ML18152A512
| ML18152A512 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/28/1997 |
| From: | Kansler M, Mason D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 97-151, NUDOCS 9703180027 | |
| Download: ML18152A512 (21) | |
Text
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.e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 12, 1997 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.97-151 NURPC Docket Nos.
50-280 50-281 License Nos. DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of February 1997.
If you have any questions or r ~uire additional information, please contact us.
Very truly yours, r:
nt - Nuclear Operations Enclosure cc:
U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 97-02 Approved:
Station Manager
TABLE OF CONTENTS Section
.urry Monthly Operating Report No. 97-02 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 NRG Approval............................................................................................ 10 Procedure or Method of Operation Changes That Did Not Require NRG Approval................................................. 13 Tests and Experiments That Did Not Require NRG Approval.................................................................................. 16 Chemistry Report..................................................................................................................................................... 17 Fuel Handling - Unit No. 1........................................................................................................................................ 18 Fuel Handling - Unit No. 2........................................................................................................................................ 18 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications....................................................................................................................... 20
OPERATING DATA REPORT
.urry Monthly Operating Report No. 97-02 Page 3 of 20 Docket No.:
Date:
50-280 03/04/97 Completed By:
D. K. Mason (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 February, 1997 2546 847.5 788 840 801 Telephone:
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9.
Power Level To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month YTD Cumulative
- 11.
Hours In Reporting Period...............................
672.0 1416.0 212040.0
- 12.
Number of Hours Reactor Was Critical............
592.1 1152.0 147986.7
- 13.
Reactor Reserve Shutdown Hours..................
0.0 0.0 3774.5
- 14.
Hours Generator On-Line................................
571.1 1130.5 145661.5
- 15.
Unit Reserve Shutdown Hours........................
0.0 0.0 3736.2
- 16.
Gross Thermal Energy Generated (MWH)......
1421706.7 2835195.0 341470638.8
- 17.
Gross Electrical Energy Generated (MWH).....
473530.0 946965.0 111919783.0
- 18.
Net Electrical Energy Generated (MWH).........
457434.0 915225.0 106508974.0
- 19.
Unit Service Factor..........................................
85.0%
79.8%
68.7%
- 20.
Unit Availability Factor.....................................
85.0%
79.8%
70.5%
- 21.
Unit Capacity Factor (Using MDC Net)............
85.0%
80.7%
64.6%
- 22.
Unit Capacity Factor (Using DER Net)............
86.4%
82.0%
63.7%
- 23.
Unit Forced Outage Rate.................................
15.0%
20.2%
15.3%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling, March 6, 1997, 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
.urry Monthly Operating Report No. 97-02 Page 4 of 20 Docket No.:
Date:
50-281 03-04-97 Completed By:
D. K. Mason (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 2 February, 1997 2546 847.5 788 840 801 Telephone:
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9.
Power Level To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month YTD Cumulative
- 11.
Hours In Reporting Period...............................
672.0 1416.0 208920.0
- 12.
Number of Hours Reactor Was Critical............
608.0 1352.0 144427.6
- 13.
Reactor Reserve Shutdown Hours..................
0.0 0.0 328.1
- 14.
Hours Generator On-Line................................
601.1 1345.1 142442.9
- 15.
Unit Reserve Shutdown Hours........................
0.0 0.0 0.0
- 16.
Gross Thermal Energy Generated (MWH)......
1516112.5 3409444.4 334883701.2
- 17.
Gross Electrical Energy Generated (MWH).....
508440.0 1143970.0 109594769.0
- 18.
Net Electrical Energy Generated (MWH).........
492371.0 1106589.0 104298468.0
- 19.
Unit Service Factor..........................................
89.4%
95.0%
68.2%
- 20.
Unit Availability Factor.....................................
89.4%
95.0%
68.2%
- 21.
Unit Capacity Factor (Using MDC Net)............
91.5%
97.6%
63.9%
- 22.
Unit Capacity Factor (Using DER Net)............
93.0%
99.2%
63.4%
- 23.
Unit Forced Outage Rate.................................
10.6%
5.0%
12.4%
- 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):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION FORECAST N/A ACHIEVED
(1)
Date Type 02/19/97 F
02/19/97 F
(1)
F:
Forced S:
Scheduled (4)
UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: February, 1997
.urry Monthly Operating Report No. 97-02 Page 5 of 20 Docket No.:
50-280 Unit Name:
Surry Unit 1 Date:
03-05-97
. Completed by:
M. J. Fanguy Telephone:
(804) 365-2155 (2)
(3)
(4)
(5)
Method Duration of LER No.
System Component Cause & Corrective Action Hours NA 62.7 Reason A
A (2)
REASON:
Shutting Down Rx NA 2
97-003 A
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction Code AB AB E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
Code to Prevent Recurrence EHTR Start ramp down due to "C" group of Pzr heaters failing.
EHTR Manual Rx trip for same reason.
(3)
METHOD:
1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NU REG 0161)
Exhibit 1 - Same Source
.urry Monthly Operating Report No. 97-02 Page 6 of 20 UNIT SHUTDOWN AND POWER REDUCTION (1)
(2)
(EQUAL To OR GREATER THAN 20%}
REPORT MONTH: February, 1997 (3)
Method (4)
Docket No.:
50-281 Unit Name:
Surry Unit 2 Date:
03-05-97 Completed by:
M. J. Fanguy Telephone:
(804) 365-2155 (5)
Duration of LER No.
System Code Component Cause & Corrective Action Date 2/18/97 (1)
F:
Forced Type Hours
. Reason Shutting Down Rx F
70.9 A
2 97-001 (2)
REASON:
S:
Scheduled A
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction TG 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 (NUREG 0161)
Code to Prevent Recurrence JX Manual Rx trip due to partial loss of power to the EHC panel and
- 4 governor valve going closed with other starting to go closed.
(3)
METHOD:
1 -
Manual 2 -
Manual Scram 3 -
Automatic Scram 4 -
Other (Explain)
(5)
Exhibit 1 - Same Source
MONTH:
February, 1997 Day 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 INSTRUCTIONS
.urry Monthly Operating Report No. 97-02 Page 7 of 20 AVERAGE DAILY UNIT POWER LEVEL Average Daily Power Level (MWe - Net)
Day 0
17 132 18 733 19 827 20 826 21 826 22 826 23 825 24 825 25 824 26 825 27 824 28 825 825 825 825 Docket No.: 50-280 Unit Name:
Surry Unit 1 Date: 03-03-97 Completed by:
J. D. Kilmer Telephone: (804) 365-2792 Average Daily Power Level (MWe - Net) 825 815 755 0
0 169 770 824 825 825 822 813 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.
MONTH:
February, 1997 Day 1
2 3
4 5
6 7
8 9
10 11 12 13 14 15 16 INSTRUCTIONS AVERAGE DAILY UNIT POWER LEVEL
.urry Monthly Operating Report No. 97-02 Page 8 of 20 Docket No.: 50-281 Unit Name:
Surry Unit 2 Date: 03-03-97 Completed by:
John D. Kilmer Telephone:
(804) 365-2792 Average Daily Power Level Average Daily Power Level
- (MWe - Net)
Day (MWe - Net) 827 17 830 827 18 511 828 19 0
828 20 0
828 21 145 829 22 782 829 23 828 829 24 829 830 25 828 830 26 830 830 27 825 829 28 827 831 831 830 830 On this format, list the average daily unit power level in MWe - Net for each day in the reporting month. Compute to the nearest whole megawatt.
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: February, 1997
.urry Monthly Operating Report No. 97-02 Page 9 of 20 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:
02/01/97 02/02/97 02/03/97 02/19/97 02/22/97 02/23/97 02/27/97 02/28/97 UNIT TWO 02/01/97 02/18/97 02/21/97 02/22/97 02/28/97 0000 2306 1410 1754 2052 2259 0748 1342 1353 1900 2400 000 1449 0650 0553 2400 Unit 1 begins the month off-line for repairs on "B" Main Steam line.
Reactor critical.
Unit on-line.
Reactor at 100%, 853 MWe.
Start power reduction at 255 MWe/hr from 855 MWe due to decrease in RCS pressure.
"C" group Pressurizer heaters failed causing decrease in RCS pressure.
Manual Reactor trip from 55%, 430 MWe.
Reactor critical.
Unit on-line.
Unit 1 at 100%, 850 MWe.
Commence unit coastdown at end of life maintaining Tave median at Tref.
Unit finishes month at 98.5%, 842 MWe.
Unit 2 starts the month at 100%, 855 MWe.
Manual Reactor trip due to partial loss of power to the EHC panel and #4 governor valve going closed with the others starting to go closed.
Reactor is critical.
Unit 2 is at 100%, 855 MWe.
Unit 2 finishes the month at 100%, 855 MWe.
FS 97-06 DCP 97-01 FS 97-10 FS 96-12
.urry Monthly Operating Report No. 97-02 Page 10 of 20 FACILITY CHANGES THAT DID Nor REQUIRE NRC APPROVAL MONTH/YEAR: February, 1997
{Safety Evaluation 97-015) 2-7-97 Updated Final Safety Analysis Report Change FS 97-06 revised Section 9.4, "Component Cooling Systems," to correct discrepancies noted during a review of this section of the UFSAR.
This change was administrative in nature and was made to accurately reflect the current plant condition.
None of the changes to the UFSAR increases the probability of occurrence or increases the consequence of an accident.
Therefore, an unreviewed safety question does not exist.
Design Control Package
{Safety Evaluation 97-004) 2-11-97 During a run of the 58 B fan, it spuriously tripped on low flow. The reason for this trip was identified as a flow switch {1-VS-FS-1178) being out of calibration. The switch provides the low flow trip for the 588 fan. The flow switch was replaced, however, the replacement switch could not be calibrated. Location of the switch was identified as a contributing factor to the calibration problems since it did not provide a representative flow condition.
The DCP moves the switch to a location having a more representative flow. The function of the flow switch is unchanged. Therefore, an unreviewed safety question did not exist.
Updated Final Safety Analysis Report Change
{Safety Evaluation 97-017) 2-13-97 Updated Final Safety Analysis Report Change 97-10 revised Section 11.2, "Radioactive Waste Systems," to correct a discrepancy identified by Station Deviation S-96-2810. The UFSAR incorrectly describes normal use of the Catalytic Recombiner in Section 11.2.2 and correctly describes its non-use {abandoned in place) in Sections 11.2.5.1 and 11.2.5.3.1.
The implications of operating Surry Power Station Radioactive Waste Systems different than the original intent of the Boron Recovery System and Catalytic Recombiner are bounded by analysis. Liquid releases are bounded by federal regulation.
Monitoring release rates and inventories in accordance with Technical Specifications and the Offsite Dose Control Manual guidelines ensure that an unreviewed safety question does not exist.
Updated Final Safety Analysis Report Change
{Safety Evaluation 96-034 Rev. 2) 2-17-97 Updated Final Safety Analysis Report Change FS 96-12 revised various sections that address fuel handling to accurately reflect current station practices.
None of the changes represented significant deviations from the design basis of the fuel handling system and did not reduce the Technical Specifications margin of safety. The changes also did not affect any of the assumptions made in any fuel handling or other design basis accident analyses. Therefore, an unreviewed safety question does not exist.
FS 96-22 R1 SE 97-018 SE 97-019 FS 97-04
.urry Monthly Operating Report No. 97-02 Page 11 of 20 FACILITY CHANGES THAT DID Nor REQUIRE NRC APPROVAL MONTH/VEAR: February, 1997 Updated Final Safety Analysis Report Change (Safety Evaluation 96-059 Rev. 1) 2-17-97 Updated Final Safety Analysis Report Change FS 96-22 revised various sections that address fuel handling to accurately reflect current station practices.
None of the changes represented significant deviations from the design basis of the fuel handling system and did not reduce the Technical Specifications margin of safety. The changes also did not affect any of the assumptions made in any fuel handling or other design basis accident analyses. Therefore, an unreviewed safety question does not exist.
Safety Evaluation 2-17-97 (Safety Evaluation No.97-018)
This Safety Evaluation assesses a circulating water pump being out of service for greater than 30 days.
Circulating water pumps provide water required to condense turbine exhaust steam and supply water to the Service Water System.
This condition meets the requirements of Technical Specifications and adequate intake level is maintained by the remaining operable circulating water pumps. Therefore, an unreviewed safety question does not exist.
Safety Evaluation 2-17-97 (Safety Evaluation No.97-019)
This Safety Evaluation assesses equipment abandoned in place. None of the equipment abandoned is used in any of the analyzed transients.
The abandoned equipment is not used to mitigate or monitor a design basis accident.
The Technical Specification margin of safety was not affected by this activity. Therefore, an unreviewed safety question did not exist.
Updated Final Safety Analysis Report Change (Safety Evaluation 97-020) 2-17-97 UFSAR Section 6.3.1.2.1 states that This system contains the sodium hydroxide solution only while operating during an accident, which is a period of approximately 30 minutes."
This statement implies that no sodium hydroxide is present in containment spray piping during normal plant operations. This statement is incorrect due to minor leakage past the chemical addition tank isolation motor-operated valve.
An engineering evaluation documented in ET MAT 97-001, concludes that the presence of sodium hydroxide in low temperature and low pressure environments will not have any deleterious effects on 304 SS, sensitized or non-sensitized. Therefore, an unreviewed safety question does not exist.
FS 97-05 FS 97-07 FS 97-01 TM S2-97-001
-Surry Monthly Operating Report No. 97-02 Page 12 of 20 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1997 Updated Final Safety Analysis Report Change (Safety Evaluation 97-016) 2-18-97 UFSAR Section 4.2 and 9.1 currently provides only normal steady state RCS dissolved hydrogen values of 25-50 cc/Kg. This revision to the UFSAR will expand the range to include startup, shutdown and off-normal operating conditions.
The proposed change will not change the existing normal range for dissolved hydrogen, but will allow operation of the RCS with hydrogen concentrations >5 cc/Kg during off-normal conditions without reactor shutdown.
No significant chemistry changes are expected for operation > 5 cc/Kg, and when operation is ::,_ 15 cc/Kg, station chemistry will increase RCS monitoring to ensure the chemistry remains unaffected. Because RCS chemistry will not change significantly, the probability and/or consequence of accidents will not increase and the probability of an new unreviewed accident is not increased.
Therefore, an unreviewed safety question did not exist.
Updated Final Safety Analysis Report Change (Safety Evaluation 97-023) 2-19-97 UFSAR Chapters 6 and 15 are being revised to reflect the current design of the Surry Containment ground water control equipment, Containment ground water protection methods and liquid level alarms. This revision is based upon an engineering review of the UFSAR, Station Design Drawings, Design Change History, Station Procedures and Regulatory History.
No physical changes to the Station, procedures or methods of operation are involved with this change. The changes made do not affect the safety related systems, components or other items important to safe operation. Therefore, an unreviewed safety question did not exist.
Updated Final Safety Analysis Report Change (Safety Evaluation 97-026) 2-24-97 UFSAR Section 9B.2, "Control of Heavy Loads," is being revised to include the spent fuel pool transfer canal gate lifting rig.
Adding the spent fuel pool transfer canal gate lifting rig to the UFSAR maintains our commitments to NUREG-0612.
The purpose of compliance with NUREG-0612 is to provide defense-in-depth for controlling heavy loads in order to prevent load drops.
Therefore, an unreviewed safety question did not exist.
Temporary Modification (Safety Evaluation No.97-030) 2-28-97 This Temporary Modification (TM) provides a temporary discharge flow path for the Unit 2 Service Water Radiation Monitoring (RM) Pumps while the outlet Motor Operated Valves from the Recirculation Spray Heat Exchangers are removed for inspection, pipe cleaning and recoating.
The Engineering evaluation concludes that the temporary hose and fittings used to redirect RM Pump flow to the proposed spare penetration are of sufficient diameter to provide rated flow and are adequately rated to meet or exceed system design conditions.
The temporary installation will be functionally tested to ensure the system operates as designed.
The system will also be tested once the temporary installation has been removed. Therefore, an unreviewed safety question does not exist.
_J
01-0P-RC-011 Rev. 3 1-MOP-FC-003 O-OP-FC-003 2-0PT-Sl-022
-Surry Monthly Operating Report No. 97-02 Page 13 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID Nor REQUIRE NRC APPROVAL MONTH/YEAR: February, 1997 Operating Procedure (Safety Evaluation No.96-095 Rev. 5)
Operating Procedure 01-0P-RC-011 Rev. 3, "Pressurizer Relief Tank Operations," aids in degassing for the Unit 1 Refueling Shutdown. The existing Unit 2 continuous Pressurizer Relief Tank (PRT} to Overhead vent will be secured and a procedurally controlled temporary modification made to vent the Unit 1 PRT. The duration of the Unit 1 PRT vent will be finite and the Unit 2 PRT continuous vent will be re-established. Unit 1 's PRT shutdown gases will be processed through the Overhead Gas System in lieu of the designed vent path to the process vent in order to limit station gaseous releases.
Since this process involves an improvement in the processing of gaseous waste and properly utilizes the existing system for processing the gas, there is no unreviewed safety question.
Maintenance Operating Procedure Operating Procedure (Safety Evaluation No. 97-022}
2-17-97 Maintenance Operating Procedure 1-MOP-FC-003, "Removal and Installation of the Swing Check Assembly of 1-BR-506," and Operating Procedure O-OP-FC-003, "Spent Fuel Pit-Makeup From and Transfer To The Boron Recovery Tanks," will allow fluid transfer between the spent fuel pit and the boron recovery tanks (BRT) to support fuel handling operations. The procedure will allow approximately 15,000 gallons of borated water to be stored in the BRTs during fuel handling operation rather than processing this volume as liquid waste. Prior to returning the borated water to the spent fuel pit, a sample will be drawn to ensure that the borated water has a minimum concentration of 2300 ppm which ensures that the Tech Spec limit, as well as administrative limit for Spent Fuel Pit boron concentration, is not violated.
Based on procedural limitations, the presence of the anti-siphon hole, the expected heat load of the Spent Fuel Pit, and the chemistry control, no unreviewed safety question exists.
Operations Periodic Test Procedure (Safety Evaluation Nos.96-045, rev. 2) 2-17-97 Operations Periodic Test Procedure, 2-0PT-Sl-022, "SI Accumulator Discharge Check Valve Test with Reactor Head Removed," was revised to provide instructions for verifying that the Safety Injection System accumulator discharge check valves are free to open by discharging the accumulators into an open, de -fueled reactor coolant system.
The Unit will be at Refueling Shutdown and defueled. Controls are in place to avoid injection of nitrogen from the accumulators into the RCS. Either containment purge will be in operation or the containment hatch properly secured with at least one personnel hatch closed. To mitigate the potential radiological consequences if nitrogen is injected into the reactor vessel and ultimately into the containment atmosphere. The equipment and systems will be operated within design limits during the performance of this test.
Therefore, an unreviewed safety question does not exist.
1/2-0P-RC-003 1/2-E-O 1/2-ES-1.1 1/2-FR-S.1 FP-VPA-FR1
-Surry Monthly Operating Report No. 97-02 Page 14 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1997 Operating Procedure 2/19/97 (Safety Evaluation No.97-024)
Operating Procedures 1/2-0P-RC-003, "Reactor Coolant System Vent," contains a procedurally controlled Temporary Modification to defeat the Reactor Coolant (RC) Low Flow Alarms. This is being performed to eliminate nuisance alarms that would distract the operators. The RC Low Flow Alarms will be restored to fully operable following RC flow transmitter venting.
This Temporary Modification will be removed prior to the start of the first RCP during restart from the Unit 1 Refueling Outage. The safety function these alarms provide is not required below 10% power. Therefore, an unreviewed safety question does not exist.
Emergency Procedures (Safety Evaluation No.97-025) 2-20-97 A Deviation Report was submitted documenting a condition where the turbine for the Auxiliary Feedwater Pumps could overspeed if the steam admission valves received an open signal within approximately 15 seconds of a normal shutdown. This condition is due to the governor needing time to allow the oil to drain down to reset the low speed stop.
The procedures were revised to increase the point at which the turbine is secured.
Additionally the procedures place the bench board switch from AUTO to OPEN when the pumps are required to operate.
The changes to the procedures do not alter the Safety Function of the Auxiliary Feedwater Pump as described in the UFASR, Technical Specifications, or the Design Basis Documents. Additionally, these changes do not alter the results of PSAs for any accidents. Therefore, an unreviewed safety question does not exist.
Vendor Procedure 2-24-97 (Safety Evaluation No.97-028)
This safety evaluation address the portion of Vendor Procedure FP-VPA-FR1, "Fuel Assembly Repair for Surry Unit #1," which specifically calls for the temporary replacement of the original equipment fuel elevator basket with a functionally equivalent Westinghouse basket. The temporary modification will be procedurally controlled in accordance with VPAP-1403, "Temporary Modifications."
The replacement basket is functionally equivalent to original equipment with the exception that the Westinghouse basket accommodates fuel assembly reconstitution with irradiated fuel in the basket. Fuel repair procedures will require the mechanical stop to be installed whenever irradiated fuel is in the fuel elevator basket to prevent the lifting of a fuel assembly to unsafe elevations.
Fuel handling will be performed in accordance with existing site procedures. Therefore, an unreviewed safety question does not exist.
1-MOP-EP-304 1 [2]-0PT-Sl-021
-Surry Monthly Operating Report No. 97-02 Page 15 of 20 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1997 Maintenance Operating Procedure (Safety Evaluation No.97-029) 2-26-97 Maintenance Operating Procedure 1-MOP-EP-304, "RSS Transformer A Outage with Backfeed of Transfer Bus D and Emergency Bus 1J via Alternate AC Diesel Bus OL," was developed to provide instructions for the maintenance of Reserve Service Station Transformer 'A' while Bus 1J remains operable. This allows Bus 1J maintenance to be scheduled separately, providing greater flexibility for outage planning and decreases the unavailability of Emergency Diesel Generator 3.
The proposed change does not alter any electrical power system design or operating limit and satisfies the requirements of GDC-17 of 10CFR50 Appendix A. Existing Technical Specification requirements for electrical power system operability continue to be satisfied.
Therefore, an unreviewed safety question does not exist.
Operations Periodic Test Procedures (Safety Evaluation Nos.95-131 rev. 1) 2-26-97 Operations Periodic Test Procedures, 1 [2]-0PT-Sl-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.
-Surry Monthly Operating Report No. 97-02 Page 16 of 20 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: February, 1997 None During the Reporting Period
Primary Coolant Analysis Gross Radioactivity, µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml 1131, µCi/ml 113111133 HvdroQen, cc/kQ Lithium, oom Boron - 10, ppm*
Oxygen, (DO), ppm Chloride, oom pH at 25 deQree Celsius Boron - 10 = Total Boron x 0.196 Comments:
None CHEMISTRY REPORT MONTH/YEAR: February, 1997 Unit No. 1 Max.
Min.
AvQ.
2.19E+O 3.95E-1 9.08E-1 0.050
- -=;0.010 0.030 3.16E-2 2.77E-3 2.15E2 7.62E-1 6.76E-3 1.60E-1 0.33 0.18 0.29 36.0 27.5 31.9 2.15 0.58 1.04 124.5 0.3 40.6
- -=;0.005
- -=;0.005
- -=;0.005 0.003
<0.001
<0.001 8.71 6.77 7.46 e
Surry Monthly Operating Report No. 97-02 Page 17 of 20 Unit No. 2 Max.
Min.
AvQ.
3.92E-1 7.63E-3 2.14E-1
- -=;0.010
- -=;0.010
- -=;0.010 3.93E-1 1.89E-1 3.14E-1 1.52E-4 1.94E-5 5.54E-5 0.11 0.05 0.08 30.5 27.3 29.1 2.34 2.01 2.16 262.8 164.6 194.3
- -=;0.005
- -=;0.005
- -=;0.005 0.006 0.002 0.004 6.45 6.16 6.34
New Fuel Shipment or Date Stored or Cask No.
Received TN 32-02 2-11-97 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: February, 1997 Number of Assemblies Assembly ANSI per Shipment Number Number 32 1R2 LMOC1X 2E9 LMODED 308 LMOAN3 3PO LM05YP 3P2 LM05XZ 401 LMOAMS 403 LMOMAT 405 LMOAMA 408 LMOAMU 502 LMOAM7 503 LMOAMZ 505 LMOAN6 507 LMOAMS 509 LMOAN1 600 LMOAN2 602 LMOBDG 604 LMOBDH J13 LM0359 J20 LM0353 J34 LM035J N48 NOANSI N49 NOANSI N51 NOANSI N52 NOANSI R05 LMOOU4 R06 LMOOU3 RO?
LMOOU6 e
Surry Monthly Operating Report No. 97-02 Page 18 of 20 New or Spent Initial Fuel Shipping Enrichment Cask Activity 3.5993 N/A 3.5986 3.6081 3.6070 3.6070 3.5980 3.6125 3.6030 3.6019 3.6078 3.6067 3.6062 3.6082 3.6062 3.6073 3.5847 3.5857 2.9020 2.9020 2.9020 2.5560 2.5560 2.5560 2.5560 3.0970 3.0970 3.0970
New Fuel Shipment or Date Stored or Cask No.
Received TN 32-02 2-11-97 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: February, 1997 Number of Assemblies Assembly ANSI
- per Shipment Number Number R11 LMOOU5 32 R14 LMOOTW R40 LMOOUM R43 LMOOVJ R49 LMOOVX e
Surry Monthly Operating Report No. 97-02 Page19of20 New or Spent Initial Fuel Shipping Enrichment Cask Activity 3.0970 3.0970 NIA 3.0970 3.0970 3.0970
e Surry Monthly Operating Report No. 97-02 Page 20 of 20 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHIYEAR:FEBRUARY, 1997 None During the Reporting Period