ML18153B580
| ML18153B580 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1988 |
| From: | Cartwright W, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8901230249 | |
| Download: ML18153B580 (23) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. R. CARTWRIGHT VICE PRESIDENT NucLEAB January 16, 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.89-015 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 December 1988.
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 l
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 88-12 APPROVED:
f e
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 NRG Approval Facility Changes That Did Not Require NRG Approval e
Procedure or Method of Operation Changes Requiring NRG Approval Procedure or Method of Operation Changes that Did Not Require NRG Approval Tests and Experiments Requiring NRG Approval Tests and Experiments That Did Not Require NRG 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 13 14 15 16 17 18 19 20
1 e
e PAGE 1 OPERATING DATA REPORT DOCKET NO.
50-280.
DATE 1/4/89 COMPLETED BY L. A. warren TELEPHONE 804-357-3184 x355 OPERATING STATUS
- 1. Unit Name:
Surry Unit 1 Notes
- 2. Reportirig Period: December 01-31, 1988
- 3. Licensed Thermal Power (MWt):
2441
--=-=-------
- 4. Nameplate Rating (Gross MWe): __
8_4_7_.s ____ _
- 5. Design Electrical Rating (Net MWe):
788
- 6.
Maximum Dependable Capacity (Gross MWe):
820
- 7. Maximum Deperidable Capacity (Net MWe):
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 Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Hootb Yr.-to-Date
- 11. Hours In Reporting Period 744.0 8784.0
- 12. Number of Hours Reactor Was Critical 0
3755.2
- 13. Reactor Reserve Shutdown Hours 0
0
- 14. Hours Generator On-Line 0
3634.2
- 15. Unit Reserve Shutdown Hours 0
0
- 16. Gross Thermal Energy Generated (MWB) 0 8451045.6
- 17. Gross Electrical Energy Generated (HWB) 0 2828500.0
- 18. Net Electrical Energy-Generated (MWH) 26B~QZZ,Q
- 19. Unit Service Factor 0
41.4%
- 20. Unit Available Factor 0
41.4%
- 21. Unit Capacity Factor (Using MDC Net) 0 39.1%
- 22. Unit Capacity Factor (Using DER Net) 0 38.8%
- 23. Uoit Forced Rate 100%
43%
- 24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Eacb)r Forced Maintenance Outage on 09/12/88, on line date scheduled
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 01/31/89.
Cumulative 140496.0 88478.6 3774. 5 86605.4 JZJf2.Z 201171267.0 6520J6Z3 1 0 6J8~0~03.0 61.6%
64.3%
56.9%
55.9%
19.1%
Achieved (9/77)
e PAGE 2 OPERATDIG DArA REPORr DOCKET NO.
50-281 DATE 1/4/89 COMPLETED BY L. A. Warren TELEPHONE 804-357-3184 x355 OPERATING STATUS
- 1. Unit Name:
Surry Unit 2 Notes
- 2. Reportirig Period: December 01-31, 1988
- 3. Licensed Thermal Power (MWt):
2441
- 4. Nameplate Rating (Gross MWe): --9-47-.-5-----
S. Design Electrical Rating (Net MWe):
788
- 6. Maximum Dependable Capacity (Gross MWe):
___ 8 __ 2 __ 0 __
- 7. Maximum Dependable Capacity (Net MWe):
781
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Laat Report, Give Reasons:
- 9. Power Level To Which Restricted, If Aoy (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Mooth Yr.-to-Date
- 11. Hours In Reporting Period 744.0 8784.0
- 12. Number of Hours Reactor Was Critical 0
5028.3
- 13. Reactor Reserve Shutdown Hours 0
0
- 14. Hours Generator On-Line 0
4994.7
- 15. Unit Reserve Shutdown Hours 0
0
- 16. Gross Thermal Energy Generated (HWB) 0 11570100.4
- 17. Gross Electrical Energy Generated (MWH) 0 3763420.0
- 18. Net Electrical Energy-Generated (MWB) 0 3570901. 0
- 19. Unit Service Factor 0
56.9%
- 20. Unit Available Factor 0
56.9%
- 21. Unit Capacity Factor (Using MDC Net) 0 52.1%
- 22. Unit Capacity Factor (Using DER Net) 0
~l.6'26
- 23. Ut,it Forced Rate 0
24%
- 24.
- Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Eachh Refueling Outage on 09/09/88, scheduled on line date 02/12/89.
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to Camnercial Operation):
Forecast INmAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Cumulative 137376.0 89694.3 328.1 88293.0 0
206740463.1 67136244.0 63647378.0 64.3%
64.3%
59.5%
58.8%
15%
Achieved (9/77)
- i.
HO.
DAD CL 88-13 12/01/88 F
l F: Forced 2
S:
Scheduled
, (9/77)
PAGE 3 UNl't SHUIDOWNS AND POWER DDUC'tlONS DOCICE't NO.
50-280 REPOR7 tOml L
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LICENSEE i:
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II EVEN'!
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IX L
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REPOR:t
- D...
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0 D
744.0 F
1
- 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)
UNl't NAHi SJ.lrrv llDU l DATE 1/4/89 CX1tPLE'tED BY l.1 Ai WMreD December 1988
'tELEPHONE 804-357-a10jxa55 e,
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.. 'a 0
'a CAUSE & CORREC'tlVE AC'tlON 'IO
- 8 CL O
~ 0 PltEVEN't UCURREN'J:
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0 Unit shutdown due to emergency diesel 9"enerator operability concerns.
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Exhibit G - lnatructioo*
Hethodz l - Hasual for Preparation of Data 2 - Manual Scram.
Entry Sheets for Licensee 3 - AutOll8tic Scram.
Event Report (LER) File 4 - Other (Explain)
(NUREG 0161) 5 Exhibit l - Saae Source I
- I NO.
Dil'E
- a.
88-21 12/01/88 s
1 F: forced 2
S:
Scheduled (9/77)
PAGE 4 UNI't SHU'IDOWNS AND POWEil UDUC'tlOHS NO 50-281 DOCICEt
- --------------~
UHl't NAME _,.S..,u.. rry
_ _.J... Jp.. j.. t__,2 ______ _
DA7E_....,l/... 4... /8... 9.._..~~---~~
CXIIPLEDD BY _..,L.....,A... ;.. w
.. arr_.,.e.. n _____ _
REPOR7 HONnl December 1988 TELEPHONE ____
80... 4...
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-3=1=8_,.4..-ix_3M,l55 __ _
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- Reason, A - Equipment failure (Explain)
- B - Maintenance or 'test C - Refueling D - Regulato~ Restriction LICENSEE EVP.Ht REPORT#
E - Operator Training lo License Examination F - Adainistrative G - Operational Error (Explain)
H - Otber (Explain) 3 C
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C
- CAUSE lo CORRECrlVE AC'tlON to
.. "D 0
"D 0
Q.
0
~u E U PREYEN'I UCURREN't 0
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Unit shutdown for refueling outage, automatic reactor trip.
Method:
1 - Hamaal 2 - Manual Scram.
3 - Automatic Scraa.
4 - Other (Explain) 5 Exhibit G - lnatruction*
for Preparation of Data Entry Sheets for Licenaee Event Report CLER) rue (NUREG 0161)
Emibit 1 - Sue Source e
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PAGE 5 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-280 UNIT Surry Unit l DATE 1/5/89 COMPLETED BY L.A. Warren TELEPHONE 801-35Z-Jl84 xJ~~
MONTH
- December 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7.
0 23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
(9/77)
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PAGE 6 AVERAGE DAILY UNIT POWER LEVEL ooCKET No. --l;'!s~a~~z;..i,,au.:i-=-~ ____ _
UNIT Surry Unit :2 DATE 1/5/89 COMPLETED BY L.A. Warren MONTH
- December 1988 TELEPHONE 804-357-3184 x355 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
6 0
22 0
7.
0 23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
14 0
30 0
15 0
31 0
16 0
INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
(9/77)
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PAGE 7
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR December 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 12/01/88 12/18/88 12/31/88 UNIT TWO 0000 1117 2400 12/01/88 0000 12/31/88 2400 This reporting period begins with the unit at RSD.
Unit at CSD.
This reporting period ends with the unit at CSD.
This reporting period begins with the unit at RSD.
This reporting period ends with the unit at RSD.
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PAGE 8 F AGILITY CHANGES REQUIRING NRC APPROVAL MONTH/YEAR December 1988 NONE DURING THIS PERIOD
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PAGE 9 FACILlTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR DECEMBER 1988 AC-S 1-88-1204 ADMINISTRATIVE CONTROL 12/04/88 Placed valve l-EG-15 under administrative control when opened. This valve is the crosstie between the air bottle banks.
Administrative control of the emergency diesel. generator air start bottle banks will ensure air start circuit redundancy. An unreviewed safety question was not created.
RELOAD SAFETY EVALUATION FOR SURRY 1 CYCLE IOA 12/05/88 This report represents an evaluation which demonstrates that the modified Cycle 10 (henceforth called Cycle 1 OA) core will not adversely affect the safety of the plant during refueling and cold shutdown.
This report concluded that no changes to the Technical Specifications are required and none of the Chapter 14 UFSAR accidents require reanalysis for refueling and cold shutdown conditions.
SCAFFOLDING REQUEST 12/06/88 Erected temporary scaffolding located in Unit 2 Containment at 3' elevation to remove and test RH-RV-2721, RV-CC-219B and RV-CC-219A.
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-88-169 TEMPORARY MODIFICATION 12/07/88 The spent fuel pool cleanup ion exchanger is full of spent resin and cannot be changed out until the new spent resin transfer system is operational.
This modification is to allow use of temporary ion exchangers for spent fuel pool water cleanup.
The probability of leakage of water from the spent fuel pool is increased.
However, the design of the system prevents a decrease in water level below the technical specification limit for refueling. This condition was previously analyzed in the UFSAR. Consequences of leakage would be loss of spent fuel pool cooling until water level is restored. This modification would not inhibit restoration of fuel pool level. In addition, operation of the system will be in accordance with approved procedures and abnormal procedures are in ef feet for loss of level.
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PAGE 10 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR DECEMBER 1988 SCAFFOLDING REQUEST 12/07/88 Temporary scaffolding was erected in mechanical equipment room 3 to install lift rig for 1-VS-S-l B.
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-S2-88-151 TEMPORARY MODIFICATION 12/08/88 Temporary modification to block the high flux at shutdown alarm from NI-32. NI-31 high flux at shutdown alarm will be maintained operable and periodic monitoring of strip chart recording of NI-32 will be performed to verify no legitimate reactivity excursion exists.
Since a legitimate reactivity excursion ha~. a distinctive signature and occurs over a period of at least 37 minutes, periodic monitoring of NI-32 on the strip chart recorder provides indication of reactivity transients. NI-31 high flux at shutdown will remain operable. Therefore, no unreviewed safety question is created by this temporary modification.
SCAFFOLDING REQUEST 12/10/88 Erected temporary scaffolding in the Unit 1 Containment 'A' loop room to work HCV-1556A.
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 12/10/88 Erected temporary scaffolding in Unit 1 Turbine building basement to work A & B component cooling heat exchangers.
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.
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PAGE 11 F ACUITY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR DECEMBER 1988 AC-SI-88-1210 ADMINISTRATIVE CONTROL 12/11/88 SW-MOV-102A/B breakers were placed under administrative control to allow closure if the canal level dropped below 18 feet.
The previous justification for continued operation evaluated 20' canal level operation. This documented that 45 minutes would be available to ensure valve closure, this administrative control allows 10 minutes.
Therefore, no unreviewed safety question is created.
SCAFFOLDING REQUEST 12/16/88 This request erected temporary scaffolding located in the reactor cavity floor to work installation of the drain extension on the reactor head vents.
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 12/19/88 This request erected temporary scaffolding located in emergency switchgear room Unit 2 to work cable and conduit.
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-88-179 TEMPORARY MODIFICATION 12/20/88 This modification documented the operability of 1-SW-P-lB with a temporary repair installed on its angle drive cooling water line. This safety analysis only addressed the suitability of the use of a stainless steel fitting in place of original carbon steel as per this modification.
Since the stainless steel fitting was used for less than six months, no significant corrosion of the fitting is expected. The temporary fitting meets or exceeds pressure and temperature requirements. The fitting dimensions are the same as the original fitting.
Therefore, no unreviewed safety question is created.
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PAGE 12 FACIUTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR DECEMBER 1988 SCAFFOLDING REQUEST 12/20/88 This request erected temporary scaffolding located in emergency fire protection house to work light fixture hangers.
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.
l-EWR-88-436 ENGINEERING WORK REQUEST 12/20/88 Request to document that the spent fuel pit cooling pump (1-FC-P-lB) was overhauled and new wear rings were installed.
An analysis was performed with the vendor data provided. It was determined that the minimal loss in flow is acceptable. Therefore, an unreviewed safety question was not created.
SCAFFOLDING REQUEST 12/29/88 This request erected temporary scaffolding located in # 1 EDG room to work light fixture.
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 12/29/88 This request erected temporary scaffolding located in Unit 1
containment to work O l-RH-MOV-l 720B.
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 malfunction are not affected.
SCAFFOLDING REQUEST 12/31/88 This request erected temporary scaffolding located in the radiological controlled area to work Unit 1 refueling water storage tc3.nk.
Deteriorated insulation required replacement.
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.
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PROCEDURE OR METHOD OF OPERATION CHANGES REQUIRING NRG APPROVAL MONTH/YEAR December 1988 NONE DURING THIS PERIOD PAGE 13
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PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR DECEMBER 1988 PAGE 14 2-EMP-C-EPH-06B ELECTRICAL MAINTENANCE PROCEDURE PROCEDURE DEVIATION 12/06/88 PS-88-57 Deviation to allow the change in sequencing of steps to enable performance of an uncoupled run of the reactor coolant pump motor prior to installation of the oil collection system.
A dilution during refueling was evaluated along with a loss of residual heat removal. This change has no effect on the above accidents, as only the pump motor will be run. The reactor coolant pump impeller and shaft are not connected, therefore no possibility of a reactor coolant system transient is possible.
UFSAR CHANGE REQUEST 12/15/88
- The change request was to revise section 6.2 and section 14.3.1.3 to reflect the emergency procedures.
Steam generator isolation without loop isolation valve closure is an analyzed condition.
In addition, sampling to determine whether to release a ruptured steam generator is not in accordance with the emergency procedures.
EP-4.0 isolates the ruptured steam generator secondary side and directs cooldown using the intact steam generators~ Therefore, this change will not adversely affect any plant systems, equipment, or safety analysis.
e PAGE 15 TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR December 1988 NONE DURING THIS PERIOD
e PAGE 16 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL l-ST-233 l-ST-224 l-ST-215 MONTH/YEAR DECEMBER 1988
)
SPECIAL TEST 12/09/88 This test measures component cooling and service water temperatures and establishes the position of valves l-SW-27 and l-SW-31 to maintain service water flow at il 1,640 GPM when intake canal level is between 20 and 21 feet.
The review determined that safety concerns did not exist because the plant systems were operated in accordance with existing approved normal operating procedures and the test did not require operation outside those procedures.
SPECIAL TEST 12/09/88 Special test performed to demonstrate the leak limiting capabilities of the J-seal component of the reactor cavity seal assembly. The leakage has been evaluated and determined to be acceptable.
This change has no effect on the probability of occurrence of the accidents evaluated in the UFSAR. The consequences of the accidents discussed are not significantly increased as a result of this change.
The possibility of an accident or equipment malfunction of a different type is not created. The margin of safety as described in the basis section of the UFSAR is not reduced.
SPECIAL TEST 12/23/88 Test to verify auxiliary feedwater flow to all steam generators.
This test was run during cold shutdown and the availability of the auxiliary feedwater pumps for the operating Unit was not affected.
PRIMARY COOLANT ANALYSIS Gross Radioact., 2Ci/ml Susoended Solids, ppm Gross Tritium, 2Ci/ml lodine131-, 2Ci/ml 1131 / 1131 i--
Hydrogen, cc/ka Lithium, Pl>lll Boron-10, ppm*
Or,1.en, (DO)' ppm Chloride, ppm oB@ 25 dearee Celsiu*
VIRGIHU POWD SURRY POWER STAT-CIIEKISTRY REPORT December 19 88 UNIT NO, l MAX.
MIN.
AVG.
l.70E-2 ~. l 4E-5 3.58E-3 0.0 0.0 0.0 419.4 409.1 414.2 3.0 1.0 1.3 o.o 11 0.003 0.006 4.73 4.56 4.67
- Boron-10
- Total Boron X 0.196 REMARKS:
PAGE 17 UNIT NO. 2 MAX.
MIN.
AVG.
7.35E-2 2.33E-3 2.39E-2 0.0 0.0 0.0 431.6 420.0 426.1 4.5 2.5 3.8 0.028 0.009 0.016 4.90 4.60 4.69 UNIT ONE:
Began December at refueling shutdown with RL purification through B-MB and A-DEB. On 12/5 at 1945, RHR pumps were started. Reloading of fuel into the core commenced at 1230 on 12/6. At 1815 on 1210, the RL system was tagged out.
At 1315 on 12/18, one complete pass was completed in retensioning the reactor head.
At O 136 on 12/ 19 tensioning of the reactor head was complete and the reactor was at cold shutdown where. it finished the month.
UNIT TWO:
The unit was at refueling shutdown for the month of December. On 12/7 at 2145, flooding of the reactor cavity commenced. Cavity level reached 16' on 12/8 at 0300. At 0749 on 12/9, the level was 26'2 11
- Hydrogen peroxide was added to the cavity twice: a 2 gallon addition at 0905 on 12/9 and 1 gallon at 0930 on 12/11.
On 12/21 at 1440, purification through A-MB was attempted, but stopped due to leaks.
At 1240 on 12/31, purification was successfully restarted.
e PAGE 18 UNIT __ l_
FUEL HANDLING DATE Dec. 1988 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 DUI ~NG THIS P ~RIOD
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PAGE 19 UNIT _2_
FUEL HANDLING DATE Dec. 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPINC SHIPMENT II RECEIVED PER SHIPMENT 11 II ENRICHMENT CASK ACTIVITY LEVEL 6
12/16/88 1
SU3 LMOQ71 3.8 NIA
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PAGE 20 DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR December 1988 NONE DURING THIS PERIOD