ML20053B974
| ML20053B974 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/07/1982 |
| From: | Sarsour B TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20053B971 | List: |
| References | |
| NUDOCS 8206010388 | |
| Download: ML20053B974 (8) | |
Text
AVERAGE DAILY UNIT POWER LEVEL l
DOCKET NO.
50-346 Davis-Besse #1 WIT DATE S/07/82 COMPLETED BY Bilal Sarsour TELEPHONE (419) 259-5000 ext. #384 MONTH April, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe-Net)
(MWe-Net) 0 17 0
2 0
0 18 3
0 0
39 4
0 20 0
5 0
0 21 6
0 0
22 7
0 0
23 x
0 0
24 9
0 0
25 10 0
0 26 I
0 0
27 12 0
28 0
13 0
29 0
34 30 0
15 0
3, 16 0
INS'IR tl(.TIONS f in Iliis Innnat int flie avesa;;c daily unit ginwes level.. MWe Net for eae), day in it,e,eg,,,,in,g,,,,,g,g,, g.iini iule to I se neasest winite niegawatI, (9/77 )
820 6 010 3B6
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OPERATING DATA REPORT DOCKET NO.
50-346 DATE 5/7/82 COMPLETED BY Bilal Sarsour TELEPHONE (419) 259-5000
' ext. #384 OPERATING STATUS Davis-Besse Unit #1 Notes
- 1. Unit Name:
- 2. Reporting Period:
April, 1982
- 3. Licensed Thermal Power (MWt):
2772
.l. Nameplate Rating (Gross MWe):
925 906
- 5. Unign Electrical Rating (Net MWe):
918
- 6. Maximum Dependable Capacity (Gross MWe):
874
- 7. Maximum Dependable Capacity (Net MWe):
M. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. l'ower Level To Which Restricted,1f Any (Net MWe):
- 10. Reasum For Restrictions,If Any:
This Month Yr..to.Dat e Cumulative
- 11. Iluurs In Reporting Period 719 2,879 32,880
- 12. Number Of Hours Reactor Was Critical 0
1,708 17,938
- 13. Reactnr Reserve Shutdown flours 0
0 3,334.7 l l. linurs Generatur On.Line 0
1,707.4 16,957.6
- 15. Unit Reserve Shutdown Hours 0
0 1,731.4
- 16. Grou Thermal Energy Generated (MWH) 0 3,641,078 38,762,603 17 Grow Eicetrical Energy Generated (MWH) 0 1,202.294 12,884,545 1h. Nel 1.lectrical I.nergy Generated (MWil) 0 1,124,093 _
12,021,378
- 19. Unit Service Factor 0
59.3 51.6 0
59.3 56.8
- 20. Unit Availability Factor
- 21. Unit Caiueity Factor (Using MDC Net) 0 44.7 41.8 0
43.1 40.4
- 22. Unit Calueity Factor (Using 1)ER Net)
- 23. Unit Forced Outage Rate 0
0 29.9
- 24. Shutdowm Scheduled Over Next 6 Months (Type, Date.and Duration of Each t:
- 25. If Shnt Down AI End Of Report Period Estimated Date of Startup:
August 1, 1982
- 26. Units in Test Status IPrior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIA L ELECTRICITY COMMERCIAL. OPERATION (u/77)
3 DOCKET NO.
50-346 _
UNIT SHUTDOWNS AND POb:.;l REDUCIiONS UNIT N AME Davis-Besse Unit 1 DATE 5/7/82 COMPLETED BY Bilal Sarsour REPORT MONTil April, 1982 TELEPIIONE 419-259-5000. Ext. 384 i
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j.$ 5 Licensee
,E.r, ge, Cause & Corrective No.
Date g
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Event 3,7 9.'8 Action to yV Prevent Recurrence-H fE j gg g Report a vi o 6
4 82 03 13 S
719 C
4 NA NA NA Unit outage which began on March 13, 1982 was still in progress through the end of April, 1982. See Opera-tional Summary for further details.
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F: Forced Reason:
Method:
Exhibit C Instructions S: Schedu!cd A Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scrum.
Event Report (LER1 File (NUREG.
D Regniatory Restriction i 4-Continuation from Previous Month 0161)
E-Operator Training & License Examination l 5-Load Reduction F-Administrative
! 60ther (Explain) 5 G. Operational Eiror (Explain)
Exliibit !- Same Source (9/77)
Il Other (Explain)
OPERATIONAL
SUMMARY
April, 1982 04/01/82 - 04/30/82:
The unit outage which began on March 13, 1982 was still in progress through the end of April, 1982.
The following are the more significant outage activities performed during this month:
(1)
An Automatic Reactor Inspection System (ARIS) inspection of the reactor vessel hot leg nozzle welds was conducted.
(2)
Eddy Current testing in steam generators. During that test it was discovered that some of the steam generator tubes located adjacent to the auxiliary feedwater header showed potential interaction with the header support system. A secondary side manway from steam generator 1-1 was removed and it was determined by direct visual observation and fiberoptic inspection that the auxiliary feedwater header was not securely fastened and had experienced damage.
In-spection of the other steam generator yielded similar re-suits. The root cause of this event has not yet been deter-mined. Toledo Edison is working with other owners to eval-uate possible corrective action.
(3)
The turbine, associated valves, and the #2 main feed pump were disassembled and inspected. Problems were found in the 'A' low pressure turbine rotor (1-2) lith stage buckets.
The problem was cracks appearing on the steam admission side of the dovetail. The failure mechanism appears to la fre-quency related, high cycle fatique.
Similar problems were found to exist en the 'B' low pressure turbine rotor (1-1) lith stage buckets. All lith stage buckets on both low pressure turbine rotors have been sent to the factory for modification to allow the installation of tie wires which will dampen out any vibration. The problems discovered do not have a nuclear safety significance.
(4)
The condenser inspection revealed the ruptured 10" expan-sion joint in the high pressure condenser was one that was replaced in November.
The probable cause of failure was pipe misalignment. Corrective action will be to add in-creased supports and braces to prevent piping disalignment in the future.
(5)
The visual inspection of thermal shield bolts were completed satisfactorily with no abnormalities noted and no corrective action required.
(6)
Fuel shuffle was successfully completed, one broken hold-(
down spring was found on a fuel assembly scheduled for removal this cycle. This spring was removed for the inspection.
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OPERATIONAL
SUMMARY
Page 2 April, 1982 (7)
The Bailey 855 station computer was removed and replaced by the nev MODCOMP classic dual central processing unit i
computer system.
(8)
- 2 diesel generator inspection was completed with only one problem found. The main oil pump assembly was worn due to a factory assembly problem and the whole pump was replaced.
(9)
Atmospheric vent valves were disassembled and inspected.
(10)
Thirteen of the eighteen main steam safety valves were re-moved and sent to Mark Controls for overhaul. Problems were found in the stems and the defective stems are being i
replaced.
1 (11)
FCR work continued this month. A detailed list of the major FCRs completed will be provided at a later date.
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REFUELING INFORMATION DATE:
April, 1982 1.
Name of facility:
Davis-Besse Unit 1 2.
Scheduled date for nert refueling shutdown:
March 12, 1982 3.
Scheduled date for restart following refueling:
August 1, 1982 4.
Will refueling or resumption of operation thereafter require a technical specifi-cation change or other license amendment?
If answer is yes, what in general, will these be?
If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
The final reload analysis for Cycle 3 has been completed and submitted to the NRC (See Serial No. 787 dated March 5,1982).
This analysis identifies several __
technical specification changen relating to core operational limits and reactor protection system setpoints. An option to provide flexibility in the overall cycle length is also provided therein.
b.
Scheduled date(s) for submitting proposed licensing action and supporting infor-mation.
See response to No. 4 above 6.
Important licensing considerations associated with refueling, e.g.,
different fuel dusign or supplier, unreviewed design or performance analysis new or methods, significant changes in fuel design, new operating procedures.
Mono identified to date 1
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
(u) 177 (b) 92 - Spent Fuel Assemblies 8.
The present licensed spent fuel pool storage capacity and the size of any in-number of fuel assemblies. crease in licensed storage capacity that has been request Present 735 Increase size by 0 (zero) 9 The pro.jected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
Date 1988 - assuming ability to unload the entire core into the spent fuel pool is maintained.
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COMPLETED FACILITY CHANGE REQUEST a
FCR NO:
79-194 4
j SYSTEM: N/A
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t COMPONhNT: Setpoint Index M-620S i
l CHANGE, TEST, OR EXPERIMENT: Facility Change Request 79-194 was written to revise setpoint index M-620S to include as-built setpoints.
REASON FOR CHANGE: To update setpoint index to reflect as-built setpoints.
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SAFETY EVALUATION: All changes to the setpoint index have been reviewed by Bechtel Engineering and Toledo Edison Engineering. All changes in this revision accurately reflect as-built conditions and are consistent with the Davis-Besse Unit 1 systems i
- designs as described in the FSAR. Exceptions include where changes to Davis-Besse Unit 1 have been made in accordance with 10 CFR 50.59 and documented by FCRs as j
required. Therefore, this change is not an unreviewed safety question.
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COMPLETED FACILITY CHANGE REQUEST FCR NO:
77-056 SYSTEM:
Boric Acid' Addition COMPONENT:
Boric Acid Pumps 1 and 2 l
CHANCE, TEST, OR EXPERIMENT:
Facility Change Request 77-056 was implemented to re-place the vent plug for Boric Acid Pumps 1 and 2 with a valved line to act as a cas-ing vent.
REASON FOR CHANGE:
Previously, the only vent path or means to vent the Boric Acid Pumps was the removal of the pipe plug. This modification allows the pump casing to be periodically vented by operation of a small manual valve instead of requiring tools to remove a vent plug.
SAFETY EVALUATION:
The function of the Boric Acid Pumps will not be affected by the addition of casing vent. Therefore, en unreviewed safety question does not exist.
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