ML18152A290
| ML18152A290 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/30/1988 |
| From: | Cartwright W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-690, NUDOCS 8810210454 | |
| Download: ML18152A290 (26) | |
Text
'.
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 88-09 APPROVED:, J~d L )Je/Yl.A.on.
STATION MANAGER
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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 Procedure or Method of Operation that Did Require NRC Approval Tests and Experiments Requiring NRC Approval Tests and Experiments That Did Not Require NRC 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 16 17 18 19 20 21 22 23
OPERATING DATA REPORT OPERATING STATUS
,1. Unit Name:
Surry Unit # 1 Notes
- 2. Reporting Period:
September 01-30, 1988
- 3. Licensed Thermal Power (MWt):
2441
- 4. Nameplate Rating (Gross MWe): __ 8;...4a.a7..:a*.;;.5 _____ _
S. Design Electrical Rating (Net MWe):
788
- 6. Maximum Dependable Capacity (Gross MWe):
820
- 7.
Maximum Dependable Capacity (Net MWe): ___ 7 __ 8 __ 1 __ _
PAGE 1 DOCKET NO.
50-280 DATE 10/4/88 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 To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month Yr.-to-Date
- 11. Hours In Reporting Period 720.0 6575.0
- 12. Number of Hours Reactor Was Critical Jl8 1 2 3755.2
- 13. Reactor Reserve Shutdown Hours Q.Q 0 0
- 14. Hours Generator On-Line 312.fl 363412
- 15. Unit Reserve Shutdown Hours Q.Q 0 0
- 16. Gross Thermal Energy Generated (MWH) 2666~2.Z 845104516
- 17. Gross Electrical Energy Generated (MWH) 2:5494Q.Q 2828500.0
- 18. Net Electrical Energy Generated (MWH) 242Q4l.Q 2f285Q2Z.O
- 19. Unit Service Factor H.1%
55.3%
- 20. Unit Available Factor
~~.1%
55 1 3%
- 21. Unit Capacity Factor (Using MDC Net) 43%
52.3%
- 22. Unit Capacity Factor (Using DER Net) 42.2%
~1.8%
- 23. Unit Forced Rate 55.9%
1219%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Forced Maintenance Outage on 09/13/88 to 11/18/88
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to COl!Ullercial Operation):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Forecast Cumulative 138287.0 88478.6 3774.5 86605.4 3736.2 201171267.0 65203673.0 61840403.0 62.6%
65.3%
57.8%
- 56. 7%
17.4%
Achieved (9/77)
e OPERATING DATA REPORT OPERATING STATUS
- 1. Unit Name:
Surry Unit # 2 Notes
- 2. Reporting Period:
September Ol-30, 1988
- 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 __ _
PAGE 2 DOCKET NO.
50-281 DATE 10/ 4/88 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 To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month Yr.-to*Date
- 11. Hours In Reporting Period 720.0 6575.0 12, Number of Hours Reactor Was Critical 218.0 5028.3
- 13. Reactor Reserve Shutdown Hours o.o o.o
- 14. Hours Generator On-Line 218.0 4994.7
- 15. Unit Reserve Shutdown Hours o.o 0.0
- 16. Gross Thermal Energy Generated (MWB) 376719.4 11570100.4
- 17. Gross Electrical Energy Generated (MWH) 114285.0 3763420.0
- 18. Net Electrical Energy Generated (MWB) 106075. 0 3570901.0
- 19. Unit Service Factor 30.3%
76%
- 20.
Unit Available Factor 30.3%
76%
- 21. Unit Capacity Factor (Using MDC Net)
- 18. 9%
69.5%
- 22. Unit Capacity Factor (Using DER Net)
- 18. 7%
68.9%
23., Unit Forced Rate
- 69. 7%
. 24%
- 24.
Shutdowns Scheduled Over Next 6 Months.(IIpe, Date, and Duration of Each):
Refueling Outage 09/09/88 to 12/02/88
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26.
Units In Test Status (Prior to Commercial Operation):
INITIAL CRITICALin' INITIAL ELECTRICITY COMMERCIAL OPERATION Forecast Cumulative 135167.0 89694.3 328.1 88293.0 o.o 206740463.1 67136244.0 63647378.0 65%
65%
60.4%
5~.8%
15%
Achieved (9/77)
II NO.
DATE
- a.......
88-10 09/07 /88 F
88-11 09/13/88 F
l F: Forced 2
S:
Scheduled (9/77)
PAGE 3 UNIT SHUfDOWNS AND POWER REDUCTIONS DOCKET NO.
50-280 UNIT NAME S1.u:x:y :U:n11 tt DATE 10£04£88 COMPLETED BY L.A. Warren REPORT MONTH September I 988 TELEPHONE 804-357-3184 C
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1 Reason:
A - Equipment Failure (Explain)
B - Maintenance or Test C - Refueling D - Regulatory Restriction LICENSEE EVENT REPORT#
LER-280/
88-032 LER-280/
88-034 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 CAUSE & CORRECTIVE ACTION 'IO D
'C II 0
- a.
D
~o E
0 PREVENT RECURRENCE D
0 Unit reduced to 87% 720 MWE to repair isolated phase bus duct grounding straps.
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 1 - Same Source
- ~
l
-II NO.
DATE
- 0.
I-88-19 09-09-88 s
1 F: Forced 2
S:
Scheduled (9/77)
PAGE 4 I
UNI'I SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-281 UNI'I NAME si.u:ri llnit tJ.
~
DATE 10/04/88 COMPLETED BY L.A. Warren REPORT MONTH September 1988 TELEPHONE 804-357-3184 C
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LICENSEE E ::r C
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.. 'tJ CAUSE & CORRECTIVE ACTION 'IO m
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1, 3 LER-281/
Unit shutdown for refueling outage. Automat Reason:
A - Equipment Failure (Explain)
B - Maintenance or 'Iest C - Refueling D - Regulatory Restriction 88-022 E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain) 3 Reactor trip at 4% reactor power.
Method:
1 - Manual 2 - Manual Sc.ram.
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
MONTH September 1988
- e e
AVERAGE DAILY UNIT POWER LEVEL DOCKET No........,.5'""'0""--=2"""8 o;:,.,,-.,..-.,,.....,....-
UNIT Surry Unit # 1 DATE 10/04/88 COMPLETED BY L. A. warren TELEPHONE 804-357-3184 PAGE 5 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 769 17 0
2 769 18 0
3 769 19 0
4 769 20 0
'5 770 21 0
6 772 22 0
7 765 23 0
8 775 24 0
9 774 25 0
10 772 26 0
11 768 27 0
12 769 28 0
l'3 770 29 0
14 329 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)
MONTH e
PAGE 6 e
AVERAGE DAILY UNIT POWER LEVEL Sentember 1988 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 509 2
519
'3 507 4
497 5
490 6
491 7
489 8
464 9
444 10 119 11 0
12 0
l'3 0
14 0
15 0
16 0
INSTRUCTIONS DOCKEl' NO.
50-281 UNI l' Surry Unit # 2 DATE 10/04/88 COMPLETED BY L. A. warren TELEPHONE 804-357-3184 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 17 18 19 20 21 22 2'3 24 25 26 27 28 29
'30
'31 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)
PAGE 7 e
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR
- SEPTEMBER 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 09-01-88 0000 09-07-88
- 1513 1550 1712 1803 09-13-88 2341 09-14-88 0536 This reporting period begins with the unit at 100% 805 MWE.
Commenced power reduction at 150 MW /hr to permit repairs to isolated phase bus duct grounding straps.
Holding power at 87% 720 MWE.
Commenced power increase at 150 MWE/hr.
Unit at 100% 805 MW.
Commenced power reduction at 150 MW /hr for unit shutdown due to Emergency Diesel Generator operability concerns. Entered Emergency Plan, NOUE.
Unit off the line.
0610 Performed manual reactor trip.
09-15-88 0552 09-30-88 2400 UNIT TWO 09-01-88 0000 0536 0800 09-09-88 2147 09-10-88 0154 0158 09-11-88 0425 09-30-88 2400 Unit at CSD, secured from Emergency Plan, NOUE.
This reporting period ends with the unit at CSD.
This reporting period begins with the unit at 70% 490 MWE due to 3B feedwater heater being out of service, 'C' waterbox removed from service and EOL coastdown in progress.
Commenced power increase at 1 %/hr.
Holding power at 72% 545 MWE.
Commenced power reduction at 150 MW /hr for unit shutdown for refueling outage.
Unit off the line.
Reactor trip due to turbine trip from first stage impulse pressure spike at 4% reactor power.
Unit at CSD.
This reporting period ends with the unit at CSD for refueling outage.
F AC,TY CHANGES REQUIRING NRC A.ROVAL PAGE 8 MONTH/YEAR SEPTEMBER 1988 NONE DURING TIIlS PERIOD
e e
PAGE 9 FACIUTY CHANGES'THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR SEPTEMBER 1988 SCAFFOLD REQUEST 09/02/88 Erection of temporary scaffolding located in Unit 2 safeguards to work NRV-MS-201A/B/C.
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 09/06/88 Erection of temporary scaffolding located in the Unit 1 Turbine Building Basement to work piping for bowser.
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 S2-88-0906 ADMINISTRATIVE CONTROL 09/06/88 Administrative control will be maintained while the charging pump component cooling pump drain valve is open to feed and to bleed the system to increase chromate concentration; an operator will be stationed at the drain valve to close it immediately should the head tank level drop to~ 30%.
Feeding and bleeding the charging pump component cooling system by opening its pump's drain valve will not affect the operability of the charging system. It will enhance corrosion control by the addition of chromates. Therefore, this change does not constitute an unreviewed safety question.
SCAFFOLD REQUEST 09/08/88 Erection of temporary scaffolding located in Unit 2 Safeguards to work IS! Inspections for NOE.
Installation of this temporary scaffolding was reviewed accident analyses and equipment operability/function.
that assumptions, bases and probabilities of accident equipment malfunctions are not affected.
for effect on Conclusion is analyses and
e e
PAGE 10 FACIUTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR SEPTEMBER 1988 TM S2-88-069 TEMPORARY MODIFICATION 09/09/88 This modification removed check valve internals from 2-BD-558 and installed adapter and jumper hose to Condensate Polishing waste neutralization or low conductivity sumps.
The steam generators will be at atmospheric pressure during implementation of this jumper. Therefore, the probability of a steam generator tube rupture is not credible. If leakage on the jumper should occur, the release can be terminated immediately by securing the R & T pump. Therefore, no unreviewed safety question exists.
AC Sl-88-0911 ADMINISTRATIVE CONTROL 09/10/88 Administrative control will be maintained at the emergency switchgear room door while it is temporarily removed by establishing flood watch at the door and turbine building pit areas. The dike will be reinstalled in the event of a flood.
The removal of this dike will not adversely affect any safety related equipment, therefore does not create an. unreviewed safety question.
AC S2-88-0909 ADMINISTRATIVE CONTROL 09/10/88 Valve 2-CC-104, manual isolation valve downstream of TV-CC-209A will be used while under administrative control in accordance with SUADM-0-026 to ensure containment integrity.
Administrative control of 2-CC-l 04 does not constitute an unreviewed safety question, since it will ensure that containment integrity is maintained.
SCAFFOLD REQUEST 09/12/88 Erection of temporary scaffolding located in Unit 2
- Safeguards to work DC-86-14 in the vicinity of Auxiliary Feedwater pumps.
Installation of this temporary scaffolding was reviewed accident analyses and equipment operability/function.
that assumptions, bases and probabilities of accident equipment malfunctions are not affected.
Scaffolding before exceeding 350°, 450 psig 'in.reactor coolant system.
SCAFFOLD REQUEST for effect on Conclusion is analyses and was removed 09/12/88 Erection of temporary scaffolding located in Auxiliary Building 2' level
'A' charging pump cubicle to work MOVATS testing.
Installation of this temporary scaffolding was reviewed accident analyses and equipment operability/function.
that assumptions, bases and probabilities of accident equipment malfunctions are not affected.
for effect on Conclusion is analyses and
e e
PAGE 11 FACILlTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR SEPTEMBER 1988 SCAFFOLD REQUEST 09/12/88 Erection of temporary scaffolding located in Auxiliary Building 2' level 1B1 charging pump cubicle to work MOV tests and inspection.
Installation of this temporary scaffolding was reviewed accident analyses and equipment operability /function.
that assumptions, bases and probabilities of accident equipment malfunctions are not affected.
SCAFFOLD REQUEST for effect on Conclusion is analyses and 09/12/88 Erection of temporary scaffolding located in Unit 2 Containment Basement to work !SI Inspections for NOE in vicinity of RHR, SI and CH 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. Scaffolding is to be removed prior to exceeding 200°F in Reactor Coolant System.
SCAFFOLD REQUEST 09/12/88 Erection of temporary scaffolding located in Unit 2 Containment 1B1 loop room to work !SI inspection in the vicinity of RHR 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. Scaffolding to be removed before reactor coolant system exceeds 200°F.
SCAFFOLD REQUEST 09/12/88 Erection of temporary scaffolding located in Unit 2 Containment 316 11 elevation to work !SI inspections in vicinity of RHR suction piping from loop.
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. Scaffolding will be removed prior to reactor coolant system> 200°F.
PAGE 12 e
e FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR SEPTEMBER 1988 SCAFFOLD REQUEST 09/12/88 Erection of temporary scaffolding located in Unit 2 containment to work IS! inspection in the vicinity of RHR 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 maifunctions are not affected. Scaffolding to be removed prior to reactor coolant system exceeding 200°F.
SCAFFOLD REQUEST 09/12/88 Erection of temporary scaffolding located in the Unit 2 containment RHR flats to work IS! inspections in the vicinity of both RHR pumps and associated 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. Scaffolding will be removed prior to reactor coolant system >200°F.
AC-Sl-88-0912 ADMINISTRATIVE CONTROL 09/12/88 Administrative control is required to close the door between the emergency switchgear room and the turbine building when necessary.
The door is blocked open to allow access for an exhaust duct for maintenance work.
The design basis accident was reviewed and it was determined that the emergency switchgear door will be closed by the dedicated continuous fire watch when the control room is required to be pressurized.
Therefore, no unreviewed safety question exist.
TM-S2-88-075 TEMPORARY MODIFICATION 09/12/88 This change installed pressure gauges on 2-RH-38/39 and the suction lines for 2-RH-P-lA/lB while performing 2-PT-30.1.
Since the probability of the temporary fittings and/or gauges chance of failing is minimum, the bases, assumptions and probabilities of accident analyses and equipment malfunctions are not affected.
EWR-88-039 EWR-88-296 e
e FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR ENGINEERING WORK REQUEST PAGE 13 09/12/88 This request was to document that the auxiliary feedwater control switch lights (green, amber, red) would extinguish with the switch in "pull-to-lock" position. A white light (added above the red light) would illuminate when the pump breaker was in the "connected" position and the breaker closing control power was available.*
The added white light enhances operator's awareness of the breaker status.
Changing to lights extinguishing on "pull-to-lock" complies with human factors concerns.
There is no other effect on plant operation. Therefore, no unreviewed safety question exists **
ENGINEERING WORK REQUEST 09/12/88 This request was to evaluate operation with the emergency diesel generators (EDG) main air intake louvers failed open.
This change does not affect the operation of the EDGs because the louvers are open while they are in operation. Leaving the louvers open will help to enhance air displacement (in the event of a fire) if the carbon dioxide system is actuated. Therefore, an unreviewed safety question does not exist.
TM-Sl-88-136 TEMPORARY MODIFICATION 09/14/88 This change removed the check valve internals from 1-BD-558 and installed adaptor and jumper hose to condensate polishing waste neutralization or low conductivity sumps.
The steam generators will be at atmospheric pressure during implementation.
The probability of a steam generator tube rupture is not credible. If leakage on the jumper should occur the release can be terminated immediately by securing the RT pump. Therefore no unreviewed safety question exists.
TM-S2-88-082 TEMPORARY MODIFICATION 09/19/88 This change installed a flexible hose from 2-DG-74 to 2-CH-443. In
- addition, valves MOV-2381, 2-DG-TV-208B, HCV-2522A/B/C and HCV-2523 were closed.
Installation of a hose allowing the primary drains tank to be pumped to the volume control tank was reviewed for effect on accident analyses and equipment operability/function.
Conclusion is that assumption_s, bases and probabiliti~s of accident analyses* and equipment malfunctions are not affected.
e e
PAGE 14 FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR SEPTEMBER 1988 TM-Sl-88-141 TEMPORARY MODIFICATION 09/19/88 This change installed pressure gauges on l-RH-38/39 and the suction lines for 1-RH-P-lA/lB while performing l-PT-30.1 Since the probability of the temporary fittings and/or gauges chance of failing is minimum, the bases, assumptions and probabilities of accident analyses and.equipment malfunctions are not affected.
TM-S2-88-084 TEMPORARY MODIFICATION 09/22/88 This change blocked open the pressurizer power operated relief valves (PORVs) prior to initiation of maintenance to ensure that overpressure protection is available.
Technical specification 3.1.G requires a relief path equivalent to one open PORV. This change ensures two relief paths, one through each PORV and therefore, provides adequate overpressure protection. No unreviewed safety question is created.
TM-S2-88-087 TEMPORARY MODIFICATION 09/24/88 This change removed the PORVs for the pressurizer and a piece of one-eighth inch garlock gasket material will be placed over the PORVs flanges using four of the eight bolts to hand tighten. The gasket of material will not hold pressure but will keep dirt out of the pressurizer PORV lines.
With the PORVs removed at cold shutdown, a pressure relief path is assured. The material placed over the valve flange will not interfere With the relief flow thru the lines. Therefore, no unreviewed safety question is created.
TM-S2-88-088 TEMPORARY MODIFICATION 09/24/88 The safety valves
- for the pressurizer will be removed and a piece of one-eighth inch garlock gasket material will be placed over the three safety valve flanges using four of the eight bolts hand tightened. The gasket material will not hold pressure but will keep dirt out of the safety valve lines.
With the safety valves removed at cold shutdown, a pressure relief path is assured. The material placed over the valve flange will not interfere with the relief flow thru the lines. Therefore, no unreviewed safety question is created.
e e
PAGE 15 FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR SEPTEMBER 1988 TM-S2-88-089 TEMPORARY MODIFICATION 09/25/88 This change was to defeat the automatic reactor trips by jumpering out relays affecting the closed reactor trip breakers. While the change is in effect all power to control and shutdown rods will be physically disconnected and the rods will be fully inserted.
While this temporary modification is in effect the reactor will remain at cold shutdown with all rods inserted and all sources of power to the rod drive mechanisms removed. Reactor trip breakers shall be opened each night upon completion of the work.
No method exists for uncontrolled rod withdrawal with all power removed from rod drive mechanisms.
Therefore, there is no possibility of this accident and an unreviewed safety question is not created.
FS-88-055
. EWR-88-319 e
e PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR SEPTEMBER 1988 FINAL SAFETY ANALYSIS REPORT PAGE 16 09/06/88 This revision to section 9.9 is a general revision to clarify and update the data within the UFSAR with present operational and design information.
This review determined that no unreviewed safety question exists since this revision has not altered the basic function of the affected systems.
ENGINEERING WORK REQUEST 09/12/88 This request justified the operation of Surry Unit 2 with RV-2209 in an untested condition per ASME XI.
No unreviewed safety question exists as calculations have been performed which show even if the relief valve does not lift and piping pressurization occurs. No unsafe malfunction of equipment will occur.
r:....---=---=--~ ----- ~-
If'.,
I e
e PROCEDURE OR METHOD OF OPERATION THAT DID REQUIRE NRC APPROVAL MONTH/YEAR SEPTEMBER 1988 NONE DURING TlllS PERIOD PAGE 17
PAGE 18 TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR SEPTEMBER 1988 NONE DURING TIIlS PERIOD
2-ST-214 PAGE 19 e
e TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR SEPTEMBER 1988 SPECIAL TEST 09/14/88 This change was to test the main steam safety valves at power using Furmanite Trevitest equipment.
During this test, valves will be tested individually and setpoints will be adjusted as necessary. The worst case scenario analyzed in the FSAR is for single valve f allure full open. Since the valves-disks will only be lifted breifly and individually, an unreviewed safety question does not exist.
---=-=---
---=--=--= -
---=---- =---
VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT e
e PAGE 20 19 88 SEPTEMBER PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2
- ANALYSIS MAX.
MIN.
AVG.
MAX.
MIH.
. AVG.
Gross Radioact ** ~Ci/ml
- 1. 07E 0 2.86E-2
- 1. 92E-l
- 1. 52E-l.ooE-2 2.93E-2 Suspended Solids. DDD o.o o.o o.o o.o o.o o.o Gros* Tritium. ~Ci/ml 2.89E-l 2.52E-l 2.71E-l 6.54E-2 6.54E-2 6.54E-2 131 Iodine
, uCi/ml
- 1. 45E 0
3.75E-4 7.81E-2 2.56E-=3 5.nE-5 3.82E-4 1131 / 11'Jl 0.62 0.07 0.49 0.14 0.07 0.10 Hydrogen, cc/k&
BO.O 3.6
- 11. 2 1.0 3.7
~0.7 Lithium, ppm 2.28 2.16 2.22 0.45 0.39 0.42 Boron-IO, ppm*
366.1 177.6 273.0 387.0 0.5 204.3 Oxygen, (DO), PPlll 3.0
<0.005
- 1. 1 4.0 0.005
- 1. 7 Chloride, ppm 0.011 0.002 0.008 0.011 0.001 0.005 pH@ 2~ degree Cel1iua 6.54 5.58 6.07 8.43 4.73 6.23
- Boron-10
- Total Boron X 0.196 UNIT 1:
Started the month at 100%. On 9/3, normal sampling indicated a large increase in the iodine dose equivalent and the iodine ratio. On 9/7, the unit was ramped down 10% due to a problem with the main generator, but was back to 100% later that day. On 9/14, the unit was ramped down to cold shutdown. On 9/14 at 0720 the iodine dose equivalent was greater than 1.0 µCi/ml and stayed above 1.0 until 1605.
The month ended at CSD. No 1iOH was added. Hydrogen peroxide was added on 9/21 at 1140, 121; 9/22 at 0305, 41; 9/22 at 1345, 81; 9/23 at 1415, 81; 9/25 at 0425, 81; 9/28 at 2115, 41; 9/29 at 2300, 41. Total of 48 liters (12 gallons).
UNIT 2:
Started the month at 70%.
On 9/9, started ramp down to CSD for maintenance/refueling outage. Flushed 1B1 mixed bed and put in service on 9/12 at 2143.
The effluent sodium concentration was too high and 'B' mixed bed was taken out of service on 9/13 at 0245. 'A' mixed bed was put back in service. 95 gms of LiOh was added on 9/3 at 2030. Hydrogen peroxide was added on 9/12 at 2305, 121; 9/13 at 1450, 41; 9/14 at 0100, 41; 9/16 at 1510, 41; 9/16 at 2300, 41. Total 28 liters(? gallons). On 9/25 at 2205, letdown flow through the mixed bed was taken out of service for maintenance.
Ended the month in CSD/refueling.
.. ~.
CASTOR V /21 #009 e
PAGE 21 UNIT I
FUEL HANDLING DATE SEPT. 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPIN(
SHIPMENT II RECEIVED PER SHIPMENT II II ENRICHMENT CASK ACTIVITY LEVEL N/A N/A N/A Pl8 N/A 3.11 N/A N/A N/A N/A Pl9 N/A 3.11 N/A N/A N/A N/A P21 N/A 3.11 N/A N/A N/A N/A P31 N/A 3.11 N/A N/A N/A N/A P32 N/A 3.11 N/A N/A N/A N/A P33 N/A 3.11 N/A N/A N/A N/A P34 N/A 3.11 N/A N/A N/A N/A P35 N/A 3.11 N/A N/A N/A N/A P36 N/A 3.11 N/A N/A N/A N/A P37 N/A 3.11 N/A N/A N/A N/A P38 N/A 3.11 N/A N/A N/A N/A P40 N/A 3.11 N/A N/A N/A N/A P42 N/A 3.11 N/A N/A N/A N/A P4"3 N/A 3.11 N/A N/A N/A N/A P44 N/A 3.11 N/A N/A N/A N/A P45 N/A 3.11 N/A N/A N/A N/A P46 N/A 3.11 N/A N/A N/A N/A P47 N/A 3.11 N/A N/A N/A N/A P48 N/A 3.11 N/A N/A N/A N/A P49 N/A 3.11 N/A N/A N/A N/A P52 N/A 3.11 N/A CASK LOADED & TESTED BUT NOT SENT TO ISFSI
PAGE 22
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e-UNIT 2
FUEL HANDLING DATE SEPT. 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPIN(
SHIPMENT II RECEIVED PER SHIPMENT II II ENRICHMENT CASK ACTIVITY LEVEL NONE DU RING TIIlS P ERIOD
~*
I e
PAGE 23 DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME UMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR SEPTEMBER 1988 NONE DURING THIS PERIOD
e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 14, 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.88-690 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 September 1988.
W. R. Cartwrigh 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