ML20058B067
| ML20058B067 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/07/1982 |
| From: | Sarsour B TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20054M010 | List: |
| References | |
| NUDOCS 8207220618 | |
| Download: ML20058B067 (8) | |
Text
i AVERAGE DAILY UNIT POWER LEVEL s
DOCKET NO.
50-346 7)
Davis-Besse #1 g,lT DATE 5/07/82 COMPLETED BY Bila1 Sarsour TELEPHONE (419) 259-5000 ext. #384 MONTH April, 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(Mwe. Net) 1 0
17 0
2 0
18 0
3 0
g9 0
4 0
20 0
5 0
21 0
(,
0 0
22 7
0 23 0
M 0
0 24 9
0 25 10 0
0 26 l1 0
0 27 12 0
yg o
I.4 0
29 0
14 0
30 0
15 0
3, 1(.
O INS'lK Lit.*llONS On tlus loimas.In: the avesar.c ilaily imst powei lesci ni MWe Nel los cacia day in alie reposting nn.nili,(:oisapute in ifee sic.asess winite nwg.swaii.
(9/77 )
k 8207220618 820609 PDR ADOCK 05000346 R
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OPERATING DATA REPORT DOCKET NO.
50-346 DATE 5/7/82 COMPLETED BY Bilal Sarsour TELEP110NE f419) 259-5000 OPER ATING STATUS Davis-Besse Unit #1 Notes
- 1. Unit Name:
- 2. Reimrting Feriod:
April, 1982
- 3. Licensed Thermal Power (MWI):
2772
- 4. Nameplate Rating (Grow MWe):
925
- 5. Design Electrical Rating (Net MWe):
906
- 6. Maximum Dependable Capacity (Gross MWe): 918
- 7. Masimum Dependable Capacity (Net MWe):
874 M. If Changes Occur in Capacity !tatings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted lf Any (Net MWe):
- 10. Reasons For Restrictions.lf Any:
This Month Yr. to-Date Cumulative II. Iluurs in Reporting Period 719 2,879 32,880
- 12. Number Of Hours Reactor Was Critical 0
1,708 17,938 1.1. Hractor Reserve Shutdown Hour, 0
0 2.334.7
- 11. Ilonrs Generator On-L' nc 0
1,707.4 16,957.6 u
- 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 Electrical Energy Generated (MWH) 0 1.202.294 12.884.545 th. Net I.lectrical linergy Generated (MWH) 0 1,124,093 12,021,378
- 19. linia Service Factor 0
59.3 51.6 lit. thiit Availability Factor 0
59.3 56.8
- 21. Unit Capacity Factor (Using MDC Net) 0 44.7 41.8 l
- 22. linia Capacity Factor (Using DER Net) 0 43.1 40.4
!1 2.1. Unit Forced Outage Rate 0
0 23.0 2 3. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each t:
- 25. If Simt flown At End Of Report Period. Estimated Date of Startup:
August 1, 1982 2r.. tinits in lest Statu.(Prior to Commercial Operation):
Forecast Achiesed INITIAL CRITICALITY INITIA L ELECTRICITY i
COMMiiRCI A L OPER ATION I
l (9/77I
3 DOCKET NO.
50-346 UNIT SHUTDOWNS AND PON;t REDUCT:UNS UNIT NAME Davis-Besse Unit 1 DATE 5/7/82 COMPLETED BY Bilal Sarsour REPORT MONT!!
April, 1982 TELEPIIONE 419-?59-5000- Ext. 384 n.
E E
5g 3
j.Y Q Licensee Eg go Cause & Corrective No.
Date
.g Eg i
js&
Event gy 91 Action to yV yE j gf3 g Report a mu Prevent Recurrence-H 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.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G-Instructions S: Schedu!cd A-Equipment Failure (Explain) 1-Manual for P eparation of Data B Maintenance or Test 2 Manual Scram,.
Entry Sheets for Licensee C Refueling 3 Automatic Scram.
Event Report (LER1 File (NUREG-D Regulatory Restriction
- 4-Continuation from Previous Month 0161) l E Operator Training & License Examination 15-Load Reduction F Administrative 60ther (Explain) 5 G Operational Eisor (Explain)
Exfiibit I - Same Source
~
l (9/77)
Il Oiher (Explain) l a
J
OPERATIONAL
SUMMARY
April, 1982
(
04/01/82 - 04/30/82:
The unit outage which began on March 13, 1982 was still in progresa 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 othar 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-unte possible corrective action.
(3)
The turbine, associated valves, and the #2 main feed pump 1 f-were disassembled and inspected.
Problems were found in
{-
The problem was cracks appearing on the steam admission side the 'A' low pressure turbine rotor (1-2) lith stage buckets.
of the dovetail. The failure mechanism appears to be fre-quency related, high cycle fatique.
Similar problems were found to exist on 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 discoverc i 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
Paga 2 April, 1982
('
(7)
The Bailey 855 station computer was removed and replaced by the new MODCOMP classic dual central processing unit 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 replaced.
(11)
FCR work continued this month. A detailed list of the major FCRs completed will be provided at a later date.
BMS/lmr
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REFUELING INFORMATION DATE:
April, 1982
~
1.
Name of facility:
Davis-Besse Unit 1 2.
Scheduled date for next 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 s cation change or other license amendment?
pecifi-If answer is yes, what in general, will these be?
tion been reviewed by your Plant Safety Review Committee to deter CFR Section 50.59)?any unreviewed safety questions are associated with the core reload (
e whether
. 10 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 changes relating to core operational limits and reactor protection system setpoints.
cycle length is also provided An option to provide flexibility in the overall therein.
S.
Scheduled date(s) for submitting proposed licensing action and supporti mation.
See response to No. 4 above ng infor-6 Important licensing considerationc associated with refueling different mett.ods, significant changes in fuel design, new operating proc e.g., new or Nonn identified to date 7.
The number of fuel assemblies (a) in the core and (b) in the spent f pool.
uel storage (u)_
177 (b) 92 - Spent Fuel Assemblies 8.
The present licensed spent fuel pool storage capacity and the size of number of fuel assemblies. crease in licensed storage capacity that has been requested o any in-
, in Present 735 Increase size by 0 (zero) 9 The pro.]ected date of the last refueling that can be discharged to fuel puoi assuming the present licensed capacity.
the spent Date 1988 - assuming ability to unload the entire core into the spent fuel pool is maintained.
COMPLETED FACILITY CHANGE REQUEST
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FCR NO:
79-194 SYSTEM: N/A COMPONENT:
Setpoint Index M-620S 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.
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 designs as described in the FSAR. Exceptions include where changes to Davis-Besse i
Unit 1 have been made in accordance with 10 CFR 50.59 and documented by FCRs as 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 CHANGE, 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 j
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, an unreviewed safety question does not exist.
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