ML18153A762
| ML18153A762 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| 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) | |
Text
g; VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 12, 1995 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
-VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.
NO/RPC:vlh Docket Nos.
License Nos.95-471 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of August 1995.
Very truly yours,
~6~
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
TABLE OF CONTENTS Section Surry Monthly Operating Report No. 95-08 Page 2 of 20 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.:
Date:
Completed By:
50-280 09-05-95 D. Mason Telephone:
(804) 365-2459 1. Unit Name:...................................................
- 2.
Reporting Period:..........................................
- 3.
Licensed Thermal Power (MWt):.......................
- 4.
Nameplate Rating (Gross MWe):.......................
- 5.
Design Electrical Rating (Net MWe):..................
- 6.
Maximum Dependable Capacity (Gross MWe):....
- 7.
Maximum Dependable Capacity (Net MWe):........
Surry Unit 1 August, 1995 2441 847.5 788 820 781
- 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
'\\.
OPERATING DATA REPORT
('
Surry Monthly Operating Report No. 95-08 Page 4 of 20 Docket No.:
Date:
Completed By:
50-281 09-05-95 D. Mason
- 1.
Unit Name:...................................................
- 2.
Reporting Period:..........................................
- 3.
Licensed Thermal Power (MWt):.......................
- 4.
Nameplate Rating (Gross MWe):.......................
- 5.
Design Electrical Rating (Net MWe):..................
- 6.
Maximum Dependable Capacity (Gross MWe):....
- 7.
Maximum Dependable Capacity (Net MWe):........
Surry Unit 2 August, 1995 2546 847.5 788 820 781 Telephone:
(804) 365-2459
- 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 (1)
(2)
(3)
(4)
(5)
Method Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
09-04-95 Completed by:
Craig Olsen Telephone:
(804) 365-2155 Duration of LER System Component Cause & Corrective Action to Date Type Hours Reason Shutting No.
Code Code Prevent Recurrence (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 (NU REG 0161)
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 * -
Other (Explain)
(5)
Exhibit 1 - Same Source.
(1)
Duration Date Type Hours (1)
F:
Forced
)
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 (2)
(3)
(5)
Docket No.:
50-281 Unit Name:
Surry Unit 2 Date:
09-04-95 Completed by:
Craig Olsen Telephone:
(804) 365-2155 Method of Reason Shutting Down Rx LER No.
(4)
System Code Component Cause & Corrective Action to (2)
REASON:
Code Prevent Recurrence None During the Reporting Period (3)
METHOD:
S:
Scheduled A
Equipment Failure (Explain) 1 -
Manual B
Maintenance or Test C
Refueling D
Regulatory Restriction E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
(4)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NU REG 0161) 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
(5)
Exhibit 1 - Same Source.
MONTH:
August, 1995 Day 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 INSTRUCTIONS
,)
Surry Monthly Operating Report No. 95-08 Page 7 of 20 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe-Net)
Day 753 17 750 18 745 19 727 20 731 21 729 22 730 23 729 24 724 25 717 26 709 27 701 28 691 29 685 30 682 31 679 Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
09-06-95 Completed by:
Barry C. Bryant Telephone:
(804) 365-2786 Average Daily Power Level (MWe-Net) 672 663 662 655 648 639 636 631 622 625 619 611 609 599 585 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.
________ _J
MONTH:
August, 1995 Day 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 INSTRUCTIONS j
Surry Monthly Operating Report No. 95-08 Page 8 of 20 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)
Day 761 17 759 18 756 19 756 20 752 21 746 22 759 23 759 24 767 25 766 26 758 27 663 28 732 29 771 30 771 31 772 Docket No.: 50-281 Unit Name:
Surry Unit 2 Date: 09-06-95 Completed by:
Barry C. Bryant Telephone:
(804) 365-2786 Average Daily Power Level (MWe - Net) 773 771 772 772 767 764 761 759 731 740 637 679 688 753 799 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. 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 08/31/95 UNIT Two:
08/01/95 08/11/95 08/13/95 08/25/95 08/26/95 08/28/95 08/29/95 08/30/95 08/31/95 0000 2400 0000 2150 2325.
0944 The reporting period began with the unit operating at 100% power, 790 MWe.
The reporting period ended with the unit operating at 79.5% power, 590 MWe, in a power coastdown due to fuel depletion.
The reporting period began with the unit operating at 100% power, 795 MWe.
Started power reduction to maintain condenser vacuum while cleaning the "B" waterbox.
Stopped power reduction at 91 %, 715 MWe.
Started power increase following "B" waterbox maintenance.
1036 Stopped power increase at 100%, 810 MWe.
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.
2031 2130 0124 2118 Started power reduction to perform Main Control Room instrument scaling activities associated with the implementation of the uprated core power level of 2546 MWt.
Stopped power reduction at 90%, 700 MWe.
New power level established at 85.5%, 700 MWe.
Started power increase.
2204 Stopped power increase at 92.4%, 785 MWe, to resolve power indication disparity.
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.
1230 Stopped power increase at 100%, 840 MWe.
2400 The reporting period ended with the unit operating at 100% power, 845 MWe.
FS 95-26 DCP 93-054-3 FS 94-20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MoNTHNEAR: August, 1995
)
Updated Final Safety Analysis Report Change (Safety Evaluation No.95-086)
Surry Monthly Operating Report No. 95-08 Page 10 of 20 8-01-95 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.
Design Change Package (Safety Evaluation No.93-203) 8-03-95 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.
Updated Final Safety Analysis Report Change (Safety Evaluation No.95-087) 8-03-95 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.
SE 95-094 DCP 87-013-2 DCP 87-029-2 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1995 Safety Evaluation
)
Surry Monthly Operating Report No. 95-08 Page 11 of 20 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.
Design Change Package (Safety Evaluation No.91-020) 8-10-95 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.
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.
TM S1-95-12 TM S2-95-11 TM S1-95-14 DCP 95-014-3 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MoNTHNEAR: August, 1995 Temporary Modification (Safety Evaluation No.95-097)
)
Surry Monthly Operating Report No. 95-08 Page 12 of 20 8-15-95 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.
Temporary Modification (Safety Evaluation No.95-099) 8-23-95 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.
Temporary Modification (Safety Evaluation No.95-103) 8-28-95 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.
Design Change Package (Safety Evaluation No.95-036) 8-30-95 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.
New or Spent Fuel Shipment Date Stored or Number Received Spent Fuel Cask CASTOR V/21 500.11-022.2 8/30/95 FUEL HANDLING UNITS 1 & 2 MONTHNEAR: August, 1995 Number of Assemblies Assembly ANSI eer Shiement Number Number 21 C28 NOANSI S10 LMOOTR S13 LMOOV1 C07 NOANSI' 4A2 LM04TN 4A7 LM04U9 1RO LMOC2J S22 LMOOV5 C25 NOANSI 4A3 LM04U6 5A5 LM04V7 1R6 LMOC1S 3R3 LMOC1J C26 NOANSI 4A6 LM04U6 5A6 LM04UO 2R3 LMOC1A S30 LMOOVK C37 NOANSI S12 LMOOV4 S14 LMOOV6
)
,/
Surry Monthly Operating Report No. 95-08 Page 19 of 20 New or Spent Initial Fuel Shipping Enrichment Cask Activit~
3.1170 N/A 2.6060 2.6060 3.1170 3.3930 3.3930 3.5974 2.6060 3.1170 3.3930 3.3930 3.5923 3.5886 3.1170
- 3.3930 3.3930 3.5932 2.6060 3.1170 2.6060 2.6060
WO 318998-02 TM 81-95-15 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1995 Work Order (Safety Evaluation No.95-104)
\\
j Surry Monthly Operating Report No. 95-08 Page 13 of 20 8-30-95 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.
Temporary Modification (Safety Evaluation No.95-105) 8-31-95 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.
1 [2]-GOP-2.5 1 [2]-GOP-2.6 1 [2]-GOP-2.5 1 (2]-GOP-2.6 CH-93.120
)
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 General Operating Procedures (Safety Evaluation No.95-092) 8-08-95 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.
General Operating Procedures Chemistry Procedure (Safety Evaluation No.95-092) 8-08-95 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.
2-MOP-EP-009 1 [2]-GOP-2.4 1 [2]-GOP-2.5 1 [2]-GOP-2.6
.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 Maintenance Operating Procedure (Safety Evaluation No.95-090) 8-03-95 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.
General Operating Procedures (Safety Evaluation No.95-093) 8-08-95 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.
1 [2]-IPT-FT-MS-P-446 1 [2]-1 PT-FT-MS-P-447 1 [2]-IPT-CC-MS-P-446 1 [2]-IPT-CC-MS-P-447 O-TMOP-3034 JCO S95-002
)
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 Instrument Periodic Test Procedures (Safety Evaluation No.95-095) 8-10-95 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.
Temporary Maintenance Operating Procedure (Safety Evaluation No.95-100) 8-23-95 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.
Justification For Continued Operation (Safety Evaluation No.95-102) 8-24-95 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.
1 [2]-ST-314
)
Surry Monthly Operating Report No. 95-08 Page 17 of 20 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: August, 1995 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.
CHEMISTRY REPORT MONTHNEAR: August, 1995 Unit No. 1 Primarv Coolant Analysis Max.
Min.
AvQ.
Gross Radioactivity, µCi/ml 4.69E-1 2.26E-1 3.16E-1 Suspended Solids, ppm
.$.0.01
.$.0.01
.$.0.01 Gross Tritium, uCi/ml 5.37E-2 4.36E-2 4.82E-2 1131, uCVml 1.40E-3 6.38E-4 9.17E-4 113111133 0.17 0.07 0.11 Hydrogen, cc/kQ 40.8 31.9 37.5 Lithium, oom 0.81 0.71 0.76 Boron - 10, oom*
1.82 0.20 0.30 Oxygen, (DO), ppm
.$.0.005
.$.0.005
.$.0.005 Chloride, ppm
<0.050
<0.001 0.004 pH at 25 degree Celsius 9.90 8.80 9.60 Boron - 1 O = Total Boron x 0.196 Comments:
None Surry Monthly Operating Report No. 95-08 Page 18 of 20 Unit No. 2 Max.
Min.
AVQ.
2.09E-1 1.41 E-1 1.69E-1
.$.0.01
.$.0.01
.$.0.01 5.39E-1 4.89E-1 5.12E-1 1.48E-4 6.50E-5 1.09E-4 0.09 0.04 0.07 42.6 35.3 39.4 2.34 2.08 2.20 176.6 164.6 171.5
.$.0.005
.$.0.005
.$.0.005
<0.050 0.002 0.007 6.82 6.59 6.74
____J
)
Surry Monthly Operating Report No. 95-08 Page 20 of 20 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: August, 1995 None During the Reporting Period J