ML18152A287
| ML18152A287 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/30/1988 |
| From: | Benson D, Cruden D, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-292, NUDOCS 8805240402 | |
| Download: ML18152A287 (28) | |
Text
-- -~- -
VIRGINIA ELECTRIC AND POWER COMP ANY SURRY POWER STAl'ION MONTHLY OPERATING REPORT REPORT 88-04 APPROVED: )(1/1/1}:L ~et'ZUUm STATIO ANAGER
(~----------~
I 8805240402 880430 1
PDR ADOCK 05000280 R
ncn
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 e
PAGE 1
2 3
4 5
6 7
8 9
10-15 16-18 Procedure or Method of Operation Changes that Did Require NRC Approval 19 Tests and Experiments Requiring NRC Approval 20 Tests and Experiments That Did Not Require NRC Approval 21 Chemistry Report 22 Fuel Handling - Unit No. 1 23 Fuel Handling - Unit No. 2 24 Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications 25 I
~I
OPERilING DAIA REPOR'.I OPERATING STAXUS
- 1. Unit Name:
Surry Unit # 1 Notes
- 2. Reporting Period:
April O 1 - 30, 1988
- 3. Licensed Thermal Power (MWt):
2441
--a~.=.--------
- 4. Nameplate Rating (Gross MWe): _.::;8.:.4.:..7:..:*5=----,,~--
- 5. Design Electrical Rating (Net MWe):
788
- 6. Maximum Dependable Capacity (Gross MWe):
...;;8.;;;2~0 __ _
- 7.
Maximum Dependable Capacity (Net MWe):
781 e
PAGE 1
DOCKET NO.
50-280 DAIE 5/5/88 COMPLETED BY L. A. warren
'IELEPHONE 804-357-318~
- 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 719.0 2903.0
- 12. Number of Hours Reactor Was Critical 193.6 2312.6
- 13. Reactor Reserve Shutdown Hours o.o o.o
- 14. Hours Generator On-Line 192.8 2297.6
- 15. Unit Reserve Shutdown Hours 0
0
- 16. Gross Thermal Energy Generated (MWH) 369249.8 5322810.2
- 17. Gross Electrical Energy Generated (MWH) 120255.0 1794685.0
- 18. Net Electrical Energy Generated (MWH) 112948.0 1705504.0
- 19. Unit Service Factor 26.8%
79.2%
- 20. Unit Available Factor 26.8%
79.2%
- 21. Unit Capacity Factor (Using MDC Net) 20.1%
75.2%
- 22. Unit Capacity Factor (Using DER Net) 19.9%
74.6%
- 23. Unit Forced Rate 0.0%
3.3%
- 24. Shutdowns Scheduled Over Next 6 Months (l'ype, Date, and Duration of Each):
Refueling Outage 04/08/88 thru 06/08/88
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to COIIIDercial Operation):
INITIAL CRITICALm INITIAL ELECTRICm COMMERCIAL OPERATION Forecast Cumulative 134615.0 87036.0 3774.5 85268.8 3736.2 198043031.6 64169858.0 60860880.0 63.3%
66.1%
- 58-c {!%--
- 57-.4%
17.3%
Achieved
e OPERATING DATA.REPORT OPERATING S'!A:rUS
- 1. Unit Name:
Surry Unit # 2 Notes
- 2. Reporting Period:
April 01-30, 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):
8.;;;;2....;;.0 __ _
- 7.
Maximum Dependable Capacity (Net MWe):
781 PAGE 2
DOCICE:r NO.
50-281 DilE 5/5/88 COMPLE'IED BY L. A. warren l'EL!PHONE 804-357-3184
- 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:
Ibis. Month Yr.-to-Date
- 11. Hours In Reporting Period 719.0 2903.0
- 12. Number of Hours Reactor Was Critical 604.4 2684.8
- 13. Reactor Reserve Shutdown Hours 0.0 o.o
- 14. Hours Generator On-Line 576.5 2656.9
- 15. Unit Reserve Shutdown Hours
- 0.0 o.o
- 16. Gross Thermal Energy Generated (MWH) 1391179.6 6428995.2
- 17. Gross Electrical Energy Generated (HWH) 464035.0 2143685.0
- 18. Net Electrical Energy Generated (MWH) 441794.0 2040475.0
- 19. Unit Service Factor 80.2%
91.5%
- 20.
Unit Available Factor 80.2%
91.5%
- 21. Unit Capacity Factor (Using MOC Net)
- 78. 7%
90%
- 22. Unit Capacity Factor (Using DER Net) 78%
89.2%
- 23. Unit Forced Rate 19.8%
8.5%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling Outage 8/19/88 48 days
- 25. If Shut Down At End Of Report Period Estima'ted Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
INITIAL CRITICALITY INITIAL ELEC'l'RICITY COMMERCIAL OPERA?ION Forecast Cumulative 131495.0 87350.8 328.1 85955.2 o.o 201599357.9 65516509.0 62116952.0 65.4%
65.4%
6~ o.li%
60% *.
14.2%
Achieved
-II NO.
DATE
- a.
88-04 04..;09-88
- s 1
F: Forced 2
S:
Scheduled (9/77)
UNIT SHUTDOWNS AND POWER REDUCTIONS REPORT MONTH __
- .;;A""'p __
ri=l..al-9_8_8 __
p:,
L C
C) 0 0 -
N 0
C C
u 0
"C...
m II 0.. m L
D
.c
- , a:
- J:
II
~
a:
m.c C
0 Ul 3
0 0
526.2 C
1 Reason:
A* Equipment Failure (Explain)
B - Maintenance or Iest C
- Refueling D - Regulatory Restriction LICENSEE EVENT REPORT
~~
E - Operator Irsining & License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain)
- 3.
C E "'"
II in m m C
II "C
0 "C
0
- a.
0
- 0 E
0 0
CJ Method:
1 - Manual 2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain)
...,***~................. -..,...,~.*---**-.. *- '...
PAGE 3
DOCKET NO. -~5-~... _-2_s_o_* _____ _
UNIT NAME Surry Unit I 1
-~----...... --,-:-=-,:-
' DATE _0'='5_../~0_.5/-,;;8.,_8 ___ ;..,.__
COMPLETED BY L *. A. Warren TELEPHONE :::a:04:-:3:s:1:-3~1~8:4:::::*_
i CAUSE & CORREC'IIVE ACTION IO PREVENT RECURRENCE e
Unit was shutdown for refueling outage.
4 5
I I
i Exhibit *G
- Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Exhibit 1 - Same Source e
II NO.
DATE
- a.,..
I-88-06 03/27/88 F
1 F: Forced 2
S:
Scheduled (9/77)
PAGE 4
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-281 uN1T NAME -.:.!'s":!!!u~r~ry~U~-~n~tt....i:#-=2-.. __ _
D1.tE~~os_1_o~s~,a~0 ________ __
COMPLETED BY L. A. Warren REPORT MONTH _..;;.A_.p_.r.;;;il ___ l 9"""8""'8..__ __
TELEPHONE ::~a:o:4-:3:5:7:-:3:10:4::::::::::
C
~ Cl 0
0 -
N 0
C LICENSEE C
u 0
'C m
0..
II EVENT
- 0
.c.. IX
.. J:
II
.c REPORT~
C -
IX II in C
- E 0
0 142.5 A
2 LER-281/
88-004 Reason:
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)
C e ::r II in II II C
II
.. 'C CAUSE & CORREC'UVE AC'IION IO 0
0
'C
- , u
- a.
0 E U PREVENT RECURRENCE 0 u e
Unit was manually tripped due to vital bus 2-III inverter failure, unit was kept down to inspect AFW system for blockage, none found.
- - *~
e
.3 Method:
4 Exhibit G - InstTI1ctions 1 - Manual for Preparation of Data 2 - Manual Scram.
Entry Sheets for Licensee 3 - Automatic Scrsm.
Event Report (LER) File 4 - Other (Explain)
(NUREG 0161) 5 Exhibit 1 - Ssme Source
e PAGE 5
AVERAGE DAILY UNrr POWER LEVEL DOCKEt NO.
- -S.0~280 UNIT S1;!$ Unit# l DAn:
~5 tBB COHPLE'IED BY L.A. Warren l'ELEPHONE 804-357-3184 MONTH April 1988 DAY AVERAGE DAILY POWER LEVEL DAY
!VERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 619 17 0
2 611 18 0
'3 604 19 0
4 597 20 0
5 583 21 0
6 581 22 0
7 582 23 0
8 549 24 0
9 81 25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
'30 0
'I 15 0
'31 16 0
INSTRUCTIONS i
I 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 e
PAGE 6
AVERAGE DAILY UNll POWER LEVEL DOCKET NO.
50-281 UNI'!
Sur!Z Unit I 2 DilE 05/05/88 COMPLETED BY L.A. Warren TELEPHONE 804-357-3184 April 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 780.
2 0
18 781
'3 0
19 781 4
0 20 782
'5 0
21 781 6
12 22 780 7
625 2'3 781 8
770 24 781 9
773 25 780 10 773 26 780 11 774 27 780 12 776 28 779 l '3 780 29
~ 779 14 781
'30 654 1 '5 779
'31 16 780 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)
e e
PAGE 7
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR __
A....ap""-ril_I_98_8 __ _
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 04-01-88 0000 04-08-88 2100 04-09-88 0148 0238 1044 04-10-88 0120 1307 04-12-88 0840 04-15-88 0408 04-16-88 0732 04-17-88 0156 04-30-88 2400 This reporting period begins with the unit at 81% power, 660 MWs in end of life cycle coast down.
Unit is at 75% power, 615 MWs, commenced rampdown for refueling outage.
Generator off line.
Reactor shutdown.
RCS at 500°F, setting safeties.
RCS at 350°F, 450 psig, holding for chemistry on RHR.
RCS at <200°F.
RCS degassed.
Completed cleanup from crud burst, depressurizing RCS.
RCS at mid-nozzle.
Completed RCS head evacuation, isolating RCS loops.
This reporting period ends with the RCS level at 171 standpipe, preparing to start refueling activities.
e e
PAGE
SUMMARY
OF OPERA TING EXPERIENCE MONTH/YEAR __
A_p_rn_1_9_88 __
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 TWO 04-01-88 0000 04-04-88 1100 1835 04-05-88 0159 1932 04-06-88 2329 04-07-88 0250 0543 0945 1805 04-30-88 1105 1314 1715 1742 2400 This reporting period begins with the unit at CSD on RHR.
RCS >200°F.
RCS >350°F, 450 psig.
RCS at HSD.
Reactor critical.
Generator on line, commencing power increase at 150 MWs/hr.
Holding power at 55%, 460 MWs, working secondary plant.
Commenced power increase at 150 MW /hr.
Holding power at 95%, 755 MWs, working secondary plant.
Unit at 100%, 815 MWs.
Commenced rampdown at 150 MW/hr. for PT-29.1.
Holding power at 73%, 600 MWs.
Commenced rampdown at 150 MW /hr. to work isolated phase bus duct fan.
Holding power at 66%, 545 MWs.
This reporting period ends with the unit at 66% power, 545 MWs while repairing 'A' isolated phase bus duct fan.
8
PAGE F ACIUTY CHANGES REQUIRING NRG APPROVAL MONTH/YEAR April 1988 NONE DURING Tms PERIOD 9
.i -t I I
J 1
DC 84-51 PAGE 10 FACILITY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR April 1988 STATION PERSONNEL FACIIJTIES RENOVATION This design change added a second story over part of the service building and a two story addition to the west end of the service building.
The spaces allocated to Chemistry, Health Physics and the Instrument Shop were enlarged and/or relocated in the same general area. The laundry and warehouse facilities were relocated to other areas of the station.
Additional office spaces, locker rooms with toilet facilities and a PBX room were installed.
SUMMARY
OF SAFETY ANALYSIS The control room annex and the slab roof over the relay room, cable vault and mechanical equipment room No. 3 have not been degraded structurally, seismically or with respect to missile protection.
The loading on these structures has been minimized.
The new CMU wall at column line 10 has been designed so as not to fail and damage the control room annex door or wall during a seismic event. The structural integrity of the Turbine Building has not been affected.
The additional loading on the service water discharge tunnel has been reviewed and found to be acceptable.
The main steam and main feedwater piping will be unaffected by these modifications.
The ability of chiller l-VS-E-3A or 3B (and associated pump l-VS-P-3A or 3B) to provide a backup control room chilled water supply in the unlikely event of a fire which disables all three control room chillers will not be affected.
The relocation of the breathing air compressor to the loss prevention storage room will not reduce access of the fire brigade to breathing air.
These modifications are non-safety-related and do not affect the design basis, operation, or control of equipment important to safety.
No accidents or malfunctions previously evfil.uated will be affected and no new accidents or malfunctions will be created.
UNITS 1 & 2
FACIIJTY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR April 1988 SCAFFOLD REQUEST A temporary scaffolding platform. was located in the control room annex.
Installation of temporary scaffolding in the Control Room Annex was reviewed for effect on accident analyses. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunction are not affected.
SCAFFOLD REQUEST A temporary scaffold platform was located in Unit 1 containment 'C' loop room to work snubber hanger 01-WGC-MSS-10.
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.
SCAFFOLD REQUEST A temporary scaffolding platform was located in the Unit 1 containment, 'B' loop room to work snubber hangers O 1-W GC-MSS-1 BA.
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.
SCAFFOLD REQUEST A
temporary scaffold was located in Unit 1
containment, 'A' loop room to work snubber hangers 01-WGC-MSS-13/14A I
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 11 04-11-88 04-13-88 04-13-88 04-13-88 I
i I
- i I
e e
F ACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL TM S2-88-25 MONTH/YEAR April 1988 SCAFFOLD REQUEST A temporary platform was located in Unit 1 Turbine Building basement to work l-CN-110, condensate outlet of the flash evaporator.
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.
SCAFFOLD REQUEST A temporary platform was located in the Unit 1 containment, residual heat removal flats to inspect welds and components.
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 and equipment malfunctions are not affected.
TEMPORARY MODIFICATION This change involved wiring open the exhaust motor operated dampers for fans 2-VS-F-lB & 2-VS-F-lC.
This change does not constitute an unreviewed safety question in that the containment air recirculation system is not required to function during design basis events.
. SCAFFOLD REQUEST A temporary platform was located in the Unit 1 Safeguard, elevation 45' level, to work l-MS-92,127,128, 165 and 166.
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 12 04-13-88 04-13-88 04-13-88 04-14-88
e e
FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR __
A_.p,_ril_' ;_1_9_8_8_
SCAFFOLD REQUEST A temporary scaffold platform was located in the Unit 1 containment at the 18' elevation to perform NDE of various primary piping.
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.
SCAFFOLD REQUEST A temporary scaffold platform was located in the Unit 1 containment to perform NDE of various primary piping.
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.
SCAFFOLD REQUEST A temporary platform was located in the 27'7" elevation of Containment to perform NDE of various primary piping and components.
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.
SCAFFOLD REQUEST A temporary platform was located in the Unit 1 containment 'B' SIG cubicle and loop room to perform NDE of primary piping welds and components.
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 13 04-14-88 04-14-88 04-20-88 04-20-88
e e
FACIIJTY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR SCAFFOLD REQUEST April 1988 A temporary platform was located in the Unit 1 containment electrical penetration area to work pipe and hanger installation !AW DCP-86-15.
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.
AC SI-88-0423 ADMINISTRATIVE CONTROL The dike at the emergency switchgear room door was temporarily removed and a flood watch placed at the door and turbine building sump areas.
The dike would be reinstalled in the event of the flood.
The removal of this dike did not adversely affect any safety related equipment or create an unanalyzed accident.
AC S2-88-0424 ADMINISTRATIVE CONTROL TM Sl-88-42 A flood watch was posted at mechanical equipment room (MER) #3 while the flood dike was removed.
The operator would isolate the line if a break occurred in MER #3 until the flood dike was replaced. If the line break occurred downsteam of MER #3 the Turbine Building operators would isolate the line break.
Since administrative control will ensure flood protection of safety related equipment, an unreviewed safety question is not created.
TEMPORARY MODIFICATION This temporary modification was required to provide a letdown flow path for reactor coolant system clean up while work was being done on the letdown trip valve TV-1204.
The requirements of containment isolation will be met because the jumper will be removed prior to leaving cold shutdown and the trip valve (TV-1204) will be operable.
PAGE 14 04-21-88 04-23-88 04-24-88 04-26-88
e FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL TMSl-88-40 EWR 88-037 MONTH/YEAR SCAFFOLD REQUEST April 1988 A temporary platform was located in the containment 1B1 loop room, 18' and 316 11 annulus to work replacement of the RCP feeder.
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.
TEMPORARY MODIFICATION This temporary modification was required to i!).stall a flexible hose from l-DG-74 to l-CH-413 maintaining the following valves shut: MOV-1381, l-DG-TV-108A, HCV-1522A,B,C and HCV-1523.
Since the installation was verified for leak tightness, and the design specifications for the hose used exceed expected pressure and temperature, and possible leakage paths were contained, and possible dilution paths were isolated, no unreviewed safety question was created.
SCAFFOLD REQUEST A
temporary platform was located in Unit 1
containment 316 11 annulus to install conduit from cable trays to location of new transmitters on the wall.
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.
ENGINEERING WORK REQUEST This engineering work request replaced the existu_:ig liquid waste demineralizer with Duratek skid mounted package system of demineralizer,
- filters, pump, instrumentation, associated piping, etc.
The new system improves waste processing efficiency and reduces personal exposure to radiation.
The system is fully tested and inspected.
Failure of equipment is analyzed in the UFSAR. No unreviewed safety question involved.
PAGE 15 04-26-88 04-26-88 04-29-88
_J 04-12-88
1 & 2-MOP-14.3 1&2-MOP-14.4 1&2-0P-14A e
e PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR APRIL 1988 MAINTENANCE OPERATING PROCEDURES (MOP)/
OPERA TING PROCEDURES (OP)
These procedural changes were required to recognize the normal positions of the RHR pump seal vents and constant casing vents. and to recognize RH-MOV-200 as lock closed.
These changes updates the normal positions of the RHR pump seal and casing vents to open and as such have no affect on the consequence or probability of any analyzed accident/malfunction and does not create any new accident/malfunction sequences.
These changes will ensure the pump casing/seals remain vented.
AC Sl-88-0418 ADMINISTRATIVE CONTROL Administrative control was required to close the door between the emergency switchgear room and the turbine building.
The door was blocked open to allow access for an exhaust duct for maintenance work.
The design basis accident was reviewed and it was determined that since the emergency switchgear door would be closed by the dedicated continuous fire watch when the control room is required to be pressurized, an unreviewed safety question did not exist nor is a technical specification change required.
PAGE 16 04-07-88 04-18-88
Sl-87-946 e
PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR __
A
....... p_ril_l9_8_8_
DEVIATION REPORT The 'B' and 'C' control room/relay room chiller units are not 100% capacity (90 tons) as described in the UFSAR. The change involved operation of the system under more restrictive conditions in order to be
- consistent with the mode of operation described in the UFSAR.
If service water (SW) temperature at the inlet of the control room/relay room (CR/RR) chillers is limited to 70°F, then a single chiller unit is capable of maintaining the CR/RR spaces below 100°F. The equipment in the CR/RR is designed to 120°, therefore, plant operation with one chiller operating and one chiller operable (per technical specifications) provides the necessary redundancy such that no unreviewed safety question is created.
Operation with SW temperature in excess of 70°F requires that all three CR/RR chillers be operable which provides for 100%
redundancy, so that no unreviewed safety question is created.
Subsequent to the performance of this safety analysis, the 'B' chiller was restored to 100% capacity. The upgrade on 'C' chiller is in progress. Service water temperatures have not yet reached. 70°F.
AC S2-88-0419/ ADMINISTRATIVE CONTROL AC S2-88-0420 The 'A' feedwater regulating valve was jacked open~-
MOV-FW~254A throttled and 'A' S/G level was controlled on the bypass, FCV-255A.
An operator was stationed at 'A' feedwater regulating valve to shut the valve should feedwater isolation be required by an automatic signal. The operator was in contact with the control room by way of a radio and could close the feedwater regulating valve in thirty seconds if required..
(
AC Sl-88-0421 ADMINiSTRATIVE CONTROL Administrative control (reactor operator notification by the gaitronics system) of the high flux at shutdown alarm system was taken because the evacuation alarm in containment was inoperable.
Using the gaitronics to evacuate containment in lieu of the evacuation alarm, should a high flux condition exist, has no impact on the UFSAR safety analysis.
PAGE 17 04-19-88
- 04-19-88/
04-20-88 04-21-88
e e
PAGE 18 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR April 1988 AC S2-88-0426 ADMINISTRATIVE CONTROL 04-26-88 Administrative control was required to perform maintenance on the limit switches for TV-:DA-203A, and to comply with the technical specification for containment integrity.
The containment isolation valve TV:-DA-203A will be closed and under administrative control to provide containment integrity, but can be operated within two hours if a sample is needed.
Therefore, an unreviewed safety question does not exist.
AC SI-88-0427 ADMINISTRATIVE CONTROL Administrative control was required to close mechanical equipment room #3 door and emergency switchgear room/turbine building door.
The doors were blocked open to allow access for welding hoses, cables and air hoses to perform work on l-VS-E-4B/4C.
The design basis accident was reviewed and it was determined that since the mechanical equipment room
- 3 door and emergency switchgear/turbine building door will be closed upon receiving an safety injection signal, the control room pressure boundary will be satisfied.
1&2-0P-62.1/
OPERATING PROCEDURES 2-0P-12A UFSAR 11.3.3.8 states that all three steam generators blowdown flows are through one radiation monitor.
These procedures align two steam generator blowdowns to flow through one radiation monitor and the remaining steam generator blowdown to flow through the other radiation monitor.
Changing the steam generator blowdown radiation
. monitor flow alignment from flowing through one radiation monitor to flow through
- two radiation monitors enhances the ability to detect primary-to-secondary leakage.
Therefore, SGTR accident and consequences are unaffected.
04-27-88 01-28-88
e e
PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID REQUIRE NRC APPROVAL MONTH/YEAR April 1988
'=;..___:;.__
NONE DURING THIS PERIOD PAGE 19
-~I
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PAGE 20 TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR ___
A_p_ril_I_9a_a ___ _
NONE DURING TIIlS PERIOD
2-ST-2ll 2-ST-211 e
PAGE 21 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR APRIL 1988 SPECIAL TEST This special test was used to verify the auxiliary feedwater flow paths to 'A' steam generator to ensure that there were no obstructions in the line.
This test was performed when Unit 2 was at cold shutdown and only a motor driven pump was used for the test; therefore, no effect was identified in I0CFRS0.59/10CFR72.35 review.
SPECIAL TEST This special test was used to verify the auxiliary feedwater flow paths to all steam generators to ensure that there were no obstructions in the line.
This test was performed when Unit 2 was at cold shutdown and only a motor driven pump was used for the test; therefore, no effect was identified in 10CFRS0.59/10CFR72.35 review.
04-01-88 04-03-88
PRIMARY COOLANT ANALYSIS Cross Radioact., ~Ci/ml Susoended Solids, oom Gross Tritium, ~Ci/ml 131 Iodine
, ~Ci/ml 1111 / 11 '31 Hvdrosten, cc/kR.
Lithium, ppm Boron-10, ppm*
Oxv2en, (DO), DDm Chloride, ppm PH@ 25 degree Celsius e
VIRGINIA.POWER SURRY POWER STATION CHEMISTRY REPORT APRIL 19 88 UNIT NO. 1 MAX.
MIN.
AVG.
1.85EO 4.55E-2 3.21E-l o.o
. o.o
. o.o 4.57E-2 4.57E-2 4.57E-2
. 3.09E:-i 6.73E-4 4.47E-2 0.18 0.11 0.14 34.9 3.9 14.9 0.46 0.42 0.44 397.880 0.764 192.682 5.500 0.005 2.412 0.030 0.001 0.013 8.31 5.35 6.35
- Boron-IO* Total Boron X 0.196 PAGE 22 UNIT NO. 2 MAX.
MIN.
AVG.
2.57E-1 l.50E-2 l.30E-l o.o
'().Q o.o
~
- 6. 30E-"' 2.56E-2 4.47E-2 3.87E
-i 5.94E-5 l.36E-4 0.12 0.06 0.08 34.7 17.5 30.2 1.98 0.51 0.76 231. 08~ 24.500 72.283 0.005 0.005 0.005 0.010 0.002 0.007 6.99 5.98 6.71 REMARKS:
UNIT ONE:
u~ 1 began the m:>nth at 82% rower, coasting toward refueling shutdown.
On 4-8 rrurpdown to refueling began and the unit was at cold shutdown at the end of the month.
No LiOH additions for U-1 in April.
UNIT 'Il\\7G:
U-2 began the rronth at 0% rower; reactor went critical on 4-5 and the unit was at 100% On 4-7 where it stayed until 4-30 when the unit was*
rarrped back to 73% for Pl'-29.1. Lithiufi"t additions:
4-3 at 1500, 1635g; 4-5 at 1025, 320g; 4-7 at 0400,200g; 4~7 at 1435, 204g; 4-8 at 1010, 248g; for a monthly total of 2607 grams of LiOH.
cation bed was placed in service for lithium removal on 4-16 fran 1845 until 2048.
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PAGE 23 UNIT __
1_
FUEL HANDLING DATE April 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPINC SHIPMENT I RECEIVED PER SHIPMENT I
I ENRICHMENT CASK ACTmn LEVEL NONE DUB NG TlllS PI RIOD I. I
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PAGE 24 UNIT __
2_
FUEL HANDLING DATE ApdJ 19RR NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPIN(
SHIPMENT#
RECEIVED PER SHIPMENT ENRICHMENT CASK ACTIVITI LEVEL NONE DUR tNG TlllS PE rooo t
r
e PAGE 25 DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE _TIME LIMITS SPECIFIED IN TECHNICAL SPECIFIC A TIO NS
- .MONTH/YEAR ___
A_p_ril_I_9_aa ___ _
NONE DURING TIIlS PERIOD
J Ill,.*.,.
~
D.S.CRUDEN VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 16, 1988 VICE PRESIDENT-NUCLEAR 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 N~.88-292 NO/DAS:vlh Docket Nos.
50-280 50-281 License Nos. DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of April 1988.
Very truly yours, 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
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