ML18153C117

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Monthly Operating Repts for Jan 1990 for Surry Power Station Units 1 & 2.W/900214 Ltr
ML18153C117
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/31/1990
From: STEWART W L, WARREN L A
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-079, 90-79, NUDOCS 9002270352
Download: ML18153C117 (23)
v • d • e


Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 14, 1990 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.90-079 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of January 1990. Very truly yours, 0.L~ W. L. Stewart Senior Vice President

-Nuclear Enclosure cc: U. S. Nuclear Regulatory Commission Region II ( 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station 9002270352 900131 PDR ADOCK 05000280 R PNU e rs POW 34-04 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT II 90-01 APPROVED:

..

  • e TABLE OF CONTENTS SECTION Operating Data Report -Unit No. 1 Operating Data Report -Unit No. 2 Unit Shutdowns and Power Reductions

-Unit No. 1 Unit Shutdowns and Power Reductions

-Unit No. 2 Average Daily Unit Power Level -Unit No. 1 Average Daily Unit Power Level -Unit No. 2 Summary of Operating Experience

-Unit No. 1 Summary of Operating Experience

-Unit No. 2 Facility Changes That Did Not Require NRC Approval Procedure or Method of Operation Changes that Did Not Require NRC Approval Tests and Experiments That Did Not Require NRG Approval Chemistry Report Fuel Handling -Unit No. 1 Fuel Handling -Unit No. 2 Description of Periodic Test(s) Which Were Not Completed Within the Time Limits Specified in Technical Specifications PAGE 1 2 3 4 5 6 7 9 12 16 17 18 19 19 20

,. I, .. ,.; .<

  • e e OPERATING DATA REPORT DOCKET NO.: 50-280 DATE: ...,,.02"'"'/..-::::0=7-,,/

9=0=-------

COMPLETED BY: L.A. Warren TELEPHONE:

(804)357-3184 x355 OPERATING STATUS NOTES 1. Unit Name: Surry Unit 1 2. Reporting Period: JAN 01-31, 1990 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. Reason For Restrictions, If Any: ----------------------

THIS MONTH YTD CUMULATIVE

11. Hours In Reporting Period 744.0 744.0 150000.0 12. Number of Hours Reactor Was Critical 744.0 744.0 93494.8 13. Reactor Reserve Shutdown Hours 0 0 3774.5 14. Hours Generator On-Line 744.0 744.0 91567.2 15. Unit Reserve Shutdown Hours 0 0 3736.2 16. Gross Thermal Energy Generated (MWH) 1789748.0 1789748.0
  • 212906551.0
17. Gross Electrical Energy Generated (MWH) 606545.0 606545.0 69151948.0
18. Net Electrical Energy Generated (MWH) 578112.0 578112 .o 65589042.0
19. Unit Service Factor 100% 100% 61% 20. Unit Availability Factor 100% 100% 63.5% 21. Unit Capacity Factor (Using MDC Net) 99.5% 99.5% 56.5% 22. Unit Capacity Factor (Using DER Net) 98.6% 98.6% 55.5% 23. Unit Forced Outage Rate 0% 0 21.5 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 Startup: .--..-==---
26. Unit In Test Status (Prior to Commercial Operation):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 1

' ,. .(
  • e OPERATING DATA REPORT DOCKET NO.: 50-281 DATE: ......,,.0.,...2/..,..,0""'7...,/'""9"""0------

COMPLETED BY: L.A. Warren --,,~.,......,,..,,....-..,...,,...,_.....,,...,,,..,,.....-

TELEPHONE:

(804)357-3184 x355 --------------

OPERATING STATUS NOTES 1. Unit Name: Surry Unit 2 2. Reporting Period: JAN 01-31, 1990 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. Reason For Restrictions, If Any: ---------------------

THIS MONTH YTD CUMULATIVE

11. Hours In Reporting Period 744.0 744.0 146880.0 12. Number of Hours Reactor Was Critical 744.0 744.0 91942.6 13. Reactor Reserve Shutdown Hours 0 0 328.1 14. Hours Generator On-Line 744.0 744.0 90392.9 15. Unit Reserve Shutdown Hours 0 0 0 16. Gross Thermal Energy Generated (MWH) 1694307.6 1694307.6 211304642.4
17. Gross Electrical Energy Generated (MWH) 572250.0 572250.0 68652849.0
18. Net Electrical Energy Generated (MWH) 544553.0 544553.0 65085512.0
19. Unit Service Factor 100% 100% 61.5% 20. Unit Availability Factor 100% 100% 61.5% 21. Unit Capacity Factor (Using MDC Net) 93.7% 93.7% 56.9% 22. Unit Capacity Factor (Using DER Net) 92.9% 92.9% 56.2% 23. Unit Forced Outage Rate 0% 0% 15.6% 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 Startup: 26. Unit In Te;st Status (Prior to Commercial Operation):

FORECAST--A-C_H_I_E_V_E_D_

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 2

NO. F: S: DATE TYPE(l) 01/07/90 S 01/14/90 F 01/21/90 S (1) UNIT SHUTDOWN AND POWER REDUCTION

()20%) REPORT MONTH: JANUARY 1990 METHOD OF LICENSEE SHUTTING EVENT DURATION (HOURS) REASON(2)

DOWN REACTOR(3)

REPORT# 0 B 0 A 0 B 4 (manual power reduction) 4 (manual power reduction) 4 (manual power reduction)

SYSTEM CODE(4) SD SD EL Forced Scheduled (2) REASON: A -Equipment Failure (Explain)

B -Maintenance or Test (3) METHOD: 1 -Manual C -Refueling D -Regulatory Restriction E -Operator Training & License Examination F -Administrative G -Operational Error (Explain)

H -Other (Explain) 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain) 3 t .... DOCKET NO.: 50-280 UNIT NAME: _S_u_r-ry_U_n_1._*

t---_ 1--:.-DATK: 02/07/90 COMPLETED BY: ....,,,.L-.A.a,--.

-,;W~a-r_r_e_n

___ _ TELEPHONE:

804-357-3184 x355 COMPONENT CODE(5) CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE V p FAN Ramped down to repair leak on l-CN-207.

Valve is associated with l-FW-P-..* 1.£: The main feed p~ 1-FW-P-lA, was secured to facilitate valve repair. Ramped down upon securing 1-SD-P-lB due to fire in seal area of pump. Ramped down to replace belt on 'C' phase bus duct cooling fan. (4) Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) (5) Exhibit 1 -Same Source NO. F: S: *, DATE TYPE(l) UNIT SHUTDOWN AND POWER REDUCTION

()20%) REPORT MONTH: JANUARY 1990 METHOD OF LICENSEE SHUTTIN'G EVENT SYSTEM DURATION (HOURS) REASON(2)

DOWN REACTOR(3)

REPORT# CODE(4) 01/06/90 S 0 B 4 SJ (1) Forced Scheduled (2) REASON: (manual power reduction)

A -Equipment Failure (Explain)

B -Maintenance or Test C -Refueling D -Regulatory Restriction E -Operator Training & License Examination F -Administrative G -Operational Error (Explain)

H -Other (Explain)

(3) METHOD: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain) 4 ,. -'.* DOCKET NO.: 50-281 UNIT NAME: ---S-u-rry--U-n_i_t

___ 2 __ :. -DATE: 02/07/90 COMPLETED BY: L.A. Warren TELEPHONE:

804-357-3184 x355 COMPONENT CODE(5) CAUSE & CORRECTIVE ACTION TO PREVENT RECURRENCE p Ramped down to remove 2-FW-P-lB from service for repairs. (4) Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) (5) Exhibit I -Same Source e

.=--------=

'" *'" ... e e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: 50-280 UNIT NAME: Surry Unit 1 DATE: 02707790 COMPLETED BY: L.A. Warren TELEPHONE:(804)357-3184 x355 MONTH: JANUARY 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 788 17 782 2 791 18 789 3 788 19 789 4 785 20 787 5 791 21 734 6 792 22 787 7 560 23 788 8 791 24 789 9 791 25 790 10 789 26 791 11 788 27 790 12 786 28 791 13 787 29 789 14 763 30 789 15 761 31 787 16 767 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.

5

'** ., . e e AVERAGE DAILY UNIT POWER LEVEL MONTH: JANUARY 1990 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 783 2 779 3 783 4 774 5 774 6 497 7 771 8 783 9 782 10 783 11 783 12 779 13 780 14 761 15 783 16 783 INSTRUCTIONS DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 DOCKET NO.: 50-281 ---,,,---.=---,----,,---

UNIT NAME: Surry Unit 2 .DATE: 02/07/90 COMPLETED BY: L.A. Warren TELEPHONE:(804)357-3184 x355 AVERAGE DAILY POWER LEVEL (MWe-Net) 783 742 708 726 779 677 670 669 667 671 673 672 679 698 697 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.

6

,, e e

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR:

JANUARY 1990 Listed below in chronological sequence by unit is experiences for this month which required load significant non-load related incidents.

a summary of operating reductions or resulted in UNIT ONE 01/01/90 0000 01/04/90 1141 1249 1618 1712 01/07/90 0402 This reporting period began with the Unit at 100% power, 830 MW. Started rampdown for l-ST-273; 2-FW-P-2 full flow test; 100% power, 830 MW. Stopped ramp, 95.5% power, 790 MW. Started ramp up, l-ST-273 completed; 95% power, 785 MW. Stopped ramp; 100% power, 830 MW. Started ramp down to remove 1-FW-P-lA in order to repair l-CN-207; 100% power, 830 MW. 0639 Stopped ramp; 60% power. 0700 Started ramp down to decrease flow requirements for 1-FW-P-lB; 60% power. 0730 1936 01/12/90 2025 2037 01/13/90 0030 01/14/90 2011 2018 Stopped ramp; 56% power, 445 MW. Started ramp up, l-CN-207 repaired and 1-FW-P-lA returned to service; 56% power, 440 MW. Started ramp down in order to prepare for testing of Ch-2 over power/over temperature delta temperature (OP/OT DT) (Ch-3 alarming intermittently);

100%, 825 MW. Stopped ramp; 99% power, 820 MW. Ramped up after completion of test for Ch-2 OP/OT DT; 100% power, 825 MW. Started ramp down; fire occurred in the lower seal area of 1-SD-P-lB and as a result the pump was secured; 100% power, 830 MW. Plant stable at 96% power. 2039 Started ramp down to increase main feed pump suction pressure; 96% power. 2108 Stopped ramp; 90% power 700 MW. 7

, .. ". Ly OF OPERATING EXPERIENCE e MONTH/YEAR:

JANUARY 1990 Listed below in chronological sequence by unit is a summary of operating

.. experiences for this mo.nth which required load. reductions or resulted in .. significant non-load rel~ted incidents.

UNIT ONE 01/14/90 2125 Started ramp down to pressure to 425 psig power, 700 MW. increase main feed pump suction for reset of pressure switch; 90% 01/15/90 01/16/90 01/21/90 01/31/90 . 01/31/90 2140 Stopped ramp; 87% power, 670 MW. 2150 Started ramp down to maintain main feed pump suction pressure while closing the condensate polisher bypass valve (l-CP-AOV-122).

2225 0302 0421 1156 1252 1817 1901 0830 1018 1217 1454 1108 1120 1315 1330 2400 Stopped ramp; 80% power, 620 MW. Started ramp up; 1-SD-P-lA placed in service; 80% power, 650 MW. Stopped ramp; 100% power, 825 MW. Started ramp down to prepare for l-PT-29.1.

Stopped ramp, 90% power, 745 MW. Started ramp up; l-PT-29.1 completed; 90% power, 745 MW. Stopped ramp; 100% power, 825 MW. Started ramp down to allow belt replacement on 'C' isolated phase bus duct cooling fan; 100% power, 830 MW. Stopped ramp; 62% power, 500 MW. Started ramp up; belt on 'C' cooling fan replaced and fan returned to service; 63% power, 480 MW. Stopped ramp; 100% power, 830 MW. Started ramp down to prepare for turbine driven auxiliary feed pump, l-FW-P-2, operation; 100% power 825 MW. Stopped ramp; 98% power, 800 MW. Started ramp up; l-FW-P2 secured; 98% power, 800 MW. Stopped ramp; 100% power, 830 MW. This reporting period ended with the Unit at 100% power, 830 MW. 8 e e

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR:

JANUARY 1990 Listed below in chronological sequence by unit is experiences for this month which required load significant non-load related incidents.

a summary of operating reductions or resulted in UNIT TWO 01/01/90 0000 01/04/90 0950 1005 01/05/90 1959 This reporting period began with the Unit at 100% power, 820 MW. Started ramp down to ensure <7% difference exists between 'A' loop over temperature delt~temperature (OTDT) setpoint (STPT) and actual delta temperature (DT); 100% power, 825 MW. Stopped ramp; 98% power, 815 MW. Started ramp up; adequate margin exists between OTDT STPT. and actual DT for 'A' loop; 98% power, 810 MW. 2012 Stopped ramp; 100% power, 820 MW. 01/06/90 0104 Started ramp down to remove 2-FW-P-lB from service for repairs; 100% power, 820 MW. 0344 Stopped ramp; 60% power, 510 MW. 2230 Started ramp up; 2-FW-P-lB returned to service, waterboxes cleaned; 60% power, 500 MW. 01/07/90 0130 Stopped ramp; 99.5% power, 825 MW. Started ramp down because of receipt of 'B' loop Hi DT (protection) computer alarm; 99.5% power, 825 MW. 0140 Stopped ramp; 98.3% power, 815-MW. 1409 Started ramp up; 2-PT-2.lB completed on OTDT; 98.3% power, 810 MW. 1422 01/08/90 2230 01/09/90 0533 01/09/90 0'620 Stopped ramp; 100% power, 820 MW. Started ramp down after placing Ch-1 OP/OT DT in trip. Channel placed in trip after being declared inoperable from slowly increasing TAVE indication; Ch-2 reading slightly high; 100% power, 820 MW. Stopped ramp; 99% power, 820 MW. Started slow power increase to 100%; Ch-1 OP/OT DT returned to service; 99% power, 820 MW. Stopped power increase; 100% power, 820 MW. 9 OF OPERATING EXPERIENCE e MONTH/YEAR:

JANUARY 1990 -----------

Listed below in chronological sequence experiences for this month which required sig~ificant non-load related incidents.'

by unit is a summary of operating load -reductions or resulted, .. in UNIT TWO 01/12/90 1657 1723 2009 2030 01/13/90 2037 2111 01/14/90 1447 1519 01/18/90 1016 1102 01/20/90 1757 1855 01/21/90 2025 2040 01/22/90 0132 0228 01/29/90 1722 Started ramp down in preparation for auxiliary feed flow test, 2-ST-273; 100% power, 820 MW. Stopped ramp; 95% power, 790 MW. Started ramp up after flow test completed; 95% power, 790 MW. Stopped ramp; 100% power, 820 MW. Started ramp down for implementation of EWR-90-021, DT setpoints; 100% power, 820 MW. Stopped ramp; 95% power, 780 MW. Started ramp up after EWR-90-021 completed; 95% power, 785 MW. Stopped ramp; 100% power, 820 MW. Started ramp down to prepare for 2-PT-29.1; 100% power, 820 MW. Stopped ramp; 90% power, 755 MW. 2-PT-29.1 test of #2 LP intercept and reheat valves caused 2-MS-SV-206A to lift. As a result of the lift a crack developed in an associated 2" drain line. Started ramp up to complete checks of crossunder safties; 91% power, 750 MW. Stopped ramp; 100% power, 825 MW. Started ramp down due to results of analysis on crossunder safety valves; all operable except 2-MS-SV-207A; 100% power, 820 MW. Stopped ramp; 97% power, 800 MW. Started ramp down; initial calculations on crossunder safety indicate relieving capability of operable safety is approximately 86% of 100% steam flow. 97% power, 800 MW. Stopped ramp; 85% power, 710 MW. Started ramp after determining satisfactory calibration on 2-MS-SV-206B; 85% power, 715 MW. 10

"* ., . . ' OF OPERATING EXPERIENCE e MONTH/YEAR:

JANUARY 1990 -----------

Listed below in chronological sequence experiences for this month which required significant non-load related incidents.

by unit is a summary of operating load reductions or resulted_

in (' UNIT TWO 01/31/90 2400 This reporting period ended with the Unit at 89% power, 735 MW. 11 r EWR-90-003 EWR-89-716 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

JANUARY 1990 ENGINEERING WORK REQUEST UNITS 1&2 (Safety Evaluation

  1. 90-0004) 01/13/90 This Engineering Work Request installed permanent audio radiological postings at the entrance to the auxiliary building basement.

This does not constitute an unreviewed safety question in that this is a health physics posting device which is non-safety related and does not affect any safety related systems. This change does not increase the probability or consequences of any accidents as analyzed in the UFSAR, nor does it change the basis for any technical specifications.

ENGINEERING WORK REQUEST UNITS 1&2 (Safety Evaluation

  1. N89-0042)

This Engineering Work Request added filters to coolant system temperature channels, resulting in an time delay in both delta-T and TAVG signals. 01/18/90 the reactor additional Tne additional time delay does not exceed the allowable limits of the existing safety analysis.

Therefore, an unreviewed safety question does not exist. Sl-AC-90-0119 ADMINISTRATIVE CONTROL (Safety Evaluation

  1. 90-0008) 01/19/90 Administrative control will be established over 1-SW-124, the manual isolation to TCV-SW-108C, while the normal temperature control valve is under repair. By maintaining control of the manual valve the temperature can be maintained within required ranges the charging pump to operate per design. Therefore an safety question is not created. Sl-AC-90-0122 ADMINISTRATIVE CONTROL (Safety Evaluation
  1. 90-0009) lube oil and allow unreviewed 01/22/90 This administrative control documents that the dike at the emergency switchgear room door will temporarily be removed, a flood watch will be placed at the door and a roving flood watch will walk down the turbine building while the dike is down. Administrative measures are provided for reinstallation of the dikes if flooding is observed.

The removal of this dike will not adversely affect safety related equipment or create an unanalyzed condition since the administrative measures compensate.

12

... . , .

  • e e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

SCAFFOLD REQU~ST UNIT 1 (Safety Evaluation

  1. 90-0010)

JANUARY 1990 r 01/22/90 Temporary scaffold was erected to support the maintenance on damper/actuator mark #01-VSP-AOD-lllA for the containment purge exhaust. The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function.

It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 1 (Safety Evaluation

  1. 90-0011) 01/22/90 Temporary scaffold was erected to support the maintenance work on damper/actuator for fuel building filter exhaust damper. The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high cpnfidence level against failure and was reviewed for*eff~cts on accident analyses and equipment operability/function.

It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 1 (Safety Evaluation

  1. 90-0012) 01/22/90 Temporary scaffold was erected to support the maintenance work on damper/actuator mark # Ol-VSP-AOD-107A for the auxiliary building.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function.

It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 1 (Safety Evaluation

  1. 90-0013) 01/22/90 Temporary scaffold was erected to support the maintenance work on damper/actuator mark #Ol-VSP-AOD-109A for general area exhaust fan discharge.

13

==-~~~~~~=-===-~-=~~~-~~=;:;;:;;;_;;:;;_;:;:;~=""-===----------------------------------. ., r e e .... FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

JANUARY 1990 ----------

,** The temporary scaff~ld is required for safe working* *~anditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function.

It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

SCAFFOLD REQUEST UNIT 1 (Safety Evaluation

  1. 90-0015) 01/25/90 Temporary scaffold was erected to support the maintenance work on an auxiliary steam line which has a leak and is causing airborne contamination.

The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function.

It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are;not affected.

Sl-AC-89-1227 ADMINISTRATIVE CONTROL UNIT 1 (Safety Evaluation

  1. 90-0016) 01/25/90 Administrative control will be placed on l-IA-446 and l-IA-447 to ensure that containment integrity can be maintained.

The administrative control established on l-IA-446 and l-IA-447 in accordance with SUADM-0-26 ensures the ability to maintain containment integrity as defined in technical specifications.

The valves will be closed immediately upon notification by the main control room. In addition, control over the valves will ensure the ability to maintain the containment partial pressure within the limits established by Technical Specification 3.8. Therefore, an unreviewed safety question is not created. Sl-AC-89-1228 ADMINISTRATIVE CONTROL UNIT 1 (Safety Evaluation

  1. 90-0017) 01/25/90 Administrative control will be placed onf2-IA:;::.446 and 2-IA-447 to ensure that containment integrity can be/maintained.

The administrative control established on 2-IA-446 and 2-IA-447 in accordance with SUADM-0-26 ensures the ability to maintain containment integrity as defined in technical specifications.

The valves will be closed immediately upon notification by the main control room. In addition, control over the valves will ensure the ability to maintain the containment partial pressure within the limits established by Technical Specification 3.8. Therefore, an unreviewed safety question is not created, 14 EWR-89-681 e -FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

JANUARY 1990 ---------SCAFFOLD REQUEST UNIT 1 01/30/90 (Safety Evaluation

  1. 90-0022)

Temporary scaffold was erected to support the maintenance work on damper/actuator mark #Ol-VSP-AOD-103A for decon building filter exhaust damper. The temporary scaffold is required for safe working conditions.

Installation of scaffold constructed per SUADM-ADM-07 has a high confidence level against failure and was reviewed for effects on accident analyses and equipment operability/function.

It is thus concluded that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.

ENGINEERING WORK REQUEST UNITS 1 & 2 Change request to UFSAR Sec. 9.10.4.19 (Safety Evaluation

  1. N89-0025) 01 /31/90 This EWR evaluated permanently leaving the Emergency Diesel Generator (EDG) rooms air supply louvers open and making a change to the UFSAR. This change removes the temporary modifications which covered keeping these louvers open and makes permanent design changes disconnecting the actuation mechanism.

The loss of the EDG from overheating was considered and since the air louvers will be maintained opened, the EDG will continue to operate as designed.

Therefore, an unreviewed safety question does not exist. 15

. *, ,* V PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

JANUARY 1990 NONE DURING THIS REPORTING PERIOD 16

. .. , ... TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR:

JANUARY 1990 NONE DURING THIS REPORTING PERIOD 17 PRIMARY COOLANT ANALYSIS Gross Radioact., µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml Iodine-131, µCi/ml Iodine-131/Iodine-133 Hydrogen, cc/kg Lithium, ppm Boron -10, ppm* Oxygen, (DO), ppm Chloride, ppm pH@ 25 degree Celsius ----------------~~-~ e e VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT MONTH/YEAR:

JANUARY 1990 UNIT NO. 1 MAX. MIN. AVG. MAX. 8.53E-1 6.61E-2 7.34E-1 2. 71E-1 0.0 0.0 0.0 o.o 1.89E-1 1.51E-1 1.66E-l 3.99E-1 1.44E-2 3.02E-3 6.33E-3 1. 03E-3 0.20 0.09 0.13 0.25 31.5 25.9 28.4 34.5 2.34 2.06 2.19 2.33 107 85 93 191 0.005 0.005 0.005 0.005 0.010 0.006 0.007 0.010 7.05 6. 77 6.90 6.67

  • Boron -10 = Total Boron x 0.196 REMARKS: UNIT NO. 2 MIN. 167E-1 0.0 2.88E-1 3. llE-4 0.08 27.5 2.11 176 0.005 0.006 6.40 UNIT ONE: Excess letdown was placed in service on 1/10 at 0928 hrs. to perform work on normal letdown; normal letdown was returned to service on 1/11 at 1059 hrs. The following lithium additions were made: 1/7, 250 gm; 1/8, 420 gm; 1/10, 410 gm; 1/15, 450 gm; 1/16, 400 gm; 1/19, 480 gm; 1/21, 489 gm; 1/27, 437 gm. Total addition was 3317 gms. UNIT TWO: Cation bed was placed in service on 1/16 from 0540 hrs. to 0710 hrs. lithium additions were made during January. 18 No AVG. 2.13E-1 0.0 3.36E-1 5.48E-4 0.12 31.2 2.22 180 0.005 0.007 6.53

.. , .... ... af ** -* lml'.f 1&2 hw OR SPENT FUEL SHIPMENT If DATE SHIPPED OR RECEIVED FUEL HANDLING NUMBER OF ASSEMBLIES PER SHIPMENT ASSEMBLY ANSI NUMBER NUMBER DATE: JANUARY 990 INITIAL ENRICHMENT NEW OR SPENT FUEL SHIPPING CASK ACTIVITY LEVEL NONE DURING THIS REPORTING PERIOD 19

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. ' .-> '~ ' -DESCRIPTION OF PERIODIC TEST(S) WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR:

JANUARY 1990 NONE DURING THIS REPORTING PERIOD 20

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