ML20083B990
| ML20083B990 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/30/1983 |
| From: | Hukill H, Casey Smith GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC |
| References | |
| 5211-83-365, NUDOCS 8312220051 | |
| Download: ML20083B990 (7) | |
Text
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O GPU Nuclear Corporation NggIgf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057-0191 717 944-7621 TELEX 84 2386 Writer's Direct Dial Number:
December 16, 1983 5211-83-365 Office of Management Information and Program Control c/o Distribution Services Branch DPC, ADM U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for November Enclosed please find two (2) copies of the November Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, 0
h-II. D. Hu il Director, TMI-l HDH:vj f Enclosures cc:
V. Stello Dr. Thomas E. Murley l
NY I(
8312220051 831130 gDRADOCK 05000289 PDR GPU Nuclear Corpora; ion is a subsidiary of the General Public Utilities Corporation
_.a OPERATING DATA REPORT DOCKET NO.
50-284 ETAYE December 16', 1983 COMPLETED BY C. W. Smyth TELEPHONE (717) 948 8551 h
OPERATING STATUS NOTES
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1
~- 2NPORTING7ERIOD:
NOVEMBER,1983.
{6 -
- 3. LICENSED THERMAL POWER (MWT):
2535.
- 4. NAMEPLATE RATING (GROSS MWE):
871.
d.
DESIGN 7LTCTRICAL RATING (NET 71WE ) :
819.
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
824.
[
7 MAXIMUM DEPENDABLE CAPACITY (NET MWE):
776.
r i
t I
%- TF CHANGES OCCUR IN-(TTEMS 3;7) 61NUL LAbT RBPuxr, Ulvt xtASONb:
p-L l
77 POWER LLVEL TO WHICH-'RESTRICTEDMF 7sNY (NLr Mwn) l 10 REASONS FOR RESTRICTIONS, IF ANY:
i i
+
THIS MONTH YR-TO-DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD 720 8016.
81049.
i-4-2----NUMBER-OF-HOURS--REACTOR-WAS~ CRITICAL O.0 0-0 3t?3t-fi
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 838.5 14 HOURS GENERATOR ON-LINE 0.0 0.0 31180.9 15.~~ UNIT RESERVE SHUTDOWN HOURS 00
-0;0 n,n
- 16. GROSS THERMAL ENERGY GENERATED (MWH)
O.
O.
76531071.
17 GROSS ELECTRICAL ENERGY GENERATED (MWH)
O.
O.
25484330
- 3 '.-NET ~ ELECTRICAL" ENERGY-GENERATED-( MWH ) ----
O.
O.
2384~n053.
- 19. UNIT SERVICE FACTOR 0.0 0.0 38.5 20 UNIT AVAILABILITY FACTOR 0.0 0.0 38.5
~ 21~.- UNIT ~ CAPACITY-FACTOR-'( USING ' MDC ~ NET )-
0.0 0-0 3776
~
2.2. UNIT CAPACITY FACTOR (USING DER NET) 0.0 0.0 35.9
- 23. UNIT FORCED OUTAGE RATE 100.0 100.0 57.7 q
24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH
!S.- IF SHUT ~ DOWN AT END OF~ REPORT PERIOD, TSTIMATED7 ATE OF STARTUP:~
==
m-6
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m.--.
..-m-i m.-%-~.
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l AVERAGE DAILY UNIT POWER LEVEL b
-4, I
i DOCKET NO.
50-289 UNIT TM1-1 I
DATE December 16, 1983 COMPLETED BY C. W. Smyth 5--
TELEPHUNE~ (7177 941I-8531 p
F MONTH 1 rTOVEMBER I
F DAY-AVERAGE-DATLNER-LtVEL DAY AVERAGE DAILY POhr.,x LLv6L (MWE-NET)
(MWE-NET) i 1
0 17 0
2 G.
15 O.
3 0,
19 0
4 0
20 0
5 O.
21 6
6 0
22 0
7 0
23 0
8 0.
24 6
U 9
0 25 0
1.
10 0
26 0
I 11 G.
27 n.
- l L
12 0
28 0
L 13 0
29 0
}
~
11 G.
36 6
15 O.
31 N/A if 16 0.
e l
l---..
~
l l
w waw a
- -atmewee wwe w +
--M aymm.hso-!3ese
+m-m e.
50-289 UNIT SilUIDOWNS AND POWER REDUCTIONS DOCKET NO.
UNIT NAME TM1-1 DATE December 16. 1983 COMPLETED RY C. W. Smyth REPORT MONTil November. 1983 TELEPilONE -(7171 QLR-R551 I
s c_
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3
-a S
cX Licensee g-r, aa.
Cause & Corrective
.5! e E
7 c
No.
Date g
g g
.;g g 5 Event u?
83 Action to E
$E 3 5 :!
RePor8 2' N0 o'
Prevent Recurrence e
u 6
1 83/11/01 F
744 D
1 N/A ZZ ZZZZZZ i
i 2
3 4
F l'orced Reason.
Method:
Exhibit G. Instructions 5 Sc heduled A.I quipment Failure (Explain) 1 -Manual for Preparation of Data Il-Maintenance of Test 2-Manual Scram.
Entry Sheets for 1.icensee C-Rel ueling 3 Auf omatic Sciam.
livent Repor (l.I.R) File (Ntliti G-D Regulatory itestriction 4 Other (lixplain) 0161) li-Operator 1 raining & Iicense lisamination F-Ad minist rative 5
G-Operatjonal 1:r ror (lisplain t I:shibit i. S.une Source II-Ot her (I' xplaio l
L OPEP.ATIONS
SUMMARY
The Plant has been in cold shutdown the entire month by order of the NRC.
Core cooling was provided by the Decay Heat Removal System. The Primary System was partially drained for the repair of DH-V1.
It was maintained partially drained until ll/24.
The root valves for the Reactor Vessel water level trending in-strumentation and the head vents were installed.
The Primary System was then re-filled for the remainder of the month and was maintained with a bubble in the pressurizer and RCS pressure at about 310 psig and a temperature of 120-130 F.
Upon filling the Primary System, sulfates and chlorides exhibited a definite increas-ing trend.
One RCP was run continuously to prevent the settling out and concentra-tion of the cantaminants while cleanup was in progress. By the end of the month, both chlorides and sulfates had been reduced to well within specifications.
MAJOR SAFETY RE1ATED MAINTENANCE The following work was performed during the month:
Snubber Testing The Snubber Testing and Repair program continued with appro:cimately 20 snubbers being rebuilt. This program is nearly completed and has resulted in the overhaul of all but about 20 snubbers in the plant.
DH-V1 Repair Decay Heat Removal valve DH-V1 (RCS Loop B DER suction valve) had been dis-assembled the previous month af ter it was found to be leaking (body to bonnet seal ring leak).
This valve had been furmanited approximately six years ago.
Minor erosion of the seal ring was found.
The seal ring was reolaced and the valve reassembled.
Core Flood Valve Repair The following work was performed on three core flood system valves:
CF-VIA (14" "A" CFT Dischg Iso Valve) - repaired pressure seal ring leak CF-VlB (14" "B" CFT Dischg Iso Valve)- repacked CF-V4B (14" "B" CFT Dischg Check Valve)
_apaired pressure seal ring leak.
Main Steam Safety Relief Valves A major program to disassemble, inspect, and perform seat work on 14 main steam safeties was started. Nine of the 14 were completed.
The remaining valves will be completed during December.
This work is being performed be-cause the 14 valves were found to be weeping during Hot Functional Testing.
-o.
t WDG-V-12 Waste Gas System relief valve V-12 was found to be leaking through and was disassembled, overhauled and reassembled. The valve was satisfactorily bench tested and reinstalled.
MU-V16A Makeup System valve MU-V16A (IIPI Isolation Valve) was disassembled for replacement of a scored stem.
Valve Repacking Program A major program of valve repacking was completed during the month with numerous valves in the Reactor Coolant System,' Decay Heat Removal System,
-and the. Makeup and Purification System being repacked, t
i t
i 4 t I
t i
EIRT1:US THFCPRATICT EI "Z5:
1.
Kane of Facility:
Three Mile Island Nuclear Station, Unit 1 2.
Scheduled date for next refueling shutdown:
Unknown 3
Scheduled date for restart following refueling:
Unknown h.
- 'ill refueling or resu=ption of operation thereafter require a technical w
specification change or other license amendment?
If answer is yes, in general, what vill these be?
If answer is no, has the reload fuel design and core configuration 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)?
If no such review has taken place, when is it scheduled?
Amendment No. 50, cycle 5 reload, was approved on 3-16-79 5
Scheduled date(s) for sut=itting proposed licensing action and supporting information:
N/A 6.
Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or perfcrmance analysis methods, significant changes in fuel design, new operating procedures:
N/A 7
The number of fuel assemblies (a) in the cere, and (b) in the spent fuel storage pool:
(a) 177 (b) 208 8.
The present licensed spent fuel pool storage capacity and the site of any increase in licensed storage capacity that har been requested er is planned, in number of fuel assemblies:
The present licensed capacity is 752.
There are no planned increases at this time.
9 The projected date of the last refueling that can be discharged ic the spent fuel poc1 assuming the present licensed capacity:
1967 is tha last refuelinc discharge which allers full core cff-1 cad capacity (177 fuel assentlies).
.