ML18153B778
| ML18153B778 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/30/1989 |
| From: | Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18153B767 | List: |
| References | |
| NUDOCS 8906230231 | |
| Download: ML18153B778 (23) | |
Text
ATTACHMENT 1 MONTHLY OPERATING REPORT MAY 1989 8906230231 890531 PDR ADOCK 05000280
~ PDR
e e POW 34-04 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 89-05 APPROVED:
i SECTION PAGE Operating Data Report - Unit No. 1 1 Operating Data Report - Unit No. 2 2 Unit Shutdowns and Power Reductions - Unit No. 1 3 Unit Shutdowns and Power Reductions - Unit No. 2 4 Average Daily Unit Power Level - Unit No. 1 5 Average Daily Unit Power Level - Unit No. 2 6 Summary of Operating Experience - Unit No. 1 7 Summary of Operating Experience - Unit No. 2 7 Facility Changes Requiring NRC Approval 8 Facility Changes That Did Not Require NRC Approval 9 Procedure or Method of Operation Changes Requiring NRC Approval 14 Procedure or Method of Operation Changes that Did Not 15 Require NRC Approval Tests and Experiments Requiring NRC Approval 16 Tests and Experiments That Did Not Require NRC Approval 17 Chemistry Report 18 Fuel Handling - Unit No. 1 19 Fuel Handling - Unit No. 2 19 Description of Periodic Test Which Were Not Completed Within 20 the Time Limits Specified in Technical Specifications
PAGE 1 e
DOCKET NO, 50-280 DATE 06/06/89
-~;..;...;...;;.:.~--
COMPLETED BY L. A. warren TELEPHONE 804-357-3184 x355 OPERATING STATUS 1, Unit Name: Surry Unit 1 Notes 2, Reportiflg Period: 05/01/89 - 05/31/89 3, Licensed Themal Power {~t) : _,__,,2,...,4..,,,4,.....1_ _ _ __
847.5
- 4. Nameplate Rating (Gross HWe):
- 5. Design Electrical Rating (Net HWe): 788
- 6. Maximum Dependable Capacity (Gross MWe): --=8~2.;.0____
7, Maximum Depe!'ldable 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 Any (Net HWe):
- 10. Reasons For Restrictions, If Any:
This Mooth Yr,-to-Date Cumulative
- 11. Hours In Reporting Period 744.0 3623.0 144119.0 12, Number of Hours Reactor Was Critical 0 0 88478.6
- 13. Reactor Reserve Shutdown Hours 0 0 3774.5 14, Hours Generator On-Line 0 0 86605.4
- 15. Unit Reserve Shutdown Hours 0 0 3736.2
- 16. Gross Thermal Energy Generated (HWH) 0 0 201171267.0
- 17. Gross Electrical Energy Generated (HWH) 0 0 65203673.0
- 18. Net Electrical Energy- Generated (HWH) 0 0 61840403.0
- 19. Unit Service Factor 0 0 60.1%
20, Unit Available Factor 0 0 62. 7%
- 21. Unit Capacity Factor (Using MDC Net) 0 55.4%
- 22. Unit Capacity Factor (Using DER Net) 0 0 54.5%
- 23. Unit Forced Rate 100% 100% 21.8%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)1 Forced Maintenance Outage on 09/14/8 9, scheduled on line date of 06/23 /89.
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
26, Units In Test Status (Pr~or to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERA:rION (9/77)
PAGE 2 e
DATE COMPLETED BY DOCKET NO. _ ...s....a....
06/06/89
-...2...a...1___
L. A. Warren TELEPHONE 804-357-3184 x355
. OPERATING STATUS
- 1. Unit Name: Surry Unit 2 Notes
- 2. Reporting Period: 05/01/89 - 05/31/89
- 3. Licensed Thermal Power (MWt): 2441
- 4. Nameplate Rating (Gross HWe): --..,8-.4""'7-.5-----
- 5. Design Electrical Rating (Net HWe): 788
- 6. Maximum Dependable Capacity (Gross HWe): __8_2_0____
- 7. Maximum Depe'C1dable Capacity (Net HWe): 781 S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level Io Which Restricted, If Any (Net HWe):
- 10. Reasons For Restrictions, If Any:
This Moath Yr.-to-Date Cumulative
- 11. Hours In Reporting Period 744.0 3623.0 140999.0
- 12. Number of Hours Reactor Was Critical 0 0 89694.3
- 13. Reactor Reserve Shutdown Hours 328.1
- 14. Hours Generator On-Line 88293.0
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (HWH) 206740436.1
- 17. Gross Electrical Energy Generated (MWH) 67136244.0
- 18. Net Electrical Energy- Generated (MWH) 2Jfi~Z3Z810
- 19. Unit Service Factor 62.6%
- 20. Unit Available Factor 6Z.6%
- 21. Unit Capacity Factor (Using MDC Net) 0 0 57.9%
- 22. Unit Capacity Factor (Using DER Net) 0 0 57 .3%
- 23. Unit Forced Rate Q 0 15%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each)s Refueling: Outage on 09/10/88, scheduled on line date of 07/15/89.
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INmAL CRmCALiff INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)
PAGE 3 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. _.;;.5~0-..;...2;;;.8;..;0;_.._ _ _ __
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DATE _ _ 06....;/_0_6_/8_9_____
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REPOR:I l'K)N'.IH May 1989 TELEPHONE 804-357-3184 JJ355 -* *
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89-05 05/01/89 F 744.0 F 1 Unit shutdown due to Emergency Diesel Generator operability concerns.
e l 2 3 4 F: Forced Reasonz Method: Exhibit G - Instructions S: Scheduled A - Equipment Failure (Explain) l - Manual for Preparation of Data
- B - Maintenance or Test 2 - Manual Scram. Entry Sheets for Licensee C - Refueling 3 - Automatic Scram. Event Report (LER) File D - Regulatory Restriction 4 - Other (Explain) (NUREG 0161)
E - Operator Trsining 6, License Examination 5
F - Administrative Exhibit l - Same Source G - Operational Error (Explain)
(9/77) H
- Other (Explain)
PAGE 4 UNI'I SHU'!DOWNS AND POWER REDµc'IIONS DOCKET NO. __ so_-_2_8_1______
UNI'I NAME __ s_u_rry _ _.J....Io...1
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DATE 06/06/89 Cc>>4PLE'IED BY _ ...L,...._.A""';"""""W...au-.:i,,.en..._____
REPORI t<<>N'IH _ _M_a_y_l9_8_9_ _ __ 'IELEPHONE __ 80_4_-..;:;3... 5.,_7-_3....I_.8_..4...;x.,.3""'55...._**_
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89-05 05/01 /89 s 744.0 C 1,3 . Unit shutdown for refueling outage, automatic reactor trip.
e l 2 3 4 F: Forced Reason, Method: Exhibit G - Instructions S: Scheduled A - Equipment Failure (Explain) l - Manual for Preparation of Data B - Maintenance or test 2 - Manual Scram. Entry Sheets for Licensee C - Refueling 3 - Automatic Scram. Event Report (LER) File D - Regulatory Restriction 4 - Other (Explain) (NUREG 0161)
E - Operator Training & License Examination 5
F - Administrative Exhibit l - Same Source G - Operational Error (Explain)
(9/77) H - Other (Explain)
e PAGE 5 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. ___;;..;;._~.:.._
50-280 UNIT Surry Unit I DATE 06/06/89 COMPLETED BY L. A. "ii/ arren TELEPHONE 804-357-3184 x355 MONTH . MAY 1989 DAY AVERAGE DAILY POWER LEVEL c, 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)
e PAGE 6 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-281 UN IT Surry Unit 2 DATE 06/06/89 COMPLETED BY L. A. *",/ arren TELEPHONE 804-357-3184 x355 MONTH . MAY 1989 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)
PAGE 7
-suMMARY OF OPERATING EXPERIENCE MONTH/YEAR _ _ M_A_Y_l_98_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 05/01/89 0000 This reporting period begins with the Unit at CSD.
05/31/89 2400 This reporting period ends with the Unit at CSD.
UNIT TWO 05/01/89 0000 This reporting period begins with the Unit at CSD~
05/31/89 2400 This reporting period ends with the Unit at CSD.
F-- . ---*
e PAGE 8 I
F AGILITY CHANGES REQUIRING NRC APPROVAL MONTH/YEAR - - MAY 1989 NONE DURING THIS PERIOD
- -- -=----~---
PAGE 9 e e FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR
- -MAY - -1989 DC 87-02 ACCUMULATOR TANKS PRESSURE TRANSMITTER UPGRADE UNIT 2 This design change installed six new qualified accumulator tank pressure transmitters above the flood level to replace six nonqualified pressure transmitters mounted below the flood level in the reactor containment.
SUMMARY
OF SAFETY ANALYSIS This modification provides qualified instrumentation to allow the operator to monitor the pressure of the safety injection accumulator tanks. The replacement of the instrumentation (transmitters and power supplies) does not impact the operation of safety related equipment or systems. The new instrumentation is environmentally and seismically qualified. Safety limits, as defined in the Technical Specifications, are not changed.
SCAFFOLDING REQUEST 05/02/89 This request erected temporary scaffolding in the fuel building, elevation
.45' to work ventilation registers.
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 05/02/89 This request erected temporary scaffolding in the mechanical equipment room #3, elevation 916 11 to work l-VS-P-2A discharge and l-VS-287 replacement.
Installation of this temporary scaffolding was reviewed. for effect on acciderit analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
1&2-FS 89-23 UFSAR CHANGE 05/02/89 This request was to change the UFSAR section 9.4.4.2 to delete a statement referring to the component cooling system as not normally being expected to contain radioactive water.
Since component cooling water is monitored for radioactivity and the station drains system is designed to collect component cooling water leakage for treatment as liquid waste, an unreviewed safety question is not created.
e e FACILlTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL PAGE IO MONTH/YEAR MAY 1989 SCAFFOLDING REQUEST 05/06/89 This request erected tem*porary scaffolding in the Unit* 1 containment loop rooms to work 2-RC-HCV-2557C and 2-RC-6 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 05/06/89 This request erected temporary scaffolding in the Unit 2 cable vault to work cable pulls. This scaffolding will be in the vicinity of the electrical penetration area.
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-89-188 ENGINEERING WORK REQUEST 05/12/89 This engineering work request evaluated the test of the residual heat removal (RHR) system flow paths through the B and C accumulator discharge lines following maintenance to the accumulator discharge check valves. -
An unreviewed safety question is not created because precautions are taken during the test to ensure uninterrupted RHR flow *.
1&2 EWR-89-246 ENGINEERING WORK REQUEST- UNITS I & 2 05/12/89 This engineering work request evaluated the underground fuel oil storage tank l~EE-T_K-2B being drained for inspection. Provisions for a reliable supply of fuel oil to operate the emergency diesel generators in accordance with the technical specifications are maintained.
The design basis, margin of safety and consequences of malfunction have been considered as it relates to the emergency electrical system due to this EWR. This EWR will not adversely affect this station, personnel or the public.
SCAFFOLDING REQUEST 05/16//89 This* request erected temporary scaffolding in the auxiliary basement to work l-RC-LIS-1320.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
PAGE 11 FACILITAHANGES THAT DID NOT REQUIR,NRC APPROVAL MONTH/YEAR MAY 1989 SCAFFOLDING REQUEST 05/17/89 This request erected temporary scaffolding in the Unit 1 cable vault to work cable splices at penetrations lA and SA.
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 05/17/89 This request erected temporary scaffolding in the Unit 1 containment to work l-RC-LS-1320 in 11 B11 loop room.
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.
1&2 EWR-89-152 ENGINEERING WORK REQUEST 05/19/89 This EWR documented the addition of flow sensing elements in the service water inlet side to the component cooling heat exchanger (CCHX) to determine service water flow. The EWR also documented the addition of Delta P gauges between the inlet and outlet of the CCHX tubes to measure macrofouling and microfouling.
This modification does not pose an unreviewed safety question since the annubar and Delta P instrumentation will be installed in accordance with previously approved codes and standards. The instrumentation will not alter the function of the service water system but will improve the ability to monitor CCHX performance.
SCAFFOLDING REQUEST 05/20/89 This request erected temporary scaffolding in the Unit 2 emergency switchgear room to work ventilation duct close to the ceiling.*
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-89-107 TEMPORARY MODIFICATION 05/23/89 This modification blocked open a pressurizer power operated relief valve (PORV) l-RC-PCV-1456 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 js created.
PAGE 12 FACIIJT~HANGES THAT DID NOT REQUIR,NRC APPROVAL MONTH/YEAR MAY 1989 TM-Sl-89-109 TEMPORARY MODIFICATION 05/23/89 This modification blocke*d open a pressurizer power operated relief valve (PORV) l-RC-PCV-1455C 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.
i-EWR-88-176 ENGINEERING WORK REQUEST 05/23/89 This engineering work request replaced the existing bowser turbine lube oil conditioner with a unit of improved design.
This replacement is an enhancement and does not create an unreviewed safety question. The turbine lube oil conditioner is non-safety related equipment* located in the turbine building and its normal operation does not affect safety related equipment.
TM-Sl-89-110 TEMPORARY MODIFICATION 05/24/89 This modification wired open the exhaust damper for l*-VS-F-lA.
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.
1&2 EWR-88-308 ENGINEERING WORK REQUEST 05/25/89 This engineering work request evaluated the additional information obtained from Westinghouse that needs to be incorporated into the package.
The UFSAR accidents were reviewed to determine the impact of Westinghouse recommendations.
SCAFFOLDlNG REQUEST 05/25/89 This request erected temporary scaffolding in the emergency service water pump house to work the ceiling louvers.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
PAGE 13 FACILIT.HANGES THAT DID NOT REQUIR~RC APPROVAL MONTH/YEAR MAY 1989 SCAFFOLDING REQUEST 05/25/89 This request erected temporary scaffolding in the Unit l containment to cable splices at penetrations lA and SA.
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 05/29/89 This request erected temporary scaffolding in the Unit l 'B' loop room to work l 1/2" CC-802-1501 hanger modifications.
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 05/29/89 This request erected temporary scaffolding in the Unit l 'A' loop room to work l 1/2" CC-800-1501 hanger modifications.
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.
1 &2-FS-88-15 UFSAR CHANGE 05/30/89 The UFSAR states that two isolation valves are located in the stearri generator channel head drain. There is actually one valve and one blank flange. Based on drawing revisions, the original steam generator did not have these drains and the new steam generators have always had one valve and one blank flange.
There are no unreviewed safety questions posed by this difference since equivalent isolation has always been provided.
SCAFFOLDING REQUEST 05/30/89 This request erected temporary scaffolding in the Unit 2 containment residual h~at removal flat to work snubber 2-RH-HSS-11.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function. Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
PAGE 14 e e PROCEDURE OR METHOD OF OPERATION CHANGES REQUIRING NRG APPROVAL MONTH/YEAR
- - MAY
- - 1989 NONE DURING THIS PERIOD
PAGE 15
=--.---~*---------=---
PR.DURE OR METHOD OF OPERATI-CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR MAY 1989 1&2-STP-30 SURVEILLANCE TEST PROCEDURE 05/07/89 This test procedure ensures that instrument air compressors 1-IA-C-l and 2-IA-C-l load/unload and run properly. The test is also required to ensure that the instrument air system design flow rate can be achieved.
The instrument air system will be fully operable during performance of this test. The components will be operated per design. Technical specification limiting condition of operation will be met during the test. There is no unreviewed safety question.
1&2-STP-31 SURVEILLANCE TEST PROCEDURE 05/10/89 This test procedure involves air sampling at the outlet of the instrument air dryers for baseline data. The normal operating configuration for this system is not affected.
This test does not constitute an unreviewed safety question, nor does it change the technical specifications. This conclusion is based on a review of technical specifications, UFSAR, and performance requirements in the Test Procedure.
TTI ENGINEERING PROCEDURE 05/23/89 This procedure has been revised to simplify its use and decrease the change of spreading contamination due to air usage.
Resin transfer by this procedure is acceptable and safe. Therefore, an unreviewed safety question is not created.
PAGE 16 TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR MAY 1989
=-...:..::..=...::........;;;;_ _ _ __
NONE DURING THIS PERIOD
i
---*------.- PAGE 17 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR _ _,--M_A_Y_I_9_8_9 _ _ _ __
NONE DURING THIS PERIOD
.. PAGE 18 e VIRGINIA POWER e
SURRY POWEll STATION CHEMISTRY REPORT MAY 1939 PRIMARY COOLANT UNIT NO. 1 UNIT NO. 2 ANALYSIS MAX. MIN, AVG. MAX, MIN, AVG.
Gross Radioact., µCi/ml 9.62E-3 5.95E-4 2.69E-3 l.07E-2 1. OIE-3 2.67E-3 Suspended Solids, ppm 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, 1,.1Ci/ml --- --- --- --- --- ---
131 µCi/ml --- --- --- --- --- ---
Iodine 1131 I Il33 --- --- --- --- --- ----
Hydrogen, cc/kg --- --- --- --- --- ---
Lithium, ppm 1. 31 0.30 0.67
- 0. 20 0 .18 0 .19 Boron-10,.ppm* 414.9 396.3 405.3 427.3 417.9 422.8 Oxygen, (DO), ppm 5.5 0.005 1.116 0.005 0.005 0.005 Chloride, ppm 0.014 0.004 0;007 0.014 0.009 0.011 pH@ 25 degree Celsius 5.70 4.97 5. 18 5.16 4.95 5.06
- Boron-10
- Total Boron X 0.196 UNIT ONE: The month started with the unit at cold shutdown with RHR and BMB in service.
On 5/4 at 2300 hrs., letdown was isolated for maintenance. Letdown was restored on 5/7 at 0340 with BMB in service. On 5/11 thru 5/12, all three RCPs were jogged to get each leg solid.
1C RCP was left running in order to heat up to 175° to establish primary chemistry. On 5/13 BMB diverted for 3 gallons hydrazine addition to RCS. Another 1 gallo11 hydrazine added at 1837 hrs. on 5/13, Commenced cooling back down at 5/14 at 0200 hrs. in order to perform maintenance on the pressurizer MOVs. On 5/30 started IC RCP and later added another 1 gallon of hydrazine at 2035 hrs. with BMB diverted. On 5/31 at 0230 hrs added 1780 grms. LiOH to RCS. Switched to IA RCP to continue to hold primary at approximately 175°.
UNIT TWO: Started the month at cold shutdown on RHR and AMB in service. On 5/23 letdown was isolated for .maintenance on the charging system MOVs. The month ended with letdown isolated, RHR in service, and at cold shutdown.
PAGE 19
_.:_~-~--- e
=----
e UNIT 1 & 2 FUEL HANDLING DATE MAY 1989 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT II RECEIVED PER SHIPMENT fl
" ENRICHMENT CASK ACTIVITY LEVEL NONE DUR ING THIS Pl RIOD
... PAGE 20 e e DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS
- MONTH/YEAR ---,--M_A_Y_I_98_9_ _ __
NONE DURING THIS PERIOD