ML18153A786

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Monthly Operating Repts for Sept 1995 for Surry Power Station Units 1 & 2.W/951013 Ltr
ML18153A786
Person / Time
Site: Surry  Dominion icon.png
Issue date: 09/30/1995
From: Mason D, Olsen C, Saunders R
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-520, NUDOCS 9510200138
Download: ML18153A786 (23)
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 13, 1995 U.S. Nuclear Regulatory Commission Serial No.95-520 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 September 1995.

Very truly yours, R. F. Saunders Vice President - Nuclear Operations 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 9510200138 950930 PDR ADOCK 05000280 R PDR

~i,I

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 95-09 Approved:

~~cD- Station Manager

/0-(2 *5 Date s

  • e Surry Monthly Operating Report No. 95-09 Page 2 of 22 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 NRG Approval ............................................................................... 1O Procedure or Method of Operation Changes That Did Not Require NRG Approval ........................................... 15 Tests and Experiments That Did Not Require NRG Approval ...................................................................... 19 Chemistry Report ............................................................................................................................. 20 Fuel Handling - Unit No. 1 ...................................................................... ,.* ........................................... 21 Fuel Handling - Unit No. 2 ................................................................................................................... 21 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications ................................................................................................... 22
  • Surry Monthly Operating Report No. 95-09 Page 3 of 22 OPERATING DATA REPORT Docket No.: 50-280 Date: 10-03-95 Completed By: D. Mason Telephone: (804) 365-2459
1. Unit Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . September, 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 .......................... 720.0 6551.0 199631.0
12. Number of Hours Reactor Was Critical .......... 171.3 5823.0 136292.7
13. Reactor Reserve Shutdown Hours ............... 0 0 3774.5
14. Hours Generator On-Line ........................... 170.7 5787.9 134028.9
15. Unit Reserve Shutdown Hours ..................... 0 0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 305398.3 13754722.2 312208461.4
17. Gross Electrical Energy Generated (MWH) .... 95170.0 4566930.0 102180763. 0
18. Net Electrical Energy Generated (MWH) ........ 90297.0 4396199.0 97105222.0
19. Unit Service Factor ................................... 23.7% 88.4% 67.1%
20. Unit Availability Factor ............................... 23.7% 88.4% 69.0%
21. Unit Capacity Factor (Using MDC Net) ........... 16.1% 85.9% 62.7%

22., Unit Capacity Factor (Using DER Net) ........... 15.9% 85.2% 61.7%

23. Unit Forced Outage Rate ............................ 0.0% 3.6% 16.2%
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: October 18, 1995
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

  • Surry Monthly Operating
  • Report No. 95-09 Page 4 of 22 OPERATING DATA REPORT Docket No.: 50-281 Date: 10-03-95 Completed By: D. Mason Telephone: (804) 365-2459 1 . Unit Name: .................................................. . Surry Unit 2
2. Reporting Period: ......................................... . September, 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): ... . 840
7. Maximum Dependable Capacity (Net MWe): ....... . 801
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

Maximum Dependable Capacity (Gross MWe) was increased from 820 to 840 and Maximum Dependable Capacity (Net MWe) was increased from 781 to 801 based on the implementation of Amendment 203 to Facility Operating License DPR-37, which 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 .......................... 720.0 6551.0 196511.0
12. Number of Hours Reactor Was Critical .......... 720.0 5306.6 133644.1
13. Reactor Reserve Shutdown Hours ............... 0 0 328.1
14. Hours Generator On-Line ........................... 720.0 5236.7 131703.8
15. Unit Reserve Shutdown Hours ..................... 0 0 0
16. Gross Thermal Energy Generated (MWH) ...... 1821754.6 12575075.4 307843539.7
17. Gross Electrical Energy Generated (MWH) .... 600305.0 4158470.0 100600764.0
18. Net Electrical Energy Generated (MWH) ........ 581173.0 4010089.0 95603125.0
19. Unit Service Factor ................................... 100.0% 79.9% 67.0%
20. Unit Availability Factor ............................... 100.0% 79.9% 67.0%
21. Unit Capacity Factor (Using MDC Net) ........... 100.8% 78.2% 62.4%
22. Unit Capacity Factor (Using DER Net) ........... 102.4% 77.7% 61.7%
23. Unit Forced Outage Rate ............................ 0.0% 3.8% 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

  • e Surry Monthly Operating Report No. 95-09 Page 5 of 22 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: September, 1995 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-02-95 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 950908 s N/A C 2 N/A N/A N/A Scheduled Refueling Outage (1) (2) (3)

F: Forced REASON: METHOD:

S: Scheduled A - Equipment Failure (Explain) 1 - Manual B Maintenance or Test 2 - Manual Scram.

C Refueling 3 - Automatic Scram.

D Regulatory Restriction 4 - Other (Explain)

E Operator Training & Licensing Examination F Administrative G Operational Error (Explain)

(4) (5)

Exhibit G - Instructions for Preparation of Data Entry Sheets Exhibit 1 - Same Source.

for Licensee Event Report (LER) File (NUREG 0161)

  • 4lturry Monthly OperatingNo.Report 95-09 Page 6 of 22 UNIT SHUTDOWN AND POWER REDUCTION (EOUAL To OR GREATER THAN 20%)

REPORT MONTH: September, 1995 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-02-95 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)

  • e Surry Monthly Operating Report No. 95-09 Page 7 of 22 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-05-95 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: September, 1995 _

Average Daily Power Level Average Daily Power Level Day (MWe - Net) Day (MWe- Net) 1 543 17 0 2 450 18 0 3 564 19 0 4 548 20 0 5 563 21 0 6 548 22 0 7 530 23 0 8 17 24 0 9 0 25 0 10 0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0 15 0 16 0 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.

-- ---- _J

  • e Surry Monthly Operating Report No. 95-09 Page 8 of 22 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 10-05-95 Completed by: Barry C. Bryant Telephone: (804) 365-2786 MONTH: September, 1995 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe - Net) 1 787 17 762 2 809 18 816 3 810 19 817 4 810 20 813 5 809 21 811 6 809 22 810 7 802 23 811 8 810 24 780 9 809 25 816 10 809 26 816 11 809 27 817 12 809 28 802 13 810 29 818 14 808 30 818 15 813 16 796 INSTRUCTIONS On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.
  • e Surry Monthly Operating Report No. 95-09 Page 9 of 22

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: September, 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:

09/01/95 0000 The reporting period began with the unit operating at 79.5% power, 590 MWe, in a power coastdown due to fuel depletion.

09/07/95 2203 Began power reduction from 73%, 565 MWe, to prepare for start of refueling outage.

09/08/95 0241 Generator off-line.

0320 Reactor manually tripped.

09/14/95 0920 Reactor Coolant System (RCS) standpipe level indication dropped from 18 feet to 13.3 feet. The Residual Heat Removal system remained operable during this event.

1036 Indicated RCS standpipe level restored to 18 feet.

09/29/95 0801 Emergency Diesel Generator No. 1 automatically started due to an undervoltage condition on the F transfer bus.

09/30/95 2400 The reporting period ended with the unit at refueling shutdown.

UNIT Two:

09/01/95 0000 The reporting period began with the unit operating at 100% power, 845 MWe.

09/16/95 1140 Started power reduction to perform Operations Surveillance Procedure 2-0SP-TM-001, Turbine Inlet Valve Freedom Test.

1220 Stopped power reduction at 95.5%, 810 MWe.

2254 Started power increase.

2358 Stopped power increase at 100%, 842 MWe.

09/17/95 0840 Started power reduction to perform Operations Surveillance Procedure 2-0SP-TM-001, Turbine Inlet Valve Freedom Test.

1149 Stopped power reduction at 81.5%, 700 MWe.

1753 Started power increase.

2015 Stopped power increase at 100%, 845 MWe.

09/24/95 0557 Started power reduction to perform Operations Surveillance Procedure 2-0SP-TM-001, Turbine Inlet Valve Freedom Test.

1020 Stopped power reduction at 81.5%, 710 MWe.

1316 Started power increase.

1518 Stopped power increase at 100%, 845 MWe.

09/29/95 0801 Emergency Diesel Generator No. 3 automatically started due to an undervoltage condition on the F transfer bus.

09/30/95 2400 The reporting period ended with the unit operating at 100% power, 840 MWe.

  • FACILITY CHANGES THAT DID NOT e Surry Monthly Operating Report No. 95-09 Page 10 of 22 REQUIRE NRC APPROVAL MONTHNEAR: September, 1995 TM S1-95-16 Temporary Modification 9-01-95 (Safety Evaluation No.95-108)

Temporary Modification (TM) S1-95-16 installed temporary seals on damaged Unit 1 and Unit 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 by condenser vacuum only 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.

TM S2-95-12 Temporary Modification 9-01-95 (Safety Evaluation No.95-107)

Temporary Modification (TM) S2-95-12 installed an electrical jumper to maintain power to downstream steam dump control relays during the replacement of Unit 2 failed relay 63X1 -

B.

The TM did not affect Safety Injection (SI) Train "A" and enabled SI Train "B" to provide its safety function. Double verification of jumper installation/removal was performed.

Therefore, an unreviewed safety question does not exist.

SE 95-110 Safety Evaluation 9-07-95 Safety Evaluation 95-110 was performed to evaluate the 1995 Unit 1 refueling outage schedule.

The evaluation concluded that the refueling outage schedule is acceptable based on a review of the planning, procedures, policies, shutdown risk, and monitoring by management that are performed for the outage. Therefore, an unreviewed safety question does not exist.

TM S1-95-17 Temporary Modification 9-11-95 (Safety Evaluation No.95-116)

Temporary Modification S1-95-17 temporarily installed a television camera in the Unit 1 containment, associated cables, and a television monitor in the main control room to enable operators to monitor a leak from the casing of Residual Heat Removal pump 1-RH-P-1 A.

This modification did not impact plant control or protection systems. The camera was mounted in a manner that ensured that equipment would not be damaged if it fell.

Therefore, an unreviewed safety question does not exist.

  • FACILITY CHANGES THAT DID NOT e Surry Monthly Operating Report No. 95-09 Page 11 of 22 REQUIRE NRC APPROVAL MONTHNEAR: September, 1995 SE 95-118 Safety Evaluation 9-12-95 Safety Evaluation 95-118 assessed the continued operation of Unit 1 with the "B" Main Transformer automatic fire protection deluge system isolated due to spurious actuations.

The nonsafety-related deluge system can continue to be manually actuated, if necessary.

In addition, the Surry Pre-Fire plans include the use of nearby hose houses to manually suppress a transformer fire. The evaluation concluded that the substitution of these manual actions is acceptable for a fire at the "B" Main Transformer and is within the capability and training of the Fire Brigade to determine which method of manual suppression is best suited for a given fire. Therefore, an unreviewed safety question does not exist and this condition is acceptable until repairs can be made.

TM S2-95-13 Temporary Modification 9-13-95 (Safety Evaluation No.95-119)

Temporary Modification (TM) S2-95-13 installed a mechanical jumper to temporarily route the discharge of Unit 2 recirculation spray heat exchanger (RSHX) radiation monitor pumps 2-SW-P-58, 2-SW-P-5C, and 2-SW-P-50 to a drain connection and spare penetration on the Unit 1 service water (SW) outlet line from RSHX 1-RS-E-1A. The TM was implemented to facilitate the inspection, cleaning, and coating application of RSHX outlet motor-operated valves 1-SW-MOV-1058 and 1-SW-MOV-105C. The TM will also allow the discharge line from RSHX 1-RS-E-10 to be breached to connect the discharge from the charging pump SW pumps.

The mechanical jumper was pressure and temperature rated to safely convey the discharge of the subject pumps and was functionally tested after installation. The RSHX service water radiation monitoring system was maintained in an operable condition while the TM was in place and was tested following the removal of the jumper. Therefore, an unreviewed safety question does not exist.

WO 318998-02 Work Order 9-13-95 (Safety Evaluation No.95-104, Revision 1)

Safety Evaluation No.95-104, Revision 1 evaluated Work Order 318998-02, which was initiated to install plugs in four tubes of the Main Control Room chiller condenser, 1-VS-E-

40. Minor through wall leaks were identified in the affected tubes.

The evaluation concluded that plugging four 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.

  • FACILITY CHANGES THAT DID NOT e Surry Monthly Operating Report No. 95-09 Page 12 of 22 REQUIRE NRC APPROVAL MONTHNEAR: September, 1995 TM S1-95-18 Temporary Modification 9-14-95 (Safety Evaluation No.95-121)

Temporary Modification (TM) S1-95-18 maintained the Primary Drains Transfer Tank (POTT) pressure control valve, 1-DG-PCV-100, in the open position to eliminate spurious High Flux at Shutdown alarms caused from electrical noise generated when 1-DG-SOV-100 energizes to open 1-DG-PCV-100.

The TM was in place while the unit was at Cold Shutdown or Refueling Shutdown with the containment at atmospheric conditions. At these conditions, the Primary Drains System functioned normally. Containment isolation capability was unaffected by this TM.

Therefore, an unreviewed safety question does not exist.

DCP 94-040 Design Change Package 9-15-95 (Safety Evaluation No.95-041)

Design Change Package 94-040 replaced the safety-related motor operator on the Unit 1 alternate High Head Safety Injection cold leg isolation valve, 1-SI-MOV-1842, and installed a new valve yoke to accommodate the replacement actuator. The larger, similarly designed replacement motor operator provides additional margin to ensure the reliability of 1-SI-MOV-1842 in performing its safety function.

The modification was performed at cold shutdown. The replacement motor operator did not change the valve function or impact the system design basis. Therefore, an unreviewed safety question does not exist.

DR S-95-0747 Deviation Report 9-21-95 (Safety Evaluation No.95-124)

Safety Evaluation 95-124 assessed Deviation Report S-95-0747 concerning the degraded operation of Unit 2 auxiliary spray valve 2-CH-HCV-2311. The subject valve would not shut completely during the last Unit 2 startup and had to be mechanically closed.

Leakage from the valve has been noted, but cannot be quantified.

The evaluation concluded that this condition is acceptable since the auxiliary spray is not assumed to be available for any design basis accident scenario and the valve leakage will not produce spray temperatures that will violate applicable Technical Specifications.

Therefore, an unreviewed safety question does not exist.

  • FACILITY CHANGES THAT DID NOT e Surry Monthly Operating Report No. 95-09 Page 13 of 22 REQUIRE NRC APPROVAL MONTHNEAR: September, 1995 SE 95-125 Safety Evaluation 9-21-95 Safety Evaluation 95-125 was performed to evaluate the Unit 1 Cycle 14 reload core and the operation of Unit 1 at an uprated core power of up to 2546 MWt. Operation at 2546 MWt was recently approved by the NRC through the issuance of Technical Specification Amendment No. 203.

The Cycle 14 core design parameters were calculated for uprated conditions 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.

TM S1-95-19 Temporary Modification 9-28-95 (Safety Evaluation No.95-135)

Temporary Modification S1-95-19 installed electrical jumpers to bypass test switch LC-475-TA on the Unit 1 Safety Injection (SI) Train "A" circuitry to allow the switch to be replaced without rendering the circuits inoperable.

SI Train "B" was not affected by this activity and both trains remained capable of operating as designed. Double verification of jumper installation/removal and post-maintenance testing were performed. Therefore, an unreviewed safety question does not exist.

TM S1-95-20 Temporary Modification 9-28-95 (Safety Evaluation No.95-134)

Temporary Modification S1-95-20 installed electrical jumpers to bypass test switch LC-474-TA on the Unit 1 Safety Injection (SI) Train "A" circuitry to allow the switch to be replaced without rendering the circuits inoperable.

SI Train "B" was not affected by this activity and both trains remained capable of operating as designed. Double verification of jumper installation/removal and post-maintenance testing were performed. Therefore, an unreviewed safety question does not exist.

  • FACILITY CHANGES THAT DID NOT e Surry Monthly Operating Report No. 95-09 Page 14 of 22 REQUIRE NRC APPROVAL MONTHNEAR: September, 1995 AC 81-95-0921 Administrative Control 9-29-95 (Safety Evaluation No.95-122, Revision 1)

Administrative control of the Unit 1 Component Cooling Heat Exchanger (CCHX) Service Water (SW) outlet manual isolation valves and the Unit 1 Turbine Building SW supply manual isolation valve was established while SW system motor operated valves (MOV) 1-SW-MOV-102A and 1-SW-MOV-1028 were de-energized in the open position.

The administrative controls were established to maintain the capability to isolate the non-essential SW flowpaths affected by the de-energized SW MOVs. The subject manual isolation valves were controlled by a licensed operator who was capable of closing the valves within the time limit assumed as part of the design bases to ensure that intake canal inventory was maintained. Therefore, an unreviewed safety question does not exist.

TM S1-95-21 Temporary Modification 9-29-95 (Safety Evaluation No.95-136)

Temporary Modification (TM) S1-95-21 installed electrical jumpers to maintain power to downstream Hi-Consequence Limiting Safeguards (Hi-CLS) system output relays during the replacement of Unit 1 failed relay 3/4-CLS-1 B.

The activity was performed while Unit 1 was at cold shutdown when the CLS system was not required. Double verification of jumper installation/removal was performed. Therefore, an unreviewed safety question does not exist.

DR 81-95-2319 Deviation Report 9-30-95 (Safety Evaluation Nos.95-137 and 95-138)

Safety Evaluation Nos.95-137 and 95-138 assessed the condition reported by Deviation Report S1-95-2319 concerning the discovery of small pieces of foreign material (one-eighth inch Flex Gasket material ranging in length from 1.25 to 3.25 inches) on the lower Unit 1 core plate subsequent to the Cycle 13 core offload. The foreign material was removed from the lower core plate and the area below was vacuumed.

In case not all of the foreign material was identified and removed, an evaluation was performed to determine the impact on the fuel in the Unit 1 Cycle 14 core and the ability to insert the control rods. The evaluation concluded that the presence of any small pieces of Flex Gasket material will not result in a failure of instrument tubes or rod control cluster assembly interference problems. The presence of such material could result in a few failed fuel rods, but would not result in the Technical Specifications limit for coolant activity being exceeded.

An evaluation was also performed to determine the impact of any remaining foreign material on the operation of systems associated with the Reactor Coolant System (RCS).

Specifically, the Sample, Residual Heat Removal, Safety Injection, Chemical and Volume Control, and RCS Vents and Drains systems were evaluated. The evaluation concluded that any remaining foreign material would not be large enough to cause a catastrophic failure of these systems or prevent them from performing their intended function during accident conditions. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES e Surry Monthly Operating Report No. 95-09 Page 15 of 22 THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: September, 1995 1-0PT-ZZ-001 Operations Periodic Test Procedures 9-05-95 1-0PT-ZZ-002 (Safety Evaluation No.95-109)

Opt3rations Periodic Test Procedures 1-0PT-ZZ-001, "ESF Actuation with Undervoltage and Degraded Voltage - 1H Bus" and 1-0PT-ZZ-002, "ESF Actuation with Undervoltage and Degraded Voltage - 1J Bus" were revised to reflect a change in the test initial conditions regarding reactor cooling.

The revised initial test conditions require both trains of the Residual Heat Removal (RHR) system to be operable with one train in service. This change allows the reactor coolant pumps to be secured before the test is performed. The unit will be at cold shutdown and only one train of the RHR system will be tested at a time (for up to two hours). The procedures also provide instructions to place the RHR train being tested back in service, if required. Therefore, an unreviewed safety question does not exist.

2-NPT-RX-002 Engineering Periodic Test Procedure 9-07-95 (Safety Evaluation No.95-111)

Engineering Periodic Test Procedure 2-NPT-RX-002, "Reactor Core Flux Maps" was temporarily changed to provide instructions for installing an electrical jumper around the limit switch for the detector withdrawn position on the Unit 2 "A" incore detector drive motor. This jumper will allow use of the "A" detector 1O path transfer device to perform Technical Specifications required full core flux maps. The "A" detector 5 path transfer switch will also be disabled to prevent damaging the detector cable when the detector is inserted into its storage location.

This change will facilitate the continued performance of full core flux mapping and will prevent unnecessary radiation hazards. Furthermore, operation of the incore instrumentation system will not be adversely affected and the integrity of the reactor coolant system boundary at the seal table will not be compromised. Therefore, an unreviewed safety question does not exist.

1-0P-VS-001 Operating Procedure 9-08-95 1-TOP-4064 Temporary Operating Procedures 1-TOP-4065 (Safety Evaluation No.95-112)

Operating Procedure 1-0P-VS-001, "Containment Ventilation," was revised and Temporary Operating Procedures 1-TOP-4064, "Connecting Temporary Hard Duct for Purging Unit 1 Containment with 1-VS-F-59," and 1-TOP-4065, "Disconnecting Temporary Hard Duct for Purging Unit 1 Containment with 1-VS-F-59," were developed to provide instructions for the installation, operation, and removal of a mechanical jumper between the Unit 1 containment purge and the nonsafety-related auxiliary building charcoal exhaust filter 1-VS-FL-14.

The subject ventilation alignment protects the safety-related filters from potential contaminants originating from the Unit 1 containment while shutdown and does not impact the ability of the safety-related filters to respond to a Unit 2 safety injection signal. These procedure changes reflect the requirement for the Unit 1 containment purge to be aligned to the safety-related charcoal exhaust filters during fuel handling operations in the Unit 1 containment. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES e Surry Monthly Operating Report No. 95-09 Page 16 of 22 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1995 1[2]-0PT-RC-001 Operations Periodic Test Procedures 9-08-95 (Safety Evaluation No.95-113)

Operations Periodic Test Procedures 1[2]-0PT-RC-001, "Testing the Przr PORV Air Supply Check Valves and Verifying the Alternate Air Supply," were revised to provide instructions for temporarily lifting electrical leads to facilitate the performance of the test.

The procedurally controlled temporary modification allows independent testing of each of the solenoid valves that control air to the air operated power operated relief valves (PORV). The procedures include post-modification testing to ensure the solenoid valves operate properly and require double verification of electrical lead termination. The testing is performed with the affected unit at Cold Shutdown or Refueling Shutdown. Therefore, an unreviewed safety question does not exist.

1-0PT-81-006 Operations Periodic Test Procedure 9-08-95 (Safety Evaluation No.95-115)

Operations Periodic Test Procedure, 1-0PT-81-006, "SI Accumulator Discharge Check Valves Full Open Test" was revised to provide instructions for verifying that the Safety Injection system accumulator discharge check valves exhibit full stroke operation during a controlled accumulator dump into the closed Reactor Coolant System (RCS).

The unit will be at cold shutdown and the equipment and systems will be operated within design limits during the performance of this test. Measures will be taken to preclude the introduction of gas into the RCS and Residual Heat Removal system. Reactivity addition will be precluded by ensuring the accumulator boron concentration is greater than the RCS minimum refueling shutdown margin concentration and by ensuring that the accumulator temperature is greater than the minimum RCS shutdown margin temperature. Therefore, an unreviewed safety question does not exist.

1-08P-81-002 Operations Surveillance Procedure 9-08-95 (Safety Evaluation No.95-114)

Operations Surveillance Procedure, 1-0SP-81-002, "Charging Pump Head Curve Verification," was developed to provide instructions for throttling the Unit 1 charging pump discharge isolation motor operated valves during the performance of the subject test to facilitate accurate full range flow testing of the charging pumps. The change also provides directions for the implementation of associated temporary system modifications (e.g., removal of seal-in contacts).

Unit 1 will be at Cold Shutdown or Refueling Shutdown during the performance of this test.

The installation and removal of the temporary modifications will be independently verified and will not affect the operation of the system. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES e Surry Monthly Operating Report No. 95-09 Page 17 of 22 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September, 1995 1[2]-EPT-0903-01 Electrical Periodic Tests 9-21-95 (Safety Evaluation No.95-030, Revision 1)

Electrical Periodic Tests 1[2]-EPT-0903-01, "RCP Heat Detector Testing," were developed to provide instructions for implementing temporary modifications to facilitate testing of the continuous fire detectors in each reactor coolant pump cubicle. The fire detector element leads and alarm output leads will be lifted and test equipment installed to test the circuit.

The fire detector control module is tested by simulating the detector element and verifying the actuation of the alarm to the control box for annunciation in the control room.

System operation is verified upon removal of the test equipment by pushing the local test button on the control panel to ensure circuit cqntinuity, and by monitoring the alarm response in the control room. To ensure that a fire in the reactor coolant pump (RCP) cubicles during the test would be detected, a Technical Specification limiting condition for operation will be entered that requires monitoring of the RCP pump bearing and motor temperature or containment RTDs during performance of the procedure on an hourly basis. As an alternative, containment walkdowns may be performed once every eight hours or containment temperature may be monitored through the P250 computer every 15 minutes. These measures will ensure a fire in the RCP cubicle will not go undetected.

Therefore, an unreviewed safety question does not exist.

1-EPT-0106-06 Electrical Periodic Test 9-24-95 (Safety Evaluation 95-127, Revision 1)

Electrical Periodic Test 1-EPT-0106-06, "Main Station Battery 1A Refueling Performance Test," was revised to ensure the capability of Station Battery 1A to supply its associated DC bus during refueling interval performance testing.

The evaluation concluded that Station Battery 1A could continue to meet its design functions during the performance testing. The testing is performed when the Unit 1 reactor is de-fueled and battery loads are minimal. Therefore, an unreviewed safety question does not exist.

FDTP-92-052-3-6 Final Design Test Procedure 9-25-95 (Safety Evaluation No.95-128)

Final Design Test Procedure FDTP-92-052-3-6 was developed to provide instructions for functionally testing the Station Blackout (SBO) Diesel Generator to verify the requirements of 10 CFR 50.63 and R. G. 1.155 are met.

The testing will be conducted with Unit 1 at Cold Shutdown and the reactor de-fueled. The No. 1 and No. 2 Emergency Diesel Generators will be fully operable. Therefore, an unreviewed safety question does not exist.

PROCEDURE OR METHOD OF OPERATION CHANGES lturry Monthly Operating Report No. 95-09 Page 18 of 22 THAT DID NOT REQUIRE NRC .APPROVAL MONTHNEAR: September, 1995 1[2]-0PT-81-021 Operations Periodic Test Procedures 9-26-95 (Safety Evaluation Nos.95-130 and 95-131)

Operations Periodic Test Procedures, 1[2]-0PT-81-021, "SI Accumulator Discharge Check Valves Partial Open Test" were developed to provide instructions for implementing a temporary modification {TM) to remove the seal-in function for the Safety Injection {SI) accumulator isolation valves during the performance of the subject test. The TM will allow the valves to be partially opened. The procedure revision also includes instructions for verifying that the Safety Injection system accumulator discharge check valves are free to open and exhibit partial stroke operation during a controlled accumulator dump into the closed Reactor Coolant System (RCS).

The Unit will be at cold shutdown and the equipment and systems will be operated within design limits during the performance of this test. Reactivity addition will be precluded by ensuring the accumulator boron concentration is greater than the RCS minimum refueling shutdown margin concentration and by ensuring that the accumulator temperature is greater than the minimum RCS shutdown margin temperature. Therefore, an unreviewed safety question does not exist.

2-0SP-TM-001 Operations Surveillance Procedure 9-27-95 TM 82-95-14 Temporary Modification (Safety Evaluation No.95-133)

Operations Surveillance Procedure 2-0SP-TM-001, "Turbine Inlet Valve Freedom Test" was revised to address the implementation of a temporary modification (TM) that allows the solenoid operated valves for the "A" main steam reheat intercept and reheat stop valves to be energized in order to verify the valves are free to cycle.

This testing activity will verify that the turbine inlet valves are free to move to provide assurance that they will close following a turbine trip. The TM affects only test circuitry and does not involve safety-related equipment. Therefore, an unreviewed safety question does not exist.

1-TMOP-3033 Temporary Maintenance Operating Procedure 9-29-95 (Safety Evaluation No.94-008, Revision 2)

Temporary Maintenance Operating Procedure 1-TMOP-3033, "Unit 1 34.5 KV Bus 6 and RSS Transformer C Outage" was developed to provide instructions for conducting an outage of the 34.5 KV Bus No. 6 and Reserve Station Service Transformer (RSST) "C".

The bus outage is required to perform maintenance on the bus's electrical components.

This procedure provides for a controlled reliable electric plant line-up that is allowed by the UFSAR and Technical Specifications. Unit 1 will be at cold shutdown and in a backfeed line-up. Unit 2 will enter the appropriate Technical Specification Limiting Condition for Operation since the primary power supply to Emergency Bus 2J will not be available.

Procedurally controlled temporary modifications will be implemented to maintain the station blackout signal from a loss of reserve circuit function. The emergency diesel generators will remain operable during this procedure. Therefore, an unreviewed safety question does not exist.

TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL e .

Surry Monthly Operating Report No. 95-09 Page 19 of 22 MONTHNEAR: September, 1995 2-ST-200 Special Test 9-26-95 (Safety Evaluation 95-055)

Special Test 2-ST-200, "Core Uprate Instrumentation Setpoint Implementation Plan," was performed to execute the setpoint and scaling changes required to implement Amendment 203 to Facility Operating License DPR-37, which 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).

The test procedure was performed successfully and a new power level was established on August 28, 1995.

Plant operation 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.

  • e Surry Monthly Operating Report No. 95-09.

Page 20 of 22 CHEMISTRY REPORT MONTHNEAR: September, 1995 Unit No. 1 Unit No. 2 Primary Coolant Analysis Max. Min. AvQ. Max. Min. AvQ.

Gross Radioactivity, µCi/ml 3.93E-1 6.88E-4 1.25E-1 2.56E-1 1.14E-1 1.64E-1 Suspended Solids, ppm 0.250 :s;o.010 0.042 :s;o.010 :s;0.010 :s;o.010 Gross Tritium, uCi/ml 5.53E-2 5.53E-2 5.53E-2 5.31 E-1 4.73E-1 4.99E-1 1131, uCi/ml 1.13E-1 3.30E-5 1.85E-2 1.59E-4 8.51 E-5 1.18E-4 113111133 0.22 0.18 0.20 0.10 0.05 0.08 HvdroQen, cc/kQ 39.5 0.5 19.4 41.9 34.3 37.8 Lithium, ppm 0.85 :s;o.10 0.14 2.32 2.06 2.18 Boron - 10, oom'" 495.9 0.196 356.0 163.3 148.2 156.5 Oxygen, (DO), ppm 6.0 :s;0.005 3.0 :s;0.005 :s;0.005 :s;0.005 Chloride, ppm :s;0.050 :s;o.001 0.004 :s;0.050 0.003 0.005 oH at 25 deQree Celsius 9.68 4.70 5.57 6.86 6.70 6.79 Boron - 1O = Total Boron x 0.196 Comments:

None

  • FUEL HANDLING e Surry Monthly Operating Report No. 95-09 Page 21 of 22 UNITS 1 & 2 MoNTHNEAR: September, 1995 New or Spent Number of New or Spent Fuel Shipment Date Stored or Assemblies Assembly ANSI Initial Fuel Shipping Number Received per Shipment Number Number Enrichment Cask Activity No Fuel Received or Stored During the Reporting Period
  • Surry Monthly Operating

. Report No. 95-09 Page 22 of 22 DESCRIPTION OF PERIODIC TEST{S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MoNTHNEAR: September, 1995 None During the Reporting Period

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