ML18152A482
| ML18152A482 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/28/1989 |
| From: | Cartwright W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 89-174, NUDOCS 8903220156 | |
| Download: ML18152A482 (23) | |
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,;.-**1t VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. R. CARTWRIGHT VxcE PRESIDENT NUCLEAR March 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 I AND 2 MONTHLY OPERATING REPORT Serial No.
NO/RPC:vlh Docket Nos.
License Nos.89-174 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units I and 2 for the month of February 1989.
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
e POW 34-04 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERA TING REPORT REPORT 89:-02 APPROVED:
SECTION
- Operating Data Report - Unit No. 1 Operating Data Report - Unit No. 2 1
Unit Shutdowns and Power Reductions - Unit No. 1 Unit Shutdowns and Power Reductions - Unit No. 2 Average Daily Unit Power Level - Unit No. 1 Average Daily Unit Power Level - Unit No. 2 Summary of Operating Experience - Unit No. 1 Summary of Operating Experience - Unit No. 2 Facility Changes Requiring NRC Approval Facility Changes That Did Not Require NRC Approval Procedure or Method of Operation Changes Requiring NRC Approval Procedure or Method of Operation Changes that Did Not Require NRC Approval Tests and Experiments Requiring NRC Approval Tests and Experiments That Did Not Require 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 :i.n Technical Specifications PAGE 1
2 3
4 5
6 7
7 8
9 14 15 16 17 18 19 19 20
PAGE 1 DOCKET NO.
50-280 DATE
-,0~3,..,./~06,,.../"""8..,,....9--
COMPLETED BY L. A. Warren TELEPHONE 804-357-3184 x355 OPERATING STAl'US
- l. Unit Name:
Surry Unit 1 Notes
- 2. Reporting Period: 02/01/89 thru 02/28/89
- 3. Licensed Thermal Power (HWt): ____ 2~4.... 4;..;I ____ _
- 4. Nameplate Rating (Gross HWe): __
8_4_7_.S ____ _
- 5. Design Electrical Rating (Net HWe):
788
- 6.
Maximum Dependable Capacity (Gross HWe):
--=8~2.::.0 __
- 7. Maximum Dependable Capacity (Net HWe):
781
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If Acy (Net HWe):
- 10. Reasons For Restrictions, If Any:
This Month ll. Hours In Reporting Period 672.0
- 12. Number of Hours Reactor Was Critical 0
.13. Reactor Reserve Shutdown Hours 0
- 14. Hours Generator On*Lirte 0
- 15. Unit Reserve Shutdown Hours 0
- 16. Gross Thermal Energy Generated (MWB) 0
- 17. Cross Electrical Energy Generated (MWB) 0
- 18. Net Electrical Energy-Generated (HWH) 0
- 19. Unit Service Factor 0
- 20. Unit Available Factor 0
- 21. Unit Capacity Factor (Using MDC Net) 0
- 22. Unit Capacity Factor {Using DER Net) 0
- 23. U~it Forced Rate 100%
Yr.*to*Date
~1416.0 0
0 Q
0 0
0 0
0 0
0 0
1QQ%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Cumulative 141912.0 88478.6 3774. 5 B66Q5.~
3736.2 2011ZlZ2Z.Q 65203673.0 61840403.0 61%
- 63. 7%
- 56.3%
55.3%
ZQ, 2%
Forced Maintenance Outage on 09/14/88 1 scheduled on line date of 05/15/89.
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to Canmercial Operatioo):
Forecast INmAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Achieved
!c I J
. ~tJ I
- i
PAGE 2 DOCKET NO. ~5....
0-_2;;.;;8... l--=---
DATE 03/06/89 COHPLE'!'ED BY L.A. warren
-==----=~"--
TELEPHONE 804-357-3184 x355 OPERA!ING STATUS
- 1. Unit Name:
Surry Unit 2 Notes
- 2. Reporting Period:
02/01/89 thru 02/28/89
- 3. Licensed Thermal Power (MWt):
2441
- 4. Nameplate Rating (Gross HWe): --e-4..... 1..... _-s ___ _
- 5. Design Electrical Rating {Net HWe):
788
- 6.
Maximum Dependable Capacity (Gross HWe):
820
- 7.
Maximum Dependable Capacity (Net HWe):
781
- 8. If Changes Occur in Capacity Ratings (Items Number 3 nirough 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If Any (Net HWe):
- 10. Reasons For Restrictions, If Any:
This Month Yr.-to-Date
- 11. Hours In Reporting Period 672.0 1416.0
- 12.
Number of Hours Reactor Was Critical 0
- 13. Reactor Reserve Shutdown Hours Q
- 14. Hours Generator On-Line 0
- 15. Unit Reserve Shutdown Hours 0
- 16. Gross lbennal Energy Generated (HWB) 0
- 17. Gross Electrical Energy Generated (MWB) 0
- 18. Net Electrical Energy-Generated (HWB) 0
- 19. Unit Service Factor 0
.20.
Unit Available Factor 0
- 21. Unit Capacity Factor (Using MDC Net) 0
- 22. Unit Capacity Factor (Using DER Net) 0
- 23. Unit Forced Rate 0
- 24. Shutdowns Scheduled Over Ne.xt 6 Months (Type, Date, and Duration of !ach)I Refueling Outage on 09/10/88 1 scheduled on line date of 06/07 /89.
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast INITIAL CRmCALITY INinAL ELECTRICITY COMMERCIAL OPERATION 0
0 0
0 0
0 0
0 0
0 0
0 I
j Cumulative 138792.0 89694.3 328.1 88293.0 u
206740436.1 67136244.0
- S~S~?~?B.O 6~.6%
63.6%
58.8%
- 58. 2%
15%
Achieved
l!IO.
Dill
. Q.,.....
89-02 02/01/89 F
1 F: Forced 2
SI Scheduled (9/77)
PAGE3 UNl'I SHU'IDOWNS AND POWER REDUC'IIONS DOCKE'I NO.
50-280 UNl'I NAME _.._,S,..u..,qy....,.... J.,.,J.un,1,11ti.....,il._'_....;;..-
DAn: _0_3...,/...
07._./ __ 8 __ 9 ___ _
alll'LE'IIDIY_~Lu,~A...,.,,~W~arr-..~e~n..__~
m.EPIIONE 804-357-3!94 x355 REPOR7 torIH February 1989 C
a, 0 0 -
N 0
C C
u 0
'U.. *
- I 0.. *
.t::.
- I a:
- I
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a...
a:
i ID
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8
(
672.0 F
l Jleaaooa A* Equipment Failure (Explain)
- B
- Maintenance or teat C
- Refueling D
- Reaulatory Reatriction LICENSEE EVl!N't REPORl: #
E
- Operator Training & License Examination P
- Adainiatrative
-G
- Operational Error (Explain) ff* Oth~r (Explain) 3 I!.
- c....
C *
.. 'U 0
'U CAUSE 6, COIUlEC'IlVE AC'tlON 'IO 0
Q.
0
- o E U PREVENt RECURREN't 0 u Unit Shutdown due to emergency diesel generator operability concerns.
Hethoda l
- Mawal 2
- Manual Scru.
3 - Autoaatic Scraa.
4 - Other (Explain)
Exhibit G
- lnatnactiona for Preparation of Data Entry Sbeeta for Licenaee Event Report CLER) File (NUREG 0161)
\\
Exhibit l
- Saae Source 5
e
II>.
DAD
- a.,..
t-89-02 02/0 l /89 s
l F: Forced 2
S: Scheduled (9/77)
.l:'Al:it; 4 llU'I 8Hl1.r00WNS AND POWU UDUC'IlONS DOCU'I NO.
50-281 UNl'I NAME _.. s.. v.. m
......... ll
...... o... U--=2... * ----
__ 2...,/....
07._./.,.8_9 ________._.
C<IIPLE'IED BY -*~L.... _.A....,.....
w1.1,arr
...... ;i,,,e,...n __ _
REPOR:r HOlffll February 1989 rELEPHONE.__,80... 4.... -,_35.. 7.... -...
3=-l 8..,4...,x~3&.lll5~5-C
.. Ill 0 0...
N 0
C C
... u 0
"O..
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- I ID !i 8
672.0 C
1,3 Reaaona A - Equipment Failure (Explain)
- B - Maintenance or Teat C
- Refueling D ~ Regulatory Re1triction LICENSEE EVEN't REPOR'I
- E - Operator Training lo License Examination F
- Adainiatrative G
- Operational Error (Explain)
H
- Other (Explain) 3 I!.
C.
I C *
.. "O 0
"O CAUSE lo CORREC'IIVE AC'tl<lt 'IO 0
- a.
0
~u I u PREVEtrt RECUIUU!ll't u
Unit shutdown for refueling outage, automatic reactor trip.
Method:
l - Manual 2 - Hanual Scram.
3 - Autoaatic Scraa.
4 - Other (Explain) 4 5
Exhibit G - lnatructioaa for Pl'eparation of Data Entry Sheets for Licenaee Event Report (LIil) File (lfl.1REG 0161)
~lblt l - Saae Source e
PAGE 5 AVERAGE DAILY UNIT POWER LEVEL MONTH
- February 1989 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 0
2 0
3 0
4 0
5 0
6 0
7 0
8 0
9 0
10 0
11 0
12 0
13 0
14 0
15 0
16 0
INSTRUCTIONS DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 DOCKET NO.
50-280
.....,.,.........;~,.,,,.....--=----
UNIT Surry Unit 1 DATE 02/07 /89 COMPLETED BY L. A. *:..' arren TELEPHONE 804-357-3184 x355 AVERAGE DAILY POWER LEVEL (MWe-Net) 0 0
0 0
0 0
0 0
0 0
0 0
On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
(9/77)
PAGE 6 AVERAGE DAILY UNIT POWER LEVEL MON~ *February 1989 DAY AVERAGE DAILY POWER LEVEL (MWe..:Net) 1 0
2 0
3 0
4 0
5 0
6 0
7.
0 8
0 9
0 10 0
11 0
12 0
13 0
14 0
15 0
16 0
INSTRUCTIONS DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 DOCKET NO.
50-281 UN IT Surry Unit 2 DATE 02/07 /89 COMPLETED BY L. A. *.,/ arren TELEPHONE 804-357-3184 x355 AVERAGE DAILY POWER LEVEL (MWe-Net) 0 0
0 0
0 0
0 0
0 0
0 0
On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
(9/77)
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SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR FEBRUARY 1989 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 02/01/89 02/04/89 02/08/89 02/28/89 UNIT TWO 02/01/89 02/04/89
- 02/28/89 0000 2345 2015 2400 0000 2345 2400 This period begins with the Unit at CSD.
ESF actuation due to loss of power to the 'F' transfer 4160V electrical bus. # 1 EDG auto started and loaded on unit 1 'H' bus and #3 EDG auto started and loaded on Unit.2 'J' bus.
ESF actuation (safety injection - train B) during system testing.
This reporting period ends with the Unit at CSD.
This reporting period begins with the Unit at CSD.
ESF actuation due to loss of power to the 'F' transfer 4160V electrical bus.
- 3 EDG started and loaded on the Unit 2 'J' emergency bus. The RHR pump was lost during this event and restarted at 2347 *
. This reporting period ends with the Unit at CSD.
F ACIIJTY CHANGES REQUIRING NRC APPROVAL MONTH/YEAR FEBRUARY 1989 NONE DURING THIS PERIOD PAGE 8
DC 87-24 l-TOP-2071 e
e PAGE 9 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR FEBRUARY 1989 CONTROL ROOM INDICATOR REARRANGEMENT AND SCALE MODIFICATIONS - UNIT I 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 de.sign change does not alter the function or operation of existing safety related equipment or systems.
Safety limits as defined in the Technical Specifications are not changed nor the margin of safety as defined in the basis of any Technical Specifications.
SCAFFOLDING REQUEST 02/01/89 This request erected scaffolding located in the mechanical equipment room #3 to work 01-VS-292 and 01-VS-YS-28.
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 OPERA TING PROCEDURE DEVIATION 02/04/89 If required, administrative control will be established on component cooling (CC) water heat exchangers' service water discharge valves and l-CC-100 (1-TV-CC-109B manual isolation).
This allows the use of 1.. cc.. 100 to maintain CC temperattire at greater than so°F should the reactor coolant system approach so°F.
Since administrative control of* the CC water heat exchangers' service water discharge valves and l-CC-100 will maintain the components in a fully operational status, an unreviewed safety question is not created.
SCAFFOLDING REQUEST 02/05/89 This request erected temporary scaffolding located in the emergency service water pump house to work 'C' emergency service water pump exhaust.
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.
I e
e PAGE 10 FACIUTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR FEBRUARY 1989 SCAFFOLDING REQUEST 02/07 /89 This request erected temporary scaffolding located in the # 3 mechanical equipment room to work on the removal of fan # 24 and install a blank plate.
Installation of this temporary scaffolding was reviewed
- for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
TM-Sl-89-031 TEMPORARY MODIFICATION 02/07/89 This modification installed a temporary air regulator to supply air to TV-CC-105B to open the valve if 'B' reactor coolant pump is required during the performance of ST-241. Administrative control of the valve will ensure its closure within thirty minutes if containment closure is required.
The jumper is required for ST-241 and will be removed _following the special test. In addition, the valve will be under administrative control in accordance with SUADM-0-026 if the valve is required to be opened and will be closed within thirty minutes should containment closure be required.
TM-Sl-89-035 TEMPORARY MODIFICATION 02/07/89 This temporary modification defeats 'B' train safety injection and refueling water storage tank cross tie valve operation in order to perform ST-241.
Since 1B1 train safety injection auto initiation and refueling water storage tank cross tie valve auto initiation is not required with the units in cold shutdown, an unreviewed safety question is not created.
TM-Sl-89-030 TEMPORARY MODIFICATION This temporary modification installed containment air recirculation fan intake to cleanup containment atmosphere maintenance.
02/08/89 pre-filter media on the for 1-VS-F-lA, IB, and IC following outage-related Air recirculation fans are not required to operate under design basis accident conditions. Furthermore, fans and filters will be monitored to ensure proper air flow from the fans. Filters shall be removed prior to exceeding 200°F; therefore, an unreviewed safety question is not created.
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PAGE 11 FACIUTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR FEBRUARY 1989 SCAFFOLDING REQUEST 02/11/89 This request erected temporary scaffolding located in the # 1 emergency switchgear room to work l-VS-AC-7.
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 REQUEST 02/11/89 This request erected temporary scaffolding located in the mechanical equipment room to work the chilled water check valve for l-VS-E-4C.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability /function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
TM-S2-89-015 TEMPORARY MODIFICATION 02/11/89 Temporary modification to install a pre-filter media on containment air recirculation fan intake for 2-VS-F-lA to cleanup the containment atmosphere following outage-related maintenance.
Air recirculation fans are not required to function under design basis accident conditions. Also the filter assemblies will be monitored to ensure proper air flow from the fans. Filters shall be removed prior to exceeding 200°F; therefore, an unreviewed safety question is not created.
SCAFFOLDING REQUEST 02/13/89 This request erected temporary scaffolding located. in mechanical equipment room #3 to work l-VS-P-2B.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion ts that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
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PAGE 12 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR FEBRUARY-1989 SCAFFOLDING REQUEST 02/13/89 This request erected temporary scaffolding located in Unit l
containment 316 11 elevation to work on spring cans for pressurizer to pressurizer relief tank 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.
AC-Sl-89-0215 ADMINISTRATIVE CONTROL 02/15/89 EWR-88-561 Administrative control will be established on VBl-1 circuit 16 when the breaker is opened to allow adjusting limits of 1-TV-SS-l O 1 A. The control is required to maintain l-TV-CC-109A operable.
Since administrative control of VB 1-1 circuit 16 is established, operability of l-TV-CC-109A is maintained and an unreviewed safety question is not created.
SCAFFOLDING REQUEST 02/21/89 This request erected temporary scaffolding located in emergency service water pump (ESWP) house to work hurricane shields on ESWP house dampers.
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 REQUEST 02/21/89 This request erected temporary scaffolding located in mechanical equipment room # 3 to work lift rig for l-VS-S-1 B strainers.
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 02/26/89 This Engineering Work Request placed in service a temporary diesel fuel storage and dispensing system while the permanent emergency service water fuel tank was taken out of service for maintenance.
The temporary tank was seismically installed, can be refilled on short notice, and does not change or affect the capability of the emergency service water pumps.
e PAGE 13 FACIIJTY CHANGES THAT DID NOT REQUIRE NRG APPROVAL EWR-88-440 MONTH/YEAR __
F_E_B_R_U_A_R_Y_l_9_8_9_
ENGINEERING WORK REQUEST 02/28/89 This Engineering Work Request added vent valves in high points of the safety injection piping to high pressure safety injection to vent gases.
The consequences or probability of a pipe break as a result of this modification are not increased. The vents are isolated and designed to the appropriate pipe class. Therefore, probability of failure is not increased above current design.
e e
PROCEDURE OR METHOD OF OPERATION CHANGES REQUIRING NRC APPROVAL MONTH/YEAR FEBRUARY 1989 NONE DURING THIS PERIOD PAGE 14
l-TOP-2074 e
e PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR FEBRUARY 1989 TEMPORARY OPERA TING PROCEDURE PAGE 15 02/10/89 This procedure allowed blending and disposal of resin for the TT! Nuclear Radwaste Facility transporter with temporary holdup of excess resin in the liquid waste ion exchanger.
The review analyzed the effects of the modification on liquid waste release.
- No adverse effects are caused by this modification. All liquid waste releases will be contained within the Decon building; therefore, no unreviewed safety question is created.
-- ------.-:----=--*
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PAGE 16 TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR FEBRUARY 1989 NONE DURING THIS PERIOD
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PAGE 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRG APPROVAL l/2-ST-228 MONTH/YEAR FEBRUARY 1989 SPECIAL TEST 02/26/89 This test ran through a test crank of the emergency service water pump diesel that was chosen for the test and will start the same pump to determine starting and running currents. This test will render the pump inoperable for short periods of time during this test.
This test was performed within the requirements of the associated justification for continued operation. Therefore, an unreviewed safety question was not created.
e PRIMARY COOLANT ANALYSIS Groll Radtoact ** 11Ci/ml Suspended Solids. PP*
Oros, Tr1Uu.. 11Ci/al Iodtn.-lll, 11Ci/11l 11Jl / l 133 Hydroaen. cc/b.
Lithiua. PP*
loron-10, ppm*
Oxygen. (00), Dl>II Chloride. PP*
pH f 2~ dearee Cel1iu1 e
VIRGINIA J>O'wEI SURRY PO\\IER STATION CHF.HlSTRY REPORT 19 --
UNIT NO. l MAX.
HIN.
AVG.
MAX.
2.76E-3 2.38E-4
- l. lOE-3 6.68E-2 0.0 0.0 0.0 o.u 0.75 0.70 0.73 424.7 412.6 417.6 441.4 0.005 0.005 0.005 3.0 0.011 0.007 0.008 0.025 5.93 5.15 5.25 5.03
- Joron-10
- Total Boron X 0.196 RD!ARXS:
PAGE 18 UNIT NO. 2 HIN.
AVG.
2.65E-~ 4.48:S-2 o.o 0.0 428.8 433.5 2.0 2.3 0.012 0.020
- 4. 72 4.87 UNIT ONE:
Unit was at cold shutdown for the entire month. Started month with RHR and 'B' mixed bed in service. On 2/8 at 2000, 'B' mixed bed removed from service for electrical bus inspection. 'B' mixed bed returned to service on 2/9 at 1945. On 2/10 gt 0220, 'B' mixed bed bypassed for maintenance. On 2/13 'B' mixed bed returned to service and remained in service for the rest of the month.
UNIT TWO:
Unit was at cold shutdown for the entire month. RHR was in service but letdown was tagged out for the entire month.
e PAGE 19 UNIT 1 & 2 FUEL HANDLING DATE FEB 1989 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT#
RECEIVED PER SHIPMENT fl ENRICHMENT CASK -ACTIVITY LEVEL NONE DUF ING THIS P ~RIOD
e DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR __
F_E_B_R_U_A_R_Y_l 9_8_9 __
NONE DURING THIS PERIOD PAGE 20