ML20065B520
| ML20065B520 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/15/1983 |
| From: | Smyth C GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20065B516 | List: |
| References | |
| NUDOCS 8302230158 | |
| Download: ML20065B520 (12) | |
Text
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OPERATING DATA REPORT DOCKET NO.
50-289 DATE February 15, 1983:
~
COMPLETED BY
_C.h'.
Srayth TELEPHONE /m m o'e_usu OPERATING STATUS Three P.ile Island Nuclear Station, Uni: I
- 1. Unit Name:
- 2. Reporting Period:
January, 1983 2535
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWe): _ 871 019
- 5. Design Electrical Rating (Ne't MWe):
- 6. Maximum Dependable Capacity (Gross MWe): {0
- D
- 7. Maximum Dependable Capacity (Net MWe):
S. If Changes Occur in Capacity Ratings (Items Number 3 Throu;h iJ Sin:t Last Report. Gise Reasone
[
4
- 9. Power Level To Which Restricted.1f Any (Net MWe):
i
- 10. Reasons For Restrictions,1f Any:
This Mornh Yr..t o.Da t e Cumulsth e 744*
744.
73777.
- 11. Hours in Reporting Period
- 12. Number of Hours Reactor was Critical 0.0 0.0 3;732.S 0.0 0.0 840.5
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 3115g.p
- 14. Hours Generator On-Line
~
U*O 0.0 0.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 7e n1071.
- 16. Gross Thermal Energy Generated (MWH)
O.
U.
m., m.
- 17. Gross Electrical Energy Generated (MWH)
O.
v.
ao va.:.
- 15. Net Electrical Energy Generated (MWH) 0.0 0.0 42.3
- 19. Unit Senice Feetor UU U *
42.3
- 20. Unit Availability Factor 0.0 0.0 41.2
[
- 21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 39.5 l
- 22. Unit Capacity Factor (Using DER Net) 100.0 100.0 33.1
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each :
I
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
l
- 26. Units in Test Status (Prior to Commer:ial Operation):
Forecast A chies ed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8302230158 830215
"~
DR ADOCK 05000289 gg,
AVERAG5 DAILY UNIT POWER LEVEL DOCKET NO.
50-289 THI-I B'IT February 15, 1983 DATE COMPLETED BY C. W. Smyth TELEPHONE (717) 948-8551 January, 1983 MONTH DAY AVERACE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL iMWe Net) t MWe Neti 1
0 17 0
0 0
13 3
0 0
19 4
0 0
20 o
5 0
)
U 0
22 7
0 0
- 3 8
0 0
24 0
0 9
25 0
0 10 6
0 27 0
0 1
25 0
0 13 29 0
0 14 30 0
0 15 31 0
16 0
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NRC OPERATING
SUMMARY
The unit was shutdown the entire month by order of the NRC.
The primary system was partially drained to permit continuing OTSG repairs.
Core cooling was pro-vided by the Decay Heat Removal system.
During December the first of the two phase OTSG tube expansion process was suc-cessfully completed (using 19 grain / foot candles).
During January, debris was cleaned from the tubes and preparations were made to begin the second phase of expansion (using 17 grain / foot candles). The second phase commenced at the end of January and carried into February.
MAJOR SAFETY RELATED MAINTENANCE During the month of January restart modifications continued and the following major maintenance items were performed.
The Once Through Steam Generator (OTSG) program continued with the following major work items accomplished.
1.
RC-H-1A ("A" OTSG) and RC-H-1B ("B" OTSG)
A.
Removed cold leg covers B.
Reinflated cold leg bladders C.
Refilled lower head with immunol D.
Completed final phase of kinetic expansion E.
Drained immunol from generators F.
Deflated cold leg bladders G.
Installed cold leg covers H.
Removed immunol sparger from lower head I.
Installed tube cleaning equipment J.
Commensed felt plug blowing (tube cleaning)
The Local Leak Rate Testing program continued with satisfactory testing of the following valves.
1.
WDG-V-3 9.
WDL-V-535 17.
CF-V-20A/B 2.
MU-V-25/26 10.
CA-V-189 3.
NS-V-4 11.
CA-V-192 4.
NS-V-ll 12.
CF-V-2A/B 5.
NS-V-15 13.
SF-V-23 6.
NS-V-35 14.
DH-V-64 7.
CF-V-19A/B 15.
DH-V-69 8.
WDL-F-534 16.
MU-V-2A/B The scheduled Spent Fuel system outage was completed with the following work items accomplished.
1.
"A" Loop A.
X-Ray inspection of SF-207 (satisfactory)
B.
Refilled system and tested satisfactorily per SP 1300-3A/1303-11.50 C.
Retorqued SF9-FE-1
-F.
A scheduled overhaul of River Water-pump SW-P-1E commensed with the following work. items completed.
1.
Removed motor 2.
Removed pump, disassembled and performed bearing and shaft inspections 3.
Overhauled pump and balanced rotating assembly 4.
Commensed assembly of pump 5..
Disassembled motor, overhauled, balanced, and reassembled The Concentrated Waste Storage Tank piping modification continued with the following items completed.
1.
"A" CWST discharge line/ valve work L
A.
Repaired diaphragm valve WDL-V-103 B.
Flushed piping C.
Performed a staisfactory hydrostatic test A scheduled overhaul of the Spent ~ Fuel. Bridge Fuel lbst commenced with the following work items completed.
1.
Removed the fuel mast from the bridge 2.
Disassemble grapple assembly from the mast 3.
Installed and adjusted new fuel grapple Ultrasonic testing (UT) of 6A extraction line T off of MO-T-2C inlet as a 2
result of NRC Information Notice 82-22 (July 9, 1982 due.to 4 ft section of steam pipe blown through at Oconee Unit 2 destroying a 480 volt MCC) resulted in several readings of 0.14" on testing grid. Nominal pipe thick-ness for new pipe is 0.375" indicating a need for repair on this line.
Two other areas indicated minor thickness deterioration. GPUN is also pursuing testing of several other suspected problem areas.
~
REFUELI7;G INFORV.ATIOK EE0"EST 1.
Nst.e of Facility:
Three Mile Island Nuclear Station, Unit i 2.
Scheduled date for next refueling shutdown:
Unknown 3
Scheduled date for restart folleving refueling:
Unhnoun L.
iiill refueling or resu=ption of operation thereafter require a technical specification change or other license amend:ent!
e.nsver is yes, in genera.,, what vi_..A :nese ce,t 2.
If a.nsver is no, has the reload fuel desig. e.ni ::re c:nfigu a:1:n teen reviewed by your Plant Safety Review C:::ittee tc deter:ine whe:her any unreviewed safety questions are asse:iated with the core rel:ad (Ref. 10 CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
Arend=ent No. 50, Cycle 5 reloe.i, was a;;revei en 3-ic-T'.
5 Scheduled date(s) for submitting prcpesei li:ensing acticn c.nd sup r.i.c infer:ation:
/x.
c.pertant licensing considerati~ns associatei vitr re,ueling, e.g. nsv o
c.
or different fuel design or supplier, unrevievei design er perf:rnance ane. lysis methods, significant changes in fuel design, nev :;ere-ing procedures:
H/A 7
The number cf fuel assemblies (a) in the c:re, a.i '.i ' in the :;er; fuel sterar_e :>oc1:
, s kai
-iI (b) 205
.e. 2....w......=..m p.n. < 1,co,. s~... e..
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.,.. e e..
_, 4 c en 3 e,a
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.y anv. increase in licensed store-se capaci:.r that has been requestei er is
- 1anned, in nuncer of fuel asse blies
The present licensed capacity is 752.
There are n: planned increases at this time.
9 The p.cjected date of the last refueling -"=
"- te discharrei :: :he spen-fuel pool assuring the present licensed cata:i; -
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4.
4
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e capacity (177 fuel assemblies).
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[
OPERATING DATA REPORT DOCKET NO.
50-289 DATE February 15, 1983 COMPLETED BY C.W. Smyth
~
TELEPHONE 7 '" n m u 9s s, OPEILATING STATUS Three Mile Island Nuclear Station, Unit I
- 1. Unit Name:
Januarv. 1983
- 2. Reporting Period:
2535
- 3. Licensed Thermal Power (MWt):
871
- 4. Nameplate Rating (Gross MWe):
019
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe): {0
- D
- 7. Maximum Dependable Capacity (Net MWe):
- 5. If Changes Occur in Capacity Ratings (Items Number 3 Through 71 Since Last Report. Give Reasons:
4
- 9. Power Level To Which Restricted.1f Any (Net MWe):
- 10. Reasons For Restrictions,if Any:
This Month Yr.-to Date Cumulatise 744.
744.
73777.
- 11. Hours in Reporting Period 11 Number Of Hours Reactor Was Critica!
0.0 0.0 31731.E 0.0 0.0 840.5
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 31160.9
- 14. Hours Genentor On-Line O.U 0.0 0.0
- 15. Unit Reserve Shutdown Hours 0.0 0.0 7 e5M071.
- 16. Gross Thermal Energy Generated (MWH)
O.
O.
23uo,;;u.
- 17. Gross Electrical Energy Generated (MWH) u.
v.
tooeva;.
IS. Net Electrical Energy Generated (MWH) 0.0 0.0 42.3
- 19. Unit Service Factor 0.0 v.v 42.3
- 20. Unit Avai!sbility Factor 0.0 0.0 41.2
- 21. Unit Capacity Factor (Using MDC Net) 0.0 0.0 39.5
- 22. Unit Capacity Factor (Using DER Net) 100.0 100.0 h1
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Eacht:
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed INITIAL CRITICALITY INITI AL ELECTRICITY COMMERCIAL OPERATION p,e-
AVER AGE DAll Y UNIT POWER LEVEL DOCKET NO.
50-289
~1 UNIT February 15, 1983 DATE COMPLETED BY C. W. Smyth TELEPHONE _ (717) 948-8551-January, 1983 MONT11 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe Neti 3
0 17 0
2 0
0 16 3
0 0
19 4
0 0
20 0
5 21 0
6 0
7 0
0 0
8 0
0 9
25 0
0 10 26 0
II 27 0
O 1,
25 0
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0 14 30 0
0 15 31 0
16 0
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Y NRC OPERATING SISDD.RY The tait was shutdown the entire month by order of the NRC.
The primary system was partially drained to permit continuing OTSG repairs. Core cooling was pro-vided by the Decay Heat Removal system.
During December the first of the two phase OTSG tube expansion process was suc-cessfully completed (using 19 grain / foot candles).
During January, debris was cleaned from the tubes and preparations were made to begin the second phase of i
expansion (using 17 grain / foot candles).
The second phase commenced at the end of January and carried into February.
MAJOR SAFETY RELATED MAINTENANCE During the month of January restart modifications continued and the folleving major maintenance items were performed.
The Once Through Steam Generator (OTSG) program continued with the following major work items accomplished.
1.
RC-H-1A ("A" OTSG) and RC-H-1B ("B" OTSG)
A.
Removed cold leg covers B.
Reinflated cold leg bladders C.
Refilled lower head with immunol D.
Completed final phase of kinetic expansion E.
Drained immunol from generators F.
Deflated cold leg bladders G.
Installed cold leg covers H.
Removed immunol sparger from lower hea'd I
Installed tube cleaning equipment J.
Commensed felt plug blowing (tube cleaning)
The Local Leak Rate Testing program. continued with satisfactory testing of the following valves.
1.
WDG-V-3 9.
WDL-V-535 17.
CF-V-20A/B 2.
MU-V-25/26 10.
CA-V-189 j
3.
NS-V-4 11.
CA-V-192 l
4.
NS-V-ll 12.
CF-V-2A/B 5.
NS-V-15 13.
SF-V-23 6.
NS-V-35 14.
DH-V-64 7.
CF-V-19A/B 15.
DH-V-69 8.
WDL-F-534 16.
MU-V-2A/B The scheduled Spent Fuel system outage was completed with the following work items accomplished.
1.
"A" Loop A.
X-Ray. inspection of SF-207 (satisfactory) l B.
Refilled system and tested satisfactorily per SP 1300-3A/1303-ll.50 C.
Retorqued SF9-FE-1
A scheduled overhaul of River Water pump SW-P-1B commensed with the following work items completed.
1.
Removed motor 2.
Removed pump, disassembled and performed bearing and shaf t inspections 3.
Overhauled pump and balanced rotating assembly 4.
Commensed assembly of pump 5.
Disassembled motor, overhauled, balanced, and reassembled The Concentrated Waste Storage Tank piping modification continued with the following items completed.
1.
"A" CWST discharge line/ valve work A.
Repaired diaphragm valve WDL-V-103 B.
Flushed piping C.
Performed a staisfactory hydrostatic test A scheduled overhaul of the Spent Fuel Bridge Fuel Mast commenced with the following work items completed.
1.
Removed the fuel mast from the bridge 2.
Disassemble grapple assembly from the mast i
3.
Installed and adjusted new fuel grapple Ultrasonic testing (UT) of 6A extraction line T off of MO-T-2C inlet as a 2
result of NRC Information Notice 82-22 (July 9, 1982 due to 4 ft section of steam pipe blown through at Oconee Unit 2 destroying a 480 volt MCC) resulted in several readings of 0.14" on testing grid.
Nominal pipe thick-ness for new pipe is 0.375" indicating a need for repair on this line.
Two other areas indicated minor thickness deterioration. GPUN is also pursuing testing of several other suspected problem areas.
r, - -
RI"'VELING IWORV.ATION ?.IMST
- i. Name of Facility:
Three Mile Island Nuclear Station, Unit i 2.
Scheduled date for next refueling shutdown:
Unknown 3
Scheduled date for restart following refueling:
Unknown h.
Will refueling or resumption of operation thereafter require a technice.1 -
specification change or other license atendren 0 If answer is yes, in general, vnat vill these te!
If ansver is no, has the reload fuel design sni ::re c:nfigurati:n teen reviewed by your plant Safety Reviev Co=it.ee tc dete=ine whe:her any unreviewed safety questions are asse:iated with -he ecre rel:ad (Ref. 10 CFR Section 50 59)?
f If no such review has taken place, when is i; scheduledi Amend:ent No. 50, cycle 5 reload, was a;;revei en 3-16-T.0 5
Schedu. led date(s) for sutritting proposed licensing e. : den s.nd supp ting infom ation:
,. iA 6.
Important licensing considerations associatei vich refueling e.g. new or different fuel design or supplier, unreviewed design er perf:=;nce ane. lysis methods, significant changes in fue; de:ign. nev 0;ers. ing procecures:
N/A 7
The nu=ber of fuel asse=tlies (a) in the etre, and t' in he ;en; fue; s crare poel:
i
( a) mac (v )s u
Cvu 5.
The present licensed spent fuel pool s:O r sge : a; 1:i::- sna che size :f any increase in licensed storage capaci::: tht he.s teen requestei er is planned, in nu 'oer of fuel asse:blies:
-af-...s.
<er.
.w....
3-
..:.. e
....e.e r..,.e.,..sen.
34ce se4 o
c
....-~..
. % e.
c.
o.
The prcjected date of the las refueling that :in te dis:h.rgei :: the spen-fuel pool assu=ing the present licensed ca;t:it:.
1957 is the last refueling discha se -hi:t s1.:vs :til ::re :ff- :ai capacity (l'iT fuel assemblies).
'