ML18005A235: Difference between revisions
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| issue date = 11/30/1987 | | issue date = 11/30/1987 | ||
| title = Monthly Operating Rept for Nov 1987.W/871215 Ltr | | title = Monthly Operating Rept for Nov 1987.W/871215 Ltr | ||
| author name = | | author name = Hale M, Watson R | ||
| author affiliation = CAROLINA POWER & LIGHT CO. | | author affiliation = CAROLINA POWER & LIGHT CO. | ||
| addressee name = | | addressee name = | ||
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=Text= | =Text= | ||
{{#Wiki_filter:,ACCELERATED DI+IBUTION DEMONST3$TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM'(RIDS)ACCESSION NBR:8712170227 DOC.DATE: 87/11/30 NOTARIZED: | {{#Wiki_filter:,ACCELERATED DI+IBUTION DEMONST3$TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM '(RIDS) | ||
NO FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION HALE,M.W.Carolina Power&Light Co.WATSON,R.A. | ACCESSION NBR:8712170227 DOC.DATE: 87/11/30 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION HALE,M.W. Carolina Power & Light Co. | ||
Carolina Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATION | WATSON,R.A. Carolina Power 6 Light Co. | ||
RECIP.NAME RECIPIENT AFFILIATION | |||
==SUBJECT:== | ==SUBJECT:== | ||
Monthly operating rept for Nov 1987.W/871215 ltr.DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTRJ-ENCL~SIZE: I l TITLE: Monthly Operating Report (per Tech Specs)"NOTES:Application for permit renewal filed.RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY,B | Monthly operating rept for Nov 1987.W/871215 ltr. | ||
DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTRJ- ENCL~ SIZE: I l TITLE: Monthly Operating Report (per Tech Specs) ' | |||
"NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME PD2-1 LA BUCKLEY,B LTTR ENCL 1 | |||
1, 0 0 | |||
ID CODE/NAME PD2-1 PD LTTR ENCL 5 5 j A | |||
INTERNAL: AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 ARM TECH ADV 2 2 NRR/DLPQ/PEB 1 1 NRR/DOEA/EAB 1 1 RPB 1 1 NRR/PMAS/ILRB 1 1 REG FILE 01 1 1 RGN2 1 1 EXTERNAL: DOE NE32 FULNER 1 1 LPDR 1 1 NRC PDR 1 1 NSIC 1 1 8 | |||
A TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19 | |||
DOCKET NOe: 050-400 UNIT! Harris Unit 1 DATE: November 1987 COMPLETED BY: Mark Hale OPERATIONS | |||
==SUMMARY== | ==SUMMARY== | ||
Harris Unit 1 operated at a 73.07 percent Availability Factor for the month of November with a 63.01 percent capacity factor. There was 1 continued scheduled shutdown, 1 manual scram, 1 auto-scram, and 4 load reductions. | |||
Details are provided in the Unit Shutdowns and Power Reduction sheets'here are 157 fuel assemblies in the reactor and 0 spent fuel bundles in the Harris Unit 1 fuel pool. | |||
8712l70227 871130 PDR *DOCK 05000400 DCD MEM/DATAREPa/Page 1/OS3 | |||
'c | |||
'CPhL Co PLANT I El'<FORNANCE DATA AUSTEN r- AGE- | |||
..auN .DATE <2re3z87 OPERATING DATA aEPQ~ F<PD36-088 RUH 'I IHE 33:23:59 HARRIS UNIT DOCKET Ho ~ 858-488 CONPI ETED BY NARK M. HALE OPERATING STATUS TELEr-HoNE UNIT NAHE: HARRIS UHI T I NOTE There are 157 Puel I | |||
: 2. REPORTING PERIOD: NOVEMBER 87 I assemblies in the Reactor I | |||
( | : 3. LICENSED THERHAL POWER (NMT): 2775 and 0 spent fuel bundles in | ||
: 4. HAHEPLATE RATlNG (GROSS) NME): 955.3 the spent fuel pool. I 5* DESIGH ELECTRXCAL RATING (HET MME>:.. 900.0 I 6* KNAX DEPENDABLE CAPACITY (GRO.)B HME): 9 .0.8 I I | |||
: 7. HAX DEPENDABLE CAPACITY (HET NME): 868.0 8* IF CHAHGEB OCCUR IH CAPAClTY RATINGS (ITENS 3 THOU 7) SINCE LAST REPORT, GIVE REASONS: N/A 9* POWER L.EVEL TG WHICH RESTRICTED IF AHY (NET HWE): None | |||
$ 0. REASONS FOR RI=STRICTION IF AHY: N/A Tl-I I 8) YR TQ CUHUL HQNTH DATE ATIVE HOURS IN REPORTIHG PERloD 720.08 51 $ 3.00 5< <3.88 NUHBER OF HOURS REACTOR CRITICAL 536.87 3705.89 3705.89 f3. REACTOR RESERVE SHUTDOWN HRS .00 .00 F 08 | |||
: 34. HOURS GENERATOR QN LXHE 526.33 3579.60 3579.68 UNIT RESERVE SHUTDOWN HOURS- .00 .00 .80 3'6. GROBS) THERHAL EHERGY GEH. (NWH) 1288678.84 9332997.86 9132997.86 | |||
$ 7~ GROSS ELEC. EHERGY GEH. (HMH) 424384.88 2981323.88 2981823.88 38 ~ HET ELECT EHERGY CvEHERATED (HMH> 398149.88 2)737321.88 273732)1.88 l9* UNIT SI=RV ICE FACTOR 73.07 78.81 70 81 F | |||
: 20. UNX~ AVAXI.ABILITYr-ACTOR 73.07 78.83 78.81 23 | |||
* uHXT CAP. FACTOR <usxHG HDC HET> 63.81 62.25 62.25 22 UNXT CAP. FACTQF< <UslHG DER HET) 68.21 59.48 59.48 23 uHXT FoRcED ouTAGE RATE 282 12.33 12.33 BI-IUTDOWHS SCHED. OVER NEXT 6 HOHTHS (TYPE, DATE, AHD DURATION OF EACH): | |||
None | |||
: 25. XF SHUTDOMN AT END QF RLPGRT PERIOD, ESTIHATED DATE OF START UP: | |||
( | UNITS xH TEsT BTATUB <rRxoR To cove~'RCIAL opERATIQN>: FGFiECAB~ AcHxEvED INITIAI CRXTICAI XTY INITIAL. ELECTRICITY COHHERCIAL OPERAT ION K $ .16 9 | ||
) | |||
q) | |||
MEM/DATAREPa/Page 2/OS3 | |||
lg ii 4 "'f) | |||
'CPhL'O PLANT PERFORMANCE'ATA SYSTEM PAGE | |||
,~RUN'.DATE 12/03/87 EHDIX B AVERAGE DAILY )ER LEVEL RPD39-OOC RUN TIME < 3: 23: 58 HARRIS UNIT DOCKET NO. 050-480 COMPLETED BY MARK W. HALE TELEPHONE (919)362-2944 NOVEMBER DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL | |||
'MWE-NET) | |||
(MWE-HET) 20 7 878 190 I | |||
+7 870 387 873 30 877 535 1.$ 6 8 MEM/DATAREPa/Page 3/OS3 | |||
UNIT SHUTDOWNS AND POWER REDUCTION DOCKET NO,: 050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: M, W Kale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Tl R Method No. Date y Duration of Licensee System Component Cause d, Corrective P (Hours) Shutting Event Code 4 Code 5 Action to e Down Report 4 Prevent Recurrence Reactor 87-042 871009 183,05 N/A ZZ ZZZZZZ Unit removed from service to perform scheduled Surveillance Tests and Inspections. The inspections included: | |||
pipe snubbers, diesel generators, and production equipment Repairs were implemented to the Steam Generator Slowdown valves, Heater Drain pumps, Main Feed Pumps, Moisture Separator Reheaters, and other production equipment, F: Forced Reason: Method: Exhibit G-instructions S: Scheduled A-Equipment Failure (Explain) I-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued (NUREG-0161) | |||
E&perator Training d License Examination 5-Reduced Load F-Administrative 6-Other G-Operational Error (Explain) Exhibit I Same Source H-Other (Explain) | |||
MEM/DATAREPa/Page 4/OS3 | |||
UNIT SHUTDOWNS AND POWER REDUCTION DOCKET NO,: 050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: M. W, Hale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Method No. Date Duration of Licensee System Component Cause 8 Corrective (Hours) Shutting Event Code 4 Code 5 Action to Down Report ff Prevent Recurrence Reactor 87-043 871107 87&62 ZZ ZZZZZZ Automatic Reactor Scram from 4 'g power while in Mode 2 (Start-up), due to error in setting the steam dump cont-roller. As the ~A.~ MSIV was opened, a safety injection on low steam line pressure occurred'n addition to the auto-scram and safety injection, a main steam line isolation occurred'he operating procedures were revised to have the steam dump controller in manual and valves shut prior to opening MSIV's. After the MSIV's are open, then the controller will be placed in automatic. | |||
F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued (NUREG-0161) | |||
E&perator Training II, License Examination 5-Reduced Load F-Administrative 6-Other G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain) | |||
<< Corrective action to prevent recurrence per the Licensee Event Report. | |||
MEM/DATAREPa/Page 5/OS3 | |||
UNIT SHUTDOWNS AND POWER REDUCTION DOCKET NO,: 050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: M, W. Hale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Method No. Date Duration of Licensee System Component Cause d Corrective >> | |||
(Hours) Shutting Event Code 4 Code 5 Action to Down Report 4 Prevent Recurrence Reactor3 87-044 871108 10 82 87-063 ZZ ZZZZZZ Manual Reactor Trip from 22$ power initiated due to loss of normal feedwater caused by a condensate recirc. Valve being left in the open position instead of the modulating positions Procedure for Condensate System has been revised to ensure valve is in the proper operating positions F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) I-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File 0-Regulatory Restriction 4-Continued (NUREG-0161 ) | |||
E&perator Training d License Examination 5-Reduced Load F-Administrative 6-Other G-Operational Error (Explain) Exhibit I Same Source H-Other (Explain) w Corrective action to prevent recurrence per the Licensee Event Report. | |||
MEM/DATAREPa/Page 6/OS3 | |||
Vy | |||
-I 4 '4 ~ | |||
UNIT SHUTDOWNS AND POWER REDUCTION DOCKET NO,: 050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: M. W. Hale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Method Date Duration of Licensee System Component Cause 4 Corrective No. | |||
(Hours) Shutting Event Code 4 Code 5 Action to Down Report f Prevent Recurrence Reactor 87-045 871111 N/A INSTRU Load reduced to 85% power due to the loss of heater drain pumps The pump trips were attributed to poor level control by the pneumatic controller, Poor level control caused high level in Feedwater Heaters. This caused the extraction steam valves to shut which caused the trips on Low NPSH, After heater levels stabilized on alternate control, ihe extraction steam valves were reopened which allowed the Low NPSH interlock to clear. The pumps were then restarted. | |||
Reason: Method: Exhibit G-Instructions F: Forced A-Equipment Failure (Explain) 1-Manual for Preparation of Data S: Scheduled B&aintenance or Test 2-Manual Scram Entry Sheets for Licensee 3-Automatic Scram Event Report (LER) File C-Refueling 4-Continued (NUREG-0161 ) | |||
D-Regulatory Restriction E-Operator Training 4 License Examination 5-Reduced Load F-Administrative 6-Other Exhibit 1 Same Source G-Operational Error (Explain) | |||
H-Other (Explain) | |||
MEM/DATAREPa/Page 7/OS3 | |||
UNIT SHUTDOWNS AND POWER REDUCTIONDOCKET NO,:050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: M. W. Hale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Method of Licensee System Component Cause Ii, Corrective No, Date Duration (Hours) Shutting Event Code 4 Code 5 Action to Down Report $ Prevent Recurrence Reactor 87-046 871III N/A MOTORX Load reduced to 50$ to inspect IB mainfeed pump motor bearings due to excess vibration. The bearings were relieved at the horizontal parting joints per vendor recommendations Unit returned to full service, Reason: Method: Exhibit G-Instructions F: Forced A-Equipment Failure (Explain) I-Manual for Preparation of Data S: Scheduled B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee 3-Automatic Scram Event Report (LER) File C-Refueling 4-Continued (NUREG-0161) | |||
D-Regulatory Restriction E-Operator Training 4 License Examination 5-Reduced Load F-Administrative 6-Other Exhibit I - Same Source G-Operational Error (Explain) | |||
H-Other (Explain) | |||
MEM/DATAREPa/Page 8/OS3 | |||
UNIT SHUTDOWNS ANO POWER REOUCT IONDOCKET NO,:050-400 UNIT NAME: Harr I s DATE: 12/3/87 COMPLETED BY: H, W Hale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Method No. Date Duration of Licensee System Component Cause 8, Corrective (Hours) Shutting Event Code 4 5 | |||
'ode Action to Down Report J Prevent Recurrence Reactor 87-047 871114 N/A INSTRU Load reduced to 89/ due to the loss of IA heater drain pump low net positive suction head The pump trip was attributed to 4A feedwater heater level pneumatic controller. The controller was adjusted to correct the levels Unit returned to full service. | |||
F: Forced Reason: Hethod: Exhibit G-Instructions S: Scheduled A<quipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Hanual Scram Entry Sheets for Licensee C~fueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued (NUREG-0161 ) | |||
E-Operator Training II, License Examination 5-Reduced Load F-Administrative 6-Other G-Operational Error (Explain) Exhibit I - Same Source H-Other (Explain) | |||
MEH/OATAREPa/Page 9/OS3 | |||
i' UNIT SHUTDOWNS AND POWER REDUCTIONDOCKET NO,:050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: H. W, Hale TELEPHONE: (919) 362-2944 REPORT HONTH: NOVEMBER 1987 T Hethod of Licensee System Component Cause 8, Corrective No. Date y Duration (Hours ) Shutting Event Code 4 Code 5 Action to P | |||
e Down Report 4 Prevent Recurrence Reactor N/A HECFUN Load reduced to 50$ to perform 1B 87-048 871 I 15 mainfeed pump/motor hot alignment. | |||
The alignment was completed and unit was returned to full service. | |||
Reason: Hethod- Exhibit G-Instructions F: Forced A-Equipment Fai lure (Explain) 1-Manual for Preparation of Data S: Scheduled B-Maintenance or Test 2-Hanual Scram Entry Sheets for Licensee 3-Automatic Scram Event Report (LER) File C-Refueling 4-Continued (NURE~161 ) | |||
D-Regulatory Restriction E-Operator Training II, License Examination 5-Reduced Load F-Administrative 6-Other Exhibit 1 Same Source G-Operational Error (Explain) | |||
H-Other (Explain) | |||
MEH/DATAREPa/Page 10/OS3 | |||
r | |||
~ <<~ ~ | |||
Carolfna Power 8 Lfght Company HARRIS NUCLEAR PROJECT P. 0. Box 165 New Hill, North Carolina 27562 DEC 15 1987 File Number.'HF/10-15505 Letter Number: HO-875019 (0) | |||
Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555 HARRIS NUCLEAR PROJECT DEPARTMENT UNIT NO. 1 DOCKET NO. 50-400 LICENSE NOo NPF-63 MONTHLY OPERATIONS REPORT | |||
==Dear Sirs:== | |||
In accordance with Technical Specifications 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 November 1987. | |||
Yours very truly, R. A. Watson Vice President Harris Nuclear Project MWH:gmw Enclosure cc'. Dr. J. Nelson Grace (NRC) | |||
Messrs. J. M. Taylor (NRC) | |||
G, F. Maxwell (NRC-SHNPP) | |||
R. G. Oehl (DOE) | |||
MEM/HO-875019/Page 1/OS3 | |||
0 iv}} | |||
Latest revision as of 05:59, 22 October 2019
ML18005A235 | |
Person / Time | |
---|---|
Site: | Harris |
Issue date: | 11/30/1987 |
From: | Hale M, Watson R CAROLINA POWER & LIGHT CO. |
To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
References | |
HO-875019-(O), NUDOCS 8712170227 | |
Download: ML18005A235 (18) | |
Text
,ACCELERATED DI+IBUTION DEMONST3$TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM '(RIDS)
ACCESSION NBR:8712170227 DOC.DATE: 87/11/30 NOTARIZED: NO DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION HALE,M.W. Carolina Power & Light Co.
WATSON,R.A. Carolina Power 6 Light Co.
RECIP.NAME RECIPIENT AFFILIATION
SUBJECT:
Monthly operating rept for Nov 1987.W/871215 ltr.
DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTRJ- ENCL~ SIZE: I l TITLE: Monthly Operating Report (per Tech Specs) '
"NOTES:Application for permit renewal filed. 05000400 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME PD2-1 LA BUCKLEY,B LTTR ENCL 1
1, 0 0
ID CODE/NAME PD2-1 PD LTTR ENCL 5 5 j A
INTERNAL: AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 ARM TECH ADV 2 2 NRR/DLPQ/PEB 1 1 NRR/DOEA/EAB 1 1 RPB 1 1 NRR/PMAS/ILRB 1 1 REG FILE 01 1 1 RGN2 1 1 EXTERNAL: DOE NE32 FULNER 1 1 LPDR 1 1 NRC PDR 1 1 NSIC 1 1 8
A TOTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 19
DOCKET NOe: 050-400 UNIT! Harris Unit 1 DATE: November 1987 COMPLETED BY: Mark Hale OPERATIONS
SUMMARY
Harris Unit 1 operated at a 73.07 percent Availability Factor for the month of November with a 63.01 percent capacity factor. There was 1 continued scheduled shutdown, 1 manual scram, 1 auto-scram, and 4 load reductions.
Details are provided in the Unit Shutdowns and Power Reduction sheets'here are 157 fuel assemblies in the reactor and 0 spent fuel bundles in the Harris Unit 1 fuel pool.
8712l70227 871130 PDR *DOCK 05000400 DCD MEM/DATAREPa/Page 1/OS3
'c
'CPhL Co PLANT I El'<FORNANCE DATA AUSTEN r- AGE-
..auN .DATE <2re3z87 OPERATING DATA aEPQ~ F<PD36-088 RUH 'I IHE 33:23:59 HARRIS UNIT DOCKET Ho ~ 858-488 CONPI ETED BY NARK M. HALE OPERATING STATUS TELEr-HoNE UNIT NAHE: HARRIS UHI T I NOTE There are 157 Puel I
- 2. REPORTING PERIOD: NOVEMBER 87 I assemblies in the Reactor I
- 3. LICENSED THERHAL POWER (NMT): 2775 and 0 spent fuel bundles in
- 4. HAHEPLATE RATlNG (GROSS) NME): 955.3 the spent fuel pool. I 5* DESIGH ELECTRXCAL RATING (HET MME>:.. 900.0 I 6* KNAX DEPENDABLE CAPACITY (GRO.)B HME): 9 .0.8 I I
- 7. HAX DEPENDABLE CAPACITY (HET NME): 868.0 8* IF CHAHGEB OCCUR IH CAPAClTY RATINGS (ITENS 3 THOU 7) SINCE LAST REPORT, GIVE REASONS: N/A 9* POWER L.EVEL TG WHICH RESTRICTED IF AHY (NET HWE): None
$ 0. REASONS FOR RI=STRICTION IF AHY: N/A Tl-I I 8) YR TQ CUHUL HQNTH DATE ATIVE HOURS IN REPORTIHG PERloD 720.08 51 $ 3.00 5< <3.88 NUHBER OF HOURS REACTOR CRITICAL 536.87 3705.89 3705.89 f3. REACTOR RESERVE SHUTDOWN HRS .00 .00 F 08
- 34. HOURS GENERATOR QN LXHE 526.33 3579.60 3579.68 UNIT RESERVE SHUTDOWN HOURS- .00 .00 .80 3'6. GROBS) THERHAL EHERGY GEH. (NWH) 1288678.84 9332997.86 9132997.86
$ 7~ GROSS ELEC. EHERGY GEH. (HMH) 424384.88 2981323.88 2981823.88 38 ~ HET ELECT EHERGY CvEHERATED (HMH> 398149.88 2)737321.88 273732)1.88 l9* UNIT SI=RV ICE FACTOR 73.07 78.81 70 81 F
- 20. UNX~ AVAXI.ABILITYr-ACTOR 73.07 78.83 78.81 23
- uHXT CAP. FACTOR <usxHG HDC HET> 63.81 62.25 62.25 22 UNXT CAP. FACTQF< <UslHG DER HET) 68.21 59.48 59.48 23 uHXT FoRcED ouTAGE RATE 282 12.33 12.33 BI-IUTDOWHS SCHED. OVER NEXT 6 HOHTHS (TYPE, DATE, AHD DURATION OF EACH):
None
- 25. XF SHUTDOMN AT END QF RLPGRT PERIOD, ESTIHATED DATE OF START UP:
UNITS xH TEsT BTATUB <rRxoR To cove~'RCIAL opERATIQN>: FGFiECAB~ AcHxEvED INITIAI CRXTICAI XTY INITIAL. ELECTRICITY COHHERCIAL OPERAT ION K $ .16 9
)
q)
MEM/DATAREPa/Page 2/OS3
lg ii 4 "'f)
'CPhL'O PLANT PERFORMANCE'ATA SYSTEM PAGE
,~RUN'.DATE 12/03/87 EHDIX B AVERAGE DAILY )ER LEVEL RPD39-OOC RUN TIME < 3: 23: 58 HARRIS UNIT DOCKET NO. 050-480 COMPLETED BY MARK W. HALE TELEPHONE (919)362-2944 NOVEMBER DAY AVG. DAILY POWER LEVEL DAY AVG. DAILY POWER LEVEL
'MWE-NET)
(MWE-HET) 20 7 878 190 I
+7 870 387 873 30 877 535 1.$ 6 8 MEM/DATAREPa/Page 3/OS3
UNIT SHUTDOWNS AND POWER REDUCTION DOCKET NO,: 050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: M, W Kale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Tl R Method No. Date y Duration of Licensee System Component Cause d, Corrective P (Hours) Shutting Event Code 4 Code 5 Action to e Down Report 4 Prevent Recurrence Reactor 87-042 871009 183,05 N/A ZZ ZZZZZZ Unit removed from service to perform scheduled Surveillance Tests and Inspections. The inspections included:
pipe snubbers, diesel generators, and production equipment Repairs were implemented to the Steam Generator Slowdown valves, Heater Drain pumps, Main Feed Pumps, Moisture Separator Reheaters, and other production equipment, F: Forced Reason: Method: Exhibit G-instructions S: Scheduled A-Equipment Failure (Explain) I-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued (NUREG-0161)
E&perator Training d License Examination 5-Reduced Load F-Administrative 6-Other G-Operational Error (Explain) Exhibit I Same Source H-Other (Explain)
MEM/DATAREPa/Page 4/OS3
UNIT SHUTDOWNS AND POWER REDUCTION DOCKET NO,: 050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: M. W, Hale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Method No. Date Duration of Licensee System Component Cause 8 Corrective (Hours) Shutting Event Code 4 Code 5 Action to Down Report ff Prevent Recurrence Reactor 87-043 871107 87&62 ZZ ZZZZZZ Automatic Reactor Scram from 4 'g power while in Mode 2 (Start-up), due to error in setting the steam dump cont-roller. As the ~A.~ MSIV was opened, a safety injection on low steam line pressure occurred'n addition to the auto-scram and safety injection, a main steam line isolation occurred'he operating procedures were revised to have the steam dump controller in manual and valves shut prior to opening MSIV's. After the MSIV's are open, then the controller will be placed in automatic.
F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued (NUREG-0161)
E&perator Training II, License Examination 5-Reduced Load F-Administrative 6-Other G-Operational Error (Explain) Exhibit 1 - Same Source H-Other (Explain)
<< Corrective action to prevent recurrence per the Licensee Event Report.
MEM/DATAREPa/Page 5/OS3
UNIT SHUTDOWNS AND POWER REDUCTION DOCKET NO,: 050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: M, W. Hale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Method No. Date Duration of Licensee System Component Cause d Corrective >>
(Hours) Shutting Event Code 4 Code 5 Action to Down Report 4 Prevent Recurrence Reactor3 87-044 871108 10 82 87-063 ZZ ZZZZZZ Manual Reactor Trip from 22$ power initiated due to loss of normal feedwater caused by a condensate recirc. Valve being left in the open position instead of the modulating positions Procedure for Condensate System has been revised to ensure valve is in the proper operating positions F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) I-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File 0-Regulatory Restriction 4-Continued (NUREG-0161 )
E&perator Training d License Examination 5-Reduced Load F-Administrative 6-Other G-Operational Error (Explain) Exhibit I Same Source H-Other (Explain) w Corrective action to prevent recurrence per the Licensee Event Report.
MEM/DATAREPa/Page 6/OS3
Vy
-I 4 '4 ~
UNIT SHUTDOWNS AND POWER REDUCTION DOCKET NO,: 050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: M. W. Hale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Method Date Duration of Licensee System Component Cause 4 Corrective No.
(Hours) Shutting Event Code 4 Code 5 Action to Down Report f Prevent Recurrence Reactor 87-045 871111 N/A INSTRU Load reduced to 85% power due to the loss of heater drain pumps The pump trips were attributed to poor level control by the pneumatic controller, Poor level control caused high level in Feedwater Heaters. This caused the extraction steam valves to shut which caused the trips on Low NPSH, After heater levels stabilized on alternate control, ihe extraction steam valves were reopened which allowed the Low NPSH interlock to clear. The pumps were then restarted.
Reason: Method: Exhibit G-Instructions F: Forced A-Equipment Failure (Explain) 1-Manual for Preparation of Data S: Scheduled B&aintenance or Test 2-Manual Scram Entry Sheets for Licensee 3-Automatic Scram Event Report (LER) File C-Refueling 4-Continued (NUREG-0161 )
D-Regulatory Restriction E-Operator Training 4 License Examination 5-Reduced Load F-Administrative 6-Other Exhibit 1 Same Source G-Operational Error (Explain)
H-Other (Explain)
MEM/DATAREPa/Page 7/OS3
UNIT SHUTDOWNS AND POWER REDUCTIONDOCKET NO,:050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: M. W. Hale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Method of Licensee System Component Cause Ii, Corrective No, Date Duration (Hours) Shutting Event Code 4 Code 5 Action to Down Report $ Prevent Recurrence Reactor 87-046 871III N/A MOTORX Load reduced to 50$ to inspect IB mainfeed pump motor bearings due to excess vibration. The bearings were relieved at the horizontal parting joints per vendor recommendations Unit returned to full service, Reason: Method: Exhibit G-Instructions F: Forced A-Equipment Failure (Explain) I-Manual for Preparation of Data S: Scheduled B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee 3-Automatic Scram Event Report (LER) File C-Refueling 4-Continued (NUREG-0161)
D-Regulatory Restriction E-Operator Training 4 License Examination 5-Reduced Load F-Administrative 6-Other Exhibit I - Same Source G-Operational Error (Explain)
H-Other (Explain)
MEM/DATAREPa/Page 8/OS3
UNIT SHUTDOWNS ANO POWER REOUCT IONDOCKET NO,:050-400 UNIT NAME: Harr I s DATE: 12/3/87 COMPLETED BY: H, W Hale TELEPHONE: (919) 362-2944 REPORT MONTH: NOVEMBER 1987 Method No. Date Duration of Licensee System Component Cause 8, Corrective (Hours) Shutting Event Code 4 5
'ode Action to Down Report J Prevent Recurrence Reactor 87-047 871114 N/A INSTRU Load reduced to 89/ due to the loss of IA heater drain pump low net positive suction head The pump trip was attributed to 4A feedwater heater level pneumatic controller. The controller was adjusted to correct the levels Unit returned to full service.
F: Forced Reason: Hethod: Exhibit G-Instructions S: Scheduled A<quipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Hanual Scram Entry Sheets for Licensee C~fueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued (NUREG-0161 )
E-Operator Training II, License Examination 5-Reduced Load F-Administrative 6-Other G-Operational Error (Explain) Exhibit I - Same Source H-Other (Explain)
MEH/OATAREPa/Page 9/OS3
i' UNIT SHUTDOWNS AND POWER REDUCTIONDOCKET NO,:050-400 UNIT NAME: Harris DATE: 12/3/87 COMPLETED BY: H. W, Hale TELEPHONE: (919) 362-2944 REPORT HONTH: NOVEMBER 1987 T Hethod of Licensee System Component Cause 8, Corrective No. Date y Duration (Hours ) Shutting Event Code 4 Code 5 Action to P
e Down Report 4 Prevent Recurrence Reactor N/A HECFUN Load reduced to 50$ to perform 1B 87-048 871 I 15 mainfeed pump/motor hot alignment.
The alignment was completed and unit was returned to full service.
Reason: Hethod- Exhibit G-Instructions F: Forced A-Equipment Fai lure (Explain) 1-Manual for Preparation of Data S: Scheduled B-Maintenance or Test 2-Hanual Scram Entry Sheets for Licensee 3-Automatic Scram Event Report (LER) File C-Refueling 4-Continued (NURE~161 )
D-Regulatory Restriction E-Operator Training II, License Examination 5-Reduced Load F-Administrative 6-Other Exhibit 1 Same Source G-Operational Error (Explain)
H-Other (Explain)
MEH/DATAREPa/Page 10/OS3
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Carolfna Power 8 Lfght Company HARRIS NUCLEAR PROJECT P. 0. Box 165 New Hill, North Carolina 27562 DEC 15 1987 File Number.'HF/10-15505 Letter Number: HO-875019 (0)
Document Control Desk United States Nuclear Regulatory Commission Washington, D.C. 20555 HARRIS NUCLEAR PROJECT DEPARTMENT UNIT NO. 1 DOCKET NO. 50-400 LICENSE NOo NPF-63 MONTHLY OPERATIONS REPORT
Dear Sirs:
In accordance with Technical Specifications 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 November 1987.
Yours very truly, R. A. Watson Vice President Harris Nuclear Project MWH:gmw Enclosure cc'. Dr. J. Nelson Grace (NRC)
Messrs. J. M. Taylor (NRC)
G, F. Maxwell (NRC-SHNPP)
R. G. Oehl (DOE)
MEM/HO-875019/Page 1/OS3
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