ML18005A812
| ML18005A812 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 02/28/1989 |
| From: | Hale M, Watson R CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| HO-893005-(O), NUDOCS 8903220183 | |
| Download: ML18005A812 (11) | |
Text
" ACCELEPJTED DI~BUTION DEMONSTR10K, SY)~gg REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:8903220183 DOC.DATE: 89/~8 NOTARXZED: NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFXLIATION HALE,M.W.
Carolina Power 6 Light Co.
WATSON,R.A.
Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION DOCKET g
05000400
SUBJECT:
Monthly o ating rept for Feb 1989 for Harris Nuclear Plant Unit 1.W 89031 ltr.
DISTRIBUTION CODE:
IE24D COPIES RECEIVED LTR ENCL SIZE:
TITLE: Monthly Operating Report (per Tech Specs)
NOTES:Application for permit renewal filed.
05000400 RECIPIENT ID CODE/NAME PD2-1 LA BECKER,D INTERNAL: ACRS AEOD/DSP/TPAB NRR/DLPQ/PEB 11 NR~R RPB 10 REG FILE Ol EXTERNAL EG&G S IMPSON i F LPDR NSIC COPIES LTTR ENCL 1
0 1
0 10 10 1
1 1
1 1
1 1
1 1.
1 1'
1 1
RECIPIENT ID CODE/NAME PD2-1 PD.
AEOD/DOA ARM TECH ADV NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RGN2 EGGG WILLIAMS,S NRC PDR COPIES LTTR ENCL 5
5 1
1 2
2 1
1 1
1 1
1 1
1 1
1 D
R I
h NOTE 'IO ALL "RXDS" RZCIPXENIS PLEASE HELP US IO REMJCE WASTE!
CGHI'ACI'HE DOCUMEFZ CXNZROL DESK, RcjOM Pl-37 (EXT. 20079)
KO EXZMZNATE~ MME FRY DISTRIBUTION LX8IS H)R DOCUMENZS YOU DGNiT NEEDI D
S TOTAL NUMBER OF COPIES REQUIRED:
LTTR 32 ENCL 30
, '. OF%<<I CG PLAHT O'ERFORHAHCE DATA <<~TEH I'HUH..DATE. 83/86/89
+
OPERATING DATA REPOI+
RUH TIHE 07: 48: 46 IIARR IS UNIT PAGE RF'D36-eee Ql"FRATIHG STATUS DGCI<ET HQ. 058-400 COHF'LETED K<Y HARI( M.
I-IALE TELFF'I.IQHE
<919)362-2944 A
- 4 5
7.
8.
LIHIT HAHE:
I IARR IS L)NXT I
HGlEB I
REPQRTXHG PERIOD:
FEBRUARY 89 I There are 157 fuel assemblies in LICENSED Tl IERHAI F'04IER
< HMT): 2775 the reactor and 52 spent fuel RAI1NG
<GROSS HML'>: 958.9 I assemblies in the spent fuel pool.
I DEBIGH El ECTRXCAL RATING (HET HME): 988.8 I
I HAX DEPENDABLE CAPAC1TY (GROSS HMF): 920.8 I
HAX DEPENDABLE CAPACITY
( NET HME): 860. 8 IF CHANGES OCCUR IN CAPACITY RATXNGS (1TEHS 3
THOU 7)
BIHCE LAST RFI"ORT, GIVE REASONS '/A 1e.
PO4IER LEVEL TO Wl-IICIS RESTRICTED IF AHY (HET'4IE) -'one
~
REASONS FOR RESTRICTION XF ANY: N/A THIS HOHTI-I YR TO DATE CUHUL ATIVE h
k 13.
14.
16.
17m 18.
20.
22 A
23.
I-IOURS XH REF'QRTXHG O'ERXGD NUHBER OF HOUI(S REACTOR CR1T ICAL REACTOR RESERVE SFILITDOMH HRB I-IOURS Gr=HERATOR GN LINE UNIT RESERVE Bl-IUTDOMN I IQURS GROSS TIIERHAL ENERGY GEH.
(HMH>
GROSS ELE(
~
ENERGY GEH.
( HMI-I)
NET ELEC.
ENERGY GEHERATED (HMH)
UNIT SERVICE FACTOR UHIT AVAILABILITYFACTOR UHIT CAP.
FACTOR (USING HDC HET)
UHIT CAP.
I=ACTOR (USING DER NET)
UNIT FORCED OUTAGE RATE SHUTDOWNS SCI-IED.
OVER HEXT 6 HGNTHS 672.00 616.23
.08 601.30
.ee 1472512.68
'906 8.88 454531.00 89.48 89.48 78.65
- 75. 'I 5 10.52 (TYF'E, DA1E, 1416.08 1351.20
.88 1315.93
.88 3411871.38 1141727.00 1863523.00 92.93 92.93 87.33 83.45 7.07 AHD DURATION 16857.88 12386.28
.88 12180. 16
.00 31668534.44 1<)542234.80 9769839.88 75.36 75.36 70.75 67.61 6.85 GF EACH):
25.
76 Il-Sl-ILITDOMH AT END GF RErORT FERIOD, EBTIHATED DATF OF START Ur-'.
UNXTS IN TEST STATUS (PRIOR TO COHHERCIAL OPERATION):
FORECAST ACHIEVED INXTIAL CRITICALX'1'Y 1HITXAI.
ELI=CTR1'CITY COHHERCI AL OPERATION 8903220'183 00400 pDR ADOCK 05000pDC R
MEM/DATAREPa/3/OS4 1.16 9
/i,,
I~l-',~iL CU
", OUI"." DATL:
03/'06/89 RUN TINE '7: 40: 44 I='LANT PERFORNANCF DATA SYSTEYi t
ENDIX 8 AVERAGE DAILY F'~='Ii LEVEL I-IARRIS UN1T F'AGE RPD39-Oe('EBRUARY
~i 5'8'F DAY AVG ~
DAXLY F'OMEI'~ LEVEL (HME-NET)
DOCI<ET NO. ere-4ee COHF'LETED BY IARI( M. HALi TELEPhQNE (939)362-2944 DAY AVG. DAILY I-"OMI:-Ik LEVEI (HME-NET) 857 877 884 424 460 878 7.>4 858 MEM/DATAREPa/4/OS4
UNIT SHUTDOWNS AND POWER REDUCTION REPORT MONTH:
FEBRUARY 1989 DOCKET NO.:
050-400 UNIT NAME:
Harris DATE:
3/6/89 COMPLETED BY:
M. W. Hale TELEPHONE:
(919) 362-2944 No.
Date Tl Y
P e
Duration (Hours)
R Method of Shutting Down Reactor Licensee Event Report P
System Code 4
Component Code 5
Cause 8, Corrective Action to Prevent Recurrence 89-005 890206 25.93 89-003 PUMPXX Reactor Trip from full power due to Low-Low Steam Generator Level caused by the loss of IA Main Feed pump.
The Main Feed pump shaft sheared.
Preliminary investigation results Indicate the shaft failed due to fatigue.
A metalurgical study is ongoing.
The unit was returned to 50$ using B
Feedwater Train and repairs were implemented.
I F:
Forced S:
Scheduled Reason:
A-Equipment Failure (Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training Ii, License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
Method:
I-Manual 2-Manual Scram 3-Automatic Scram 4-Continued 5-Reduced Load 6-Other 4
Exhibit G-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161) 5 Exhibit I - Same Source
" Corrective action to prevent recurrence per the Licensee Event Report.
MEM/DATAREPa/5/OS4
UNIT SHUTDOWNS AND POWER REDUCTION REPORT MONTH:
FEBRUARY 1989 DOCKET NO.:
050-400 UNIT NAME:
Harris DATE:
3/6/89 COMPLETED BY:
M. W. Hale TELEPHONE:
(919) 362-2944 No.
Date Tl y
P e
Duration (Hours)
R Method of Shutting Down Reactor Licensee Event Report S
System Code 4
Component Code 5
Cause II, Corrective Action to Prevent Recurrence 89-006 890207 35.1 89-004 WD INSTRU Reactor Trip from 475 due to loss of condenser vacuum caused by the loss of all circulating water." The Circ Water Pumps tripped on loss of seal water caused by a problem In the potable water system.
The potable water was supplying the seal water for the pumps.
The problem was corrected.
The unit was returned to service.
F:
Forced S:
Scheduled Reason:
A-Equipment Failure (Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training II, License Examination F-Administrative G-Operational Error (Explain)
Hither (Explain)
Method:
I-Manual 2-Manual Scram 3-Automatic Scram 4-Continued 5-Reduced Load 6-Other Exhibit G-Instructions for Preparation of Data Entry Sheets for I icensee Event Report (LER) File (NUREG-0161)
Exhibit I Same Source
" Corrective action to prevent recurrence, per the Licensee Event Report.
MEM/DATAREPa/6/OS4
UNIT SHUTDOWNS AND POWER REDUCTION REPORT MONTH:
FEBRUARY 1989 DOCKET NO.:
UNIT NAME:
DATE:
COMPLETED BY TELEPHONE:
050-400 Harris 3/6/89 M. W. Hale (919) 362-2944 No.
Date Ti y
P e
Duration (Hours)
R Method of Shutting Down Reactor Licensee Event Report If System Code 4
Component Code 5
Cause II Corrective Action to Prevent Recurrence 89~7 890208 00 N/A PUMPXX Load maintained at 505 to replace the failed IA Main Feed pump shaft.
Performance tests were performed on the pump upon completion of the repair.
The test indicated the pump parameters were satisfactory per the shop test curve.
The unit was returned to full service.
F:
Forced S:
Scheduled Reason:
A-Equipment Failure (Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 8, License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
Method:
I-Manual 2-Manual Scram 3-Automatic Scram 4-Continued 5-Reduced Load 6-Other Exhibit G-Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161)
Exhibit I Same Source MEM/DATAREPa/7/OS4
UNIT SHUTDOWNS AND POWER REDUCTION REPORT MONTH:
FEBRUARY 1989 DOCKET NO.:
050-400 UNIT NAME:
Harris DATE:
3/6/89 COMPLETED BY:
M. W. Hale TELEPHONE:
(919) 362-2944 No.
Date Tl y
P e
Duration (Hours)
R Method of Shutting Down Reactor Licensee Event Report S
System Code 4
Component Code 5
Cause 8, Corrective Action to Prevent Recurrence 89-008 890222 9.67 89-005 ZZ ZZZZZZ Reactor trip from full power due to steam flow/feed flow mismatch caused by the performance of Maintenance Surveillance Test 1-0023.
The procedure called for the ITIC Technician to place 3 channels of feedwater level indication into test.
This caused a 2 of 3 signai to activate the steam generator's preheater bypass logic and caused the main feedwater isolation valves and the main feedwater regulating valve to close, and led to a reactor trip on feed flow steam flow mismatch coincident with lo level.
F:
Forced S:
Scheduled Reason:
A-Equipment Failure (Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training II, License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
Method:
I-Manual 2-Manual Scram 3-Automatic Scram 4-Continued 5-Reduced Load 6-Other 4
Exhibit G-instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161) 5 Exhibit I Same Source
" Corrective action to prevent recurrence per the Licensee Event Report.
MEM/DATAREPa/8/OS4
Carolina Power 8 Light Company HARRIS NUCLEAR PROJECT P. 0.
Box 165 New Hill, North Carolina 27562 8
r5>ass File Number:
SHF/10-15505 Letter Number'HO-893005 (0)
Document Control Desk United States Nuclear Regulatory Commission Washington, DC 20555 HARRIS NUCLEAR PROJECT DEPARTMENT UNIT NOo 1
DOCKET NO. 50-400 LICENSE NO ~ NPF-63 MONTHLY OPERATIONS REPORT
Dear Sirs:
In accordance with Technical Specification 6.9.1.5 for the Harris Nuclear Power Plant, Unit No.
1, Carolina Power
& Light Company herewith submits the report of operation statistics and shutdown experience for the month of February 1989.
Yours very truly, MWH:crc R. A. Watson Vice President Harris Nuclear Project Enclosure cc'Messrs.
W. H. Bradford (NRC-SHNPP)
S.
D. Ebneter (NRC-RII)
R.
G. Oehl (DOE)
J.
M. Taylor (NRC)
MEM/DATAREPa/1/OS4
~ t E/
P I
DOCKET NO '50-400 UNIT:
Harris Unit 1
DATE:
February 1989 COMPLETED BY:
Mark Hale OPERATIONS
SUMMARY
Harris Unit 1 operated at a 89.48 percent Availability Factor for the month of February with a
78.65 percent capacity factor.
There were three reactor
- trips, and one load reduction.
Details are provided on the Unit Shutdowns and Power Reduction Sheet.
There are 157 fuel assemblies in the reactor vessel and 52 spent fuel assemblies in the Harris Unit 1 spent fuel pool and 0 assemblies in the new fuel pool.
MEM/DATAREPa/2/OS4
0 4
~I t
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