ML18153C999

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Apr 1992 for Surry Power Station Units 1 & 2.W/920513 Ltr
ML18153C999
Person / Time
Site: Surry  Dominion icon.png
Issue date: 04/30/1992
From: Negron M, Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
92-239, NUDOCS 9205190002
Download: ML18153C999 (23)
v • d • e


Text

.. ......,

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 13, 1992 U.S. Nuclear Regulatory Commission Serial No.92-329 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 April 1992.

Very truly yours,

.Lt*~

W. L. tewart Senior Vice President - Nuclear 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 1 g1)_M_3 -.-~

(-~9-2-0~5-190002 920430 \

l PDR. ADOCK 05000280 1

R PDR

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 92-04 Approved:

.urry Monthly Operating Report No. 92-04 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 NRC Approval. .............................................................................. 1O Procedure or Method of Operation Changes That Did Not Require NRC Approval ........................................... 15 Tests and Experiments That Did Not Require NRC 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

e . u r r y Monthly Operating Report No. 92-04 Page 3 of 22 OPERATING DATA REPORT Docket No.: 50-280 Date: 05-07-92 Completed By: D. Mason Telephone: (804) 365-2459

1. Un~ Name: .................................................. . Surry Unit 1
2. Reporting Period: ......................................... . April 1992
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 .......................... 719.0 2903.0 169679.0
12. Number of Hours Reactor Was Critical .......... 0.0 1288.0 109522.2
13. Reactor Reserve Shutdown Hours ............... 0.0 0.0 3774.5
14. Hours Generator On-Line ........................... 0.0 1271.8 107512.0
15. Unit Reserve Shutdown Hours ..................... 0.0 0.0 3736.2
16. Gross Thermal Energy Generated (MWH) ...... 0.0 2727607.2 249844283.9
17. Gross Electrical Energy Generated (MWH) .... 0.0 919665.0 81434853.0
18. Net Electrical Energy Generated (MWH) ........ 0.0 871153.0 77245219.0
19. Unit Service Factor ................................... 0.0% 43.8% 63.4%
20. Unit Availability Factor ............................... 0.0% 43.8% 65.6%
21. Unit Capacity Factor (Using MDC Net) ........... 0.0% 38.4% 58.7%
22. U,nit Capacity Factor (Using DER Net) ........... 0.0% 38.1% 57.8%
23. Unit Forced Outage Rate ............................ 0.0% 11.6% 19.2%
24. Shutdowns Schedule Over Next 6 Months (Type, Date, and Duration of Each):

Refueling - February 29, 1992 - 64 days.

25. If Shut Down at End of Report Period Estimated Date of Start-up: May 3, 1992
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e -Surry Monthly Operating Report No. 92-04 Page 4of 22 OPERATING DATA REPORT Docket No.: 50-281 Date: 05-07-92 Completed By: D. Mason Telephone: (804) 365-2459

1. Unit Name: ........................... : ...................... . Surry Unit 2
2. Reporting Period: ......................................... . April 1992
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):

1O. Reasons For Restrictions, If Any:

This Month YID Cumulative

11. Hours In Reporting Period ......................... . 719.0 2903.0 166559.0
12. Number of Hours Reactor Was Critical ......... . 719.0 2903.0 108111.1
13. Reactor Reserve Shutdown Hours .............. . 0.0 0.0 328.1
14. Hours Generator On-Line .......................... . 719.0 2903.0 106363.9
15. Unit Reserve Shutdown Hours .................... . 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) ..... . 1751075.8 7017208.0 247895890.1
17. Gross Electrical Energy Generated (MWH) ... . 580450.0 2343310.0 80777159.0
18. Net Electrical Energy Generated (MWH) ....... . 552396.0 2230506.0 76594444.0
19. Unit Service Factor .................................. . 100.0% 100.0% 63.9%
20. Unit Availability Factor.............................. . 100.0% 100.0% 63.9%
21. Unit Capacity Factor (Using MDC Net) .......... . 98.4% 98.4% 59.0%
22. Unit Capacity Factor (Using DER Net) .......... . 97.5% 97.5% 58.4%
23. Unit Forced Outage Rate ........................... . 0.0% 0.0% 15.0%
24. Shutdowns Schedule 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 ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

UNIT SHUTDOWN AND POWER REDUCTION

-Surry Monthly Operating Report No. 92-04 Page 5 of 22 (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: April 1992 Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 05-07-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (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 this 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 (NUREG 0161)

.urry Monthly Operating Report No. 92-04 Page 6 of 22 UNIT SHUTDOWN AND POWER REDUCTION

{EQUAL To OR GREATER THAN 20%)

REPORT MONTH: April 1992 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 05-07-92 Completed by: Anthony Xenakis Telephone: (804) 365-2145 (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 920402 s 0 8 4 NIA TA V Ramped unit down to perform turbine valve freedom test 2-0SP-TM-001.

920425 F 0 8 4 NIA SG HX Reduced unit power to maintain condenser vacuum while cleaning waterboxes.

(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)

.urry Monthly Operating Report No. 92-04 Page 7of 22 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 05-07-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: April 1992 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe- Net) 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0 6 0 22 0 7 0 23 0 8 0 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.

  • AVERAGE DAILY UNIT POWER LEVEL

. u r r y Monthly Operating Report No. 92-04 Page 8of 22 Docket No.: 50-281 Unit Name: Surry Unit 2 Date: 05-07-92 Completed by: M.A. Negron Telephone: (804) 365-2795 Month: April 1992 Average Daily Power Level Average Daily Power Level Day (MWe- Net) Day (MWe-Net) 774 17 774 2 740 18 773 3 774 19 773 4 774 20 772 5 744 21 772 6 777 22 770 7 777 23 767 8 777 24 758 9 746 25 749 10 762 26 734 11 776 27 766 12 776 28 772 13 776 29 771 14 774 30 771 15 775 16 775 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.

SUMMARY

OF OPERATING EXPERIENCE

&urry Monthly Operating Report No. 92-04 Page 9of 22 MONTH/YEAR: April 1992 Listed below in 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 04-01-92 0000 This reporting period started with the Unit at Refueling Shutdown (RSD) with a scheduled refueling outage in progress.

04-30-92 2400 This reporting period ended with the Unit at Hot Shutdown (HSD) with preparations underway to return the Unit to power operations.

UNIT TWO 04-01-92 0000 This reporting period started with the Unit operating at 100% power, 815 MWe.

04-02-92 1034 Started ramp down to perform turbine valve freedom test, 2-0SP-TM-001; 100% power, 810 MWe.

1220 Stopped ramp; 79% power, 655 MWe.

1321 Started ramp up; 79% power, 655 MWe.

1902 Stopped ramp; 100% power, 815 MWe.

04-25-92 2030 Reduced Unit power from 100% power to 93% power to maintain condenser vacuum while cleaning waterboxes.

04-26-92 0000 Started ramp down to maintain condenser vacuum while cleaning waterboxes; 93% power, 710 MWe.

0220 Stopped ramp; 80% power, 630 MWe.

0342 Started ramp up; 80% power, 660 MWe.

0500 Stopped ramp; 100% power, 810 MWe.

04-30-92 2400 This reporting period ended with the Unit operating at 100% power, 81 O MWe.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL

  • u~~~~~~~ No. 92-04 Page 10of 22 MONTH/YEAR: April 1992 TSR 92-050 Temporary Shielding Request 04-03-92 (Safety Evaluation 92-078)

This Temporary Shielding Request installed temporary lead shielding on a charging system line (2"-CH-5-1502) in the Unit 1 containment building to reduce the radiation dose received by personnel while performing work in the area.

The portion of the subject line upstream of isolation valve 1-CH-314 was operable but was at decreased temperature and pressure since the Unit was at cold shutdown. The portion of the subject line downstream of isolation valve 1-CH-314 was not operable while the shielding was installed. Installation of the shielding while a portion of the subject line remained operable was determined to be acceptable through the performance of a deadweight piping analysis. The shielding did not adversely affect the design functions of the affected system and was removed when work in the area was complete. Therefore an unreviewed safety question was not created.

QLCR R92-038 Q-List Change Request 04-07-92 (Safety Evaluation No.91-080)

This Q-List Change Request changes the classification o,f flow switches installed on the main steam safety valve discharge piping from "Safety-Related" (SR) to "Nonsafety-Related with Special Quality/Regulatory Requirements" (NSQ).

This change makes the safety classification of the flow switches consistent with their actual function and regulatory classification. The original SR classification is based on system pressure boundary functionality, however, the safety valve discharge piping is open to the atmosphere. The subject

  • components do not interact dynamically with any system or equipment and the classification change will not impact any previously evaluated design basis accident or initiate a malfunction of any equipment important to safety.

Therefore, an unreviewed safety question is not. created.

TM S1-92-17 Temporary Modification 04-07-92 TM S1-92-18 (Safety Evaluation Nos.92-081, 92-082)

These Temporary Modifications (TM) blocked open Unit 1 pressurizer power operated relief valves (PORVs) to ensure the reactor vessel was protected

  • from potential pressure transients which could have exceeded the limits of 10

. CFR 50 Appendix G when the reactor coolant system (RCS) was s 350 ° F and the vessel head was bolted on.

This TM, which was required by applicable operating procedures, was in place when the Unit was at cold shutdown. The reactor coolant pumps were tagged out and charging pump usage was strictly controlled. Therefore, an unreviewed safety question was not created.

  • -Surry Monthly Operating Report No. 92-04 Page 11 of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1992 TM S1-92-19 Temporary Modification 04-09-92 (Safety Evaluation No.92-085)

This Temporary Modification (TM) removed Unit 1 containment sump trip valve 1-DA-TV-1 OOA for maintenance and installed a spool piece and electrical jumpers to maintain an operable flow path from containment sump pumps 1-DA-P-4A and 48.

The Unit was at cold shutdown while the TM was in place. The containment sump trip valve closure interlocks, which would shut off pumps 1-DA-P-4A and 48, were defeated to allow pump operation to continue as needed. The pump interlocks of the redundant valve 1-DA-TV-1008 remained operable.

Therefore, an unreviewed safety question was not created.

DR S-92-0671 Deviation Report 04-15-92 (Safety Evaluation No.92-087)

This Safety Evaluation was performed to evaluate Deviation Report S-92-0671 concerning the design of the bearing cooling (BC) service water (SW) system, the potential for a system expansion joint failure, and the effects of such a failure with regard to the flooding information in UFSAR Chapter 9.

The evaluation validated that the operator actions required to isolate a leak from a BC SW expansion joint failure would be performed with adequate margin to ensure the operation and performance characteristics of safety-related systems would not be impacted and the design basis flooding analysis remained bounding. Therefore, an unreviewed safety question is not created.

TM S1-92-144 Temporary Modification 04-16-92 (Safety Evaluation No.92-088)

This Temporary Modification (TM) lifted the leads to malfunctioning Unit 1 reactor coolant system loop stop valves 1-RC-MOV-1590, 1-RC-MOV-1591, and 1-RC-MOV-1593 stem switches. This action circumvented the associated reactor coolant pump (RCP) starting circuitry interlocks, enabling RCPs "A" and "B" to be started.

This change did not affect the protective functions of the RCP circuitry. The original purpose of the loop stop valve stem switch/RCP starting circuit interlock was to prevent accidental reactivity additions due to colder RCS temperatures or dilution resulting from starting an inactive loop during two loop operation. Two loop operation is currently not allowed by Technical Specifications. Therefore, an unreviewed safety question was not created.

e -Surry Monthly Operating Report No. 92-04 Page 12 of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1992 TM S 1-92-022 Temporary Modification 04-20-92 (Safety Evaluation No.92-092)

This Temporary Modification (TM) installed plugs in Unit 1 emergency condensate storage tank, 1-CN-TK-1, penetrations to aid in identifying the source of leakage from the tank.

One tank penetration was plugged at a time to determine Whether the connecting piping was the source of the leak. The unit was at least cold shutdown during this activity and appropriate limiting conditions for operation were entered in accordance with Technical Specifications. Therefore, an unreviewed safety question was not created.

TM S 1-92-026 Temporary Modification 04-23-92 (Safety Evaluation No.92-095)

This Temporary Modification (TM) installed an electrical jumper to allow an uncoupled run of Unit 1 secondary plant drains system low pressure heater drain pump motor, 1-SD-PM0-1 A.

This TM permitted a rotational check of the pump motor and was in place while Unit 1 was at cold shutdown. The secondary plant drains system is nonsafety-related and is not considered in an accident analysis. Therefore, an unreviewed safety question was not created.

SE 92-100 Safety Evaluation 04-24-92 This Safety Evaluation was performed to evaluate a Westinghouse letter NSD-ARV-90-0608 documenting the identification of a small immobile foreign object (wire approximately 1/8" to 5/32" diameter estimated to be less than 0.1 pounds) in the secondary side of the Unit 1 steam generator (SG) "A".

Attempts to remove the object were unsuccessful.

An evaluation of Unit 1 operation with the SG containing the foreign object was performed by Westinghouse Nuclear Safety. The evaluation concluded that the presence of the object will have no adverse effect on the pressure boundary integrity of the SG and does not create an unreviewed safety question provided continual eddy current inspections support no tube degradation due to wear.

-Surry Monthly Operating Report No. 92-04 Page 13 of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1992 SE 92-099 Safety Evaluation 04-24-92 This Safety Evaluation was performed to assess the isolation (for a period of seven days) of the Unit 1 refueling water storage tank (RWST) cross-connect (to Unit 2) valves Sl-TV-102A and Sl-TV-1028 to permit the performance of routine maintenance on equipment in the charging pump suction lines.

This activity was discussed with US NRC Region II and determined to be consistent with and in a fashion similar to the requirements of Technical Specification 3.2.E.2. The activity was performed while Unit 1 was shutdown and did not impact the operation of safety-related systems or components on Unit 2. Therefore, an unreviewed safety question was not created.

EWR 90-240 Engineering Work Request 04-24-92 (Safety Evaluation No.90-215)

This Engineering Work Request replaced the SMC-04 type operators on Unit 1 recirculating spray (RS) system motor operated valves (MOV) 1-RS-MOV-156A and 1-RS-MOV-1568 with SMB-000 type operators. This action was taken to provide a source of replacement parts for the remaining SMC-04 operators that are in service on other valves.

An evaluation of valve operation with the new operators determined that the stroke time was acceptable and that there is no thermal or seismic overload potential. Operation of the valves and the RS system is unaffected by this modification. Therefore, an unreviewed safety question is not created.

DR S-92-0482 Deviation Reports 04-25-92 DR S-92-0514 (Safety Evaluation No.92-102)

This Safety Evaluation was performed to evaluate Deviation Reports S 0482 and S-92-0514 concerning the inadvertent introduction of small aluminum loose parts into the Unit 1 reactor coolant system (RCS). The subject parts entered the RCS during the removal of an installed nozzle cover in the steam generator "A" hot leg channel head when one of three sections of the nozzle cover separated from the other two. Retrieval attempts were successful at recovering most of the pieces. Two pieces could not be recovered.

An evaluation of Unit 1 operation with the RCS containing the loose parts was performed by the reactor vendor. The evaluation concluded that the subject parts should dissolve in less than one fuel cycle and that their presence will have no adverse effect on fuel, safety-related instrumentation, systems or components. Therefore, an unreviewed safety question is not created.

-Surry Monthly Operating Report No. 92-04 Page 14of 22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1992 SE 92-104 Safety Evaluation 04-27-92 This Safety Evaluation was performed to assess the excavation of Unit 1 underground auxiliary feedwater (AFW), containment spray, and charging system piping to provide access to investigate a suspected leak in the AFW pump recirculation piping, 2"-WAPD-19-15. This line is located underground adjacent to the refueling water storage tank, 1-CS-TK-1 .

The subject lines were excavated for a short period of time during which there were provisions for temporary missile protection to ensure the requirements for Unit 1/Unit 2 AFW cross-connect capability was maintained. Therefore, an unreviewed safety question was not created.

-Surry Monthly Operating Report No. 92-04 Page 15 of 22 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1992 1-EMP-C-EPH-84 Corrective Electrlcal Maintenance Procedure 04-02-92 (Safety Evaluation No.92-076)

Corrective Electrical Maintenance Procedure, 1-EMP-C-EPH-84, "Switching Procedure For Reserve Station Service Transformer 'C'" was revised ("one-time only" change) to provide instructions for backfeeding transfer bus "F" through breakers 15C1 and 15C2. This configuration allowed the performance of routine servicing of reserve station service transformer "C" and associated breakers.

This procedure was performed with Unit 1 at cold shutdown and the appropriate Technical Specification limiting conditions for operation were entered. The undervoltage protection scheme for bus 1C remained operable and under/degraded voltage relaying for the emergency buses would have performed their safety function of separating the bus(es) from offsite power with emergency buses supplied by the emergency diesel generators, if conditions warranted. Therefore, an unreviewed safety question was not created.

O-EPT-1802-03 Electrical Periodic Test Procedure 04-05-92 (Safety Evaluation No.92-079)

Electrical Periodic Test Procedure, O-EPT-1802-03, "Bus 1F Undervoltage Protective Relay Testing" was developed to provide instructions for lifting an electrical lead to defeat the bus 1F undervoltage trip to breaker 15C1 during the testing of bus 1F protective relays. This temporary modification allowed the breaker to maintain the "F" transfer bus powered from the station service transformer through station service bus 1C.

This procedure was performed with Unit 1 at cold shutdown and Unit 2 at power. Normal undervoltage trip functions were provided by the respective 1H and 2J undervoltage protection schemes and the emergency diesel generators remained available. Unit 2 entered the appropriate limiting condition for operation as required by Technical Specifications during the performance of this procedure. Therefore, an unreviewed safety question was not created.

-Surry Monthly Operating Report No. 92-04 Page 16 of 22 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1992 1-IPT-CC-RP-IEL-001 Instrument Periodic Test Procedures 04-07-92 2-IPT-CC-RP-IEL-001 (Safety Evaluation No.92-084)

Instrument Periodic Test Procedures, 1/2-IPT-CC-RP-IEL-001, "ESF Steam Generator High Level Main Turbine Trip And Main Feedwater Isolation Logic Test" installed jumpers and lifted electrical leads to enable the performance of logic testing of engineered safeguards features (ESF) actuations initiated by steam generator high level.

This procedure was performed with Unit 1 at cold shutdown at which time the ESF is not required. Double verification was used to ensure the affected equipment and controls were returned to their normal configuration following the test. Therefore, an unreviewed safety question was not created.

1-0PT-CT-102 Operations Periodic Test Procedure 04-10-92 (Safety Evaluation No.92-086)

Operations Periodic Test Procedure, 1-0PT-CT-102, "Preparation, Alignment, And Restoration For Type A Test" installed temporary modifications to defeat Safety Injection (SI) and Hi Hi Consequence Limiting Safeguards (CLS) circuitry trains "A" and "8" to prevent an inadvertent engineered safeguards features actuation during the performance of the Unit 1 containment integrated leak rate test being performed pursuant to 1o CFR 50, Appendix J.

This procedure was performed with Unit 1 at cold shutdown, at which SI/CLS automatic actuation is not required. Double verification was used to ensure the affected equipment and controls were returned to their normal configuration following the test. Therefore, an unreviewed safety question was not created.

O-OPT-EG-6.3 Operations Periodic Test Procedures 4-17-92 1-0PT-EG-6.3 (Safety Evaluation No.92-090) 2-0PT-EG-6.3 Operations Periodic Test Procedures 0/1/2-0PT-EG-6.3, "Emergency Diesel Generator Starting Sequence Test", installed temporary electrical jumpers to enable the verification of the redundant starting circuits of the emergency diesel generators (EDG).

The test was performed on one EDG at a time, with the other two remaining fully operable. Appropriate Technical Specification limiting conditions for operation were entered. While each EDG was tested, it was isolated from the emergency busses and the consequence limiting safeguards circuitry.

Therefore, an unreviewed safety question was not created.

.Surry Monthly Operating Re~rt No. 92-04 Page 17 of 22 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1992 SUADM-0-26 Administrative Procedure 4-21-92 (Safety Evaluation No. 92-093A)

Administrative Procedure, SUADM-0-26, "Administrative Control Of Operational Components" was revised to clarify the requirements for administrative control of manual containment isolation valves that are opened intermittently during power operations.

This revision changed the valve closure time requirement from 30 seconds to 40 seconds. This change is based on an analysis which determined that the 40 second requirement would ensure valve closure prior to the release of fission products during a design basis loss of coolant accident. Therefore, an unreviewed safety question is not created.

SE 92-094 Safety Evaluation 04-21-92 This Safety Evaluation was performed to evaluate new calibration procedures for the Surry Radwaste Facility liquid and gas effluent line flow rate measurement device.

Implementation of these procedures does not affect safety related equipment or impact the operation of plant equipment. The assigned empirical instrument loop error in the new procedure is more conservative than the loop error used for the initial calibration of the subject instrument. Therefore, an unreviewed safety question is not created.

1-IPT-CC-RP- Instrument Periodic Test Procedure 04-23-92 Sl-001 A (Safety Evaluation No.92-096) 1-IPT-CC-RP-Sl-001 B Instrument Periodic Test Procedures, 1-IPT-CC-RP-Sl-001 A/8, "Train A/8 Safeguards Actuation Logic Test" installed temporary modifications to prevent an inadvertent safety injection (SI) actuation while performing safeguards actuation logic testing.

This procedure was performed with Unit 1 at cold shutdown at which time the SI system is not required. Double verification was used to ensure the affected equipment and controls were returned to their normal configuration following the test. Therefore, an unreviewed safety question was not created.

e .Surry Monthly Operating Report No. 92-04 Page 18of 22 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1992 1-ECA-1.1 Emergency Contingency Action Procedures 4-28-92 2-ECA-1.1 (Safety Evaluation No.92-106)

Emergency Contingency Action Procedures, 1/2-ECA-1.1, "Loss Of Emergency Cooling Recirculation" was revised to remove the seal-in contacts at the motor control center to allow the throttling of safety injection system motor operated valves (MOV), 1-SI-MOV-1842, 1-SI-MOV-1867C, 1-SI-MOV-1867D, 1-SI-MOV-1869A, 1-SI-MOV-1869B, 2-SI-MOV-2842, 2-SI-MOV-2867C, 2-SI-MOV-2867D, 2-SI-MOV-2869A, 2-SI-MOV-2869B.

This change maintains the full operating capability of the MOVs and provides additional operator flexibility in addressing emergency cooling recirculation transients. Therefore, an unreviewed safety question is not created.

1-0P-2.2.1 Operating Procedure 4-28-92 1-GOP-1.3 General Operating Procedure (Safety Evaluation No.92-105)

Unit 1 Operating Procedures 1-0P-2.2.1, "Turbine - Generator Startup To 20%" and 1-GOP-1.3, "Unit Startup, RCS Heatup From 350° F/450 PSIG To HSD" were revised to provide instructions for administratively controlling the main steam trip valve (MSTV) manual bypass valves during Unit 1 startup to heatup and pressurize the secondary system to allow opening the MSTVs.

During the performance of these procedures, the turbine stop valves and the steam dump valves remained closed and the MSTV bypass valves could have been closed promptly upon the initiation of a safety injection signal. These operating conditions during unit startup were evaluated and determined to be acceptable. Therefore, an unreviewed safety question is not created.

\

e .Surry Monthly Operating Report No. 92-04 Page 19 of 22 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: April 1992 ST-299 Reclrculation Spray Heat Exchangers Service Water Flow 4-20-92 Test (Safety Evaluation No.91-258)

This special test was performed March 16, 1992 to verify the adequacy of service water flow for design base accident events.

  • It also provided data and testing for new service water (SW) flow instrumentation and for modifications to the SW radiation monitor pumps. The test showed that actions taken in response to a previous test failure were successful in assuring service water flows. Additionally, the operability of the new flow instrumentation and radiation monitor pumps was verified. This test did not represent an unreviewed safety question as it was performed with the unit shutdown with service water to the heat exchangers not required.
  • CHEMISTRY REPORT

.Surry Monthly Operating Report No. 92-04 Page 20of 22 MONTH/YEAR: April 1992 Unit No.1 Unit No. 2 Primary Coolant Analysis Max. Min. Ava. Max. Min. AvQ.

(

Gross Radioact., J.LCi/ml 3.00E-2 1.78E-4 5.39E-3 2.14E-1 1.35E-1 1.74E-1 Suspended Solids, oom 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, u.Ci/ml --- --- --- 5.77E-1 4.85E-1 5.28E-1 1131, J.LCi/ml --- --- --- 4.81E-4 1.69E-4 3.34E-4 113111133 --- --- --- 0.14 0.07 0.09 Hydrogen, cc/kg 18.9 18.4 18.6 38.8 26.2 31.2 Lithium, oom --- --- --- 2.34 2.07 2.19 Boron - 10, oom* 490.6 436.1 478.8 179.7 160.1 168.3 Oxvaen, (DO), oom 8.0 < 0:005 3.2 < 0.005 < 0.005 < 0.005 Chloride, oom 0.014 < 0.001 0.004 0.050 < 0.001 0.004 pH at 25 degree Celsius 5.08 4.52 4.67 6.76 6.46 6.61

Unit 1 in refueling outage.

  • FUEL HANDLING

-Surry Monthly Operating Report No. 92-04 Page 21 of 22 UNITS 1 & 2 MONTH/YEAR: April 1992 New or Spent Number for 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 Stored or Received in April, 1992

v,

  • .Surry Monthly Operating Report DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED No. 92-04 Page 22 of 22 WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: April 1992 None During This Reporting Period.

'j,

Retrieved from "https://kanterella.com/w/index.php?title=ML18153C999&oldid=2402233"