ML18152A515

Monthly Operating Repts for Jan 1988.W/880215 Ltr

ML18152A515
Person / Time
Site:	Surry
Issue date:	01/31/1988
From:	BENSON D L, STEWART W L, WARREN L A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-075, 88-75, NUDOCS 8802220166
Download: ML18152A515 (23)

Text

VIRGINIA ELECTRIC AND POWER COMPANY 0 1'31 1**6*f: 88 ,,oo *aso2220 . :-osooo ,,.,o . pDR ADDCK -ncD. R SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 88-01 APPROVED:

STATION MANAGER POW 34-04

-SECTION Operating Data Report -Unit No. 1 Operating Data Report -Unit No. 2 1 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 Requiring NRC Approval Facility Changes That Did Not Require NRC Approval Procedure or Method of Operation Changes that Did Not Require NRC Approval Tests and Experiments Requiring NRC Approval Tests and Experiments That Did Not Require NRC Approval Other Changes, Tests and Experiments Chemistry Report Fuel Handling -Unit No. 1 Fuel Handling -Unit No. 2 Procedure Revisions That Changed the Operating Mode Described in the FSAR Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications PAGE 1 2 3 4 5 6 7 7 8 9 -11 12 13 14 15 16 17 18 19 20 OPERATING DAIA REPORT OPERATING STATUS 1. Unit Name: Surry I Notes 2. Reporting Period: Jan~ 01 thru Jan. 31, 19 8 8 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. Maxi.mum Dependable Capacity (Net MWe): 7 81 DOCKEI NO. 50-280 DAIE 2/5/88 COMPLETED BY L. A. warren TELEPHONE 804-357-3184

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: 9. Power Level Io Which Restricted, If Any (Net MWe): 10. Reasons For Restrictions, If Any: This Month Yr.-to-Date

11. Hours In Reporting Period 744.0 744.0 12. Number of Hours Reactor Was Critical 744.0 744.0 13. Reactor Reserve Shutdown Hours 0.0 o.o 14. Hours Generator On-Line 744.0 744.0 15. Unit Reserve Shutdown Hours 0.0 0.0 16. Gross Thermal Energy Generated (MWH) 1811710.2 1811710.2

17. Gross Electrical Energy Generated (MWH) 614935 614935 18. Net Electrical Energy Generated (MWH) 585817 585817 19. Unit Service Factor 100% 100% 20. Unit Available Factor 100% 100% 21. Unit Capacity Factor (Using MDC Net) 100.8% 100.8% 22. Unit Capacity Factor (Using DER Net) 99. 9% 99. 9% 23. Unit Forced Rate 0% 0% 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Refueling Outage April 8, 48 Days 25. If Shut Down At End Of Report Period Estimated Date of Startup: 26. Units In Iest Status (Prior to COl!Dllercial Operation):

INITIAL CRI'.CICALI!Y INil'IAL ELECl'RICil'Y COMMERCIAL OPERAl'ION Forecast Cumulative 132456.0 85467.4 3774.5 83715.2 3736.2 194531931.6 62990108.0 59741193.0 63.2% 66% 58.3% 57.2% 17 .5% Achieved (9/77) ___J OPERATING DATA REPORT DOCKET NO 5 0-2 8 1 DATE*_-_ -_,2;1:5:1=:8 8:::::: COMPLETED BY L. A. warren TELEPHONE 804-357-3184 OPERATING STATUS 1. Unit Name: Surry 2 Notes 2. Reporting Period: Jan. 01 thru Jan. 3 L 1988 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. Maxi.mum Dependable Capacity (Net MWe): 781 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: 9. Power Level To Which Restricted, If Any (Net MWe): 10. Reasons For Restrictions, If Any: This Month Yr.-to-Date

11. Hours In Reporting Period 744.0 744.0 12. Number of Hours Reactor Was Critical 744.0 744.0 13. Reactor Reserve Shutdown Hours o.o o.o 14. Hours Generator On-Line 744.0 744.0 15. Unit Reserve Shutdown Hours 0.0 o.o 16. Gross Thermal -Energy Generated (MWH) 1811065.7 1811065. 7 17. Gross Electrical Energy Generated (MWH) 606540.0 606540.0 18. Net Electrical Energy Generated (MWH) 577580.0 577580.0 19. Unit Service Factor 100% 100% 20. Unit Available Factor 100% 100% 21. Unit Capacity Factor (Using MDC Net) 99.4% 99.4% 22. Unit Capacity Factor (Using DER Net) 98. 5% 98.5% 23. Unit Forced Rate 0% 001 10 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. Units In Test Status (Prior to Commercial Operation):

INITIAL CRITICALITY INITIAL ELEC'.rRICirY COMMERCIAL OPERATION Forecast Cumulative 129336.0 85410.0 328.1 84042.3 o.o 196981428.4 63979364.0 60654057.0 65% 65% 60.2% 59.5% 14.3% Achieved (9/77)

-* NO. DAIE a. > I-88-01 1/9/88 s 1 F: Forced 2 S: Scheduled (9/77) PAGE 3 UNIT SHUTDOWNS AND POWER REDUCTIONS . DOCKET NO. 50-280 __ ..;..;;....;;..;..;;

______ ... UNIT NAME _ _..;S~u::;.:*r_rv

.. * . ...:1:.._

____ _ REPORT t-ENTH JANUARY 19 8 8 DATE~--.0=2~/0~5./~88~~~---_, COMPLETED BY __ ..,..L1a., .... A....._ * ..tw.Z.:ai,4.r,...r..ie

... n"---~ TELEPHONE

___ --,;:;8.:::.0..;..4-_,.3~5.:..7-...,3.;l..:.:;8..:.4~---~

"' .. C ... Cl D D -"' D C .. ... .. C ... u .. .. D "O .. GI * :, .. D .. II .. D Ill .I: :, :, :c II .. .I: 0 II C ::E (I] > D 0 0.0 B 1 Reason: A -Equipment Failure (Explain)

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

H -Other (Explain) 3 .. C E .:r II in Ill II C II .. "O D "O CAUSE & CORRECTIVE ACTION IO a, D 0. D t) E tl PREVENT RECURRENCE D t) . Unit was reduced to 69% power, 572 MW's to allow monthly testing of turbine valves (PT-29. Method: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain) 4 5 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) Exhibit 1 -Same Source e

-* NO. DATE a. >-I-88-01 01/23/88 s 1 2 F: Forced S: Scheduled (9/77) PAGE 4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. _..,,,s_o-_2_8_1,,.....

____ __:.. UNIT NAME __ S'""'u"'"r_ry'-"'2'--------

DATE ___ 02~/_0~5~/8~8~------~

REPORT MONTH JANUARY 1988 COMPLETED BY L. A. warren TELEPHONE

==~8:o:4-:3:5~7:-:3:1:8:4======~

,.., L C .... Cl D D -N D C ., -.. C -u L D "C II .. :, II D .. ll II D II .c .. a: L I II .. :, :, -a: ll .c C 0 :E en :, D 0 o.o B 1 Reason: A -Equipment Failure (Explain)

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

H -Other (Explain) 3 .. C E :r ll"' m ., .. "C C m CAUSE & CORRECTIVE ACTION TO a, D D "C ;:; CJ a. D E CJ PREVENT RECURRENCE D . CJ Unit was reduced to 70% power, 590 MW's to allow monthly testing of turbine valves (PT-29.1 Method: l -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain) 4 5 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) Exhibit l -Same Source e e -AVERACE DAILY UNIT POWER LEVEL MONTH JANUARY 1988 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 2 '3 4 5 6 7 8 9 10 11 12 l'3 14 15 16 INSTRUCTIONS 787 787 788 788 787 787 788 788 728 789 788 789 788 789 789 790 DOCICE'r No. __ s o_-_2_8_0

__ _ UNI-.r Surry 1 DA'IE 2/08/88 COMPLETED BY L. A. warren TELEPHONE 804-357-3184 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 18 19 20 21 22 23 24 25 26 27 28 29 30

• 31 791 791 791 791 791 791 791 791 790 791 791 790 -791 791 790 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.

(9/77)

-AVERACE DAILY UNIT POWER LEVEL DOCKET No. _so_-_2 __ s_1 ___ _ UNIT Surry 2 DATE 2/08/88 COHPLETED BY L, 8. warren 'rELEPHONE 804-357-3184 MONTH I8N!.L8.EY 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 779 17 778 2 778 18 779 '3 778 19 778 4 777 20 778 '5 778 21 779 6 778 22 778 7 778 2 '3 731 8 779 24 776 9 777 25 777 10 778 26 776 11 778 27 776 12 778 28 777 1'3 779 29 777 14 778 30 778 1 '5 778 31 779 16 778 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.

(9/77)

-

SUMMARY

OF OPERATING EXPERIENCE MONTH/YEAR January 1988 ---------Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.

UNIT ONE 01-01-88 0000 01-09-88 1000 1136 1445 1845 01-31-88 2400 UNIT TWO 01-01-88 0000 01-23-88 1213 1346 1650 1930 01-31-88 2400 This reporting period begins with the unit at 100% power, 830MW's. Commenced power reduction at 150MW /hr. for scheduled testing of turbine valves (PT-29.1).

Holding power at 69% power, 572 MW's. Commenced power increase at 150 MW /hr. Unit at 100% power, 830 MW's. This reporting period ends with the unit at 100% power, 830 MW's. This reporting period begins with the unit at 100% power, 820 MW's. Commenced power reduction at 150 MW's/hr for scheduled testing of turbine valves (PT-29.1 ). Holding power at 70%, 590 MW's. Commenced power increase at 150 MW /hr. Unit at 100% power, 815 MW's. This reporting period ends with the unit at 100% power, 815 MW's. _J

\ . F ACIIJTY CHANGES REQUIRING NRG APPROVAL MONTH/YEAR JANUARY 1988 NONE DURING THIS PERIOD

' . EW.R 87-331 EWR 87-400 EWR 87-403 EWR 87-410 F ACIUTY .NGES THAT DID NOT REQUIRE MONTH/YEAR Jartuary 1988 ADDITION OF FP CARDOX ODORIZER C APPROVAL UNITS 1 & 2 This engineering work request added an odorizer to the Cardox System to enhance worker safety by providing another means of detecting a discharge of the system. The addition of odorizers does not effect the function of the Cardox System. Therefore, the enhancement does not impact plant or public health and safety nor result in an unreviewed safety question.

REPLACE MAIN STEAM VALVE (1-MS-104)

UNIT 1 This engineering work request installed an equivalent safety related gate valve to replace l-MS-104, an isolation globe valve for the auxiliary feedwater pump steam flow transmitter which had a bonnet steam cut. The replacement valve is of the same pressure class and material as the original valve. Therefore, there are no changes in the probability or consequences of accidents analyzed in the UFSAR, nor has the possibility of a new accident being created. The margin of safety is not affected.

MODIFY FEEDWATER VALVES (1/2-FW-MOV-lSOA, B/250A, B) UNITS 1 & 2 This engineering work request evaluated modifications to the Unit 1 and 2 feedwater pump discharge valves (1-FW-MOV-150 A/B and 2-FW-MOV-250 A/B) to prevent the operator mounting studs from pulling loose from the operator body. The installation of: 1) all thread rod studs to ensure thread engagement, 2) one new stud between existing holes for support and 3) a new yoke flange will not result in an unreviewed safety question.

EVALUATE GLAND BOLT MATERIAL CHANGE {1-CH-163, 164) UNIT 1 This engineering work request compared chemical and* mechanical properties of the old (A 19 3) and the new (A582) gland bolt materials for Westinghouse valves (2 11 -T58) to determine if the new material was acceptable.

An analysis of the impact of the valve failure as analyzed in UFSAR was mad.e. As the material's properties are equivalent, there is no effect on the UFSAR analyses.

1/29/88 1/12/88 1/05/88 1/05/88

' -N/A N/A TM Sl-88-2 TM S2-88-2 FACILITY IANGES THAT DID NOT REQUIRE.C APPROVAL MONTH/YEAR ) anuary I 988 SCAFFOLD REQUEST A temporary scaffold platform was constructed in # 1 EDG Room to work # 1 Diesel Room Dampers. Installation of this temporary scaffolding was reviewed for affect on accident analyses and equipment operability/function.

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

SCAFFOLD REQUEST A temporary scaffold platform was constructed in Auxiliary Building to work FT-VS-118 and FT-VS-218.

Installation of this temporary scaffolding was reviewed for affect on accident analyses and equipment operability/function.

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

TEMPORARY MODIFICATION Temporary modification removed and blanked the piping connection on the PG tank heat exchanger thermal relief valves, l-RV-BR-114A, B. It was determined that maintaining the PG tank heat exchanger inlet and outlet isolation valves open prevents heat exchanger overpressurization while the thermal relief valves are removed. Therefore, the radioactive liquid release probability is not increased.

TEMPORARY MODIFICATION This temporary procedure closed manual valve 2-SW-117 and placed it under administrative control to prevent over-cooling of lube oil for 2-CH-P-lB while the pump is off. Closure of 2-SW-117 does not constitute an unreviewed safety question because it is under administrative control ensuring it will be opened if needed before operability of any plant equipment is affected.

1/29/88 1/20/88 1/29/88 1/07 /88 TM S2-88-3 TM S2-88-5 TM S2-88-7 FACIIJTY 'ANGES THAT DID NOT REQUIRE le APPROVAL MONTH/YEAR January 1988 TEMPORARY MODIFICATION This temporary modification closed manual valve 2-SW-168 (lube oil cooler SW isolation) under administrative control to prevent over cooling of lube oil for 2-CH-P-IA while the pump is shut down. Closure of 2-SW-168 does not constitute an unreviewed safety question since it is under administrative control ensuring it will be opened, if required, before operability of any plant equipment is affected.

TEMPORARY MODIFICATION This temporary modification placed the emergency borate valve, 2-CH-MOV-2350, under administrative control because the normal boric acid flow path from the blender was inoperable due to a heat tracing failure. Placing 2-CH-MOV-2350 under administrative control will ensure two boric-acid flow paths are available to the charging pump suction as required.

TEMPORARY MODIFICATION This temporary modification locked closed 2-RC-133 to isolate containment penetration

1. 57 and the pressurizer vent and vapor space sample. The pressurizer vent system is used as a backup bleed path in case of a loss of heat sink transient.

However, the preferred path remained available.

The pressurizer vent system can also be used to vent non-condensible gases from the pressurizer vapor space. However, the PORV's remain available if this function is required.

1/11/88 l/26/88 1/26/88 2-TOP-2015 2-TOP-2015 SUADM-ADM-21 PROC.URE OR METHOD OF OPERATIO-HANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR January 1988 AUXIUARY FEEDWATER CHECK VALVE LEAKAGE GUIDEIJNES UNIT 2 This temporary operating procedure isolated steam generator auxiliary feedwater flow paths on Unit 2 to determine potential check valve leakage paths. Since the flow paths were under administrative control during the temporary operations and since automatic actuation will return the system to the required operating condition, it was determined that an unreviewed safety question was not created. AUXIIJARY FEEDWATER CHECK VALVE LEAKAGE GUIDEIJNE UNIT 2 The temporary operating procedure was revised to extend the implementation date. '.fhe administrative control and automatic actuations remain in place; therefore, the evaluation above remains valid. STATION PROCEDURES This procedure revision updated the procedure deviation process to reflect the 1 OCFRS0.59 screening and review process. The updated procedure incorporated more stringent requirements governing procedure deviations than outlined in the administration section of Technical Specification (section 6.4) 1/05/88 1/26/88 1/26/88

-'.I'ESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR JANUARY 1988 NONE DURING THIS PERIOD __ _J TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH/YEAR JANUARY 1988 ----------

NONE DURING THIS PERIOD

. . OTHER CHANGES, TEST AND EXPERIMENTS MONTH/YEAR JANUARY 1988 ----------

NONE DURING TIIlS PERIOD e PRIMARY COOLANT ANALYSIS Gross Radioact., µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml Iodine 131 , µCi/ml Il'31 / Il '31 Hydrogen, cc/kg Lithium, ppm Boron-10, ppm* oxygen, (DO), ppm Chloride, ppm PH@ 2c; degree Celsius -VIRGINIA .POWEil SURRY POWER STATION CHEMISTRY REPORT JANUARY 19 88 ----------

UNIT NO. 1 MAX. MIN. AVG. 1.42 7.78E-1 1.24 o.o o.o o.o 7.82E-2 3.22E-2 S.43E-2 l.48E-2 6.41E-3 9.87E-3 0.26 0.12 0.19 39.3 31.0 33.3 0.66 0.41 0.54 37.6 15.1 25.1 -<0.005 <0.005 <o.oos 0.010 0.001 0.003 7.05 6.52 6.81

• Boron-10

• Total Boron X 0.196 UNIT NO. 2 MAX. MIN. AVG. 2.72E-1 l.27E-l 2.03E-l o.o o.o o.o 1. 32E-1 2.78E-2 9.42E-2 2.65E-4 7.88E-5 l.40E-4 0.13 0.06 0.09 34.7 30.3 32.0 1. 05 o. 77 0.91 87.2 70.2 78.2 <0.005 <0.005 <o*. 005 0.010 0.00? n _ no3 6.70 6.46 6.56 REMARKS: Unit 1: No LiOH additions made in Januarv, Deborating Bed placed in service for LiOH reroavaJ an 1-04-88 from 1115 to 1247; 1-19-88 from 1250 to 1430; 1-22-88 from 0950 to 1208; 1-29-88 from 1820 to 2031. Unit 2: No LiOH additions made in January. Cation Bed placed in service for LiOH removal on 1-3-88 from 0515 to 0844; 1-7-88 from 0945 to 1321; 1-9-88 from 1810 to 2239; 1-12-88 from 0925 to 1204; 1-15-88 from 0950 to 1326; 1-19-88 from 1810 to 2040; 1-22-88 from 1535 to 1705.

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PAGE 17 . V . e UNIT 1 --FUEL HANDLING DATE JAN 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPINC SHIPMENT I RECEIVED PER SHIPMENT , , ENRICHMENT CASK ACTIVIn LEVEL Cask #6 01-05-88 21 B02 NIA 2.57 NIA Cask #6 01-05-88 21 B03 NIA 2.57 NIA Cask #6 01-05-88 21 BOS NIA 2.57 NIA Cask #6 01-05-88 21 Bl 1 NIA 2.57 NIA Cask #6 01-05-88 21 Bl3 NIA .. 2.57 NIA Cask #6 01-05-88 21 B37 NIA 2.57 NIA Cask #6 01-05-88 21 B46 NIA 2.57 NIA Cask #6 01-05-88 21 B51 NIA 2.57 NIA Cask #6 01-05-88 21 cos NIA 3.12 NIA Cask #6 01-05-88 21 Cl6 NIA 3.12 NIA Cask #6 01-05-88 21 C22 NIA 3.12 NIA Cask #6 01-05-88 21 C23 NIA 3.12 NIA Cask #6 01-05-88 21 C29 NIA 3.12 NIA Cask #6 01-05-88 21 C30 NIA 3.12 NIA Cask #6 01-05-88 21 C31 NIA 3.12 NIA Cask #6 01-05-88 n C33 NIA 3.12 NIA Cask #6 01-05-88 21 C34 NIA 3.12 N/A Cask #6 01-05-88 21 C39 NIA 3.12 Nil-. Cask #6 01-05-88 21 C41 NIA 3.12 NIA Cask #6 01-05-88 21 C45 NIA 3.12 N/A Cask* #6 01-05-88 21 C46 NIA 3.12 N/A C'.M.UJ.o J.U UNIT . 2 FUEL HANDLING DATE JAN 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPINC SHIPMENT#

RECEIVED PER SHIPMENT fl II ENRICHMENT CASK ACTIVITI LEVEL NONE D URING THIS PERIOD /\ i J PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR MONTH/YEAR JANUARY 1988 --------NONE DURING THIS PERIOD .PAGE 19 V . . e --DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME UMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR JANUARY 1988 ----------

NONE DURING THIS PERIOD _J e* & VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L, STEWART VxcE PRESIDENT NUCLEAR OPERATIONS February 15, 1988 U. S. Nuclear Regulatory Commission Attn: 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/DAS:vlh Docket Nos. License Nos.88-075 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 1988. Very truly yours, W. L. Stewart Enclosure cc: U. S. Nuclear Regulatory Commission 101 Marietta Street, N. W. Suite 2900 Atlanta, GA 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station