ML20070B944
| ML20070B944 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/31/1991 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-91-2011, NUDOCS 9102190220 | |
| Download: ML20070B944 (6) | |
Text
.
o GPU Nuchar Corporation
--' UClMF Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Nurnber.
(717) 948-8191 February 13, 1991 c311-91-2011 U. S. Hualear Regulatory Commission
>.t '.c. i Document control Desk Wab.)ington, D.C.
20553 Centlement
Subject:
Three Mile Island Nuclear Station, Unit I (THI-1)
Operating License No. DPR-50 Docket No. 50-289 Moti6hly operating Report January 1991 Enclosed are two copies of the January, 1991 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, iW T. G. Br ughton Vice President & Director, THI-1 WGH cci Atministrator, Region I THI Senior Resident Inspector 4
Attachments 9102190220 910131 PDR ADOCK 05000289 R
PDR f"6 AL/
2 D ' ODD GPU Nuclear Corporation is a subsidiary of General Pubhc Utdities CorDoration
(/g
c.
.w f
OPERATIONS
SUMMARY
JANUARY 1991 The unit entered the month operating at -94% power.
Power output was limited by high OTSO level on the "B" side.
The number one seal leakoff on the "A"
RCP had been exceeding the 5 gpm alarm limit requiring the alarm setpoint to be increased. This raised setpoint continues to be within the manufacturer's recommendation.
The plant continued to operate at at maximum power output I
throughout the month. The unit closed the month operating at ~93% power, with power output limited by high *B* OTSG 1evel.
MMQR SAFETY RELATED_ MAINTENANCE During January, the following major safety related maintenance activity was performeds v
Ngglear Servies. River Water Pume NR-P-1C High vibrations caused Nuclear Service River Water Pump NR-F-1C to be removed from service for repair.. After disassembly, the pump was rebuilt using new pump shafts, bearings, tubes, columns-and bowl assembly.
The motor bearings were also replaced before the motor was reinstalled and the motor / pump coupling connected.
In-service testing was.satisfactorilly completed and the pump returned to service.
Main Steam Safety Relief Valve MS-V-20D Heated E213 Main Steam Safety. Relief Valve MS-V-20D Heated Post was taken out of service to repair a leaking union on the steam inlet. -The repair was effected by inctalling a gasket between the union halves Upon return of the heated _ post to service, no. leakage una observed.
Main Steam Turbine Evoass Valves MS-V-3 A/F Main: Steam. Turbine Bypass Valves MS-V-3 A/F were inspected, repaired am necessary'and testing of. valve closing times was performed in response to a
- SPI?"? recommendation.. Valve positioner closing times which meet the accep-tance criteria were acheived~after.all air line tubing was uniformly sized and i
r E
.the booster air filters wore bypassed.- The work was accomplished in accor-dance with approved engineering guidance.
p 2
l
{
J
_. - - - - ~
1 W
OPERATING DATA' REPORT DOCKET NO.
50 009 DATE 2/15/91 COMPLETED BY. W. G. Heysek TELEPHONE (717) 948 8191 OPERATING STATUS l NOTES I
i 1.
UNIT NAME:
THFEE MILE ISLAND UNIT 1 1 i
2.~,CEPORTING PERIOD:
JANUARY
,1991. I i
-3.iLICENSED THERMAL POWER (MWT):
2568. I i
4.- NAMEPLATE-RATING (GROSS MWE):
871. 1 I
G. - DESIGN -ELECTRICAL RAYING (NET MWE):
819. I
't 6., MAXIMUM DEPENDABLE. CAPACITY (GROSS MWE):
856. I i
7.
MAXIMUM DEPENDHBLE CAPACITY INET MWE):
808. I I
i
_i 8.
IF-CHANGES OCCUR IN (ITEMS'3-7) SIN *C L957 REPORT, GIVE PEASONS:
-O.-POWEF-LEVEL TO WHICH RESTFICTED. IF ANY tNE1 MUE)
- 10. REASONS FOR RESTRICTION 5, IF 4NYe THIS MONTH YR-TO-DATE CUMMUwATIUC 11.. HOURS IN REPOPTING PERIOD 744 744.
143905..
. 12. NUMBER OF HOURS' REACTOR WAS CRITICAL 744.0 744.0 C9908.2
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 2245.6 114;t HOURS GENERATOR ON-LINEL 744,0 744.0 E9863.7
.r LIO.UUNIT RESERVE SHUTDOWN HOURS 0.0 0.O' 0.0
- 16. GPOSS THERf1GL ENERGY GENERATED (11WH T 1770083.
'1770083.
ICB14885G.
- 17. GROSS ELECTRICAL ENERGY' GENERATED (MWH) 607783.
6077C3.
06E68667.
21 8. NET" ELECTRICAL ENERGY GENERATED LMWH1 572278.
572270.
53061698..
219. UNIT SERVICE FACTOR 100.0 100.0 47.9 l20. UNIT: AVAILABILITY FACTOR:
100.0 100.0 47;9
.01.
UNIT CAPACITY FACTOR (USING MDC NET) 95.2 95.2 47.0
- 22. UNIT CAPACITY FACTOR (USING DER NET) 93.9 93.9 45.0
. 23.-UNIT FORCED OUTAGE RATE O.0 0.0 46.8
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS.(TYPE, DATE. AND DURATION OF CACH l.(:
25.;IFiSHUT DOWN AT END.0F REPOPT PERIOD, ESTIMATED DATE OF STARTUP:
1.
b o
- - ~ _ - -
=>
..n AVERAGC Dr,ILY UNIT POWER LEVEL T
DOCKET NQ.
50-289 UNIT TMI-I DATE 2/15/91 COMPLETED BY - W. G. Heysek TELEPHONE _(717) 948-8191 MONTH:
JANUARY DAY AVERAGE DAILY POWEP LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NCT) 1 774 I7 766.
2 773.
10
- 759, 3
771.
19 769.
4 774.
2r 766.
5 774 21 769.
6 770.
72 770.
7 774 O3 767 C
-775.
24 767 9
773.
07 703.
10 771.
11 766.
11 770.
2*
7CE.
10 770.
20 7C4 13 769.
29 7E?.
14 772.
10 7E 5.
-lS.
770.
1; 76 3.
16 709.
i l
l
e --
e.
ButIT sutrTBoups AleB POWER RESUCTIcerS BeatET see. 50-289 WWIT Mass THI-1 REPORT MONTH January 1991-Be2E 2/15/91 Cess'EATED BY W. C. Iteysek MN (717) 948-8191 r
seethod of Licensee Systes :ews cause a corrective
- 0*
Dete' Type Buretion Beeson Shutting.
' Eve"It.
Codt CW Action to (Neurs) 9eun Reymrti ~
P'"'"t s**"'#'"
3
& P6
$g-a
- eoctor NONE n
1 2
3 4
F forced Resoon seetfied Exhibit G - Instructions for S Scheduled A-Egsisement Feiture (4mptein) 1-storest preparotion of Dete Entry Sheets a-seeintenance or Test 2-sennuel Scres for Licensee Ewept Report (LEA)
. C-sefueling 3-autametic Scree -
File (uuBEG-8161)
D-Seguletory Restriction 4-Otteer (Emplain)
E-euserotor Training & Licensing Enemination 5 Ed ibit 1 same source F-administrative
'l G-eperettenst Error (Emplain) 6 Actually used exhibits F & II musEG 0161 W-Ot%er (Emptein) -
I l
1 5
l
_1 a
~ * $
s
+
\\
- s REFUELING INPCMATip&,,BgQV11I 1.
Name of Tacility:
Three Nile Island Nuclear Station, Usit 1 2.
Scheduled date for next refueling shutdown:
October 4, 1991 (9R) 3.'
scheduled date for restart following current refueling:
NA 4.
Will refueling or resumption of operation thereafter require a technical l
specification change or other license amendment?
No.
If answer is yes, in ger.?ral, what will 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)?
No.
If no such review has taken place, when is it scheduled? 6/1/91.
- 5. _
Scheduled-date(s) for submitting proposed licensing action and support-ing information None planned.
6.
Important licensing considerations associated with refueling, e.g. new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating proceduras GPU Nuclear plans to install fourl Westinghouse Lead Test Assen-blies during the reload of the THI-1 core for cycle 9 operation.
Westinghouse fuel technology will be utilised to the extent possihte.
7.
The' number ~of fuel assemblies (a) in the core, and (b) in the spent fuel etorage pools (a).177 (b)~441 8.
'The present lic6nsed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that ha'
-een requested or is planned, in number ofifuel assemblies:
The present licensed capacity is 752. ' Planning to increase licensed capacity through fuel pool rsracking is in progress.
9.
'The projected date of the last refueling 'that can be discharged to the spent fuel pool assuming the present licensed capacity:
1991'is the last refueling dischargw which allows full core off-load espacity (177 fuel assemblies).
r 6
w
_. _ _, _ _ _. ~..... _.. _. - _.. _. _ _. -... -.. - _ _. _ _. - ~. _.. _.
.