ML18153B863
| ML18153B863 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/31/1989 |
| From: | Stewart W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8908230357 | |
| Download: ML18153B863 (25) | |
Text
,
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 August 15, 1989 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 No.
NO/RPC:vlh Docket Nos.
License Nos.89-608 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 July 1989.
Very truly yours,
~L~
W. L. Stewart Senior Vice President - Power 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
- 9(>:::2:~:(>::.::57 PDl=i:
ADOCK R
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VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 89-07 APPROVED: i))~
ATIONMANAGE POW 34-04
SECTION Operating Data Report - Unit No. 1 Operating Data Report - Unit No. 2 i
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 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
9 10 11 16 17 18 19 20 21 21 22
-~---
e PAGE 1 OPERATING DATA RKPOR7 DOCKET NO.
50-280 DATE 08/03/89 COMPLETED BY L. A. warren TELEPHONE 804-357-3184 x355 OPERATING STATUS
- 1. Unit Name:
Surry Unit 1 Notes
- 2. Reporting Period:
July 1, 1989 thru July 31, 1989
- 3. Licensed Thermal Power (MWt):
2441
- 4. Nameplate Rating (Gross MWe):
847.5
- 5. Design Electrical Rating (Net MWe):
788
- 6.
Maximum Dependable Capacity (Gross MWe):
820
- 7.
Maximum Dependable Capacity (Net MWe):
781
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Titrough 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month Yr. -to-Date
- 11. Hours In Reporting Period 744.0 5087.0
- 12. Number of Hours Reactor Was Critical 62~.Q 62~.Q
- 13. Reactor Reserve Shutdown Hours 0
0
- 14. Hours Generator On-Line 572. 7 5zz.z
- 15. Unit Reserve Shutdown Hours 0
0 16 *. Gross Thermal Energy Generated (MWH) 1176228;0 1176228:o ~
- 17. Gross Electrical Energy Generated (MWH) 380270.0 380270.0
- 18. Net Electrical Energy-Generated (MWH) 357588.0 357588.0
- 19. Unit Service Factor 77%
11.3%
- 20.
Unit Available Factor 77%
11.3%
- 21.
Unit Capacity Factor (Using MDC Net) 61.5%
9%
- 22.
Unit Capacity Factor (Using DER Net) 61%
8.9%
- 23.
Uoit Forced Rate 23%
88.7%
- 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Forecast Cumulative 145583.0 8SJQ2.6 3774.5 BZlZ8.J 3736.2 202347495.0 65583943.0 62197991.0
.59.9%
62.4%
55.2%
54.2%
22.3%
Achieved (9/77)
e PAGE 2 DOCKET NO. _..,.,,50.._-_.2=8=1 ____ _
DATE ___ o
... a...,... a.... a....,a... 9..._ __
COMPLETED BY L. A. Warren TELEPHONE 804-357-3184 x355 OPERATING STATUS
- 1. Unit Name:
Surry Unit 2 Notes
- 2. Report fog Period:
July O 1,89 thm July 31, I 989
- 3. Licensed Thermal Power (MWt):
2441
- 4. Nameplate Rating (Gross MWe): ---=9,....,4""'7,..._5------
S.
Design Electrical Rating (Net MWe):
788
- 6.
Maximum Dependable Capacity (Gross MWe):
820
- 7.
Maximum Dependable Capacity (Net MWe):
781
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9.
Pow:er Level To Which Restricted, If Any '(Net MWe):
- 10. Reasons For Restrictions, If Any:
ll.
- 12.
- 13.
- 14.
- 15.
- 16.
17 *.
- 18.
- 19.
- 20.
- 21.
- 22.
Hours In Reporting Period Number of Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thennal Energy Generated (MWH)
Gross Electrical Energy Generated (MWB)
Net Electrical Energy-Generated (MWH)
Unit Service Factor Unit Available Factor Unit Capacity Factor (Using MDC Net)
Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Rate Thia Month 744.0 0
0 0
0 0
0 Yr.-to-Date 5087.0 0
0 0
0
- 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling Outage on 09/10/88, schedule on line date of 08/2 6/89,
- 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 142463,0 89694.3 328 I 1 88293.0 206740436.1 67136244,0 63647378.0 62%
62%
57,3%
- 56. 7%
15%
Achieved (9/77)
NO.
DA'.rE
- 0.
I-c~10:...3 07/01/89 F
C-11-1 07/09/89 F
07 /13/89 s
l F:
Forced 2
S:
Scheduled (9/77)
UNI'.r SHU'IDOWNS AND POWER REDUC'tIONS DOCKE'r NO *.;......;;5..;;0...;-2;;.;8;..;0;._. _____ _
UNI'.[ NAME _ _.s""u"'rrv~...:Ii.r.l.uD.1.1Ui......l;:;._ ___ _
DA'.rE -~0~8/~0:.::.3i.:[8~9;.._,, ____..;...__..
REPOR'.l Hmml __
0_8 __
/0_3..;./_8_9 __ _
C<l4PLE'IED BY _.:L;:a,..1Au.,&....1,;WL,loarrM.,11!,e"'o------
TELEPHONE _,::.80~4:..-~3,::.5 7:..-~3~18~4..i,.x3w.i5"-ll5'--
C DI 0
0 -
N 0
C c'
u 0
'U...
0 D
- 0 z
z:
~ a:
.. :c a:
l z:
~
Q m
0 Q
149.0 F
1 22.3 G
3 0
B 4
- f Reasona A - Equipment Failure (Explain)
- B - Maintenance or test C - Refueling D - Regulatory Restriction LICENSEE EVEN'.t REPOJll: #
LER-280/
88-032 LER-280/
89-026 E - Operator training 6s License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain) 3 E,:r C....
a D
C *
.. 'U 0
'U CAUSE 6s CORREC'IIVE AC'l:ION '.IO 0
- 0. 0
- u E U PREVEN'I RECtJJUWr.r 0 u EK DG Unit shutdown on 09/14/88 due to emergency diesel gener9tor operability concerns.
JB FCV Steam generator high water level automatic scram which occurred during unit transient with manual feedwater control.
JB FCV Unit power reduction to allow maintenance on feedwater regulating valve.
Hethoda 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 - Saae Source e
NO.
- a.
I-C-9-6 07/01/89 s
1 F: Forced 2
S:
Scheduled (9/77)
PAGE 4-
.,,,;:~...
UNI'I SHU'IDOWNS AND POWER. REDUC'IIONS DOClCE'I NO.
I 50-281 UNl'I NAME Surry JJoU 2 DAn 08/03/89
<DIPLE'IED BY L.A. Warren TELEPHONE 804-357-3184 x355 REPOR'.t HON'Ill --~J_U_L_Y_I 9_8_9_
L C
DI a a -
NC, a
C u
a "D - *
!I a.. *
.. a J:
!I a:
!I %
.. J:
C...
a:
l CD !i a
C 744.0 C
1,3
.'(
Reason1 A - Equipment Failure (Explain)
- B - Maintenance or Teat C - Refueling D - Regulatory Restriction LICENSEE EVEN'I REPOR'.t I LER-281/
88-022 E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)
H - Other (Explain) 3 E "'
C.
e II C
.. "D a
"D a
- a. a
- o E
0 PREVEN'I RECURR!NI a
CJ
. Unit shutdown for refueling outage; automatic reactor trip.
Method:
1 - Manual 2 - Manual Scram.
3 - Automatic Scram.
I+ - Other (Explain)
I+
5 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG 0161)
Exhibit l - Same Source e
e
e PAGE 5 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-280
--,,~-=.::.,;__ ___
UNIT Surry Unit 1 DATE 08/03/89 COMPLETED BY L. A. Warren MONTH.
JULY 1989 TELEPHONE 804-357-3184 x355 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 770 2
0 18 770 3
0 19 766 4
0 20 764 5
0 21 760 6
0 22 751 7.
148 23 741 8
308 24 758 9
397 25 750 10 269 26 736 11 444 27 762 12 460 28 762 13 454 29 764 14 83 30 770 15 553 31 771 16 759 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)
I, PAGE 6 AVERAGE DAILY UNIT POWER LEVEL MONTH.
JULY 1989 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 2
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 UN IT Surry Unit 2
DATE 08/03/89 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 On this format, list the average daily unit power level in MWe-Net for each day in the reporting mon.th.
Compute to the nearest whole megawatt.
(9/77)
I, e
e PAGE 7
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR JULY 1989 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 07/01/89 0000 07 /02/89 2220 07 /05/89 0647 07 /07 /89 0505 0604 07 /08/89 0233 0720 0932 1603 07 /09/89 0120 0153 0643 2352 07/10/89 0502 0533 0944 1750 2218 07/11/89 0800 This reporting period begins with the unit at RCS> 200°.
RCS> 350°.
Reactor Critical.
Unit on line.
Stop ramp, 30% power, 190 MW.
Start ramp up, 30% power, 175 MW.
Stop ramp, 45% power, 290 MW (Pol. Bldg. delta pressure).
Start ramp up, 45% power, 290 MW (Pol. Bldg. delta pressure).
Stop ramp, 66% power, 440 MW (FCV-1488 and flux map).
Start ramp down, 66% power, 440 MW (Cond. Pol. strainer cleaning).
Stop ramp, 63%. power.
Reactor trip, 'B' S/G hi level, Instrument technicians grounded N-41 during PT-1.2 and CAL 0630 causing transient leading to trip.
Reactor critical.
Unit on line.
Stop ramp, 29% power, 185 MW.
Start ramp up.
Stop ramp, 60% power, 400 MW.
Start ramp up, 60% power, 400 MW.
68% power, 500 MW (no ramp in progress).
~---=---
~'
~MARY OF OPERATING EXPERIEIE PAGE 8 MONTH/YEAR JULY 1989 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 07 /13/89 2207 2239 2255 2327 2343 2349 07 /14/89 0034 0127 0204 0310 2130 2207 07/15/89 0048 0122 0127 0202 0250 0339 0600 0840 1007 1813 (CONT'D)
Start ramp down, 65% power, 490 MW (FCV-1488 repair).
Stop ramp, 60%, 430 MW (starting 1-FW-P-lB).
Start ramp down, 60%, 430 MW.
Stop ramp, 50% power, 340 MW (feed pump manipulations).
Start ramp down, 50% power, 340 MW.
Stop ramp, 49% power, 315 MW (shift turnover)
Start ramp down, 49% power, 315 MW.
Stop ramp, 34% power, 200 MW.
Start ramp down.
Stop ramp, 18% power, 80 MW.
Start ramp up, 20% power, 80 MW (FCV-1488 repair complete).
Stop ramp, 30% power, 160 MW.
Start ramp up, 30% power, 160 MW.
Stop ramp, 38% power, 250 MW (open MOV-ES-100).
Start ramp up.
Stop ramp, 48% power, 335 MW (feed pumps).
Start ramp up.
Stop ramp, 60% power, 485 MW (preparation to start second feed pump).
Start ramp up, 60% power, 440 MW.
Stop ramp, 70% power (PT-35).
Start ramp up, 70% power, 575 MW.
Stop ramp, 95% power, 760 MW.
.MMARY OF OPERATING EXPERI.CE MONTH/YEAR __
..:...J...:..U-=L=Y-'l::...c9_8...c...9 __
PAGE 9 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 (CONT'D}
07/16/89 0203 Start ramp up, 95% power, 760 MW.
0405 Stop ramp, 100% power, 805 MW.
07 /22/89 2307 Start ramp down, 100% power, 800 MW (clean water box).
2350 Stop ramp, 93.5% power, 740 MW.
07 /23/89 0030 Stop ramp, 89% power, 690 MW.
0130 Start ramp, 89% power, 690 MW.
0145 Stop ramp, 85 % power, 670 MW.
0330 Start ramp up, 85% power, 695 MW.
0440 Stop ramp, 100% power, 810 MW.
07 /25/89 0228 Start ramp down, 100% power, 785 MW (clean waterbox).
0332 Stop ramp, 84% power, 650 MW.
Start ramp up, (waterbox not cleaned).
0444 Stop ramp, 100% power, 800 MW.
2315 Start ramp down to clean waterbox.
07 /26/89 0035 Stop ramp, 87% power, 700 MW.
0442 Start ramp up, 86% power, 690 MW.
0541 Stop ramp, 100% power, 790 MW.
07/31/89 2400 UNIT TWO 07/01 /89 0000 07 /31/89 2400 This reporting period ends with the Unit at 100%.
This reporting period begins with the Unit at CSD.
This reporting period ends with the Unit at CSD.
PAGE 10 F AGILITY CHANGES REQUIRING NRC APPROVAL MONTH/YEAR JULY 1989 NONE DURING THIS PERIOD
-~~-___,___:___~---:F:A:C::II=JT=Y--C: **
- G=ES=THAT DID NOT REQUIRE N-APPROVAL PAGE 11
(
DC-85-34 DC-87-25 DC-88-32 MONTH/YEAR
- JULY 1989
-~------
VITAL BUS EXPANSION UNIT 2 This modification replaced the station batteries and battery racks with larger capacity batteries installed in seismically designed racks and related inter-cell cabling.
In addition, the battery chargers, static inverters and regulating transformers were replaced with two uninterruptible power supplies (UPS) per 125V DC bus. Each UPS consists of a rectifier/charger inverter, static switch, manual bypass switch and regulating line conditioner in one complete unit.
SUMMARY
OF SAFETY ANALYSIS The new station batteries and UPS were designed, fabricated and installed to meet or exceed the requirement sections of the original Design Basis Documents.
The larger capacity batteries enhance the 125V DC bus system and the power supplies upgrade the 125V DC and 120V AC vital bus systems.
CONTROL ROOM INDICATOR REARRANGEMENT AND SCALE MODIFICATIONS -
UNIT 2
- This design change relocated specific temperature, pressure and level indicators on the control room control board so as to be functionally grouped. In addition, some level indicators had the scales changed to allow for more accurate readings.
These modifications were in accordance with human factors criteria.
SUMMARY
OF SAFETY ANALYSIS This modification relocates indicators on the vertical board and replaces indicator scales.
This design change does not alter the function or operations of existing safety related equipment or systems. Technical Specifications are not changed nor is the margin of safety as defined in the basis of any Technical Specification.
ADDITION OF DIESEL GENERATOR SEQUENCING -
UNIT 2 This modification adds an emergency diesel generator load sequencing scheme which will be initiated by a loss of offsight power condition.
This will ensure that the maximum EDG load capabilities will not be exceeded under the worst case load applications and therefore, resolve
- NRC concerns described in IE Information Notice 85-91.
~~=---------.
FACILITY CHANGES THAT DID NOT REQUIRE NRG APPROVAL PAGE 12
)
(
DC-88-32 DC-88-34 MONTH/YEAR --'-~J_U_L_Y_l_9_89 ____ _
(CONT'D)
SUMMARY
OF SAFETY ANALYSIS The load sequencing of specific loads onto the emergency buses will ensure that the maximum load capabilities of each EDG will not be exceeded and will ensure the availability of the systems necessary to mitigate the consequences of a design basis event. With the limiting equipment sequencing delays, the results of the applicable accident analysis will still meet their acceptance criteria. There will be no increase in the calculated dose consequences since the assumptions for the dose calculations will not be impacted.
The operation of safety-related equipment or systems, or the availability of safety-related power sources are not adversely affected.
CIRCULATING WATER CONDENSER WATERBOX AND LOW LEVEL DISCHARGE PIPE VACUUM BREAKERS -
UNITS I & 2 A passive element of the original piping design allowed the circulating water pump discharge line to break vacuum at a canal level of 18 feet.
With the new technical specification minimum canal level of 23 feet, a modification was installed to retain this passive feature. A vent hole in the circulating water discharge pipe located on the canal side of.
the berm at an elevation between 24 and 25 feet to ensure interruption of the siphon effect was installed. Breaking the vacuum on the condenser waterbox involved installation of pneumatically actuated butterfly valves on each of the four condenser waterboxes per unit. The valves have local and a remote means of actuation.
SUMMARY
OF SAFETY ANALYSIS The design change was implemented to conserve water in the intake canal. The circulating water discharge pipe passive vacuum breakers are required for the operation of service water system components during a design basis accident and have been evaluated for operability during all design basis events. The condenser waterbox vacuum breaker valves will minimize the loss of canal water inventory during an Appendix "R" fire if the condenser inlet and outlet isolation valves fail to close.
The safety limits, as defined in the Technical Specifications, are not changed as a result of this design change, nor is the margin of safety reduced.
SCAFFOLDING REQUEST 07/02/89 This request erected temporary scaffolding located in Unit 1 safeguards steam side to work 1A1 main steam trap lines. The scaffold will be erected in the vicinity of l-FW-P-2.
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
~~~~---'~~~~~--~~::--~~~~
PAGE 13 FACILITY,ANGES THAT DID NOT REQUIRE !c APPROVAL MONTH/YEAR JULY 1989 SCAFFOLDING REQUEST 07 /03/89 This request erected temporary scaffolding located in the Unit_ I safeguards steam side to work the torquing of main steam safety valves.
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.
2-EWR-88-417 ENGINEERING WORK REQUEST for effect on Conclusion is analyses and 07/03/89 This request installed a manual isolation valve between the cold leg sampling valves and the containment isolation trip valves.
The valve was installed for testing purposes only and does not affect the normal operation of the system.
2-EWR-88-418 ENGINEERING WORK REQUEST 07/03/89 This request installed a manual isolation valve between the hot leg sampling valves and the containment isolation trip valves.
The valve was installed for testing purposes only and does not affect the normal operation of the system.
1 &2-EWR-89-325 ENGINEERING WORK REQUEST 07/04/89 This request documented the change of the time delay relay setting of the Recirculation Mode Transfer (RMT), as well as changing the maximum permissible limits for the motor operated valves to ensure that the RMT time is consistent with the containment analysis.
The relay setpoint and administrative changes will not increase the probability of occurrence or consequences of an accident or the malfunction of equipment important to safety.
TM-S2-89-072 TEMPORARY MODIFICATION 07/12/89 The pressurizer relief valve block valve (MOV-RC-2535) shall be blocked open while its actuator is being worked and to fill the reactor coolant system.
Since the valve will be blocked open to ensure a vent path for the reactor coolant system while the unit is in cold shutdown, an unreviewed safety question is not created.
~--------
e e
PAGE 14 FACIIJTY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR JULY 1989 TM-S2-89-073 TEMPORARY MODIFICATION 07/13/89 The primary power operated relief valve (PORV), 2-RC-PCV-2455C will be blocked open using a split schedule 80 pipe with clamps attached to the valve stem.
Technical specification 3.1.G requires that two (2) PORVs be operable or provide a relief path equivalent to one PORV being open. This change will provide the required relief path thru an open PORV. The blocking device will be installed on only one PORV at *a time. Therefore, no unreviewed safety question is created.
TM-S2-89-07 4 TEMPORARY MODIFICATION 07/13/89 The primary power operated relief valve (PORV), 2-RC-PCV-2456, will be blocked open using a split schedule 80 pipe with clamps attached to the valve stem.
Technical specification 3.1.G requires that two (2) PORVs be operable or provide a relief path equivalent to one PORV being open. This change.
will provide the required relief path thru an open PORV. The blocking device will be installed on only one PORV at a time. Therefore, no unreviewed safety question is created.
TM-S2-89-075 TEMPORARY MODIFICATION 07/15/89 The primary power operated relief valve (2-RC-PCV-2455C) and block valve (2-RC-MOV-2536) were blocked open with 2-RC-PCV-2455C either operable or blocked open to provide an RCS low temperature overpressure relief path while performing maintenance on PORV and block valve.
Since 2-RC-MOV-2536 will be blocked open. and 2-RC-PCV-2455C will either be blocked open or operable, a low temperature overpressure relief path will be maintained. Therefore, an unreviewed safety question is not created.
TM-Sl-89-158 TEMPORARY MODIFICATION 07/24/89 This temporary modification wired
- open the exhaust damper for 1-VS-F-lB.
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.
~~--------~
e PAGE 15 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR __
__,,_J--=U-=L=-=Y'-=-'19'-=8=9 ____ _
TM-S2-89-087 TEMPORARY MODIFICATION 07/26/89 The pressurizer relief valve block valve MOV-RC-2536 will be blocked open to remove the valve actuator for maintenance. The blocking device will maintain the relief valve operable.
Since the block valve will be maintained open to ensure a vent path for the reactor coolant system while in cold shutdown, an unreviewed safety question is not created.
SCAFFOLDING REQUEST 07/27/89 This request erected temporary scaffolding located in Unit 2 safeguards steam side to work 02-MS-TV-201C.
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
PROCEDURE OR METHOD OF OPERATION CHANGES REQUIRING NRC APPROVAL MONTH/YEAR JULY 1989 NONE DURING THIS PERIOD PAGE 1-6
PROCEI *.
E OR METHOD OF OPERATION clANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR --=-J_U_L_Y_l_9_89 __
PAGE 17 1&2-0P-4.21/
PROCEDURE DEVIATION 07/11/89 I & 2-0P-4.23 This deviation to the cask transport procedure was to ensure that the transport vehicle remained a safe distance from the excavation site.
NE Technical Report No. 709, Rev 0, has been performed and has determined that is is acceptable to transport the cask on the road near the excavation site as long as the transport vehicle remains in the specified zone.
PAGE 18 TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR JULY 1989 NONE DURING THIS PERIOD
PAGE 19 TESTS AND EXPERIMENTS THAT DID NOT.REQUIRE NRG APPROVAL MONTH/YEAR JULY-1989 NONE DURING THIS PERIOD
PRIMARY COOLANT ANALYSIS MAX.
Gross Radioact., µCi/ml 6.56E-l Suspended Solids, ppm 0.0 Gross Tritium, µCi/ml
Il31 / Il33 0.18 Hydrogen, cc/kg 3'4.8 Lithium, ppm 2.38 Boron-10, ppm*
412.2 Oxygen, (DO), ppm 0.005 Chloride, ppm 0.012 pH@ 25 degree Celsius 6.63
- Boron-10 = Total Boron X 0.196 VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT JULY 19 89 UNIT NO. 1 MIN.
AVG.
MAX.
( 2) 3.77E-4 2.26E-l 4.75E-2 0.0 0.0 0.0 2.40E-2 7.61E-2 N/A
- 1. l 7E-5 1.81E-3 N/A 0.06
- 0. 11 N/A 22.1 29.7 18.4
- 1. 41 2.14 1.55 168.2 237.7 449.0 (1) 0.005 0.005 2.0 0.006 0.009 0.026 5.60 6.36 5.82 PAGE 20 UNIT NO. 2
- MIN, AVG.
9.29E-4
- 1. 27E-2 0.0 0.0 N/A N/A N/A N/A N/A N/A 3.9 9.6 0.15 1.16 416.5 427.3 (l) 0.005 0.40 0.010 0.017 4.98 5.25 UNIT ONE:
Lithium additions: 07 /05/89 at 0130 added 1100g of LiOH; at 0415 added 1150g of LiOH; on 07 /06/89 at 1110 added 400g of LiOH; on 07 /07 /89 at 1425 added 292g of LiOH; on 07/08/89 at 1500 added 293g of LiOH; on 07/10/89 at 0140 added 310g of LiOH, at 1340 added 324g of LiOH; on 07 /11/89 at 1050 added 373g of LiOH; on 07 /15/89 at 1355 added 421g of LiOH.
Total Li OH added was 4663 grams. Cat Bed Activity: on 07 /19/89 at 1200 Cat Bed in service; on 07/19/89 at 1412 Cat Bed out of service, on 07/27/89 at 0950.Cat Bed in Service, at 1119 Cat Bed out of service.
UNIT TWO: Lithium additions: on 07/23/89 at 1540 added 2150g of LiOH; on 07/24/89 at 0525 added 1050g of LiOH; on 07/26/89 at 2145 added 805g of LiOH. Total LiOH added was 4005 grams. Hydrazine additions: on 07 /22/89 at 1345 1.5 gallons of hydrazine added~ at 2325 a.dded 1 gallon of hydrazine; on 07/23/89 at 0715 added 0.75 gallons of hydrazine. Total hydrazine added was 3.25 gallons.
NOTE: (1) Unit at cold shutdown, dissolved oxygen specification not applicable:
(2) Gross activity increased due to initial start-up of Reactor Coolant Pumps.
I
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UNIT 1&2 FUEL HANDLING DATE JULY 1989 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 DUR NG THIS PE UOD
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PAGE 22
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DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR JULY 1989 NONE DURING THIS PERIOD