Text

Monthly Operating Repts for Sept 1991 for Surry Power Station,Units 1 & 2
	ML18152A492
Person / Time
Site:	Surry
Issue date:	09/30/1991
From:	Negron M, Stewart W; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	91-629, NUDOCS 9110210075
	Download: ML18152A492 (25)
	v • d • e

.1 e

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 15, 1991 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.91-629 50-280 50-281 DPR-32 DPR-37 Enclosed in Attachment 1 is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of September 1991. Attachment 2 includes one corrected page from the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of August 1991 submitted to you in a letter* (Serial No.91-536) dated September 16, 1991.

Very truly yours,

\\~LM W. L. Stewart Senior Vice President - Nuclear Attachments

1. September 1991 Monthly Operating Report

2. Corrected Page - August 1991 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 I.

9 :l 10:2 :I. 0075 9 :l 09:30 PDR ADOCK 05000280 R

PDR

. \\1 (f Jf' 1-\\,

I I i

ATTACHMENT 1

e e

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 91-09 Approved:

e TABLE OF CONTENTS Section

-urry Monthly Operating Report No. 91-09 Page 2 of 21 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....................................................................................... 10 Facility Changes That Did Not Require NRG Approval............................................................................... 13 Procedure or Method of Operation Changes That Did Not Require NRC Approval........................................... 16 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................................................................................................... 21

.urry Monthly Operating Report No. 91-09 Page 3 of 21 OPERATING DATA REPORT Docket No.:

Date:

Completed By:

50-280 10-07-91 M.A. Negron 804-365-2795 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 September 1991 2441 847.5 788 820 781 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:

11. Hours In Reporting Period..........................

12. Number of Hours Reactor Was Critical..........

13. Reactor Reserve Shutdown Hours...............

14. Hours Generator On-Line...........................

15. Unit Reserve Shutdown Hours.....................

16. Gross Thermal Energy Generated (MWH)......

17. Gross Electrical Energy Generated (MWH)....

18. Net Electrical Energy Generated (MWH)........

19. Unit Service Factor...................................

20. Unit Availability Factor...............................

21. Unit Capacity Factor (Using MDC Net)...........

22. Unit Capacity Factor (Using DER Net)...........

23. Unit Forced Outage Rate............................

This Month 720.0 720.0 0.0 720.0 0.0 1730629.0 567500.0 539335.0 100.0%

100.0%

95.9%

95.1%

0.0%

YID 6551.0 6551.0 0.0 6551.0 0.0 15750361.4 5218220.0 4956597.0 100.0%

100.0%

96.9%

96.0%

0.0%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, February 16, 1991, 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):

Cumulative 164567.0 106025.2 3774.5 104031.2 3736.2 241970271.7 78795043.0 74739726.0 63.2%

65.5%

58.6%

57.6%

19.6%

FORECAST INITIAL CRITICALITY ACHIEVED INITIAL ELECTRICITY COMMERCIAL OPERATION

OPERATING DATA REPORT

-Surry Monthly Operating Report No. 91-09 Page 4 of 21 Docket No.:

50-281 10-07-91 M.A. Negron 804-365-2795

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):........

Date:

Completed By:

Surry Unit 2 September 1991 2441 847.5 788 820 781 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:

11. Hours In Reporting Period..........................

12. Number of Hours Reactor Was Critical..........

13. Reactor Reserve Shutdown Hours...............

14. Hours Generator On-Line...........................

15. Unit Reserve Shutdown Hours.....................

16. Gross Thermal Energy Generated (MWH)......

17. Gross Electrical Energy Generated (MWH)....

18. Net Electrical Energy Generated (MWH)........

19. Unit Service Factor...................................

20.

Unit Availability Factor...............................

21.

Unit Capacity Factor (Using MDC Net)...........

22.

Unit Capacity Factor (Using DER Net)...........

23.

Unit Forced Outage Rate............................

This Month 720.0 519.0 0.0 511.8 0.0 1020357.4 326575.0 307698.0 71.1%

71.1%

54.7%

54.2%

28.9%

YTD 6551.0 4109.0 0.0 4006.3 0.0 8296811.7 2723010.0 2576112.0 61.2%

61.2%

50.4%

49.9%

18.1%

Cumulative 161447.0 103281.3 328.1 101576.9 0.0 236432280.0 76953124.0 72954837.0 62.9%

62.9%

58.0%

57.3%

15.4%

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):

FORECAST INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION ACHIEVED I

J

(1)

Date Type 9-13-91 s

9-30-91 s

(1)

F:

Forced S: Scheduled (4) tlurry Monthly Operating Report No. 91-09 Page 5 of 21 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: September 1991 (2)

(3)

(4)

(5)

Method Docket No.: 50-280 Unit Name: Surry Unit 1 Date:

10-07-91 Completed by:

M. A. Negron Telephone: 804-365-2795 Duration of LER System Component Cause & Corrective Action to Hours 0

0 Reason Shutting No.

Code Code Prevent Recurrence B

B (2)

REASON:

Down Rx 4

NIA 4

NIA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction TA SPT TA V

E Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

Ramped unit from 100% to 58%

to repair No. 2 Governor Valve spring support.

Ramped unit from 100% to 56.5% to perform turbine valve freedom test (1-0SP-TM-001 ).

(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.

j

tlurry Monthly Operating Report No. 91-09 Page 6 of 21 UNIT SHUTDOWN AND POWER REDUCTION (ECUAL To OR GREATER THAN 20%)

REPORT MONTH: September 1991 Docket No.: 50-281 Unit Name: Surry Unit 2 Date:

10-07-91 Completed by: M.A. Negron Teleehone:

804-365-2795 (1)

(2)

(3)

(4)

(5)

Method Duration of LER System Component Cause & Corrective Action to Date Type Hours 9-7-91 F

208.2 9-16-91 F

0 9-18-91 s

0 9-19-91 s

0 9-24-91 s

0 9-28-91 s

0 (1)

F:

Forced S:

Scheduled Reason B

F B

B B

B (2)

REASON:

Shutting No.

Down Rx NIA 4

NIA 4

NIA A

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Code Code AA CL KD COND SH HX SH HX SH HX SH HX E

Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

(4)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NU REG 0161)

Prevent Recurrence Shut unit down, in accordance with normal operating procedures, to cold shutdown to replace coil stack for control rod D-4.

Reduced unit power from 54%

to 30% due to entry into Chemistry Action Level Ill for high cation conductivity in Condenser Hotwell.

Reduced power from 100% to 68% to maintain condenser vacuum while cleaning waterboxes.

Reduced power from 100% to 79% to maintain condenser vacuum while cleaning waterboxes.

Reduced power from 100% to 77% to maintain condenser vacuum while cleaning waterboxes.

Reduced power from 100% to 75% to maintain condenser vacuum while cleaning waterboxes.

(3)

METHOD:

1 -

Manual 2 -

Manual Scram.

3 -

Automatic Scram.

4 -

Other (Explain)

(5)

Exhibit 1 - Same Source.

4lurry Monthly Operating Report No. 91-09 Page ?of 21 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name: Surry Unit 1 Date: 10-07-91 Completed by: M.A. Negron Telephone: 804-365-2795 Month:

September 1991 Average Daily Power Level Average Daily Power Level Day (MWe-Net)

Day (MWe-Net) 1 757.4 17 747.5 2

760.2 18 717.3 3

755.9 19 758.9 4

753.2 20 763.5 5

741.2 21 765.2 6

725.2 22 754.2 7

763.6 23 772.9 8

761.6 24 773.5 9

751.3 25 771.0 10 740.8 26 770.3 11 751.7 27 772.3 12 730.0 28 772.5 13 655.5 29 772.4 I

14 740.1 30 661.3 15 760.0 31 16 751.7 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.

-urry Monthly Operating Report No. 91-09 Page 8 of 21 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-281 Unit Name:

Surry Unit 2 Date:

10-07-91 Completed by:

M.A. Negron Telephone:

804-365-2795 Month:

September 1991 Average Daily Power Level Average Daily Power Level Day (MWe-Net)

Day (MWe-Net) 1 401.1 17 512.0 2

416.6 18 698.9 3

419.0 19 692.5 4

359.0 20 752.0 5

388.5 21 765.4 6

0.0 22 769.1 7

0.0 23 763.2 8

0.0 24 742.7 9

0.0 25 725.5 10 0.0 26 738.0 11 0.0 27 750.2 12 0.0 28 719.8 13 0.0 29 758.5 14 0.0 30 756.4 15 87.6 31 16 204.5 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.

tlurry Monthly Operating Report No. 91-09 Page 9of 21

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: September 1991 Listed below in chron_ological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT ONE 09-01-91 09-05-91 09-06-91 09-09-91 09-10-91 09-12-91 09-13-91 09-14-91 09-18-91 0000 2150 This report period started with the Unit operating at 100% power, 795 MWe.

Started power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 770 MWe.

2255 Stopped power reduction; 84% power, 680 MWe.

0600 Started ramp up; 84% power, 680 MWe.

0752 Stopped ramp; 100% power, 810 MWe.

2250 0422 Started power reduction to maintain condenser vacuum while cleaning waterboxes; 1 00% power, 780 MWe.

Stopped power reduction; 91 % power, 680 MWe.

0523 Started ramp up; 91 % power, 695 MWe.

0559 Stopped ramp; 100% power, 805 MWe.

2032 0625 0830 1735 2146 2315 0623 0127 Started power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 780 MWe.

Started ramp up; 84% power, 650 MWe.

Stopped ramp; 100% power, 810 MWe.

Started ramp down to close #2 Governor Valve for repair of broken spring support; 100% power, 805 MWe.

Stopped ramp; 58% power, 440 MWe.

Started ramp up; 58% power, 440 MWe.

Stopped ramp; 99.4% power, 800 MWe.

Started power reduction to maintain condenser vacuum while cleaning waterboxes; 100%, 780 MWe.

0727 Started ramp up; 84% power, 690 MWe.

1 059 Stopped ramp; 100% power, 805 MWe.

r~..;;:;;;======~~~------------

UNIT ONE [continued]

09-25-91 2243 tlurry Monthly Operating Report No. 91-09 Page 10 of 21

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: September 1991

[continued]

Reduced power to 96.4%, 790 MWe. to stroke test #2 Governor Valve.

2321 Returned Unit to 100% power, 815 MWe.

09-30-91 0401 0735 1114 1530 2400 UNIT TWO 09-01-91 0000 09-04-91 1640 2215 09-05-91 0253 0412 0901 2348 09-06-91 0102 2036 09-07-91 0036 0102 2351 Started ramp down to perform 1-0SP-TM-001 (T~rbine valve freedom test);

100% power, 81 O MWe.

Stopped ramp; 56.5% power, 430 MWe.

Started ramp up; 57% power, 440 MWe.

Stopped ramp; 100% power, 805 MWe.

This report period ended with the Unit operating at 100% power, 805 MWe.

This report period started with the Unit operating at 60% power, 460 MWe due to dropped control rod D-4.

Started power reduction to maintain condenser vacuum while cleaning waterboxes; 60% power, 450 MWe.

Stopped power reduction; 50% power, 360 MWe.

Started power increase; 51 % power, 370 MWe.

Stopped power increase; 59% power, 425 MWe.

Started power reduction to maintain condenser vacuum while cleaning waterboxes; 59% power, 425 MWe.

Started power increase; 54% power, 420 MWe.

Stopped power increase; 60% power, 470 MWe.

Started ramp down to Cold Shutdown (CSD) to replace Coil Stack for control rod D-4; 60% power, 470 MWe.

Unit off line.

Reactor tripped manually in accordance with normal shutdown procedures.

Unit at CSD.

UNIT TWO 09-13-91 09-14-91 09-15-91 09-16-91 09-17-91 09-18-91 09-19-91 09-20-91

[continued]

1308 0354 0959 1648 2255 0113 0204 1543 1641 0236 0435 2109 2300 0121 0426 2018

.urry Monthly Operating Report No. 91-09 Page 11 of 21

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR: September 1991

[continued]

Unit left CSD and continued with heat up.

Unit at Hot Shutdown (HSD).

Reactor critical.

Unit on line and ramping up.

Unit entered Chemistry Action Level Ill due to high Cation conductivity in Condenser Hotwell. Started shutdown from 54% power.

Stopped ramp at 30% power; Cation conductivity at 1.9 micro mhos and decreasing.

Exited Chemistry Action Level Ill.

Started ramp up; 30% power, 200 MWe.

Stopped ramp due to exceeding 2% flux tilt; 49% power, 335 MWe.

Started ramp up from 46% power after new steam flow data was entered into "CALCALC" program (computerized calorimetric program).

Unit at 100% power, 795 MWe.

Started power reduction to maintain condenser vacuum while cleaning waterboxes; 1 00% power, 755 MWe.

Stopped power reduction; 68% power, 500 MWe.

Started ramp up; 68% power, 530 MWe.

Stopped ramp; 100% power, 775 MWe.

Started power reduction to maintain condenser vacuum while cleaning waterboxes; 1 00% power, 760 MWe.

21 34 Stopped power reduction; 79% power, 605 MWe.

221 4 Started ramp up; 79% power, 605 MWe.

0519 Stopped ramp; 100% power, 805 MWe.

.urry Monthly Operating Report No. 91-09 Page 12 of 21

SUMMARY

OF OPERATING EXPERIENCE MONTH/VEAR: September 1991

[continued]

UNIT TWO [continued]

09-24-91 09-25-91 09-26-91 09-27-91 09-28-91 09-30-91 2100 Started power reduction to maintain condenser vacuum while cleaning waterboxes; 100% power, 780 MWe.

2346 Stopped power reduction; 77% power, 590 MWe.

0306 Started ramp up; 77% power, 620 MWe.

0520 Stopped ramp; 100% power, 800 MWe.

0054 Started ramp down to maintain condenser vacuum while cleaning waterboxes; 1 00% power, 760 MWe.

0352 Stopped ramp; 86% power, 680 MWe.

0524 Started ramp up; 86% power, 680 MWe.

0622 Stopped ramp; 100% power, 800 MWe.

2245 0055 Started ramp down to maintain condenser vacuum while cleaning waterboxes; 100% power, 755 MWe.

Stopped ramp; 75% power, 580 MWe.

0335 Started ramp up; 75% power, 600 MWe.

0545 Stopped ramp; 99% power, 815 MWe.

2400 This report period ended with the Unit operating at 100% power, 800 MWe.

SE 91-209 DCP 87-030 e

4lurry Monthly Operating Report No. 91-09 Page 13 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/VEAR: September 1991 Safety Evaluation 09-05-91 This Safety Evaluation assesses the operation of Unit 2 at 60% power with Rod Cluster Control Assembly D-4 fully inserted for a period of twenty eight days during which troubleshooting and corrective actions will be performed to address the related dropped rod event.

The evaluation concluded that safety limits will continue to be met while operating under these conditions for a period of twenty eight days. In addition, it was determined by an evaluation that the applicable UFSAR accident analyses remain bounding. Therefore, an unreviewed safety question is not created.

Design Change Package (Safety Evaluation No.90-192) 09-09-91 This Design Change Package (DCP) installs a new Chemical and Volume Control System (CVCS) Letdown line trip valve, 1-CH-TV-1204A (inside Containment) and reinstalls CVCS Letdown Leakage Monitoring isolation valve 1-CH-427.

The new trip valve, 1-CH-TV-1204A, performs the isolation function previously served by eves Letdown Flow Orifice isolation valves 1-CH-HCV-120DA, 8, and C and will improve leakage testing concerns, reduce personnel exposure and improve penetration design features.

Reinstallation of valve 1-CH-427 will improve maintenance accessibility to the letdown orifices.

The new trip valve and related limit switches were designed consistent with the original design basis criteria for containment isolation valves and the requirements of Regulatory Guide 1.97. The reinstallation of 1-CH-427 involves the replacement of original equipment. CVCS operation is unchanged by these modifications. Therefore, an unreviewed safety question is not created.

EWR 91-112 Engineering Work Request (Safety Evaluation No.91-197) 09-09-91 This Engineering Work Request (EWR) installs additional switches in the rod control cabinet to jumper "DC Hold" to the moveable gripper for Control Rod D-4.

This modification was made in response to previous Control Rod D-4 stationary gripper coil fuse failures. Until the cause of these failures can be determined, this change will enable the moveable gripper coil to be energized when the control rod is fully withdrawn and prevent it from being inadvertently dropped into the core.

This modification does not affect the ability of the rod control system to perform its intended safety function and will reduce the probability of dropping a control rod into the core. Therefore, an unreviewed safety question is not created.

-urry Monthly Operating Report No. 91-09 Page 14 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL TM S2-91-38 TM S2-91-39 TM S2-91 -34 MONTH/YEAR: September 1991

[continued]

Temporary Modification (Safety Evaluation No. 91 -212) 09-14-91 This Temporary Modification (TM) installed electrical jumpers to permit the replacement of Unit 2 Reactor Protection System High Steam Line Differential Pressure relay, 2-RP-REL-103.

This TM maintained the Safety Injection system "A" train logic during the replacement activity.

The "B" train and the ability to perform its intended safety function were not affected. Therefore, an unreviewed safety question is not created.

Temporary Modification (Safety Evaluation No.91-213) 09-14-91 This Temporary Modification (TM) installed electrical jumpers to permit the replacement of Unit 2 Reactor Protection System High Steam Line Differential Pressure relay, 2-RP-REL-104.

This TM maintained the Safety Injection system "B" train logic during the replacement activity.

The "A" train and the ability to perform its intended safety function were not affected. Therefore, an unreviewed safety question is not created.

Temporary Modification (Safety Evaluation No. 91 -216) 09-23-91 This Temporary Modification (TM) installs electrical jumpers to defeat the Control Rod K-2 (Control Bank "A") rod bottom bistable inputs to the Individual Rod Position Indication (!RPI) dropped rod runback and rod stop circuits.

This TM will prevent a spurious turbine runback while troubleshooting and repairing IRPI circuits for Control Rod K-2.

This modification defeats only the

!RPI runback and rod stop signals from Control Rod K-2. The other inputs to the runback and rod stop circuitry are unaffected and will remain operable. The analyzed rod drop accident assumptions and conclusions remain bounding during this evolution. Therefore, an unreviewed safety question is not created.

-urry Monthly Operating Report No. 91-09 Page 15 of 21 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL DR S-91-1062 MONTH/YEAR: September 1991

[continued]

Deviation Report (Safety Evaluation No.91-219) 09-30-91 This Safety Evaluation assesses the consequences of the Condenser steam dump permissive setpoint being incorrectly altered (during the implementation of a design modification) from 25 inches to 26.5 inches when the condenser vacuum was below 26.5 inches.

The evaluation concluded that the Condenser steam dumps are not safety related and are not required to be operable to meet the assumptions of the UFSAR Chapter 14 accident analyses. Therefore, an unreviewed safety question is not created.

O-MCM-0705-01 MMP-C-FS-260 EWR 91-076A 9urry Monthly Operating Report No. 91-09 Page 16 of 21 PROCEDURES OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1991 Mechanical Corrective Maintenance Procedure (Safety Evaluation No.91-208) 09-05-91 Mechanical Corrective Maintenance Procedure, O-MCM-0705-01, "Emergency Diesel Injector Rack, Governor Compensation, and Speed Limit Switch Adjustments" was revised to provide instructions for installing an in-line ammeter in the governor control circuit to monitor current to the synchronizer motor and operation of the VSR1 and VSR2 relays (to verify output breaker permissive setpoints).

During the performance of this procedure, the affected Emergency Diesel Generator (EOG) will be inoperable (however, the EDG could be placed in service if plant conditions warrant) and the redundant EDG will be fully operable.

Technical Specification 3.16 allows for one EDG to be inoperable for up to seven days. Therefore, an unreviewed safety question does not exist.

Corrective Mechanical Maintenance Procedure (Safety Evaluation No.91-211, Revision 1) 09-12-91 Corrective Mechanical Maintenance Procedure, MMP-C-FS-260, "Freeze Sealing - Liquid Nitrogen Method - Single Freeze" was performed on the Unit 2 Reactor Coolant System (RCS) "B" loop Resistance Temperature Detector (RTD) manifold return piping to isolate and allow the return isolation valve, 2-RC-63, to be repaired.

The Unit was at Cold Shutdown during the installation and special RCS pressure and temperature requirements were imposed.

Limiting conditions were established to limit potential RCS leakage, as a result of freeze seal failure, and to ensure the leakage would remain within the make-up capacity of the Safety Injection system. 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 does not exist.

Engineering Work Request (Safety Evaluation No. 91-14 7) 09-13-91 This Engineering Work Request (EWR) removes the internals and bonnet from Unit 2 Reactor Coolant System (RCS) Resistance Temperature Device (RTD) manifold outlet isolation valve, 2-RC-63, and installs a blind flange.

The subject valve was installed to provide isolation for maintenance purposes, provides no nuclear safety function and remains open during normal plant operation. This modification does not adversely affect flow through the RTD manifold, RCS operating characteristics, or system pressure boundary integrity.

Therefore, an unreviewed safety question does not exist.

. ~

EMP-C-RT-218 1-0SP-TM-001 aurry Monthly Operating Report No. 91-09 Page 17 of 21 PROCEDURES OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1991

[continued]

Corrective Electrical Maintenance Procedure (Safety Evaluation No.91-218) 09-26-91 Corrective Electrical Maintenance Procedure, EMP-C-RT-218, "Troubleshooting, Repair and Replacement of Protective Relays and Associated Control Circuits" was performed to replace the Unit 2 Reactor Protection System {RPS) "B" train test switch, 2-RP-CS-158.

This activity affected only the test portion of the RPS train "B" circuit.

Both RPS trains "A" and "B" were able to perform their intended safety function.

Furthermore, this type of maintenance activity is permitted by Technical Specification 3.7. Therefore, an unreviewed safety question does not exist.

Operations Surveillance Procedure

{Safety Evaluation No.91-220) 09-29-91 Unit 1 Operations Surveillance Procedure, 1-0SP-TM-001, "Turbine Inlet Valve Freedom Test" was revised to permit the subject testing to be performed with the turbine controls in "Manual" due to an electronic failure.

The revised test procedure contains specific precautions, instructions and expected results for the prescribed activities.

The test parameters are bounded by existing control systems, protections systems, and UFSAR analyses. Therefore, an unreviewed safety question is not created.

)

.urry Monthly Operating Report No. 91-09 Page 18 of 21 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: September 1991 None During This Reporting Period.

CHEMISTRY REPORT MONTH/YEAR: September 1991 Unit No. 1 Primary Coolant Analvsis Max.

Min.

Ava.

Gross Radioact., uCi/rnl 8.65E-1 3.69E-1 6.11E-1 Suspended Solids, corn 0.0 0.0 0.0 Gross Tritium, uCi/rnl 1.89E-1 1.66E-1 1.78E-1 1131, uCi/rnl 3.24E-3 1.58E-3 2.26E-3 113111133 0.13 0.07 0.09 Hydrogen, cc/kg 41.2 29.4 34.0 Lithium, corn 2.30 1.92 2.15 Boron - 10, corn*

79 55 65 Oxvaen, (DO), nnrn

<0.005

<0.005 Chloride, corn 0.004 0.001 0.002 pH at 25 degree Celsius 7.27 7.04 7.16 Boron -10 = Total Boron x 0.196 Comments:

.urry Monthly Operating Report No. 91-09 Page 19 of 21 Unit No. 2 Max.

Min.

Ava.

2.49E-1 2.97E-3 8.26E-2 0.0 0.0 0.0 2.80E-1 1.21E-1 1.41 E-1 7.92E-4 8.74E-5 2.79E-4 0.16 0.07 0.10 42.6 26.1 35.7 3.30 1.47 2.20 465 247 341

<0.005

<0.005 0.006 0.002 0.003 6.46 5.55 6.11 Unit 1:

Lithium was outside the limits of the Boron/Lithium Program for a total of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and 56 minutes (low on 9 91 for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and 45 minutes and on 9-30-91 for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 11 minutes).

Unit 2:

Lithium was outside the limits of the Boron/Lithium Program, low on 9-15-91 for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

Units One and Two Cask Stored e

FUEL HANDLING UNITS 1 & 2 MONTH/YEAR: September 1991 Number for Assemblies per Shipment Assembly Number ANSI Number None during this reporting period.

e Surry Monthly Operating Report No. 91-09 Page 20 of 21 Nominal Initial Enrichment New or Spent Fuel Shipping Cask Activity J

e

.urry Monthly Operat;ng Report No. 91-09 Page 21 of 21 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR: September 1991 None During This Reporting Period.

e ATTACHMENT 2 CORRECTED PAGE

I l 1

e CHEMISTRY REPORT MONTH/YEAR: August 1991 Unit No. 1 Primary Coolant Analysis Max.

Min.

AvQ.

Gross Radioact., uCi/ml 6.68E-1 3.96E-1 5.08E-1 Susoended Solids, oom 0.0 0.0 0.0 Gross Tritium, uCi/ml 1.86E-1 1.79E-1 1.84E-1 1131, uCi/ml 3.24E-3 1.61 E-3 2.11 E-3 113111133 0.13 0.07 0.09 Hydrogen, cc/kg 38.7 29.1 32.8 Lithium, oom 2.33 1.94 2.17 Boron - 1 o, oom*

97.6 72.3 81.3 Oxvi:ien, (DO), oom

<0.005

<0.005 Chloride, oom 0.003 0.002 0.002 pH at 25 dei:iree Celsius 7.13 6.89 7.04 Boron - 1 O = Total Boron x 0.196 Comments:

-Surry Monthly Operating Report No. 91-08 Page 23 of 25 Unit No. 2 Max.

Min.

Avi:i.

2.17E-1 3.99E-3 1.05E-1 0.0 0.0 0.0 2.29E-1 1.89E-1 2.09E-1 4;33E-3 5.35E-5 5.22E-4 0.21 0.07 0.12 40.0 29.6 32.7 3.29 1.77 2.26 372.2 257.7 293.2

<0.005

<0.005 0.003

<0.001 0.002 6.38 5.81 6.26 Unit 1:

Lithium was outside the limits of the Boron/Lithium Program, low on 8-24 for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and 20 minutes.

Unit 2:

Lithium was outside the limits of the Boron/Lithium Program, low on 8-15 for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and 5 minutes, and 8-16 for 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months . Lithium was outside the limits of the Boron/Lithium Program for a total of 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months and 5 minutes.

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