ML20080T994

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Monthly Operating Repts for Jan 1984
ML20080T994
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 01/31/1984
From: Jun Lee, Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Haller N
NRC
References
071, 71, NUDOCS 8403020122
Download: ML20080T994 (23)
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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION HONTHLY OPERATING REPORT MONTH January YEAR 1984 l

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S403020122 840131 y PDR ADOCK 05000338 R PDR

l OPERATING DATA REPORT DOCKET NO. 50-338 DATE 02-04-84 COMPLETED BY Joan N. Lee TELEPHONE (703) 894-5151 X2527 OPERATING STATUS Notes:

1. Unit Name: North Anna 1
2. Reporting Period: January 1984
3. Licensed Thermal Power (MWt): 2775 4.. Nameplate Rating (Gross MWe): 947
5. Design Electrical Rating (Net MWe): 907
6. Maximum Dependable Capacity (Gross MWe): 930
7. Mayimum Dependable capacity (Net MW'e): 877
8. If Changes Occur in capacity Ratings (Items No. 3 thru 7) Since Last Report, Give Reasons:

N/A ___

9.- Power Level To Which Restricted, If Any (Net MWe): N/A

10. Reasons For Restrictions, If Any: N/A This Month Yr.-to-Date Cumulative
11. Hours In Reporting Period 744 744 49,185
12. Number of Hours Reactor Was Critical 214 214 33,800.5
13. Reactor Reserve Shutdown Hours 0 0 3,021.5
14. Hours Generator On-Line 197.3 197.3 32,858.9
15. Unit Reserve Shutdown Hours 0 0 0 t
16. Gross Thermal Energy Cenerated (MWH) 539,653 539,653 85,591,426
17. Gross Electrical Energy Generated (MWH) 27,565,902 181,715 181,715
18. Het Electrical Energy Generated (MWH) 172,680 172,680 26,003,854
19. Unit Service Factor 26.6 26.6 66.8
20. Unit Availability Factor 26.6 26.6 66.8
21. ' Unit Capacity Factor (Using MDC Net) 26.5 26.5 60.3
22. Unit Capacity Factor (Using DER Net) 25.6 25.6 58.3
23. Unit Forced Outage Rate 73.5 73.5 61.0
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Scheduled Refueling 05-25-84

25. If Shut Down At End Of Report Period, Estimated Date of Startup: 02-07-84
26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

UNIT SHUTDOWNS AND POWER REDUCTIONS' DOCKET NO. 338 UNIT NAME North Anca 1 __

DATE 02-04-84 REPORT MONTH January COMPLETED BY Joan Lee TELEPHONE (703) 894-5151 X2527 I 2 -

No. Date Type Duration Reason Method of Licensee Systea Component Cause & Corrective (Hours) Shutting 3

vent Code 4

Code 5

Action to Down Reactor Report # Prevent Recurrence 84-01 840107 S B 5 NA NA NA Ramped down for Turbine Valve Freedom Test. Unit returned to full power.

84-02 840108 F 346.7 A 2 84-001 NA NA Commenced rampdown of Unit 1 due to high undentified

. Reactor Coolant System leak rate. On January 9, 1984 at 0516, turbine was tripped manually. Repairs are being made and Unit 1 is expected to be on-line February 7, 1984.

I 2 3 4 F: Forced Reason: Method: Exhibit F - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data l B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuations (NUREG-0161) 4 E-Operator Training & License Examination 5-Load Reduction F-Administrative 9-Other

G-Operational Error (Explain) 5 H-Other (Explain) Exhibit H - Same Source

Page 1 of 1 UNIT SHUTDOWN AND POWER REDUCTIONS EXPLANATION SHEET DOCKET NO. 50-338 REPORT MONTH January UNIT NAME NA-1

. YEAR 1984 DATE 02-04-84 COMPLETED BY Joan Lee 02 (F) (1) On January 8, 1984 Unit I commenced ramping down due to high unidentified Reactor Coolant System leak rate. On January 9, 1984 the turbine was trippet manually, and by 2200 on January 9,1984 the reactor waa shut down. Tube leaks were found after completing tes ts on "B" and "C" Steam Generators. Repairs are being m.de and th: expect-ed date for Unit 1 to be on line is February 7.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-338 UNIT NA-1 DATE 02-04-84

, COMPLETED BY Joan N. Lee TELEPHONE 703-894-5151X2527 MONTH January v

DAY AVERAGE DAILY F0WER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

'l 883 17 0 2 893 18 0 3 890 19 0 4 887 20 0 5 892 21 0 6 891 22 0 7 889 23 0 8 884 24 0 9 87 25 0 10 _0 26 0 11 0 27 0 12 0 28 0 13 0 29 0 14 0 30 0

15. 0 31 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. ,

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 1 MONTH January

SUMMARY

OF OPERATING EXPERIENCE Listed below in chronological sequence is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

DATE TIME DATA January 1, 1984 0000 . Started this month with Unit at 90% power 850 MW, due to Turbine Valve Freedom Test.

0045 Completed Turbine Valve Freedom Test.

0420 Unit at 100% power.

January 7, 1984 2210 Commenced'rampdown at 3% per hour for Turbine Valve Freedom Test.

January 8, 1984~ 0058 Turbine Valve Freedom Test completc. ,

Commenced rampup to 100%.

0340 Unit at 100% power 940 MW.

January 8, 1984 2318 Commenced rampdown at 150 MW per hour due to RCS leak rate.

. January 9, 1984 0516 Manually tripped turbine, entered Mode 2.

. January 31, 1984 2400 Ended this month with Unit in Mode 5.

Expected date for Unit I to be on-line is February 7, 1984.

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OPERATING DATA REPORT DOCKET NO. 50-339 DATE 02-04-84 COMPLETED BY Joan N. Lee TELEPHONE (703) 894-5151 X2527 OPERATING STATUS Notes:

1. Unit Wase: North Anna 2
2. Reporting Period: January 1984
3. Licensed Thermal Power (MWt): 2775
4. Nameplate Rating (Gross MWe): 947
5. Design Electrical Rating (Net MWe): 907
6. Maximum Dependable Capacity (Gross MWe): 939
7. Maximum Dependable Capacity (Net MWe): 89C
8. If Changes Occur in Capacity Ratings (Items No. 3 thru 7) Since Last Report, Give Reasons:

N/A

9. Power Level To Which Restricted, If Any (Net MWe): N/A
10. Reasons For Restrictions, If Any: N/A This Month Yr.-to-Date Cumulative
11. ' Hours In Reporting Period 744 744 27,456
12. Number of Hours Reactor Was Critical 744 744 20,390.9
13. Reactor Reserve Shutdown Hours 0 0 3,780
14. Hours Generator On-Line 744 744 20,251.1
15. . Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (NWH) 1,956,857 1,956,857 52,372,898
17. Gross Electrical Energy Generated (MWH) 640,695 640,695 17,355,062
18. Net Electrical Energy Generated (MWH) 607,935 607,935 16,460,017
19. Unit Service Factor 100.0 100.0 74.0
20. Unit' Availability Factor 100.0 100.0 74.0

.21., Unit Capacity Factor (Using MDC Net) 91.8 91.5 67.4

22. Unit Capacity Factor (Using DER Net) 90.1 90.1 66.1
23. Unit Forced Outage Rate 0 0 7.9
24. Shutdowns Scheduled Over Next 5 Months (Type, Date, and Duration of Each):

Scheduled Maintenance 03-30-84

25. -If Shut Down At End Of Report Period, Estimated Date of Startup:
26. -Units In Test Status (Prior to Commercial Operation): i Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-339 UNIT NAME North Anna 2 DATE 02-04-84 REPORT MONTH January COMPLETED BY. Joan Lee TELEPHONE (703) 894-5151 X2527 Ns. Date Typel Duration Reason ' Method of Licensee System Component Cause & Corrective (Hours) Shutting 3

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Down Reactor Report # Prevent Recurrence 84-01 840107 S B 5 NA NA NA Ramped down for Turbine Valve Freedom Test. Unit returned to full power.

84-02 840114 S B 5 NA NA NA Ramped down for Turbine Valve Freedom Test. Unit returned to full power.

i 84-03 840122 S B 5 NA NA NA Ramped down for Turbine Valve Freedom Test. Unit returned to full power.

84-04 840128 S B 5 NA NA NA Ramped down for Turbine Valve Freedom Test. Unit returned to full power. Ended this month with Unit at 100% power.

1 2 3 4 F: Forced Reason: Method: Exhibit F - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuations (NUREG-0161)

E-Operator Training & License Examination 5-Load Reduction F-Administrative 9-Other

) G-Operational Error (Explain) 5 H-Other (Explain) Exhibit H - Same Source

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-339 UNIT NA-2 DATE 02-04-84 COMPLETED BV Joan N. Lee TELEPHONE 703-894-5151X2527 HONTH January DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 168 17 870 2 161 18 869 3 771 19 869 4 860 20 869 5 863 21 871 6 866 22 865 7 862 23 862 8 866 24 859 9 861 25 863 10 862 26 871 11 863 27 869 12 865 28 864 13 864 29 870 14 865 30 870 15 865 31 869 16 869 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.

Page 1 of 1 i

UNIT SHUTDOWN AND POWER REDUCTIONS EXPLANATION SHEET DOCKET NO. 50-339 REPORT MONTH January UNIT NAME NA-2 YEAR 1984 DATE 02-04-84

. COMPLETED BY Joan Lee No entries this month r

L VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NO. 2 MONTH January

SUMMARY

OF OPERATING EXPERIENCE Listed below in chronological sequence is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

DATE TIME DATA January 1, 1984 0000 Started this month with Unit at 30% power -

Chemistry Hold.

January 3, 1984 0036 Commenced rampup to 100% power per 2-0P-2.1.

0445 Holding power at 90% for calorimetric.

I 0506 Re-commenced rampup to 100% power.

0559 Unit at 100% power.

January 7, 1984 0015 Commenced rampdown to 850 MW for Turbine Valve Freedom Test.

0050 Holding power at 850 MW.

/ 0138 Completed Turbine Valve Freedom Test.

0139 Commenced rampup to 100%.

0225 Unit at 100% power.

January 14, 1984 2325 Connnenced rampdown for Turbine Valve Freedom Test. Power at 97% - 860 MW.

January 15, 1984 0052 Completed Turbine Valve Freedom Test.

January 15, 1984 0158 Unit at 100% power.

' January 22, 1984 0055 Commmanced rampdown for Turbine Valve Freedom test.

0155 Commenced Turbine Valve Freedom Test, 91% power.

-0245 Completed Turbine Valve Feedom Test.

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l 0415 Unit at 100% power. I l

January 28, 1984 0013 Commenced rampdown for Turbine Valve i Freedom Test.

0030 - Commenced Turbine Valve Freedom Test.

- Power level 94%, 870 MW. l 0138 Turbine Valve Freedom Test complete.

Commencing rampup to 100% power.

0158 Unit at 100% power.

January 31, 1984 2400 Ended this month with Unit at 100% power.

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OPERATING DATA REPORT DOCKET NO. 50-338 DATE 01-04-84 COMPLETED BY Joan N. Lee TELEPHONE (703) 894-5151 X2527 OPERATING STATUS

. Notes:

1. Unit Name: North Anna 1
2. Reporting Period: December 1983
3. Licensed Thermal Power (MWt): 2775
4. Nameplate Rating (Gross MWe): 947 _
5. Design Electrical Rating (Net MWe): 907
6. Maximum Dependable Capacity (Gross MWe): 930
7. Maximum Dependable Capacity (Net MWe): 877
8. If Changes Occur in Capacity Ratings (Items No. 3 thru 7) Since Last Report, Give Reasons:

N/A

9. . Power Level To Which Restricted, If Any (Net MWe): N/A
10. Reasons For Restrictions, If Any: N/A This Month Yr.-to-Date Cumulative
11. Hours In Reporting Period 744 8,760 48,441
12. Number of Hours Reactor Was Critical 744 6,463.5 33,586.5

-13. Reactor Reserve Shutdown Hours 0 1,767.4 3,021.5 "

14. Hours Generator On-Line 744 6,279.4 32,661.6
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 2,059,548 16,851,419 85,051,773
17. Gross Electrical Energy Generated (MWH) 695,355 5,599,655 27,384,187
18. Net Electrical Energy Generated (MWH) 661,274 5,310,441 25,831,174
19. Unit Service Factor 100 71.7 67.4
20. Unit Availability. Factor 100 71.7 67.4
21. Unit Capacity Factor (Using MDC Net) 101.3 69.1 60.8 l
22. Unit Capacity Factor (Using DER Net) 98.0 66.8 58.8
23. Unit Forced Outage Rate 0 26.0 11.1
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Scheduled Refueling Outage 05-25-84

25. If Shut Down At End Of Report Period, Estimated Date of Startup:
26. Units'In Test Status-(Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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TS 3.7-2s G. ~The Main Control Room Chlorine Detection System shall be operable at

.sil' times. The number of operable channels, alarm / trip setpoint, and required operator actions shall be as specified in Table 3.7-7. This capability shall be demonstrated by the surveillanca requirements specified in Table 4.1-1.

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TABLE 3.7 -7 MAIN CONTROL ROOM CHLORINE DETECTION SYSTEM ,

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Total No. Operator Action -if Condition- in No. Functional Unit of Charnels Alarm / Trip Setpoint Column 2 Cannot be Met

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2 s 5 ppm chlorine With one channel inoperable, re-

1. Chlorine Detector store the inonerable channel within seven days; or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, initiate and main-tain operation of the control room emergency ventilation sys-tem.

With two channels inoperable,

' within one hour initiate and maintain operation of the control room emergency ventilation sys-tem.

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TS 3.7-9 monitor indication. The pressurizer safety valves utilize an acoustic monitor channel and a downstream high temperature indication channel. This capability is consistent with the recommendations of Regulatory Guide 1.97,

" Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant

' Conditions During and Following an Accident" December 1975, and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short Term Recommendations".

i Control Room Chlorine Detection System s

The operability of the chlorine detection system ensures that sufficient capability is available to promptly detect and automatically initiate protective action in the event of an accidental chlorine release. This capability is required to protect control room personnel, and is consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release,"

February 1975.

References (1) FSAR - Section 7.5 (2) -FSAR - Section 14.5 (3) FSAR - Section 14.3.2 (4) FSAR - Section 11.3.3 ,

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35. Control Room Chlorinr Detectors .

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DISCUSSION-OF PROPOSED CHANGE

'BACKCROUND

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NUREG-0737 Item III.D.3.4, Control Room Habitability, requires licensees to assure that . control room operators will be adequately protected against the effects of the accidental release of toxic or. radioactive gases and that the facility can be safely operated or shutdown under accident conditions. This discussion addresses toxic gas detection systems.

Vepco has designed and installed reduadant chlorine detection systems at the Surry Power Station, Units 1 and 2, which meets the requirements specified in Item III.D.3.4. Descriptions of.these modifications were submitted to NRC in Vepco's response to NUREG-0737 Post-TMI Requirements, dated' December 10, 1980, as revised May'31,l1981, October 31, 1981,.and May 31, 1982.

By letter. dated November'1, 1983,' NRC requested licensees to submit propesed Technical Specifications for certain NUREG-0737 items, including Item III.D.3.4,' Control Room' Habitability.

EVALUATION' ,

_s As part of a specialf case s'tudy of chemical shipments along the James River

- submitted.to NRC on June 30,:1981, Vepco agreed to make certain modifications at the Surry Power Station to meet the requirements of' Item III.D.3.4. These modifications included installation of a redundant main control room bottled air bank, and installation.of two independent chlorine gas detection systems at.the main control room ventilation intake.

The current main'[ control room . ventilation . system consists of a normal ventilation systea, an emergency ventilation system _and a single bottled dry air. bank'available under accident conditions to pressurize the control room to

-'a positive differentia 1 ' pressure.1 with respect to . ' adjoining - areas of the auxiliary, turbine: and service buildingsc n A redundant- bottled dry air bank has :been installed and a proposed Technical Specification' will be submitted seperately?to reflect that addition. .

9 . chlorine gas detection systems, capable of-detecting less than or equal to T

5 ppa and automatically.1solating normal control room ventilation, have also been-installe'd at the main" control room ventilation intake. A new proposed limiting Condition for- Operation and- appropriate surveillance requirements

- consistent with the guidance provided'in the staff'(s' November 1, 1983 Generic Letter are attached.-

  • Pursuant to 10CFR50.59, an evaluation to determine whether an unreviewed safety question exists has been imade. Th'e . proposed' changes ' do not increase the
probability ol occurrence or the consequences pf;an accident or malfunction of equipment important to : safety previously evaluated in the 1 safety - analysis report.. The proposed change'does not. affect the probability of occurrence of aan accident.since it. serves only as.an aid to operators alert 1ng them that a hazardous. ' condition has already occurred, and can reduce ' the consequences of the accident by automatically ~1nitiatfrg protective action in.the event of an accidental chlorine' release'.

The proposed changendoes not create the - possibility for an accident or

malfunction of a different type then any previously evaluated in the SAR.

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Rather, the proposed change adds an alarm / isolation function for chlorine gas detection; this does not create any new accident type.

The proposed changes do not reduce the margin of safety as defined in the bases for any Technical Specifications. Rather, the margin of safety is considered increased by adding additional alarm / isolation functions to alert and protect control room operators from accidental chlorine releases. The human factors aspect of these alarms will bc considered during Vepco's control room design review as part of our response to Item I.D.1 Control Room Design Review, of NUREG-0737.

We have also determined whether the proposed changes involve significant hazards considerations. The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (48 FR 14870). The examples of actions involving no significant hazards consideration include:

". . .(ii) A change that constitutes an additionci limitation, restriction or control not presently included in the Technical Specifications; for example, a more stringent surveillance requirement." The proposed changes are encompassed by this example in that the addition of the new LCO and surveillance requirements for the chlorine detection systems constitute additional limitations not presently found in the specifications and thus are similar to the example cited above.

CONCLUSIONS Because the proposed change does not increase the probability of occurrence or the consequences of an accident or equipment malfunction, create the possibility of an accident not previoucly analyzed, nor reduce a safety margin, we conclude that no unreviewed safety question exists with respect to the proposed change.

Because the proposed change is similar to an example previded by the Connaission for which no significant hazards consideration exists, we conclude that the proposed change involves no significant hazards consideration.

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i VINGINIA ELECTNIC AND POWER COMPANY Rrenwown,VINGINIA 20261 w.L.svuwier ,

Vaca Pasesommt weci... o . non. February 14, 1984 Mr. N. M. Haller, Director Serial No. 071 Office of Management and Program Analysis N0/JHL: jab U. S. Nuclear R6 ,ulatory Commission Docket Nos. 50-338 Washington, D. c. 20555 50-339

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License Nos. NPF-4 NPF-7

Dear Mr. Haller:

Enclosed is the Monthly Operating Report of North Anna Power Station Unit Nos.

1. and 2 for the month of January, 1984. Also enclosed is a corrected page from the North Anna Unit No. 1 Monthly Operating Report of December, 1983.

Very truly yours, LT &

W. L. Stewart Enclosure (3 copies) cc: Mr. R. C. DeYoung, Director (12 copies)

Office of Inspection and Enforcement

'Mr.' James P. O'Reilly (1 copy)

Regional Administrator Region II Hr. M. W. Branch NRC "esident.. Inspector North Anna Power Station o

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