ML18152A520
| ML18152A520 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/31/1988 |
| From: | Cartwright W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-752, NUDOCS 8811180036 | |
| Download: ML18152A520 (22) | |
Text
e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 88-10 APPROVED:
~CVZ/2-d_ ;t_ ~~
\\::YSTATION MANAGER 1 -881-iiaoo36 881031 -------,
PDR ADOCK 050002BO R
PNU POW 34-04
1 SECTION PAGE
. I
- )
I Operating Data Report - Unit No. 1 1
Operating Data Report - Unit No. 2 2
Unit Shutdowns and Power Reductions - Unit No. 1 3
Unit Shutdowns and Power Reductions - Unit No. 2 4
Average Daily Unit Power Level - Unit No. I 5
Average Daily Unit Power Level - Unit No. 2 6
Summary of Operating Experience - Unit No. 1 7
Summary of Operating Experience - Unit No. 2 7
Facility Changes Requiring NRC Approval 8
Facility Changes That Did Not Require NRC Approval 9
Procedure or Method of Operation Changes that Did Not 12 Require NRC Approval Procedure or Method of Operation that Did Require NRC Approval 13 Tests and Experiments Requiring NRC Approval 14 Tests and Experiments That Did Not Require NRC Approval 15 Chemistry Report 16 Fuel Handling - Unit No. 1 17 Fuel Handling - Unit No. 2 18 Description of Periodic Test Which Were Not Completed Within 19 the Time Limits Specified in Technical Specifications
PAGE 1 OPERATING DATA REPORT DOCKET NO.
50-280
-~-,,..,,..-,~--
DATE 11/08/88 CO HP LE TED BY L. A. Warren TELEPHONE 804-35 7-3184 OPERATING STATUS
- 1. Unit Name:
Surry Unit # 1 Notes
- 2. Reporting Period:
October O 1-31, 19 8 8
- 3. Licensed Thermal Power (MWt):
2441
--:=:...::..:.=-------
- 4. Nameplate. Rating (Gross MWe):
_8_4""'7....::*..;;;.5 _____ _
- 5. Design Electrical Rating (Net MWe):
788
- 6.
Maximum Dependable Capacity (Gross MWe):
820
- 7.
Maximum Dependable Capacity (Net MWe):
_...;7..;:8;..:l;.._ __
- 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:
Ihis Month Yr.-to-Date
- 11. Hours In Reporting Period 745.0 7320.0
- 12. Number of Hours Reactor Was Critical 0
3755.2
- 13. Reactor Reserve Shutdown Hours 0
0
- 14. Hours.Generator On-Line 0
3634.2
- 15. Unit Reserve Shutdown Hours 0
0
- 16. Gross Thermal Energy Generated (MWH) 0 8451045.6
- 17. Gross Electrical Energy Generated (MWH) 0 2828500.0
- 18. Net Electrical Energy Generated (MWH) 0 2685027.0
- 19. Unit Service Factor 0
- 49. 7.
- 20.
Unit Available Factor 0
49.7
- 21. Unit Capacity Factor (Using MDC Net) 0 47%
- 22. Unit Capacity Factor (Using DER Net) 0 46.6%
- 23. Unit Forced Rate 100%
26~ 1%
- 24.
Shutdowns Scheduled over Next 6 Months (Type, Date, and Duration of Each):
Forced Maintenance Outag:e on 09/13/88 to 12/15/88
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26.
Units In Test Status (Prior to C011D11ercial Operation):
INITIAL CRITICALIIY INI?IAL !LEC?RICIIY COMMERCIAL OPERATION Forecast Cumulative 139032.0 88478.6 3774.5 86605.4 3736.2 201171267.0 65203673.0 61840403.0 62.3%
65%
57.5%
56*.5%
17.4%
Achieved (9/77)
OPERATING DATA REPORT.
OPERATING STATUS
- 1. Unit Name:
Surry Unit # 2 Notes
- 2. Reporting Period:
October 01-31, 1988
- 3. Licensed Ihermal 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 PAGE 2 DOCKET NO. ---:-50'="'-.,.,,2,.,,8,.,.l=---
DATE _1_1..:../..:..08.;...;/_8_8_~
COMPLETED BY L. A. Warren TELEPHONE 804-357-3184
- 8. If Changes Occur in Capacity Ratings (Items Number 3 lb.rough 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 21~.Q 7320.0
- 12. Number of Hours Reactor Was Critical saza.a
- 13. *Reactor Reserve Shutdown Hours
- 14. Hours Generator On-Line 4994.Z
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Gene.rated (MWH) 0 11570100.4 17, Gross Electrical Energy Generated (MWH) 0 3763420.0
- 18. Net Electrical Energy Generated (MWH) 0 3570901. 0 19, Unit Service Factor 0
- 68. 2%-
- 20. Unit Available Factor 0
68.2%
- 21. Unit Capacity Factor (Using MDC Net) 0 62.5%
- 22. Unit Capacity Factor (Using DER Net) 0 62%
- 23. Unit Forced Rate 0
24%
- 24. Shutdowns Scheduled Over Next 6 Months (Iype, Date8 and Duration of Each):
Refueling Outage 09/09/88 to 12/20/ 8 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 ELECTRICITY COMMERCIAL OPERATION Forecast Cumulative 135912.0 89694.3 JZB.l aazsa.Q 206740463.1 67136244.0 63647378.0 65%
65%
60.1%
59.-4%
15%
Achieved (9/77)
-a,.
NO.
DATE
- 0.
I-88-11 10/01/88 F
l F: Forced 2
S:
Scheduled (9/77)
PAGE,3 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-280 UN IT NAME _.:;:s.i,:,u,.,.rrv
....... ""'u.... 0..._ai......1,1;#_,,;;..l __
DATE ---e:-1~1/..,..0-8.._/8..,.8 ____________.........
COMPLETED BY L. A. warren REPORT MONTH OCTOBER 1988
-~~---------
TELEP HO NE __
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- 745.0 F
1 Reason:
A - Equipment Failure (Explain)
B - Maintenance or Test C - Refueling D - Regulatory Restriction LICENSEE EVENT REPORT I E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain) 3 C
E ::r II,n II II C
II
.. 'C 0
'C CAUSE & CORRECTIVE ACTION IO 0
- 0.
0 g; 0 E
0 PREVENT RECURRENCE 0
0 Unit shutdown due to emergency diesel generator operability concerns.
Method:
4 l - Manual 2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain)
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5 Exhibit l - Same Source e
-II NO.
DATE
- a.,..
I-88-19 10/01/88 s
1 F: Forced 2
S:
Scheduled (9/77)
PAGE~
UNIT SHUTDOWNS AND POWER REDUCTIONS
_DOCICE'X No. -"""'s __ o_-2=a.... 1 _______ _
UNITNAME __ ~s~u~rrv~~u~o~1t....... #__..2 ____ _
DATE _..,.l __
l.;,-/8....:./.,..8,....8 _____
COHPLE'IED BY L. A. Warren REPORT MONTH. OCTOBER 1988 TELEP00~-~80~4~-~3~57~-~3~18~4;,----
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1,3 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 11 on II II C
II
.. 'C a
'C CAUSE & CORRECTIVE ACTION TO
., a
- a. a
- u E
U PREVENT RECURRENCE a u Unit shutdown for refueling outage, reactor trip.
- Method:
1 - Manual 2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain) 4 s
Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Exhibit 1 - S8111e Source automatic e
PAGE 5 e
e AVERAGE DAILY UNIT POWER LEVEL MONTH OCTOBER 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
l'3 0
14 0
15 0
16 0
INSTRUCTIONS DOCKET NO.
50-280 UNIT Surry Unit # 1 DATE 11 / 0 8 / 8 8 COMPLETED BY L. A. warren TELEPHONE 804-357-3184 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 0
18 0
19 0
20 0
21 0
22 0
23 0
24 0
25 0
26 0
27 0
- 28.
0 29 0
'30 0
31 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)
MONTH PAGE 6 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-281 UNIT Sur!l: Unit # 2 DATE lll08/88 COMPLETED BY L.A. Warren TELEPHONE 804-357-3184 OCTOBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVER.AGE 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
l'3 0
29 0
14 0
30 0
1 '5 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.
{9/77)
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR OCTOBER 1988 PAGE 7 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 10-01-88 0000 10-23-88 0000 10-31-88 2400 UNIT TWO 10-01-88 0000 10-03-88 0000 10-31-88 2400 This reporting period begins with the unit at CSD.
Unit at RSD.
This reporting period ends with the unit at RSD~
This reporting period begins with the unit at CSD.
Unit at RSD.
This reporting period ends with the unit at RSD.
e e
F AGILITY CHANGES REQUIRING NRC APPROVAL MONTH/YEAR ~-O~C~T~O~B~E~R~I9~8~8~
NONE DURING THIS PERIOD PAGE 8
PAGE 9 e
FACIUTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR OCTOBER 1988 TM Sl-88-145 TEMPORARY MODIFICATION 10/10/88 TOP-2043 2-0P-51.5.4 An air agitator was used in the place of the mechanical agitator for mixing boric acid in the Boric Acid Batch Tank.
This does not constitute an unreviewed safety question nor does it present any safety concerns since the use of the air agitation for mixing boric acid is an acceptable alternative to the mechanical agitation.
TEMPORARY OPERATING PROCEDURE 10/10/88 Exposed resin will be flushed to demineralizer l-CH-I-3A from pipe 3"-RW-111-152 while the spent resin catch tank l-LW-TK-1 is being modified. This is to reduce radiation levels.
The procedure was reviewed for the effect on accident analyses and associated equipment operability /function.
Since this will reduce radiation levels by removing the spent resin from the pipe, an unrevie.wed safety question will not be created.
OPERATING PROCEDURE 10/10/88 This procedure allows running a charging/high head safety injection pump with service water flow isolated to both intermediate seal coolers.
and with the charging pump component cooling pump either running or shutdown.
The charging pump may run without seal cooling if the refueling water storage tank or volume control tank is used as a suction, charging pump temperatures are monitored by the P250, and the charging pump component cooling system is filled with the intermediate seal coolers isolated at least on the service water side (R WST or VCT temperatures must be kept less than 115°F to function as a source of water.)
Both units will. be in cold shutdown.
Therefore, an unreviewed safety question does not exist.
SCAFFOLDING REQUEST 10/12/88 Erection of temporary scaffolding located in Unit 2 containment to repair lights.
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.
PAGE 10 e
e FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR OCTOBER 1988 2-TMOP-2013 TEMPORARY MAINTENANCE OPERATING PROCEDURE 10/13/88 AC 88-10-13 EWR 88-390 l-OP-4.1 This temporary procedure includes measures to fill 'C' reactor coolant loop; remove interlocks which prevent the opening of MOV-2595; open MOV-2595; remove t.he modification to MOV-2595 interlocks and close MOV-2595.
This TMOP is to be performed to evaluate MOV-2595 which is presently leaking excessively.
This TMOP was reviewed for any effect on accident analyses and equipment operability/function. It was concluded that probabilities of accident analyses and equipment malfunctions are not affected.
because the hot leg loop stop valve will remain closed, the unit is shut down greater than 20% ~k/k and the 1C1 reactor coolant pump is disabled and cannot be started.
ADMINISTRATIVE CONTROL 10/13/88 Administrative control was placed on valve 3-EG-15 when the valve was opened. This valve is the cross-tie between the two air bottle banks.
Since administrative control of the emergency
- diesel generator air start bottle banks will ensure air-start circuitry redundancy, an unreviewed safety question is not created.
ENGINEERING WORK REQUEST 10/14/88 This engineering work request details the re-location of the cap screws as required. In addition, concurrence from engineering shows which caps screws may be omitted to resolve fit-up problem.
There is no impact to
- safety from this change request. The cavity seal ring assembly will continue to perform its design function.
PROCEDURE DEVIATION 10/15/88 The manipulator crane area radiation monitor (RM-RMS-162) will be turned off to allow restoration of the containment purge with high radiation levels. High radiation levels are due to the reactor head being
- removed. No refueling operations will be performed in this mode. Containment particulate and gas radiation monitors are fully functional.
Refueling operations will be performed, containment particulate and gas radiation monitors are fully functional and area radiation levels will be monitored locally by Operations or Health Physics personnel. Therefore, an unreviewed safety question does not exist.
e e
PAGE 11 F ACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR OCTOBER 1988 TM-Sl-88-149 TEMPORARY MODIFICATION 10/18/88 SP-88-llA EWR 88-240 PC-DB-E/Rl This temporary modification installed a flexibie hose from 1-DG-74 to 1-CH-413 maintaining the following valves shut: MOV-1381, 1-DG-TV-108B, HCV-I522A,B,C and HCV-1523.
Since the installation will be verified for leaktightness, and the design specifications for the hose used will exceed expected pressure and temperature, possible leakage paths will be contained and possible dilution paths will be isolated.
Therefore, no unreviewed safety question is created.
SETPOINT CHANGE 10/18/88 This change provides the specific setpoints for the low temperature overpressure protection.
- The review consisted of a RETRAN Code analysis of the heatup and cooldown of the reactor coolant system and the cold overpressurization of the reactor to prevent non-ductile pressurization or overstressing of the reactor vessel. Based on the review, the revision to the heatup and cooldown and the cold
- overpressurization setpoint does not constitute an unreviewed safety question.
ENGINEERING WORK REQUEST 10/19/88 This engineering work request to install temporary level indicators that will be periodically monitored (2-STP-25.2A) to check service water level in service water piping to unit 2 recirculation spray heat exchanger.
A new surveillance test will be implemented which will require two temporary level gauges to monitor service water levels in service water piping to recirculation spray heat exchangers. Therefore, an unreviewed safety question is not created.
ELECTRICAL PREVENTIVE MAINTENANCE SCHEDULE 10/28/88 This deviation allowed the defeat of the automatic reactor trips by jumpering out relay contacts affecting the closed reactor trip breakers.
While the change is in effect, all power to the control rods will be physically disconnected and control rods fully inserted.
While this jumper is installed, the reactor will remain at cold shutdown with all rods inserted and all sources of power. to the control rod drive mechanisms removed. The reactor trip breakers shall be opened upon the completion of the work.
There is no method for an uncontrolled rod withdrawal with all power removed from the control rod drive mechanisms.
Therefore, this change does not represent an unreviewed safety question.
2-0P-51.5.1 e
e PROCEDURE OR METHOD OF OPERATION THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR OCTOBER 1988 PAGE 12 The charging pump cooling system will be placed in service with only 12 gpm flow through the cooler instead of 30 gpm as directed in the procedure.
It has been previously determined that even without flow to the seal coolers, charging pump seals will not be adversely affected. Therefore, 12 gpm flow will not adversely affect charging pumps and no unreviewed safety question is created. The Technical Specifications does not require operable charging pumps with both units in cold shutdown.
e e
PROCEDURE OR METHOD OF OPERATION THAT DID REQUIRE NRG APPROVAL MONTH/YEAR OCTOBER 1988 NONE DURING THIS PERIOD PAGE 13
e PAGE 14 TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH/YEAR OCTOBER 1988 NONE DURING THIS PERIOD
e e
PAGE 15 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL 2-ST-221 l/2-ST-220 l-ST-224 MONTH/YEAR OCTOBER 1988 SPECIAL TEST 09/23/88 This special test governed the movement and placement of a weight on the straddle ring surrounding the reactor. The ring is cantilevered by design. This test provided information on behavior under hydrostatic loads.
It was determined that an unreviewed safety question does not exist because the special test had no potential to affect safety related equipment. The cavity was not flooded during performance of this test.
SPECIAL TEST 09/28/88 The special test collected data associated with the control room envelope air conditioning system. The data will be used to evaluate system performance.
The test was conducted with the system operating as described in the UFSAR and Technical Specification. Therefore, an unreviewed safety question was not created or was a Technical Specification change required.
SPECIAL TEST 10/19/88 This special test was performed to demonstrate the leak limiting capabilities of the J-seal component of the reactor cavity seal assembly.
The leakage has been evaluated and determined to be acceptable.
The change has no effect on the probability of occurrence of the accidents evaluated in the UFSAR. The consequences of the accidents discussed are not significantly increased as a result of this change.
The possibility of an accident or equipment malfunction of a different type is not created. The margin of safety as described in the basis section of the UFSAR is not reduced.
PRIMARY COOLANT
. ANALYSIS Gross Radioact ** µCi/ml Suspended Solids, ppm Gross Tritium, µCi/ml Iodine131, µCi/ml 1131 / Il 'H Bvdrosten, cc/b Lithium. DDm Boron-10, DDm*
Oxvsten. (DO), ppm Chloride, DDm pH@ 2~ de2ree Celsius VIRGINIA POWER
~
SURRY POWER STATION~
CHEMISTRY REPORT OCTOBER 19 88 UNIT NO. 1 MAX.
KIN.
AVG.
E-2 E-4 E-:
2.88 8.31 1 ~c; 20.0 0.0 8.3 N/A N/A E-4 E-5 E-*
6.03 1.30 2_ 6::!
N/A N/A N/A N/A N/A N/A 419.2 358.1 412.8 3.5
- 1. 0 2.0 0.016 0.002 0.009 5.65 4.73 5.16
- Boron-IO* Total Boron X 0.196 PAGE 16 UNIT NO. 2 MAX.
KIN.
- AVG.
E-:
E-3 E-2
- L lR h n?
l R::l 0.2 o.o 0.1 N/A N/A E-:-5 E-5 E-5 3.20 3.20 3.20 N/A N/A N/A N/A N/A N/A 415.9 389.6 403.4 3.5 2.5 3.0 0.014 0.005 0.009 5.28 4.64 5.01 UNIT ONE:
The month started with the unit at CSD preparing for refueling. On
- 10-02 at 1600, started to detension the reactor head and on 10-15 at 0300, started to lift the reactor head and flood the cavity. On 10-21 at 0352, the RL system was.
put into service and shortly thereafter, the Chemistry department detected an increase in total suspended solids and turbidity. Operation started a purification line-up using the letdown filter, 1B1 mixed bed, 'A' deborator and the reactor coolant filter~ By 10-27 at 1310, all sample points were showing.S.0.5 ppm turbidity. The month ended with 1B1 mixed bed and 'A' deborator in service.
UNIT TWO:
The month started with the unit at CSD waiting to refuel~ On 10-6 at 0030, 'A' mixed bed was put into service and removed from service at 1645~ On 10-10 at 1700 'A' mixed bed was put back in service to reduce activity and was removed from service on 10-17 at 1205. On 10-19 at 1000, started to detension the reactor head. Ended the month with no beds in service and the cavity not flooded~
e
- e PAGE 17 UNIT FUEL HANDLING DATE OCTOBER 1988 NEW OR DATE NUMBER OF
SHIPMENT fl RECEIVED PER SHIPMENT fl I!
ENRICHMENT CASK ACTIVITY LEVEL NONE DUF ING THIS P ~RIOD
e e
PAGE 18 UNIT 2
FUEL HANDLING DATE OCTOBER 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT 0 RECEIVED PER SHIPMENT II II ENRICHMENT CASK ACTIVITY LEVEL NONE DUI ING TIIlS P :RIOD
DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR OCTOBER 1988 NONE DURING THIS PERIOD PAGE 19
t'
,o,,!*
e e
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 November 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.88-752 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 October 1988.
W. R. Cartwri 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