ML18152A481
| ML18152A481 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/30/1988 |
| From: | Cartwright W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-830, NUDOCS 8812200104 | |
| Download: ML18152A481 (22) | |
Text
POW 34-04 e
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 88-11 APPROVED: \\!:)~
MANAGE
e 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 Requiring 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 NRG Approval Chemistry Report Fuel Handling - Unit No. 1 Fuel Handling - Unit No. 2 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 13 14 15 16 17 18 18 19
PAGE 1 OOCICET NO.
50-280
--~=---
DA:rE 12/1/88 COHPLE'l'ED BY L. A. Warren TELEPHONE 804-357-3184 x355 OPERAl'ING STATUS
- 1. Unit Name:
Surry Unit 1 Note*
- 2. hportfog Pedod: November 01-30, 1988
- 3. Licensed Thermal Power (MWt):
2441 It. Nameplate Rating (GroH HWe): --8'"'4""7'"".5 ____ _
- 5. Design Electrical Rating-(Net HWe):
788
- 6.
Maximum Dependable Capacity (Gross HWe):
___ 8_2_0_~
- 7. Maximum Depet1dable Capacity (Net MWe):
781 84 If Chat1ges Occur in Capacity Ratings (Items Number 3 l'hrougb 7) Since Last Report, Give Reas0tis:
- 9. _Power Level To Which Restricted, If Any (Net HWe):
- 10. Reasons For Restrictions, If Any:
'I'b is Mooth
- 11. Hours In Reporting Period 220, 0-
- 12.
Number of Hours Reactor Was Critical 0
- 13. Reactor Reserve Sbutdowo Hours 0
lit. Hours Generator On*Lit1e 0
- 15. Unit Reserve Shutdown Houra 0
- 16. Gross l'hennal Energy Generated (MW) 0
- 17. Gros, Electrical Energy Generated(~)
0
- 18. Net Electrical Ener&Y-Generated (HWB) 0
- 19. Ut1it Service Factor 0
- 20. Unit Available Factor Q
- 21. UDit Capacity Factor (Uling MDC Net) 0
- 22. Unit Capacity Factor (Using DER Net) 0
- 23. Ut!it Forced Rate 100%
Yr.-to*Date BIJ~O C 3755.2 0
3634.2 0
8451045.6 2828500.0 2685027.0 45,2%
~S.2~
42.8%
42.4%
JS.S~
- 24. Shutdowns Scheduled Over Next 6 H0tiths ('I'ype, Date, and Duration of Eachh Forced Maintenance Outage on 09/12/88, on line date scheduled 01/20/89.
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Unit1 In Teat Statua (Prior to Commercial Operation):
Forecast IHrnAL CRmCALiff INrnAL ELECTRICITY CCINRCIAL OPERAnON Cumulative 139252.0 88478.6 3774.5 8660~.~
3736.2 201171267,0 65203673.0 61840403.0
~2~
6~ 626 57 -2%
56.2%
JB 626 Achieved
e e
PAGE 2 DOCICE'.rNO. -~5~0-~2-8~1 __ _
DATE ____
12 __ 1_0_1 __
18_8 ___ ~
COMPLETED BY L. A. Warren TELEPHONE 804-357-3184 x355 OPERATING STATUS
- 1. Unit Name:
Surry Unit 2 Notea
- 2. Reportfog Period:
Nover.tber 01-30, 1988
- 3. Licensed l'hennal Power (MWt):
2441
- 4. Nameplate Rating (Gro111 HWe): --9"""4""7-~5-----
S. Design Electrical Rating (Net HWe):
788
- 6.
Maximum Dependable Capacity (Gross HWe):
820
--=--
- 7. Maximum Dependable Capacity (Net HWeh 781 B. If Changes Occur in Capacity.Ratings (Items Number 3 l'hrough 7) Since Last Report, Give Reasona:
- 9. Power Level To Which Restricted, If Any (Net MWeh
- 10. Reasons For Restrictions, If Any:
l'his Mooth Yr.*to*Date
- 11. Hours In Reporting Period 720.0 8040.0
- 12. Number of Hours Reactor Was Critical 0
5028.3
- 13. Reactor Reserve Shutdown Bour, 0
0
- 14. Hours Generator On-Line 0
4994.7
- 15. Unit Reserve Shutdown Roura 0
0
- 16. GroH l'beT111al Energy Generated (MWB) 0 11570100.4
- 17. Gross Electrical Energy Generated (!llll) 0 3763420.0
- 18. Net Electrical EnerlY-Generated (MWB) 0 3570901.0
- 19. Unit Service Factor 0
- 62. I%
- 20. Unit Available Factor Q
62.1%
- 21. Unit Capacity Factor (Using MDC Net) 0 56.9%
- 22. Unit Capacity Factor (Using DER Net)
Q 56.4%
- 23. Unit Forced Rate 0
24%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of !achh Refueling Outage on 09/09/88 1 scheduled on line date 01L30/89.
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units lo Test Statu1 (Prior to Commercial Operatioo):
Forecast IMinAL CRITICALITY INI?IAL ELECTRICITY CDIMERCUL OPERA?IOR Cumulative 136632.0 8~b~4.~
328.1 88293.0 0
206740463.1 67136244.0 i:i3i:i4737S.O 64.6%
64.6%
59.8%
59.1%
15%
Achieved (9/77)
NO.
DAD
- a.,.
88-12 11-1-88 F
l F: Forced 2
S: Scheduled (9/77)
PAGE 3 UNl'.l: SHU'IDOWNS AND POWER UDUC'tlONS DOClCE7 No. __
so_-_2_8_0 _____ _
UNIT NAME -~s':!'u~rry~~u~o... tr.......
1 __ ~
DA:rE _1_2_1_0_1,_8 __ 8 ________ ___
CXMPLE'IED BY ___
L..,.._.A.., *._..w... arr_..,.e.... n ___ _
TELEPHONE ___
80 __ 4
__ -_35
__ 7_-_.3.,..18~1-xJ~S...,5'----'
REPOR'.l: HONtH NOVEMBER 1988 C:
m a a -
NC:,
a C:
u a
'tJ..
- a.. *
~ :, IX
~
D -
IX
- I m i a
0 720.0 F
1 lleasona A - Equipment Failure (Explain)
- B - Maintenance or Test C - Refueling D - Regulatory Restriction LICENSEE EVEN't REPOJa
- E - Operator Training & License Examination F
- Adainistrative G - Operational Enor (Explain)
H - Other (Explain) 3 I!,
C:...,
C:
- CAUSE & CORREc.rlVE ACJ:ION m
.. 'tJ a
-a a
- a. a
- >> u
& u PREVEN't ltECURREN'I a
u Unit shutdown due to emergency diesel generator operability concerns.
Method:
l - Manual 2 - Manual Scram.
3 - Automatic Scraa.
I+ - Other (Explain)
Exhibit G - lnatructiona for Preparation of Data Entry Sheets for Licensee Event Report (LEJl) File (NUJtEG 0161) s Exhibit l - Saae Source e
e
HO.
DAD
- a.,...-
88-20 11-1-88 s
1 F: Forced 2
S:
Scheduled
- (9/77)
PAGE 4 UNIT SHIJ'IDOWNS AND POWER REDUC'J:IONS DOCKET NO.
50-281
~~
UNIT NAME _ _.S,...1.,.1rry.._._U.,...n~jt....,2..._ ___ _
DATE ___
12;;;.;;/...,0...11[.... 8_,8 __________ ~
REPOR7 MOH'l'll NOVEMBER 1988 COtPLE'lED BY --=L=i,... A
- ..,W..,..arr.....ie~n~--" --
m.EPHONE _;;.;80:;..:4.-3::;.;5~7...:-3:;,jl:.:ai8;..t,4.11X,"';J¥155"--.._
C
... m a a -
N.
a C..
C u
a "O...
- a.. *
.. a
.r:.. a:
- , :E:
...r:
D,_
a:
- I m !i a
D 720.0 C
1,3 Reasons A - Equipment Failure (Explain)
- B - Maintenance or Test C - Refueling D - RegulatoTy Restriction LICENSEE EVENT REPOR:r
- I E - Operator Training & License Examination F - Adainistrative G - Operational Error (Explain)
H - Other (Explain) 3 C
E
- I C *
.. "O a
-o CAUSE & CORREC'tIVE AC'tlON TO a
- a. a
~u E U PltEVEN'f UCURREH'J:
a u Unit shutdown for refueling outage, automatic e reactor trip, Method:
1 - Manual 2 - Manual Scram.
3 - Automatic Scraa.
4 - Other (Explain) 4 s
Exhibit G - In*tructions for Preparation of Data Entl'Y Sheets for Licensee Event Report (LER) File (NUREG 0161)
Exhibit 1 - Saae Source e
/>
MONTR "NOVEMBER 1988 PAGE 5
(
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-280
-~---,,~--=----
UN IT Surry Unit 1 DATE 12/01/88 COMPLETED BY L.A. Warren TELEPHONE 804-357-3184 x355 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7.
0 23 0
8 0
24 0
9 0
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 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.
(9/77)
PAGE 6 AVERAGE DAILY UNIT POWER LEVEL MONTI{. NOVEMBER 1988 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 0
2 0
3 0
4 0
5 0
6 0
7.
0 8
0 9
0 10 0
11 0
12 0
13 0
14 0
15 0
16 0
INSTRUCTIONS DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 DOCKET NO.
50-281 UNIT Su!:!]'. Unit 2 DATE 12/0i/88 COMPLETED BY L.A. Warren TELEPHONE 804-357-3184 x355 AVERAGE DAILY POWER LEVEL (MWe-Net) 0 0
0 0
0 0
0 0
0 0
0 0
0 0
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)
I ~.
- - ----- ----~--- -
e PAGE 7
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR NOVEMBER 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 11-01-88 0000 11-30-88 2400 UNIT TWO 11-01-88 0000 11-30-88 2400 This reporting period begins with the Unit at RSD.
This reporting period ends with the Unit at RSD.
This reporting period begins with the Unit at RSD.
This reporting period ends with the Unit at RSD.
PAGE 8 F ACIIJTY CHANGES REQUIRING NRC APPROVAL
- MONTH/YEAR NOVEMBER 1988 NONE DURING THIS PERIOD
'ji I
)
FACILITY CH,GES THAT DID NOT REQUIRE NR,APPROVAL PAGE 9 l-OP-4.15 MONTH/YEAR NOVEMBER 1988 OPERATING PROCEDURE DEVIATION 11/05/88 This procedure deviation allowed the fuel assembly gripper finger adjustment restraint to be broken off on one side so that it could be moved out of the way and the gripper finger moved to allow it to disengage so that it can be freed fr9m fuel assembly G-6.
An increase in the probability of fuel failure does not exist and is still bounded by analysis; loose part generation will be unlikely but monitored and inspected. The equipment used will be suitable for environment (demineralized water for hydraulic fluid). The gripper will be replaced or repaired after this procedure is implemented.
. SCAFFOLDING REQUEST 11/08/88 This request erected temporary scaffolding located in MER #3 above l-VS-E-4C to work l-VS-296.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
TM-$2-88-117 TEMPORARY MODIFICATION 11/10/88 2-MOP-IS.I This temporary modification removed valve TV-DA-200A to allow repair in a more controlled and low dose environment. A spool piece will be installed in its place to allow continued operation of containment sump pumps.
This modification does not present an unreviewed safety question since the unit will be at cold or refueling shutdown throughout the installation.
TV-DA-200B valve, the other series containment isolation valve, will remain operational for refueling integrity.
MAINTENANCE OPERATING PROCEDURE DEVIATION 11/10/88 11/11/88 This deviation installed a jumper to direct primary drain transfer tank (POTT) pump discharge back to the Unit 2 reactor cavity. The PDTT is presently collecting loop stop valve leakage while the unit is refueling with reactor coolant system loops drained.
Since the possibility of an accident more severe has been previously analyzed (dilution during refueling -
UFSAR 14.2.5), an unreviewed safety question has not been created and the consequences of this accident are not affected.
e e
FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR __
N_O_V_E_M_B_E_R_l_98_8_
PAGE 10 l-TMOP-2018 TEMPORARY MAINTENANCE OPERATING PROCEDURE 11/11/88 2-0P-15.2 This temporary procedure will be used for pumping the Unit 1 refueling water storage tank (R WST) to Unit 2 RWST.
This procedure does not create an unreviewed safety question. Unit 1 will be defueled and the Unit 2 R WST will be available as low head safety injection flow source. Installed and approved systems are used for the liquid transfer.
OPERATING PROCEDURE DEVlATION 11/12/88 This deviation allowed dewatering Unit 2 reactor cavity to the Unit 2 R WST through the letdown ion exchangers (IXs). This change permits cleaning of the reactor cavity water in the letdown IXs and saves it in the Unit 2 R WST to limit discharges and water waste.
Since the possibility of an accident more severe than previously analyzed (dilution during refueling, UFSAR 14.2.5). is not created; and since the consequences of the analyzed accident are not affected, an unreviewed safety question is not created.
AC-Sl-88-1116 ADMINISTRATIVE CONTROL 11/16/88 2-TOP-2049 This change isolated component cooling (CC) fuel pool coolers, using administrative control to reinstate CC flow if required.
Valves 2-CC-403 and 2-CC-431 will be under administrative control.
The maximum temperature during this evolution is 120°F. This is well below the limits assumed in UFSAR.
The cooler will remain available during this evolution if required. The UFSAR and technical specification assumptions and limits will not be exceeded.
TEMPORARY OPERATING PROCEDURE 11/16/88 This procedure allows isolation of the loop drain valve HCV-2557C for maintenance and provides an overpressure path for the "C" loop by opening the "C" cold leg loop stop valve.
The shutdown margin will not be affected because the water used to fill the "C" loop is from the RCS, thereby, being equal in boron concentration and temperature.
The conclusion is that assumptions, bases and probabilities of accident analyses are not affected.
e e
PAGE 11 FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR NOVEMBER 1988 SCAFFOLDING REQUEST 11/17 /88 Scaffolding was temporarily erected to support work under a service request to paint the relay room.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
TM-S2-88-l 37 TEMPORARY MODIFICATION 11/17/88 This temporary modification will allow the damper to 2-VS-F-lA to be locked open.
This change does not constitute an unreviewed safety question because the containment air recirculation system is not required to function during a design basis accident.
AC-Sl-88-1118 ADMINISTRATIVE CONTROL 11/18/88 This administrative control places the #3 emergency diesel generator (EDG) selector switch from 0auto 0 to "exercise" to prevent the auto start of #3 EDG.
With both units in cold shutdown and since the #3 EDG may be started within ten minutes if needed, the change will not affect any accident analyses or create the possibility of a new accident.
SCAFFOLDING REQUEST 11/19/88 This request erected temporary scaffolding located. in #3 EDG room to work on installation of "A 0 cable tray.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
Sl-88-445/446 STATION DEVIATIONS 11/27/88 This deviation documented dewatering of the refueling cavity being performed in accordance with OP-14.3 and OP-15.2 to allow the closure of MOV-1720A/B.
An unreviewed safety question did not result from this evolution because both MOVs remained fully operable during this evolution; adequate time existed to carryout AP-27 (Loss of Decay Heat Removal) actions to prevent boiling of coolant and the residual heat removal system remained in operation at all times.
I
~'
e e
PAGE 12 FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR NOVEMBER 1988 UFSAR CHANGE REQUEST 11/27/88 This change will add an additional sentence to clarify definition of component cooling heat exchanger curbed area.
An unreviewed safety question is not created by adding a clarification statement to the UFSAR.
TM-S2-88-I 47 TEMPORARY MODIFICATION 11/30/88 This modification installed a jumper from the discharge of the primary drain transfer tank pump to a drain line in the charging line. The jumper will be approximately 50' long inside containment. The jumper will be between 2-DG-86 and 2-CH-141.
Since the possibility of an accident more severe than previously analyzed (dilution during refueling) is not created and the consequences of this accident are not affected, no unreviewed safety question is created.
e e
PROCEDURE OR METHOD OF OPERATION CHANGES REQUIRING NRG APPROVAL MONTH/YEAR NOVEMBER 1988 NONE DURING THIS PERIOD PAGE 13
e e
PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR NOVEMBER 1988 PAGE 14 2-EMP-C-EPH-06B PROCEDURE DEVIATION 11/02/88 This deviation provided a method to perform an uncoupled run prior to final installation of the oil collectiqn system: This Was to ensure that all operational parameters of the motor (2-RC-PMO-lC) are acceptable.
A dilution during refueling accident and a loss of decay heat removal accident were considered and the change had no effect on the ability of the station to deal with the accidents.
e e
PAGE 15
('
TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR NOVEMBER 1988 NONE DURING THIS PERIOD
e PAGE 16 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL 2-ST-221 2-ST-226 MONTH/YEAR NOVEMBER 1988 SPECIAL TEST 09/24/88 This test will govern the movement and placement of a weight on the straddle ring surrounding the reactor. The ring is cantilevered by design. This test will provide information on straddle ring behavior under hydrostatic loads.
The solid weight that was used in this special test was transported along the heavy load path. Since the weight followed the heavy load path, there was no increased probability of an accident or equipment malfunction.
SPECIAL TEST 10/23/88 EDG #2 will be subjected to a manual full throttle load increase to collect data on cold load capability.
The EDG is designed to accept full throttle load increases. Operability will be maintained in accordance with T.S. limits.
Therefore, an unreviewed safety question was not created.
1&2-TOP-2052 TEMPORARY OPERATING PROCEDURE 11/01/88 1&2-ST-228 This procedure will perform a pressure drop test of the transfer canal door using instrument air pressure.
An unreviewed safety question is not created by this test as fuel handling will be prohibited during this test and the fuel transfer canal gate valves will remain closed. Therefore, there is a minimum potential for spent fuel pit inventory loss.
SPECIAL TEST 11/04/88 This test ran through a test crank at the emergency service water pump diesel chosen for the test and will start the same pump to determine starting and running currents. This test will render the pump inoperable for short periods of time during this test.
This test was performed within the requirements for starting a pump to maintain canal inventory setforth in a justification for continued operation (JCO). Therefore, an unreviewed safety question was not created.
f
('
PRIMARY COOLANT ANALYSIS Gross Radioact., 2Ci/ml Suspended Solids, ppm Gross Tritium, 2Ci/ml 131 Iodine--, 2Ci/ml VIRGINIA POWEil SURRY POWER STATION CHEKISTRY REPORT November 19 88 UNIT NO. 1 MAX.
MIN.
AVG.
1.14-3 1,30E-4 5.3i-4 0.0 0.0 0.0 e
PAGE 17 UNIT NO. 2 MAX.
MIN.
AVG.
6.01E-2 3.20E-3 2.06-2 0.0 0.0 0.0 1131 / 1131 Hvdro2en, cc/ka Lithium, ppm Boron-10, ppm*
420.2 412.4 416.3 435.5 413.8 428.5 Oxygen, (DO)' ppm 4.0 1.0 3.0 4.0 2.5 3.2 Chloride, ppm i0.010 0.001 0.005 0.017 0.006 0.011 pH@ 25 degree Celsius 4.88 4.47
. 4.61 5.22 4.59 4.87
- Boron-10
- Total Boron X 0.196 REMARKS:
UNIT ONE:
Due to refueling, Unit one started the month still at CSD.
The RL system is inservice along with "B" mixed bed and "A" deborator as the purification system.
UNIT TWO:
Started the month still at C~D waiting refueling. On 11-5 at 0300; the cavity was flooded to 18". On 11-8 at 1637; the reactor cavity flooded to 16' level. On 11-11 at 1810; 2AMB was put in service. On 11-12 at 1935; U-2 cavity being drained via letdown thru 2Atv1B back to U-2 RWST to work on N31
- nuclear instrumentation. On 11-15 at 1245; 2AMB out of service, at 2035 2AMB was put back*
in service. On 11-18 at 1510; 2Al\\1B was taken out of service. On 11-22 at 0955 C0-58 activity increased to ~5.oo-2 and a CAP-9 was submitted. Ended the month with no letdown in service.
e e
PAGE 18 UNIT 1 & 2 FUEL HANDLING DATE NOV. 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT II RECEIVED PER SHIPMENT II II ENRICHMENT CASK ACTIVITY LEVEL NONE Dl RING THIS l>ERIOD
' \\
t \\
PAGE 19 DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFIC A TIO NS MONTH/YEAR NOVEMBER 1988 NONE DURING THIS PERIOD
.,,-----_-___ -__ --====-=-=~-----,,
~
~--,
J VIRGINIA ELECTRIC AND PowER CoMPA.NY RICHMOND, VIRGINIA 23261 W. R. CARTWRIGHT VICE PRESIDENT NucLEAB December 15, 1988 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D. C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2 MONTHLY OPERATING REPORT Serial No.
NO/RPC:vlh Docket Nos.
License Nos.88-830 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 November 1988.
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