ML18153A644

Monthly Operating Repts for Nov 1996 for Surry Power Station Units 1 & 2

ML18153A644
Person / Time
Site:	Surry
Issue date:	11/30/1996
From:	Fanguy M, Kilmer J, Mason D, Sarver S VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
96-624, NUDOCS 9612240092
Download: ML18153A644 (20)

Text

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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 11, 1996 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.96-624 NURPC Docket Nos.

50-280 50.:.281 License Nos. DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of November 1996.

If you have any questions or require additional information, please contact us.

Very truly yours, S. P. Sarver, Acting Manager Nuclear Licensing and Operations Support Enclosure cc:

U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. R. A. Musser NRC Senior Resident Inspector Surry Power Station

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e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT No. 96-11 Approved:

/'L--/o-7b Station Manager Date l

e TABLE OF CONTENTS Section Surry Monthly Operating Report No. 96-11 Page 2 of 19 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............................................................................................ 11 Procedure or Method of Operation Changes That Did Not Require NRG Approval................................................. 14 Tests and Experiments That Did Not Require NRG Approval.................................................................................. 16 Chemistry Report..................................................................................................................................................... 17 Fuel Handling - Unit No. 1........................................................................................................................................ 18 Fuel Handling - Unit No. 2........................................................................................................................................ 18 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications....................................................................................................................... 19

'.J OPERATING DATA REPORT e

Surry Monthly Operating Report Docket No.:

Date:

50-280 12-02-96 No. 96-11 Page3of19 Completed By:

D. K. Mason

{804) 365-2459

1.

Unit Name:...........................................................

2.

Reporting Period:.................................................

3.

Licensed Thermal Power (MWt):..........................

4.

Nameplate Rating (Gross MWe):.........................

5.

Design Electrical Rating (Net MWe):....................

6.

Maximum Dependable Capacity (Gross MWe):...

7.

Maximum Dependable Capacity (Net MWe):.......

Surry Unit 1 November, 1996 2546 847.5 788 840 801 Telephone:

8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11.

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

720.0 8040.0 209880.0

12.

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

720.0 8040.0 146090.7

13.

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

0.0 0.0 3774.5

14.

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

720.0 8040.0 143787.0

15.

Unit Reserve Shutdown Hours........... :............

0.0 0.0 3736.2

16.

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

1831836.9 20344832.7 336742625.2

17.

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

613055.0 6762400.0 110339583.0

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

592053.0 6527656.0 104983629.0

19.

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

100.0%

100.0%

68.5%

20.

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

100.0%

100.0%

70.3%

21.

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

102.7%

101.4%

64.4%

22.

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

104.4%

103.0%

63.5%

23.

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

0.0%

0.0%

15.3%

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

Refueling, March 6, 1997, 37 Days

25. If Shut Down at End of Report Period, Estimated Date of Start-up:

N/A

26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e OPERATING DATA REPORT -Surry Monthly Operating Report Docket No.:

Date:

50-281 12-02-96 No. 96-11 Page4of19 Completed By:

D. K. Mason (804) 365-2459

1.

Unit Name:...........................................................

2.

Reporting Period:.................................................

3.

Licensed Thermal Power (MWt):..........................

4.

Nameplate Rating (Gross MWe):.........................

5.

Design Electrical Rating (Net MWe):....................

6.

Maximum Dependable Capacity (Gross MWe):...

7.

Maximum Dependable Capacity (Net MWe):.......

Surry Unit 2 November, 1996 2546 847.5 788 840 801 Telephone:

8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9.

Power Level To Which Restricted, If Any (Net MWe):

10. Reasons For Restrictions, If Any:

This Month YTD Cumulative

11.

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

720.0 8040.0 206760.0

12.

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

720.0 7070.2 142573.1

13.

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

0.0 0.0 328.1

14.

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

720.0 7048.1 140604.2

15.

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

0.0 0.0 0.0

16.

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

1800857.2 17700808.0 330235862.0

17.

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

605255.0 5879660.0 108035304.0

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

584511.0 5680316.0 102790731.0

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

100.0%

87.7%

68.0%

20.

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

100.0%

87.7%

68.0%

21.

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

101.4%

88.2%

63.7%

22.

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

103.0%

89.7%

63.1%

23.

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

0.0%

1.8%

12.5%

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

Maintenance, December 12, 1996, 9 Days

25. If Shut Down at End of Report Period, Estimated Date of Start-up:

N/A

26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

e Surry Monthly Operating Report No. 96-11 Page 5 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: November, 1996 (1)

(2)

(3)

(4)

Method (5)

Docket No.:

50-280 Unit Name:

Surry Unit 1 Date:

12-05-96 Completed by:

M. J. Fanguy Telephone:

(804) 365-2155 Duration of LER No.

System Code Component Cause & Corrective Action to Date Type Hours Reason Shutting (1)

F:

Forced S:

Scheduled (2)

REASON:

Down Rx None During the Reporting Period A

Equipment Failure (Explain) 8 Maintenance or Test C

Refueling D

Regulatory Restriction Code Prevent Recurrence (3)

METHOD:

1 -

Manual 2 -

Manual Scram 3 -

Automatic Scram 4 -

Other (Explain)

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)

(5)

Exhibit 1 - Same Source

e Surry Monthly Operating Report No. 96-11 Page 6 of 19 UNIT SHUTDOWN AND POWER REDUCTION (EQUAL To OR GREATER THAN 20%)

REPORT MONTH: November, 1996 (1)

(2)

(3)

Method Duration of LER No.

Date Type Hours Reason Shutting 11/19/96 S

NA 11/19/96 F

NA 11/25/96 S

NA 11/25/96 F

NA (1)

F:

Forced S:

Scheduled B

B B

B (2)

REASON:

Down Rx NA NA NA NA NA NA NA NA A -

Equipment Failure (Explain)

B Maintenance or Test C

Refueling D

Regulatory Restriction Docket No.:

50-281 Unit Name:

Surry Unit 2 Date:

12-05-96 Completed by:

M. J. Fanguy Telephone:

(804) 365-2155 (4)

(5)

System Component Cause & Corrective Action to Code Code Prevent Recurrence TA V

SB V

TA V

SB V

Reduce Power to perform 2-0SP-TM-001.

Reduce power to <50% due to "D" reheat stop valve problems during 2-0SP-TM-001.

Reduce power to perform 2-0SP-TM-001.

Reduce power to <50% due to "B" intercept valve not reopening during 2-0SP-TM-001.

(3)

METHOD:

1 -

Manual 2 -

Manual Scram 3 -

Automatic Scram 4 -

Other (Explain)

E Operator Training & Licensing Examination F

Administrative G

Operational Error (Explain)

(4)

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

(5)

Exhibit 1 - Same Source

e Surry Monthly Operating Report No. 96-11 Page 7 of 19 AVERAGE DAILY UNIT POWER LEVEL Docket No.: 50-280 Unit Name:

Surry Unit 1 Date: 12-05-96 Completed by: J. D. Kilmer Telephone: (804) 365-2792 MONTH:

November, 1996 Average Daily Power Level Average Daily Power Level Day (MWe - Net)

Day (MWe - Net) 1 819 17 824 2

823 18 823 3

823 19 823 4

824 20 823 5

822 21 824 6

822 22 824 7

819 23 823 8

822 24 824 9

822 25 823 10 822 26 819 11 822 27 823 12 822 28 823 13 823 29 823 14 818 30 822 15 819 16 823 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. 96-11 Page 8 of 19 AVERAGE DAILY UNIT POWER LEVEL MONTH:

November, 1996 Average Daily Power Level Day (MWe - Net) 1 825 2

826 3

826 4

826 5

826 6

826 7

827 8

825 9

826 10 827 11 828 12 827 13 827 14 825 15 828 16 827 INSTRUCTIONS Day 17 18 19 20 21 22 23 24 25 26 27 28 29 30 Docket No.: 50-281 Unit Name:

Surry Unit 2 Date: 12-05-96 Completed by:

John D. Kilmer Telephone: (804) 365-2792 Average Daily Power Level (MWe - Net) 828 827 642 768 827 827 827 828 654 819 823 822 821 820 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

SUMMARY

OF OPERATING EXPERIENCE MONTH/VEAR: November, 1996 Surry Monthly Operating Report No. 96-11 Page 9 of 19 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:

11/01/96 11/07/96 11/09/96 11/30/96 UNIT Two:

11/01/96 11/19/96 0000

• The reporting period began with the unit ramping up with power at 93.5% power, 803 MWe.

0332 Stopped power increase at 100%, 855 MWe.

1804 Start power reduction to switch to IMP-IN.

1856 Stopped power reduction at 98%, 840 MWe.

1930 Started power increase after switching to IMP-IN.

2016 Stopped power increase at 100%, 855 MWe.

0931 Start power reduction to switch to IMP-OUT.

0947 Stopped power reduction at 98%, 841 MWe; Started power increase after switching to IMP-OUT.

0957 Stopped power increase at 100%, 856 MWe.

2400 0000 1000 1109 1256 1432 1521 1545 The reporting period ended with the unit operating at 100% power, 850 MWe.

The reporting period began with the unit operating at 100% power, 860 MWe.

Start power reduction to perform 2-0SP-TM-001.

Stopped power reduction at 91 %, 790 MWe.

Start power reduction for reheat and intercept valve testing.

Stopped power reduction at 71 %, 618 MWe.

Start power reduction due to problems with "D" reheat valve.

Stopped power reduction at 49%, 400 MWe.

11/20/96 11/25/96 11/26/96 11/27/96 11/30/96

-Surry Monthly Operating Report

SUMMARY

OF OPERATING EXPERIENCE MONTHNEAR: November, 1996 0101 Started power increase.

0216 Stopped power increase at 70%, 615 MWe to perform 2-0PT-RX-001.

0244 Started power increase.

0722 Stopped power increase at 100%, 855 MWe.

1021 Start power reduction to perform 2-0SP-TM-001.

1103 Stopped power reduction at 91 %, 784 MWe.

No. 96-11 Page10of19 1117 Start power reduction due to problems with No. 2 governor valve oscillations.

1422 Stopped power reduction at 74%, 642 MWe.

1522 Start power reduction due to problems with "B" intercept valve not re-opening.

1535 Stopped power reduction at 71%, 606 MWe for IRPI adjustment.

1540 Start power reduction.

1716 Stopped power reduction at 49%, 385 MWe.

2155 Started power increase.

0123 Stopped power increase at 95%, 820 MWe to switch to IMP-OUT.

.0213 Started power increase.

0259 Stopped power increase at 100%, 855 MWe.

1038 Start power reduction due to computer calorimetric indication of > 100% power.

1210 Computer calorimetric determined to be inoperable due to a failed Feedwater RTD; manual calorimetric used.

2400 The reporting period ended with the unit operating at 99% power, 850 MWe.

TM S1 0018 TM S1-96-0019 SE 96-095 Rev.4 FS 96-50 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTHNEAR: November, 1996 Temporary Modification (Safety Evaluation No.96-140) e Surry Monthly Operating Report No. 96-11 Page 11 of 19 11-7-96 The purpose of this Temporary Modification is to perform troubleshooting on the Unit 1 Main Generator 230KV Leads Pilot Wire Protection Circuit. The troubleshooting will determine why the Pilot Wire Ammeter indicates current with the associated Selector Switch in Normal and to correct this condition, if possible.

An unreviewed safety question does not exist. The Surry Power Generation System is non-safety related.

Sufficient protective relaying will remain in service while primary relaying is disabled.

Temporary Modification (Safety Evaluation No.96-141) 11-13-96 This Temporary Modification is to replace test switch 1-SI-CS-FC-494-TA in the Unit 1 train "A" of the Safety Injection (SI) system. All work performed will be in the train "A" portion of the SI system only. Train "B" will remain unaffected and will function as designed at all times. With the jumper installed, train "A" of the SI system will provide all of it's manual and automatic functions.

The test switch replacement is a like-for-like replacement with no change to the design of the system or any station isolation. During the time of switch replacement both trains of SI will function as designed.

Therefore, an unreviewed safety question does not exist.

Safety Evaluation 11-14-96 Safety Evaluation 96-095, Rev. 4, was revised to evaluate the in leakage of hydrogen gas into the pressurizer relief tank (PRT). The in leakage of hydrogen displaces the nitrogen blanket normally present in the PRT.

There are no sources of oxygen to the PRT.

This eliminates the possibility of an explosive atmosphere developing in the PRT. Additionally, the previous installation of the Temporary Modification will maintain the PRT at a positive pressure, prohibiting the influx of air. Therefore, an unreviewed safety question does not exist.

Updated Final Safety Analysis Report Change (Safety Evaluation 96-142) 11-14-96 This UFSAR change revises Section 9.1.2.4, "Reactor Makeup Control," to correct an invalid description of component operation, describe actual design performance, and expand on the described method of operation.

There are no changes to plant equipment or to methods of operation as described in approved operating procedures.

Therefore, an unreviewed safety question is not created.

• J FS 96-27 FS 96-46 Appendix R Report e

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1996 Updated Final Safety Analysis Report Change (Safety Evaluation 96-144) e Surry Monthly Operating Report No. 96-11 Page 12 of 19 11-21-96 Currently, the UFSAR states that pressure-relieving devices in the Safety Injection System located outside containment that circulate radioactive water under accident conditions discharge to a closed system. Section 6 of the UFSAR is being revised to reflect actual plant configuration by changing the words "closed system" to "Liquid Waste Disposal System."

During normal operation, opening of the relief valve results in no significant radiological consequences.

If the relief valve lifts during accident conditions, highly radioactive water would be released into a partially open sump. However, the resulting offsite dose would not exceed 10 CFR 100 limits. Therefore, an unreviewed safety question does not exist.

Updated Final Safety Analysis Report Change (Safety Evaluation 96-145) 11-21-96 Testing of the Safety Injection System is not performed as described in the UFSAR. The UFSAR currently states that the test is performed by injecting a test signal and verifying component actuation in the same test. The change to the UFSAR will depict how the tests are actually performed. The Safety Systems are tested by a series of tests which test portions of each system.

The performance of a series of tests fully satisfies the Technical Specifications and the testing as required by the UFSAR. Therefore, an unreviewed safety question does not exist.

Technical Report 11-21-96 (Safety Evaluation No.96-146)

This evaluation is being performed to assess the 1996 update of the Surry 1 OCFR50 Appendix R Report.

It incorporates DCPs completed May 1995 through September 1996, and information concerning other station changes as they pertain to Appendix R.

New engineering evaluations were added that address fire barriers and penetration seals. Changes to Appendix R exemption requests were performed to reflect current plant configurations. The report was also revised to incorporate a new method to track combustibles at the station.

The level of fire protection for the station is not being diminished, and the changes will not adversely affect the capacity to achieve and maintain safe shutdown in the event of a fire. Therefore, an unreviewed safety question does not exist.

1 (2)-0SP-TM-001 FS 96-45 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1996 Temporary Modification

. (Safety Evaluation No.96-148) e Surry Monthly Operating Report No. 96-11 Page 13 of 19 This Temporary Modification will evaluate the, use of an alternate power supply to energize the test solenoid valves used to close the Intercept and Reheat Stop Valves if the test circuitry is not working properly.

Nuclear Analysis and Fuel has previously reviewed the potential failure of the turbine control system as referenced in Engineering Transmittal NAF-95010. Should the valve limiter fail, the resultant load increase is bounded by the current safety analyses. The transmittal states that the physical limit on steam flow through the governor valves full open (105.5%) is bounded by the analyzed step load increase safety analysis limit (116%). Should a step load decrease occur, plant response would be within current design requirements and the reactor protection system would function as required.

Therefore, an unreviewed safety question does not exist.

Updated Final Safety Analysis Report Change (Safety Evaluation 96-149) 11-25-96 UFSAR Change Request 96-45 revises the Manual SI Block Reference value on UFSAR page 7.5-2 from 2000 PSIA to 2000 PSIG. This change is being made for consistency with Technical Specification 3.7 and the plant's Design Basis Documents.

The 2000 PSI manual block is not one of the key parameters required for the system to fulfill its safety related function described in UFSAR chapter 14. Accident conditions are assumed to initiate from a nominal pressure of 2250 PSIA. Therefore, an unreviewed safety question does not exist.

1 [2]-CSP-HRS-003 CH-41(42).110 CH-41(42).310 1 (2)-MOP-IA-003 2-TMOP-Rl-3034 e

e Surry Monthly Operating Report PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1996 Chemistry Surveillance Procedures (Safety Evaluation No.96-005 Rev.1)

No. 96-11 Page 14 of 19 11-7-96 Chemistry Surveillance Procedures 1 [2]-CSP-HRS-003, "High Radiation Sampling System: Sampling Containment Air Chemistry Test and Operator Training," CH-41(42).110, "Post Accident High Radiation Sampling System," and CH-41 (42).310 "High Radiation Sampling System: Sampling Containment Air," were revised to provide instructions for administratively controlling specific containment isolation valves while performing the subject procedure.

The specified containment isolation valves are required to be closed to maintain post accident containment integrity. The administrative controls provided by this change allow the valves to be opened during testing while ensuring compliance with the Technical Specifications. Therefore, an unreviewed safety question does not exist.

Maintenance Operating Procedure (Safety Evaluation No.96-143) 11-14-96 Maintenance Operating Procedure 1 (2)-MOP-IA-003, "Pressurizer PORV Air Bottle Changeout," provides instructions for replacement of backup air bottles after the air pressure in those bottles has been depleted. The normal Containment Instrument Air System or the Turbine Building Instrument Air System will be available during this evoiution and system availability is listed as an initial condition.

Although normal Instrument Air supply is available and the Pressurized Power Operated Relief Valve can be cycled, that PORV will be technically inoperable during the brief period that the backup bottled air supply is being valved out and the spare bottles are being valved in. The time restrictions contained in Technical Specification 3.1.A.6 and 3.1.G.2 will be fully met. Therefore, an unreviewed safety question does not exist.

Temporary Maintenance Operating Procedure (Safety Evaluation No.96-147) 11-21-96 Temporary Maintenance Operating Procedure 2-TMOP-Rl-3034,"Removal and Return to Service of Annunicator Panel 2G," was developed to provide instructions for increased monitoring and compensatory measures required while the Unit 2 annunicator "G" panel is removed from service for maintenance.

The Unit 2 Main Control Room annunicator "G" panel will be taken out of service to allow maintenance to be performed on annunicator panel connector plugs in accordance with a work order. Maintenance will be performed when the unit is in cold shutdown. Therefore, an unreviewed safety question does not exist.

SE 95-154, Rev. 1 e

Surry Monthly Operating Report No. 96-11 Page 15 of 19 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November,* 1996 Safety Evaluation 11-27-96 Safety Evaluation 95-154 Rev.1 was performed to evaluate Unit 2 operation with pressurizer spray control valve 2-RC-PCV-2455A maintained in a fully closed position.

The evaluation concluded that operation with one pressurizer spray valve closed and disabled will not invalidate any of the UFSAR Chapter 14 safety analyses. Therefore, an unreviewed safety question does not exist.

e Surry Monthly Operating Report No.. 96-11 Page 16 of 19 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR: November, 1996 None During the Reporting Period

1,'

(

e CHEMISTRY REPORT MONTHNEAR: November, 1996 Unit No. 1 Primary Coolant Analysis Max.

Min.

AvQ.

Gross Radioactivity, µCi/ml 9.02E-1 5.01 E-1 6.72E-1 Suspended Solids, ppm Gross Tritium, µCi/ml 3.43E-1 3.22E-1 3.33E-1 1131, µCi/ml 3.25E-2 7.41 E-3 1.18E-2 113111133 0.52 0.40 0.46 HvdroQen, cc/kg 39.2 36.0 38.1 Lithium, ppm 2.25 1.66 1.98 Boron - 10, ppm*

70.6 48.0 57.3 Oxygen, (DO), ppm

0.005

0.005

0.005 Chloride, ppm 0.003

<0.001 0.002 pH at 25 dearee Celsius 7.11 6.55 6.94 Boron - 10 = Total Boron x 0.196 Comments:

None e

Surry Monthly Operating Report Unit No. 2 Max.

Min.

1.89E-1 9.77E-2 7.69E-1 6.23E-1 1.71 E-4 2.76E-5 0.10 0.06 31.2 27.5 2.34 2.06 218.5 203.6

0.005

0.005 0.005 0.003 6.31 6.09 No. 96-11 Page 17 of 19 AvQ.

1.38E-1 7.05E-1 5.17E-5 0.08 29.8 2.18 211.3

0.005 0.004 6.20

New or Spent Fuel Shipment Date Stored or Number Received New Fuel Unit 1 Batch 17 11/05/96 Shipment 5 e

FUEL HANDLING UNITS 1 & 2 MONTHNEAR: November, 1996 Number of Assemblies Assembly ANSI per Shipment Number Number 12 59B LM13V2 37B LM13UE 35B LM13UC 38B LM13UF 15B LM13TS 21B LM13TY 52B LM13UV 16B LM13TT 40B LM13UH 41B LM13UJ 17B LM13TU 36B LM13UD e

Surry Monthly Operating Report Initial Enrichment 4.0099 3.9968 4.0057 4.0095 3.8087 3.8162 4.0181 3.8152 3.9990 4.0014 3.8043 3.9964 No. 96-11 Page 18 of 19 New or Spent Fuel Shipping Cask Activity 14.94 Ci

.[

lturry Monthly Operating Report No. 96-11 Page 19 of 19 DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTHNEAR: November, 1996 None During the Reporting Period