ML19220A866
| ML19220A866 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/15/1978 |
| From: | Lengel R Metropolitan Edison Co |
| To: | NRC Office of Inspection & Enforcement (IE Region I) |
| Shared Package | |
| ML19220A864 | List: |
| References | |
| MOR-780531, NUDOCS 7904250048 | |
| Download: ML19220A866 (4) | |
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Si w ARY OF OPERATING EXPERIENCt. FOR THE "0!"TH Three Mile Island Unit 2 entered the month with the plant shu t down and depressurized pending the evaluation and implementation of a fix on Main Steam relief valve discharge piping expansion joint liners and the completion of miscellaneous outage-related work.
Primary plant chemistry clean-up continued and was completed on May 10.
Heat up commenced on May 13 with entry into Mode 3 achieved at 2130. At 0237 on May la reactor coolant pump RC-P-2A was secured due to high thrust bearing temperatures.
An investigation revealed an oil leak on RC-P-2A.
The plant was cooled down to effect a clean up of oil and repair the leak. The plant was again heated up on May 16 in preparation f or testing of main steam relief valves and rod drop testing. Rod drop testing was ccepleted on May 18 and main steam relief valve testing commenced. Relief valve performance was unsatisf actory and en May 23 further modifications to the relief discharge piping were commenced and a spare valve was returned to the vendor for =odification. On May 26 relief valve testing of the modified discharge piping continued. On May 27 the plant was cooled down for replacement of two relief valves with valves which had been modified by the vendor. On May 31 the plant was again heated up to conduct further testing of modified main steam relief valves. Presently testing of !!m modified relief valves is continuing.
MAJOR SAFETY RELATED MAINTE'!ANCE 1.
Steam generator safety valve modifications.
2.
Replaced vertical coupling on "3" emergency diesel generator.
3.
Repaired oil leak on reactor coolant pu=ps.
4 Replaced motor bearing on DC-P-1A.
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7 904 es o oe/s
g AVERAGE DAILY L"i!T PC'4ER LiviL D cc het :10,
50-320 UL; DfI-2 Date June 15, 1978 C0=pleted 3y R. A. Lengel 215-929-3601, Oct. 148 Telephone MC:iTH MAY CAY TIERAGE DAILY FC'4ER LI"JEL
- DAY A'7ERAGE DA'LY FC'ER LIVIL *
(T4e-Net)
(M'4e-Net )
1
- 4. s
-31
-4 2
18
-36
-0
-5 19
-34 3
g
-8 20
-37 5
21
-30
-8 6
-9 22
-32
-31
-5
.3
-13 2L
-30 g
-16
-30 o
25 10 26
-34
-10 11 27
-28
-22 12 23
-13
-24
-26
-12 13 29
-27
-13
.g
,o 13-
-19 2,
-33
-17
,6
- The negative numbers indicate that more energy was supplied to the unit than was produced by it, and are provided for your infor=ation only.
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4 CPERATING DATA REPCRT Decket No.
50-320 Date June 15, 1978 Cenpleted Ry A.
Lengel U
CPERATING STATUS Telechene 215-929-3601 Ex t. 148 1.
Unit Name:
Three Mile Island Unit 2 2.
Repcrting Peried: }ay1976 3
Licensed '"he: al ?cver (W.it ): 2772 961 4
Naneplate Rating (Gross MWe):
5 Design Electrical Rating (Net MWe): 906 6.
Max. Cependable Capacity (Gross MWe): 930 7
Max. Cependable Capacity (Net MWe):
880 3.
If Changes Cccur in Caracity Ratings (Ite=s No. 3 threugh 7) Since last Repert.
Give Reasons:
9
?cver Level to which Restricted. If Any (Net MWe):
2568 Mwt 10.
Resacns for Restrictions, If Any:
Power is linited pending additional 3&W analvsis of Small Break LOCA.
744 1555 1555 11. Hcurs in Reporting Period 342.2 342.2 12.
No. of Ecurs Reactor was Critical 0
568 568 568 13 Reactor Reserve Shutdevn Ecurs ik.
Heurs Generator Cn-Line 0
42 42 0
0 o
15 Unit Reserve Shutdevn Ecurs 16.
Gross Thermal Energy Generated (MWH) 0 37d21 37921 17.
Gross Elect. Energy Generated (MWH) 0 s292 cang 18.
Net Electrical Energy Generated (MWH)
-15531
-39111
-30111 "A
N/A N/A 19 Unit Se vice Factor N/A N/A N/A 20.
Unit Availability Facter 21.
Unit Capacity Factor (Using MDC Net)
N/A N/A N/A 22.
Unit Capacity Factor (Using DER Net)
N/A N/A N/A N/A N/A N/A 23.
Unit Forced Cutage Rate 2h.
Shutdevns Scheduled Cver Next 6 Months ('"ype, Date, and Ouration of Zach) :
N/A 25 If Shut Dcvn at End of Report Period, Estt:ated Cate of Startup:
- 26. Units In Test Statt s (Frier to Cc==ercial Operatien):
FCRECAST ACHIEVED INITIAL CRITICALITY 3/09/73 3/29/78 3/15/78 4/21/78
- v. t. lu e_r_;v-.n r c-.v.
.r+
r CCMMERC!AL CPEF.ATICN 9/n1/78
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50-320 tRIIT SIIUTDOWNS AND POWEH HEDUCTIONS Docket. No.
~
HEP 0ft? MONTil MAY Date -_ lune 15-1278 Completed By R.
A.
I.cn y,e !
Telerhone 215-929-3601 Ext.148 l
S3 System Component Cause and Corrective No.
Date Type m
U "l S
$ ten O'
Code 34 Code 5 Action to as as E m
6: s.
om Prevent Hecurrence bm g
gg3 g,, y S N *l 0Sf a
$ iS N
',3 M m 1
5/01/78 F
744 11 3
78-33/IP Repair and testing of main steam safety valves o
C A
P (l'
iA IF. Fo rc ed PHeason:
3
" Exhibit G - Instructions ge( g 3: Scheduled A-Eqttipment Failure (Explain) for Preparation of Data 14nu al B-Maintenance or Tes t 2-Manual Scram.
""" "" I" #
C-HeBleling 3-Automatic Scram.
D-Regulatory Hestriction 1 -Other (Explain) 6 E-Operator Training & Licensee Examination F-Administrative S
G-Operational Error (Fxplain)
Exhibit 1 - Same Source li-Ot.her (Explain)
I