ML18153B441
| ML18153B441 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1993 |
| From: | Bowling M, Mason D, Olsen C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 94-014, 94-14, NUDOCS 9401240143 | |
| Download: ML18153B441 (23) | |
Text
e e
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 January 14, 1994 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.94-014 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 December 1993.
Very truly yours,
~124 M. L. Bowling, Manager Nuclear Licensing & Programs 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
e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 93-12 Approved:
TABLE OF CONTENTS Section
-Surry Monthly Operating Report No. 93-12 Page 2 of 22 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........................................... 15 Tests and Experiments That Did Not Require NRG Approval...................................................................... 18 Chemistry Report............................................................................................................................. 19 Fuel Handling - Unit No. 1................................................................................................................... 20 Fuel Handling - Unit No. 2................................................................................................................... 20 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications................................................................................................... 22
OPERATING DATA REPORT
-Surry Monthly Operating Report No. 93-12 Page 3 of 22 Docket No.:
Date:
Completed By:
50-280 01-03-94 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 December, 1993 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 8760.0 184320.0
- 12.
Number of Hours Reactor Was Critical..........
744.0 8432.2 123807.2
- 13. Reactor Reserve Shutdown Hours...............
0 0
3774.5
- 14. Hours Generator On-Line...........................
744.0 8403.6 121679.0
- 15. Unit Reserve Shutdown Hours.....................
0 0
3736.2
- 16. Gross Thermal Energy Generated (MWH)......
1305076.1 19548466.0 283167745.1
- 17. Gross Electrical Energy Generated (MWH)....
443175.0 6521295.0 92539548.0
- 18. Net Electrical Energy Generated (MWH)........
419735.0 6229241.0 87827101.0
- 19. Unit Service Factor...................................
100.0%
95.9%
66.0%
- 20. Unit Availability Factor...............................
100.0%
95.9%
68.0%
- 21.
Unit Capacity Factor (Using MDC Net)...........
72.2%
91.1%
61.4%
- 22. Unit Capacity Factor (Using DER Net)...........
71.6%
90.2%
60.5%
- 23. Unit Forced Outage Rate............................
0.0%
1.5%
17.4%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling (10 Year ISi), January 21, 1994, 64 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. 93-12 Page 4of 22 Docket No.:
Date:
Completed By:
50-281 01-03-94 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 2 December, 1993 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 8760.0 181200.0
- 12.
Number of Hours Reactor Was Critical..........
738.5 6389.4 120076.3
- 13. Reactor Reserve Shutdown Hours...............
0 0
328.1
- 14. Hours Generator On-Line...........................
730.1 6284.6 118215.6
- 15. Unit Reserve Shutdown Hours.....................
0 0
0
- 16. Gross Thermal Energy Generated (MWH)......
1700869.3 14344668.6 2756757 42.4
- 17. Gross Electrical Energy Generated (MWH)....
571745.0 4749720.0 89945624.0
- 18. Net Electrical Energy Generated (MWH)........
551196.0 4541657.0 85332070.0
- 19. Unit Service Factor...................................
98.1%
71.7%
65.2%
- 20.
Unit Availability Factor...............................
98.1%
71.7%
65.2%
- 21.
Unit Capacity Factor (Using MDC Net)...........
94.9%
66.4%
60.4%
- 22.
Unit Capacity Factor (Using DER Net)...........
94.0%
65.8%
59.8%
- 23.
Unit Forced Outage Rate............................
0.0%
9.5%
14.1%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
None
- 25. If Shut Down at End of Report Period, Estimated Date of Start-up:
- 26. Unit In Test Status (Prior to Commercial Operation):
FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION
(1)
-Surry Monthly Operating Report No. 93-12 Page 5 of 22 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)
REPORT MONTH: December, 1993 (2)
(3)
(4)
(5)
Docket No.: 50-280 Unit Name: Surry Unit 1 Date:
01-03-94 Completed by: Craig Olsen Telephone:
(804) 365-2155 Duration Method of Reason Shutting Down Rx LER No.
System Component Cause & Corrective Action to Date Type Hours Code Code Prevent Recurrence (1)
F:
Forced S: Scheduled (4)
(2)
REASON:
None during this reporting period.
A -
Equipment Failure (Explain)
B Maintenance or Test C
Refueling D
Regulatory Restriction E
Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
(3)
METHOD:
1 -
Manual 2 -
Manual Scram.
3 -
Automatic Scram.
4 -
Other (Explain)
(5)
Exhibit 1 - Same Source.
(1)
Date Type 931222 F
(1)
F:
Forced S: Scheduled (4) e e
Surry Monthly Operating Report No. 93-12 Page 6 of 22 UNIT SHUTDOWN AND POWER REDUCTION (EaUAL To OR GREATER THAN 20%)
REPORT MONTH: December, 1993 (2)
(3)
(4)
(5)
Method Docket No.: 50-281 Unit Name:
Surry Unit 2 Date: 01-03-94 Completed by:
Craig Olsen Telephone:
(804) 365-2155 Duration of LER System Component Cause & Corrective Action to Hours 0
Reason 8
(2)
REASON:
Shutting No.
Down Rx NIA N/A A
Equipment Failure (Explain) 8 Maintenance or Test C
Refueling D
Regulatory Restriction Code Code SJ p
E Operator Training & Licensing Examination F
Administrative G
Operational Error (Explain)
Prevent Recurrence Unit power reduced to 60% to facilitate replacement of feedwater pump, 2-FW-P-1A, motor bearings.
(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 (NUREG 0161)
Exhibit 1 - Same Source.
e Surry Monthly Operating Report No. 93-12 Page 7 of 22 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 01-06-94 Completed by:
Pat Kessler Telephone: 365-2790 MONTH:
December, 1993 Average Daily Power Level Average Daily Power Level Day (MWe-Net)
Day (MWe-Net) 1 645 17 576 2
644 18 570 3
638 19 559 4
633 20 553 5
628 21 539 6
627 22 483 7
619 23 486 8
618 24 489 9
610 25 489 10 606 26 484 11 607 27 489 12 602 28 486 13 594 29 488 14 589 30 490 15 585 31 489 16 575 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. 93-12 Page 8 of 22 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 01-06-94 Completed by:
Pat Kessler Telephone: 365-2790 MONTH:
December, 1993 Average Daily Power Level Average Daily Power Level Day (MWe-Net)
Day (MWe-Net) 169 17 793 2
770 18 793 3
792 19 764 4
792 20 790 5
791 21 791 6
790 22 648 7
792 23 473 8
791 24 469 9
791 25 676 10 789 26 794 11 791 27 794 12 791 28 793 13 789 29 792 14 790 30 792 15 791 31 792 16 793 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. 93-12 Page 9 of 22
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR: December, 1993 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:
12/01 /93 0000 12/31/93 2400 UNIT Two:
12/01 /93 0000 12/01 /93 0529 12/01 /93 1354 12/01/93 1641 12/01 /93 1916 12/01 /93 2329 12/02/93 0506 12/19/93 0917 12/19/93 1121 12/19/93 1448 12/19/93 1665 12/22/93 1144 12/22/93 1444 12/25/93 0655 12/25/93 1342 12/31 /93 2400 The reporting period began with the Unit operating at 83% power, 693 MWe, in a power coast down.
The reporting period ended with the Unit operating at 63% power, 516 MWe, in a power coast down.
The reporting period began with the Unit at Hot Shutdown, preparing to startup following the completion of a maintenance outage for "C" steam generator.
Reactor critical.
Unit on-line. Power increased to 34%, 280 MWe; chemistry hold.
Started power increase at 34%, 280 MWe.
Stopped power increase at 64%, 525 MWe.
Started power increase at 64%.
Stopped power increase at 1 00%, 820 MWe.
Started power reduction to alternate high pressure heater drain pumps.
Stopped power reduction at 85%, 715 MWe.
Started power increase following start of alternate high pressure heater drain pump.
Stopped power increase at 100%, 820 MWe.
Started power reduction to facilitate replacement of feedwater pump, 2-FW-P-1A, motor bearings.
Stopped power reduction at 60%, 500 MWe.
Started power increase following replacement of feedwater pump, 2-FW-P-1 A, motor bearings.
Stopped power increase at 100%, 820 MWe.
The reporting period ended with the Unit operating at 100% power, 820 MWe.
J
e Surry Monthly Operating Report No. 93-12 Page 10 of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1993 Safety Evaluation 12-03-93 Safety Evaluation 93-225 assessed a revision of the Complete Loss of Reactor Coolant Flow transient analysis. The revised analysis takes credit for a reactor trip resulting from low flow in any reactor coolant system loop as the primary trip for mitigating this event. The reactor coolant pump under-voltage and under-frequency reactor trips are considered backup trip functions in the new analysis.
The assessment concluded that the results of the revised analysis meet the design limits for Departure from Nucleate Boiling Ratio for the fuel types used at Surry. Therefore, the margin of safety is not affected and an unreviewed safety question does not exist.
UFSAR Change 12-09-93 (Safety Evaluation 93-226)
Updated Final Safety Analysis Report Change 92-104 revised Section 9.3.4, "Tests and Inspections" to correctly reflect the current practices for operating and testing the Residual Heat Removal system.
The change was administrative in nature. No procedures or plant equipment were affected and no physical modifications were involved. Therefore, an unreviewed safety question did not exist.
UFSAR Change 12-09-93 (Safety Evaluation 93-227)
Updated Final Safety Analysis Report Change 92-148 revised Sections 6.2.2.2,
"[Safety Injection System] Components", 6.2.2.2.6, "Accumulator Check Valves", and 9.1.3.6, "Galvanic Corrosion" to clarify and provide consistency in the discussions regarding materials that come into contact with reactor coolant.
This change also reflects the acceptability of using materials that are equivalent to stellite or austenitic steel in valves and other components that are in contact with borated water.
The use of alternate materials in the applications described above does not affect the operation of any systems or any accident analyses. Replacement materials are reviewed to ensure their performance characteristics are equivalent to the materials being replaced. Therefore, an unreviewed safety question does not exist.
FS 93-50 FS 93-27 FS 93-29 FS 93-37 e Surry Monthly Operating Report No. 93-12 Page 11 of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1993 UFSAR Change Nuclear Plant Chemistry Manual (Safety Evaluation 93-231) 12-13-93 The Nuclear Plant Chemistry Manual (NPCM) was developed to provide a single source of chemistry parameters used to ensure system chemistry is maintained within the appropriate limits. Updated Final Safety Analysis Report Change 93-50 revised various sections to reflect changes in certain chemistry parameters.
The chemistry controls specified by the NPCM will enhance station operation by minimizing system and component corrosion. The NPCM parameter values were based on the Technical Specifications, UFSAR, and industry guidelines.
Revised values were equivalent to or more conservative than those previously specified by the UFSAR and did not reduce the margin of safety. Therefore, an unreviewed safety question does not exist.
UFSAR Change 12-13-93 (Safety Evaluation 93-230)
Updated Final Safety Analysis Report Change 93-27 revised Section 14.5, "Loss-of-Coolant Accident" to describe the method for complying with the reporting requirements of 1 O CFR 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors".
The change was administrative in nature. No procedures or plant equipment were affected and no physical modifications were involved. Therefore, an unreviewed safety question did not exist.
UFSAR. Change 12-13-93 (Safety Evaluation 93-229)
Updated Final Safety Analysis Report Change 93-29 revised various sections to document the function of the refueling water storage tank cross connect feature and the basis for securing the cross connect valves (for up to 7 days) to facilitate maintenance of equipment in the charging pump suction lines.
An evaluation, performed to assess the impact of securing the cross connect valves, determined that the operation of safety-related systems or components would not be affected. Furthermore, this condition would not prevent systems from performing accident mitigation functions. Therefore, an unreviewed safety question does not exist.
UFSAR Change 12-17-93 (Safety Evaluation 93-238)
Updated Final Safety Analysis Report Change 93-37 revised Sections 5.2, "Containment Isolation" and 5.5, "Containment Tests and Inspections" to clarify the design basis of certain containment penetrations and provide additional detail in describing the testing and operation of containment penetration valves.
The changes were administrative in nature. No procedures or plant equipment were affected and no physical modifications were involved. Therefore, an unreviewed safety question did not exist.
EWA 89-762 EWA 91-039 TM S2-93-45 e Surry Monthly Operating Report No. 93-12 Page 12 of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1993 Engineering Work Request (Safety Evaluation No.91-093) 12-20-93 Engineering Work Request 89-762 replaced obsolete Instrument Air system pressure switches and three-way release valves with safety-related pressure switches.
The replacement switches upgraded the existing components and did not affect their original design function.
Therefore, an unreviewed safety question does not exist.
Engineering Work Request (Safety Evaluation No.91-176) 12-20-93 Engineering Work Request 91-039 replaced carbon steel globe type vent valves on Service Water (SW) system recirculation lines with enhanced 316 stainless steel ball valves.
The replacement valves are more compatible with SW system chemistry and will help prevent valve and piping corrosion and degradation. The modification did not affect the SW system strainers or control room chiller condenser and did not reduce the margin of safety. Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.93-241) 12-22-93 Temporary Modification (TM) S2-93-45 installed an electrical jumper around the withdrawn limit switch on the Unit 2 "B" incore detector. The jumper allowed use of the "B" detector 1 O path transfer device along with the "A" detector 5 path transfer device and drive motor to perform Technical Specification required full core flux mapping. The "B" detector 5 path transfer switch was also disabled to prevent damaging the detector cable when the detector is inserted into its storage location. This option was made available due to periodic thermal trips of the "B" incore detector drive motor.
This change prevented potential containment entries (to reset the drive motor) and unnecessary radiation hazards.
Furthermore, operation of the incore detection system was not adversely affected and the integrity of the Reactor Coolant system boundary at the seal table was not compromised. Therefore, an unreviewed safety question did not exist.
FS 93-38 TM S1-93-12 WO 262059-08 e Surry Monthly Operating Report No. 93-12 Page 13 of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1993 Surry Emergency Plan (Safety Evaluation No.93-242) 12-23-93 The Surry Emergency Plan was revised to reflect a change from the Regulatory Guide 1.109 methodology to the use of ICRP-26 and EPA-400 guidelines for calculating and estimating worker population dose rates. This revision also incorporated the terminology changes, relative to whole body and thyroid dose, as reflected in the revision of 1 O CFR 20, which became effective on January 1, 1994.
These changes provide for a more complete post-accident estimation of potential population dose and lower protective action guidelines. The revision did not affect station operation. Therefore, an unreviewed safety question does not exist.
UFSAR Change 12-23-93 (Safety Evaluation 93-244)
Updated Final Safety Analysis Report Change 93-38 revised Section 15A.3.4.2, "Verification of Analysis Methods", to reflect the use of an alternate computer code for performing piping analysis.
This change was administrative in nature and involved no physical changes to the station. The alternate computer code provides equivalent results and does not reduce the Technical Specification margin of safety. Therefore, an unreviewed safety question does not exist.
Temporary Modification (Safety Evaluation No.93-245) 12-27-93 Temporary Modification (TM) S1-93-12 installed electrical jumpers to bypass test switch PC-455E-TB on the Unit 1 Safety Injection (SI) system train "B" circuitry to allow the switch to be replaced without rendering the circuits inoperable.
This TM continued to allow SI system train "B" actuation on a valid signal and did not affect train "A", thus maintaining the design SI functions. Double verification of jumper installation/removal and post maintenance testing were performed.
Therefore, an unreviewed safety question did not exist.
Work Order 12-27-93 (Safety Evaluation No.93-239, Revision 1)
Work Order 262059-08 applied a freeze seal to temporarily isolate Unit 1 Chilled Water system discharge line, 1-VS-E-4C, to facilitate the replacement of Primary Grade Water system valve, 1-PG-MOV-107C.
Application of the freeze seal was procedurally controlled to ensure that adequate provisions were employed to ensure compliance with station operating requirements.
Contingency actions were also in place to minimize the consequences of a freeze seal failure. In addition, Nondestructive Examination of the affected piping was performed prior to and following the seal installation.
Therefore, an unreviewed safety question did not exist.
EWA 90-369 DCP 93-12 WO 260090 FS 93-21 e Surry Monthly Operating Report No. 93-12 Page 14of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1993 Engineering Work Request (Safety Evaluation No.90-294) 12-29-93 Engineering Work Request 90-369 provided instructions for repairing the nonsafety-related Ground Water De-Watering system.
This was a maintenance activity that did not affect any safety-related systems or accident analyses. Therefore, an unreviewed safety question did not exist.
Design Change Package (Safety Evaluation No.91-093) 12-30-93 Design Change Package 93-12 installed a water tight door at the entrance to Mechanical Equipment Room (MER) No. 3 and removed the existing flood dike.
These modifications were implemented in order to protect the Emergency Switchgear Room (ESGR) from potential flooding (via a penetration in the wall separating the ESGR and MER No. 3) as a result of a Service Water system pipe rupture. Installation of the water tight door satisfies an Individual Plant Evaluation flooding concern, which is not a station design basis event. Therefore, an unreviewed safety question does not exist.
Work Order 12-30-93 (Safety Evaluation No.93-246)
Work Order 260090 implemented a leak repair for Unit 2 Charging System flow control valve, 2-CH-FCV-2160. The repair method failed the valve in the closed position.
The subject valve was designed for filling the reactor coolant system during cold shutdown or during 2 loop operation (which is currently not permitted). The valve is normally closed and does not perform any safety-related function. Therefore, an unreviewed safety question does not exist.
UFSAR Change 12-23-93 (Safety Evaluation 93-243)
Updated Final Safety Analysis Report Change 93-21 revised Sections 6.2.2.1.1, "Injection Phase", 6.2.3.11.1, "Low-Head Safety Injection Pumps", Table 6.2-6, "Pump Parameters", and Table 6.2-13, "Low-Head Safety Injection Pumps" to enhance the accuracy in describing the design basis requirements and capabilities of the Safety Injection system pumps and the Emergency Core Cooling system injection flows.
The changes were administrative and editorial in nature. No procedures or plant equipment were affected and no physical modifications were involved.
Therefore, an unreviewed safety question did not exist.
I e Surry Monthly Operating Report No. 93-12 Page 15 of 22 PROCEDURE OR METHOD OF OPERATION CHANGES 1/2-IPT-CC-MS-F-474, 475,484,485,494,495 1/2-IPT-FT-MS-F-474, 475,484,485,494,495 1/2-IPT-RC-T-430 1/2-IPT-RC-T-433 1-ECM-2403-02 THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1993 Instrument Periodic Test Procedures (Safety Evaluation No.93-233) 12-14-93 Instrument Periodic Test Procedures 1/2-IPT-CC-MS-F-474, 475, 484, 485, 494, 495, "Steam Line Flow Protection [Loop] Channel Calibration", and 1/2-IPT-FT-MS-F-474, 475, 484, 485, 494, 495, "Steam Line Flow Protection
[Loop] Functional Test", were developed to replace/upgrade the existing procedures and to include instructions for removing power, under certain plant conditions, from the corresponding instrument loop's signal summator to prevent a spurious safety injection signal while performing a loop calibration.
This procedurally controlled temporary modification will be implemented for a single channel at a time. The redundant channel will remain unaffected and capable of initiating a safety injection, if required. Therefore, an unreviewed safety question does not exist.
Instrument Periodic Test Procedures (Safety Evaluation No.93-232) 12-14-93 Instrument Periodic Test Procedures 1/2-IPT-RC-T-430, "Reactor Coolant Wide Range Temperature Loop T-[1/2]-430 Calibration", and 1/2-IPT-RC-T-433, "Reactor Coolant Wide Range Temperature Loop T-[1/2]-433 Calibration" were developed to replace/upgrade the existing procedures and to include instructions for removing the Unit 1 and 2 Reactor Coolant system loop "C" wide range temperature indicating instrument loops from service to facilitate calibration and other maintenance activities.
The subject instrument loops provide indication only. Sufficient redundancy exists to ensure that Technical Specification compliance is maintained during the performance of these procedures. Therefore, an unreviewed safety question does not exist.
Electrical Corrective Maintenance Procedure (Safety Evaluation No.93-236) 12-16-93 Electrical Corrective Maintenance Procedure 1-ECM-2403-02, "RSS Transformer B Outage with Backfeed of Transfer Bus E" was developed to replace/upgrade the existing procedure and to include instructions for implementing temporary modifications to defeat automatic tripping and lockout of selected 4160 volt breakers associated with transfer bus E. These modifications will ensure a reliable electric plant lineup during a reserve station service transformer B outage while on Unit 1 backfeed to transfer bus E.
This procedure will be performed with Unit 1 at cold shutdown and will provide for the normal Unit 1 backfeed line-up. Safety systems and emergency diesel generators will remain available to Unit 1. Therefore, an unreviewed safety question does not exist.
1-0PT-Sl-006 2-ECM-2403-03 O-ECM-0701-01 Surry Monthly Operating Report No. 93-12 Page 16 of 22 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1993 Operations Periodic Test Procedure (Safety Evaluation No.93-031, Revision 1) 12-16-93 Operations Periodic Test Procedure, 1-0PT-Sl-006, "SI Accumulator Discharge Check Valves Full Open Test" was developed to verify that Unit 1 Safety Injection system accumulator discharge check valves are free to open and exhibit full stroke operation.
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 Reactor Coolant and Residual Heat Removal systems.
Reactivity addition will be precluded by ensuring the accumulator boron concentration is greater than the Reactor Coolant system (RCS) concentration and by ensuring accumulator temperature is greater than the RCS shutdown margin temperature. Therefore, an unreviewed safety question does not exist.
Electrical Corrective Maintenance Procedure (Safety Evaluation No.93-237) 12-16-93 Electrical Corrective Maintenance Procedure 2-ECM-2403-03, "RSS Transformer C Outage with Backfeed of Transfer Bus F" was developed to replace/upgrade the existing procedure and to include instructions for implementing temporary modifications to defeat automatic tripping and lockout of selected 4160 volt breakers associated with transfer bus F. These modifications will ensure a reliable electric plant lineup during a reserve station service transformer C outage while on Unit 2 backfeed to transfer bus F.
This procedure will be performed with Unit 2 at cold shutdown and will provide for the normal Unit 2 backfeed line-up. Safety systems and emergency diesel generators will remain available to Unit 2. Therefore, an unreviewed safety question does not exist.
Electrical Corrective Maintenance Procedure (Safety Evaluation No.93-240) 12-22-93 Electrical Corrective Maintenance Procedure O-ECM-0701-01, "Emergency Diesel Generator Maintenance" was developed to replace/upgrade the existing procedures and to include instructions for temporarily installing electrical jumpers to facilitate opening and closing the radiator louvers on the emergency diesel generators (EDGs) when adjusting or repairing the louver controls.
This activity will not affect the ability of an EDG to perform its safety function since the EDG will be removed from service prior to implementing the procedure.
Double verification of jumper installation/removal and post maintenance testing will be performed. Therefore, an unreviewed safety question does not exist.
1-0P-CC-002 e Surry Monthly Operating Report No. 93-12 Page 17 of 22 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1993 Operating Procedure (Safety Evaluation No.93-247) 12-30-93 Operating Procedure 1-0P-CC-002, "Chilled Component Cooling System", was developed to replace/upgrade the existing procedure and to include instructions for temporarily disconnecting an electrical lead in order to maintain Unit 1 Boron Recovery system valve, 1-BR-HCV-101G, in the open position. This temporary modification is required during operation of the Component Cooling Water Clean-up system to provide a flow path through the primary drain tank vent chiller condenser.
An evaluation of Component Cooling Water Clean-up system operation with 1-BR-HCV-101G in the open position determined that the cooling loads or flow rates required of the normal or chilled Component Cooling Water systems were not adversely affected. Therefore, an unreviewed safety question does not exist.
1-ST-307 e Surry Monthly Operating Report No. 93-12 Page 18 of 22 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: December, 1993 Special Test 12-03-93 (Safety Evaluation 93-202)
Special Test 1-ST-307, "Nuclear Instrumentation System Noise Measurement and Analysis", was conducted during November, 1993, to measure and analyze electrical noise on the Nuclear Instrumentation (NI) system power range drawers while the Unit was at power. The testing was performed in preparation for the installation of Hafnium flux suppression inserts into the reactor core during the 1994 Unit 1 refueling outage. The presence of electrical noise could impact the operation of the NI system, since the flux suppression inserts will reduce the nuclear instrumentation signal.
The test results indicated that the electrical noise measured was not a significant portion of the overall power range signal. Additional testing will be performed
. during the 1994 refueling outage.
This test was performed in conjunction with the normal monthly Technical Specification required surveillance of the power range drawers. The test points in each drawer were monitored for electrical noise while the drawer was placed in the test mode, in accordance with the surveillance test procedure. Therefore; an unreviewed safety question did not exist.
CHEMISTRY REPORT MONTH/YEAR: December, 1993 Unit No. 1 Primarv Coolant Analvsis Max.
Min.
Avg.
Gross Radioactivity, µCi/ml 5.53E-1 3.05E-1 3.82E-1 Suspended Solids, oom
< 0.1
< 0.1
< 0.1 Gross Tritium, µCi/ml 5.90E-2 5.48E-2 5.72E-2 1131, µCi/ml 3.68E-3 2.24E-3 2.74E-3 1131/I133 0.35 0.20 0.25 Hydroi:ien, cc/kQ 42.4 36.2 38.5 Lithium, oom 0.81 0.72 0.76 Boron - 10, oom*
0.61 0.20 0.28 Oxygen, (DO), ppm
- 0.005
- 5:0.005
<0.005 Chloride, ppm
<0.050
None e Surry Monthly Operating Report No. 93-12 Page 19 of 22 Unit No. 2 Max.
Min.
Avo.
2.60E-1 1.69E-3 1.51E-1
< 0.1
< 0.1
< 0.1 4.02E-1 3.02E-1 3.57E-1 1.83E-4 5.00E-5 9.62E-5 0.16 0.06 0.11 42.5 33.2 37.9 2.80 1.61 2.21 323.4 200.1 224.5
<0.005
- 5:0.005
<0.005
<0.050 0.006 0.014 6.43 5.87 6.31
r-New or Spent Fuel Shipment Date Stored or Number Received Unit 1 Batch 15 Shipment 4 12/02/93 Unit 1 Batch 15 Shipment 5 12/02/93 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: December, 1993 Number of Assemblies Assembly ANSI eer Shiement Number Number 12 2K5 LMOYKZ 2K6 LMOYLO 3K7 LMOYLB 4KO LMOYLE 4K9 LMOYLP 5K2 LMOYLS 2K8 LMOYL2 2K9 LMOYL3 3KO LMOYL4 3K1 LMOYL5 5K8 LMOYLY 5K9 LMOYL.Z 12 4K3 LMOYLH 4K4 LMOYLJ 4K5 LMOYLK 4K7 LMOYLM 4K8 LMOYLN 5KO LMOYLQ OK2 LMOYKA 4K6 LMOYLL 5K1 LMOYLR 5K3 LMOYLT 5K4 LMOYLU e Surry Monthly Operating Report No. 93-12 Page 20 of 22 New or Spent Initial Fuel Shipping Enrichment Cask Activit:£ 3.8137 14.76 Ci 3.8059 3.9935 3.9979 3.9958 3.9957 3.8071 3.8137 3.8135 3.8139 3.9998 4.0012 3.9961 14.97 Ci 3.9878 3.9828 3.9815 3.9847 3.9816 3.8144 3.9833 3.9825 3.9835 3.9835 J
New or Spent Fuel Shipment Date Stored or Number Received Unit 1 Batch 15 Shipment 5 12/02/93 CASTOR V/21 500-11-015 12/09/93 FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: December, 1993 Number of Assemblies Assembly ANSI eer Shiement Number Number 12 6KO LMOYMO NIA D11 LM007W D20 LM007N D23 LM006Z D24 LM007R D29 LMOOBP D30 LMOOBQ D38 LM007F G12 LM01QD J01 LM034D J07 LM034L JOB LM034K J16 LM034X J23 LM0354 W12 LM040W W21 LM040B W25 LM040J W33 LM0415 W35 LM041G W39 LM041W W43 LM041V W51 LM0420 e Surry Monthly Operating Report No. 93-12 Page 21 of 22 New or Spent Initial Fuel Shipping Enrichment Cask Activit:r'.
3.9829 3.325 3.325 3.325 3.325 3.325 3.325 3.325 2.111 2.902 2.902 2.902 2.902 2.902 3.203 3.203 3.203 3.203 3.203 3.203 3.203 3.203
e Surry Monthly Operating Report No. 93-12 Page 22 of 22 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: December, 1993 None during this reporting period.