge supply to the down stream side of the ventilation vent isokinetic nozzle at the input of the ventilation vent radiation monitor, 1-RM-VG-109/110. This modification will enable the ventilation vent multi-ported isokinetic nozzle to be flushed with instrument air to remove a clog that prevents the radiation monitors from drawing a sample from the ventilation vent.

This modification was removed immediately following the purging operation and did not negatively impact any plant equipment or reduce the Technical Specifications margin of safety. Therefore, an unreviewed safety question does not exist.

JCO S95-002 Justification For Continued Operation 8-24-95 (Safety Evaluation No.95-102)

Justification For Continued Operation S95-002 assessed the acceptability of Unit 1 operation with Main Control Room annunciator windows on the "A," "B," "C," "D," and "E" panels inoperable due to power supply problems.

The subject panels are nonsafety-related and do not affect protection circuits.

Compensatory actions included the use of alternate indications and increased monitoring of affected plant parameters by additional control room operators. The assessment concluded that the continued operation of Unit 1 was acceptable until repairs could be effected. Therefore, an unreviewed safety question does not exist.

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Surry Monthly Operating Report No. 95-08 Page 17 of 20 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1995 1[2]-ST-314 Special Tests 8-17-95 (Safety Evaluation 95-077)

Special Tests 1[2]-ST-314, "Steam Generator Moisture Carryover Measurement," were conducted to determine the moisture carryover performance for the Unit 1 and 2 steam generators (SG) at the 96%, 98%, and 100% power levels in order to predict the moisture carryover value at core uprated conditions (i.e., 2546 MWt).

The tests involved the injection of a radioactive tracer (Sodium-24) into each main feedwater (MFW) line downstream of the MFW regulating valves and sampling the main steam lines, SG blowdown, and the common feedwater pump discharge header.

The testing procedures employed controls to prevent any impact on feedwater system performance or the reactor-protection function of the SG level circuitry. Therefore, an unreviewed safety question does not exist.

Surry Monthly Operating Report No. 95-08 Page 18 of 20 CHEMISTRY REPORT MONTHNEAR: August, 1995 Unit No. 1 Unit No. 2 Primarv Coolant Analysis Max. Min. AvQ. Max. Min. AVQ.

Gross Radioactivity, µCi/ml 4.69E-1 2.26E-1 3.16E-1 2.09E-1 1.41 E-1 1.69E-1 Suspended Solids, ppm .$.0.01 .$.0.01 .$.0.01 .$.0.01 .$.0.01 .$.0.01 Gross Tritium, uCi/ml 5.37E-2 4.36E-2 4.82E-2 5.39E-1 4.89E-1 5.12E-1 1131, uCVml 1.40E-3 6.38E-4 9.17E-4 1.48E-4 6.50E-5 1.09E-4 113111133 0.17 0.07 0.11 0.09 0.04 0.07 Hydrogen, cc/kQ 40.8 31.9 37.5 42.6 35.3 39.4 Lithium, oom 0.81 0.71 0.76 2.34 2.08 2.20 Boron - 10, oom* 1.82 0.20 0.30 176.6 164.6 171.5 Oxygen, (DO), ppm .$.0.005 .$.0.005 .$.0.005 .$.0.005 .$.0.005 .$.0.005 Chloride, ppm <0.050 <0.001 0.004 <0.050 0.002 0.007 pH at 25 degree Celsius 9.90 8.80 9.60 6.82 6.59 6.74 Boron - 1O = Total Boron x 0.196 Comments:

None

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Surry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED No. 95-08 Page 20 of 20 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: August, 1995 None During the Reporting Period J

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