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=Text=
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{{#Wiki_filter:-     , ,,        .      . - ,  ._            - . - - ~ . .
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Limerick Gener: ting Station
Limerick Gener: ting Station
                        =
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A V                                                                                                                                 '
A V
PECO NUCLEAR ecw eo- c-,
PECO NUCLEAR ecw eo-c-,
Po Box 2300                                   '
Po Box 2300 A Unit of PECO Energy Sanatoga, PA 19464 0920
A Unit of PECO Energy                                                         Sanatoga, PA 19464 0920
+
                                                                                                                                                        +
l T.S.6.9.1.6 l
l T.S.6.9.1.6                               l l                                                                                                                                                         !
l March 12,1999 Docket Nos. 50-352 50-353 License Nos. NPF-39 l
March 12,1999 l
NPF-85 l
Docket Nos. 50-352 50-353 License Nos. NPF-39 l                                                                                                               NPF-85 l
U. S. Nuclear Regulatory Commission l
!                                                                                                                                                        l l                          U. S. Nuclear Regulatory Commission l                         Atm: Document Control Desk Washington,DC 20555
Atm: Document Control Desk Washington,DC 20555 l


==Subject:==
==Subject:==
Limerick Generating Station l
Limerick Generating Station Monthly Operating Report For Units 1 and 2 Enclosed are the monthly operating reports for Limerick Units 1 and 2 for the month of February 1999 forwarded pursuant to Technical Specification 6.9.1.6.
Monthly Operating Report For Units 1 and 2 Enclosed are the monthly operating reports for Limerick Units 1 and 2 for the month of February 1999 forwarded pursuant to Technical Specification 6.9.1.6.
Very truly yours, Jos h P. Grimes Director - Site Engineering f
Very truly yours, Jos h P. Grimes Director - Site Engineering f
Enclosures cc:       H. J. Miller, Administrator, Region I, USNRC                                                 '
Enclosures cc:
.,                                  A. L. Burritt, USNRC Senior Resident Inspector LGS i                                 J. D. von Suskil, Vice President, LGS G. H. Stewart, LGS Experience Assessment Branch, SSB2-4 S. A. Auve, LOS ISEG Branch, SSB4-2 Ij 9903160372 9902283 2 m;
H. J. Miller, Administrator, Region I, USNRC A. L. Burritt, USNRC Senior Resident Inspector LGS i
          ,      PDR   ADOCK 0 R                                   -
J. D. von Suskil, Vice President, LGS G. H. Stewart, LGS Experience Assessment Branch, SSB2-4 S. A. Auve, LOS ISEG Branch, SSB4-2 Ij 9903160372 9902283 2 m; PDR ADOCK 0 R
2
2
                      -_ -                                                              ,                  ,                  ..r.
..r.


a
a Docket No. 50-352 Attachment to Monthly Operating Report for February 1999 i
;                                                                                          Docket No. 50-352 Attachment to Monthly
j Limerick Generating Station Unit 1 l
;                                                                                        Operating Report for February 1999 i
February 1 through February 28,1999 i
j                                           Limerick Generating Station Unit 1 l                                       February 1 through February 28,1999 i
I
I     - 1.       Narrative Summary of Operatino Experiences 1
- 1.
.                Unit 1 began the month of February 1999 at 100% of rated thermal power (RTP).
Narrative Summary of Operatino Experiences 1
On February 13,1999 at 0336 hours, power was reduced to 64% of RTP for control j               rod pattern adjustments. Power was raised to 98 % of RTP on February 14,1999 at 2145 hours with MFLPD being monitored and tuning being performed. Power was restored to 100% of RTP on February 16,1999 at 2257 hours.
Unit 1 began the month of February 1999 at 100% of rated thermal power (RTP).
On February 19,1999 at 2215 hours, power was reduced to 86% of RTP for control               I rod pattern adjustments. Power was restored to 100% of RTP on February 20,1999 at 0230 hours.
On February 13,1999 at 0336 hours, power was reduced to 64% of RTP for control j
rod pattern adjustments. Power was raised to 98 % of RTP on February 14,1999 at 2145 hours with MFLPD being monitored and tuning being performed. Power was restored to 100% of RTP on February 16,1999 at 2257 hours.
On February 19,1999 at 2215 hours, power was reduced to 86% of RTP for control I
rod pattern adjustments. Power was restored to 100% of RTP on February 20,1999 at 0230 hours.
On February 28,1999 at 0100 hours, power was reduced to 85% of RTP to reduce the heat load in the drywell with a loop of drywell chilled water being isolated due to an inoperable PCIV. Power was further reduced to 27% power to maintain drywell temperature below 135 degrees.
On February 28,1999 at 0100 hours, power was reduced to 85% of RTP to reduce the heat load in the drywell with a loop of drywell chilled water being isolated due to an inoperable PCIV. Power was further reduced to 27% power to maintain drywell temperature below 135 degrees.
Unit 1 ended this month at 27 % RTP.
Unit 1 ended this month at 27 % RTP.
: 11. Challenoes to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of         !
11.
February. There have been no challenges to the Main Steam Safety Relief Valves year         !
Challenoes to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of February. There have been no challenges to the Main Steam Safety Relief Valves year to date.
to date.                                                                                     l l
l 4
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OPERATING DATA REPORT t
OPERATING DATA REPORT t
DOCKET NO. 50-352                                                                                   ,
DOCKET NO. 50-352 DATE MARCH 12,1999 COMPLETED BY PECO ENERGY COMPANY P. A. HINCHEY REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3797 1
DATE MARCH 12,1999 COMPLETED BY PECO ENERGY COMPANY P. A. HINCHEY REPORTS ENGINEER                                                             -          .
SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3797 1
OPERATING STATUS
OPERATING STATUS
: 1. UNIT NAME:                   ______,______________________________________________,,_____________________________LIMERIC_K_U_ NIT _1,                                                                                                                                 ;
: 1. UNIT NAME: ______,______________________________________________,,_____________________________LIMERIC_K_U_ NIT _1,
: 2. REPORTING PERIOD:                   ,____________________________________________________________________________FEBR_U_A_RY1_999                                                                                                                 u
: 2. REPORTING PERIOD:,____________________________________________________________________________FEBR_U_A_RY1_999 u
: 3. DESIGN ELECTRICAL RATING (NET MWE):                                   ___________________,____________________________________________________1_1_34_
: 3. DESIGN ELECTRICAL RATING (NET MWE): ___________________,____________________________________________________1_1_34_
: 4. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): ____________ ,_____________________________________________________1174 S. MAXIMUM DEPENDABLE CAPACITY (NET MWE): _________________,._________________________________________ ,_________1134                                                                                                                                                     l THIS MONTH                           YR-TO-DATE                                       CUMULATIVE
: 4. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): ____________,_____________________________________________________1174 S. MAXIMUM DEPENDABLE CAPACITY (NET MWE): _________________,._________________________________________,_________1134 l
: 6. NUMBER OF HOURS REACTOR WAS CRITICAL                                                                                                                     672.0                           1,416.0                                                     97,480.6
THIS MONTH YR-TO-DATE CUMULATIVE
: 7. REACTOR RESERVE SHUTDOWN HOURS                                                                                                                             0.0                               0.0                                                           0.0
: 6. NUMBER OF HOURS REACTOR WAS CRITICAL 672.0 1,416.0 97,480.6
: 8. HOURS GENERATOR ON-LINE                                                                                                                                 672.0                           1,416.0                                                     95,771.8           ;
: 7. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
: 9. UNIT RESERVE SHUTDOWN HOURS                                                                                                                                 0.0                               0.0                                                           0.0         ,
: 8. HOURS GENERATOR ON-LINE 672.0 1,416.0 95,771.8
765,074                                                                                                            '
: 9. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
: 10. NET ELECTRICAL ENERGY GENERATED (MWH)                                                                                                                                                 1,637,319                                                   95,247,013 l
: 10. NET ELECTRICAL ENERGY GENERATED (MWH) 765,074 1,637,319 95,247,013 l
3
3


UNIT SHUTDOWNS                                                                   -
UNIT SHUTDOWNS DOCKET NO. 50-352 UNIT NAME LNERICK UNIT 1 DATE MARCH 12,1999 COMPLETED BY PECO ENERGY COMPANY D. A. HINCHEY REPORTS ENGINEER SITE ENGINEERING UMERICK GENERATING STATION REPORT MONTH FEBRUARY,1999 TELEPHONE (610)7183797 METHOD OF CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN ACTION TO NO.
DOCKET NO. 50-352                                   .
DATE (1)
UNIT NAME LNERICK UNIT 1 DATE MARCH 12,1999
(HOURS)
* COMPLETED BY PECO ENERGY COMPANY D. A. HINCHEY REPORTS ENGINEER               .        ,
(2)
SITE ENGINEERING UMERICK GENERATING STATION REPORT MONTH   FEBRUARY,1999                                             TELEPHONE (610)7183797 METHOD OF                         CAUSE AND CORRECTIVE TYPE     DURATION REASON           SHUTTING DOWN                               ACTION TO NO. DATE       (1)       (HOURS)   (2)               REACTOR (3)                       PREVENT RECURRENCE 322   990213       S                   B                   4                     REACTOR POWER WAS REDUCED TO 64% DUE TO SCRAM TIME TESTING AND CONTROL ROD PATTERN ADJUSTMENTS 323   990219       S                   H                   4                     REACTOR POWER WAS REDUCED TO 86% DUE TO CONTROL ROD PATTERN ADJUSTMENTS 324   990228       F                 A                     4                     REACTOR POWER WAS REDUCED TO 27% TO MAINTAIN DRYWELL TEMPERATURES DUE TO FAILURE OF DRYWELL CHILLEDWATER PCIV TOTAL HOURS (1)                                       (2)                                                             (3)
REACTOR (3)
F-FORCED                             REASON                                                             METHOD S- SCHEDULED                         A - EQUIPMENT FAILURE (EXPLAIN)                                     1 - MANUAL B - MAINTENANCE OR TEST                                           2- MANUAL SCRAM C - REFUELING                                                     3- AUTOMATIC SCRAM D - REGULATORY RESTRICTION                                         4-OTHER (EXPLAIN)
PREVENT RECURRENCE 322 990213 S
B 4
REACTOR POWER WAS REDUCED TO 64% DUE TO SCRAM TIME TESTING AND CONTROL ROD PATTERN ADJUSTMENTS 323 990219 S
H 4
REACTOR POWER WAS REDUCED TO 86% DUE TO CONTROL ROD PATTERN ADJUSTMENTS 324 990228 F
A 4
REACTOR POWER WAS REDUCED TO 27% TO MAINTAIN DRYWELL TEMPERATURES DUE TO FAILURE OF DRYWELL CHILLEDWATER PCIV TOTAL HOURS (1)
(2)
(3)
F-FORCED REASON METHOD S-SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL B - MAINTENANCE OR TEST 2-MANUAL SCRAM C - REFUELING 3-AUTOMATIC SCRAM D - REGULATORY RESTRICTION 4-OTHER (EXPLAIN)
E - OPERATOR TRAIN!NG + LICENSE EXAMINATION F - ADMINISTRATIVE G - OPERATIONAL ERROR (EXPLAIN)
E - OPERATOR TRAIN!NG + LICENSE EXAMINATION F - ADMINISTRATIVE G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER (EXPLAIN)
H - OTHER (EXPLAIN)


            ~
~
i Docket No. 50-353     l' Attachment to Monthly Operating Report for February 1999
i Docket No. 50-353 l
                                                                                                            ]
Attachment to Monthly Operating Report for February 1999
i Limerick Generating Station                                     l
]
                                                      - Unit 2                                               :
i Limerick Generating Station l
February 1 through February 28,1999                                   ;
- Unit 2 February 1 through February 28,1999
                                                                                                            )
)
l
l 1.
: 1.     N_grrative Summarv of Operatina Experiences Unit 2 began the month of February 1999 at 100% rated thermal power (RTP).
N_grrative Summarv of Operatina Experiences Unit 2 began the month of February 1999 at 100% rated thermal power (RTP).
On February 6,1999 at 2214 hours, power was reduced to 96 % of RTP for main turbine valve testing. Power was restored to 100% of RTP at 2321 hours.
On February 6,1999 at 2214 hours, power was reduced to 96 % of RTP for main turbine valve testing. Power was restored to 100% of RTP at 2321 hours.
On February 12,1999 at 2202 hours, power was reduced to 90 % of RTP for main turbine valve testing and to remove the 5* feedwater heaters. Power was restored to
On February 12,1999 at 2202 hours, power was reduced to 90 % of RTP for main turbine valve testing and to remove the 5* feedwater heaters. Power was restored to
              ' 100% of RTP on February 13,1999 at 0100 hours.
' 100% of RTP on February 13,1999 at 0100 hours.
On February 20,1999 at 2310 hours, power was reduced to 96 % of RTP for main turbine valve testing. Power was restored to 98% of RTP on February 21,1999 at 0130 hours.
On February 20,1999 at 2310 hours, power was reduced to 96 % of RTP for main turbine valve testing. Power was restored to 98% of RTP on February 21,1999 at 0130 hours.
On February 26,1999 at 2109 hours, power was reduced to 95 % of RTP for main turbine valve testing. Power was further reduced to 70% of RTP for entry into the main condenser area to close an instrument root valve and isolate a steam leak on February 26,1999 at 2327 hours. Power was restored to 98% of RTP on February 27,1999 at               i 0630 hours.                                                                                   !
On February 26,1999 at 2109 hours, power was reduced to 95 % of RTP for main turbine valve testing. Power was further reduced to 70% of RTP for entry into the main condenser area to close an instrument root valve and isolate a steam leak on February 26,1999 at 2327 hours. Power was restored to 98% of RTP on February 27,1999 at i
0630 hours.
Unit 2 ended this month at 95% of RTP in end of cycle coast down.
Unit 2 ended this month at 95% of RTP in end of cycle coast down.
i ll. Challenoes to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of February. There have been no challenges to the Main Steam Safety Relief Valves year to date.
i ll.
Challenoes to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of February. There have been no challenges to the Main Steam Safety Relief Valves year to date.


Y OPERATING DATA REPORT DOCKET NO. 50 - 353                                                                   ,
Y OPERATING DATA REPORT DOCKET NO. 50 - 353 DATE MARCH 12,1999 COMPLETED BY PECO ENERGY COMPANY P. A. HiNCHEY REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3797 OPERATING STATUS 1.UNITNAME_________________________,________________________________,
DATE MARCH 12,1999 COMPLETED BY PECO ENERGY COMPANY P. A. HiNCHEY REPORTS ENGINEER                                     -
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ LIMERIC_K_ UNIT _2
SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3797                                                     ,
: 2. REPORTING PERIOD; _________________,_________________________,_________________________________FEB,RU_A_RY,i_999
OPERATING STATUS 1.UNITNAME_________________________,________________________________,                                                                                 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ LIMERIC_K_ UNIT _2
: 2. REPORTING PERIOD; _________________,_________________________,_________________________________FEB,RU_A_RY,i_999                                                                                           _
: 3. DESIGN ELECTRICAL RATING (NET MWE): ________________________________________________________________________1_115
: 3. DESIGN ELECTRICAL RATING (NET MWE): ________________________________________________________________________1_115
: 4. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):                             ________________________,__,___________________________________,__11_55
: 4. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):
: 5. MAXIMUM DEPENDABLE CAPACITY (NET MWE):             _____________________________________________________________________1115_
________________________,__,___________________________________,__11_55
THIS MONTH                                         YR-TO-DATE                 CUMULATIVE
: 5. MAXIMUM DEPENDABLE CAPACITY (NET MWE): _____________________________________________________________________1115_
: 6. NUMBER OF HOURS REACTOR WAS CRITICAL                                                                                         672.0                                                 1,416.0                   73,965.3
THIS MONTH YR-TO-DATE CUMULATIVE
: 7. REACTOR RESERVE SHUTDOWN HOURS                                                                                                 0.0                                                   00                         0.0
: 6. NUMBER OF HOURS REACTOR WAS CRITICAL 672.0 1,416.0 73,965.3
: 8. HOURS GENERATOR ON-LINE                                                                                                     672.0                                                 1,416.0                   72,559.1
: 7. REACTOR RESERVE SHUTDOWN HOURS 0.0 00 0.0
: 9. UNIT RESERVE SHUTDOWN HOURS                                                                                                     0.0                                                   0.0                         0.0
: 8. HOURS GENERATOR ON-LINE 672.0 1,416.0 72,559.1
: 10. NET ELECTRICAL ENERGY GENERATED (MWH)                                                                                     735,093                                             1,566,748                 75,436,433
: 9. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
: 10. NET ELECTRICAL ENERGY GENERATED (MWH) 735,093 1,566,748 75,436,433


UNIT SHUTDOWNS                                                                                 --      !
UNIT SHUTDOWNS DOCKET NO. 50-353 UNIT NAME LIMERICK UNIT 2 i
DOCKET NO. 50-353
* UNIT NAME LIMERICK UNIT 2                                               i DATE MARCH 12,1999                                            *
[
[
COMPLETED BY PECO ENERGY COMPANY P. A. HINCHEY REPORTS ENGINEER                 .                        .
DATE MARCH 12,1999 COMPLETED BY PECO ENERGY COMPANY P. A. HINCHEY REPORTS ENGINEER SITE ENGINEERING LIMERICif GENERATING STATION REPORT MONTH FEBRUARY,1999 TELEPHONE (610)718-3797 i
SITE ENGINEERING                                             .
METHOD OF CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN ACTION TO NO.
LIMERICif GENERATING STATION                                 ,
DATE (1)
REPORT MONTH               FEBRUARY,1999                                                                                                                         TELEPHONE (610)718-3797                       .                          i METHOD OF                         CAUSE AND CORRECTIVE TYPE                                   DURATION                                                         REASON           SHUTTING DOWN                               ACTION TO NO.       DATE           (1)                                       (HOURS)                                                       (2)               REACTOR (3)                       PREVENT RECURRENCE s
(HOURS)
351       990206           S                                                                                                         B                   4                     REACTOR POWER WAS REDUCED TO 96% DUE TO MAIN                           i TURBINE VALVE TESTING                                                   ;
(2)
i 352       990212           S                                                                                                         B                   4                     REACTOR POWER WAS REDUCED TO 90% DUE TO MAIN TURBINE VALVE TESTING AND REMOVAL OF STH FEEDWATER HEATERS FROM SERVICE 353       990220           S                                                                                                         B                   4                     REACTOR POWER WAS REDUCED TO 96% DUE TO MAIN                             ,
REACTOR (3)
TURBINE VALVE TESTING 354       990226           S                                                                                                         B                   4                     REACTOR POWER WAS REDUCED TO 70% DUE TO MAIN TURBINE VALVE TESTING AND ISOLATION OF MINOR STEAM                       .
PREVENT RECURRENCE s
LEAK TOTAL HOURS                                                                                                                                                                                                                               ,
351 990206 S
i I
B 4
(1)                                                                                                                             (2)                                                                   (3)
REACTOR POWER WAS REDUCED TO 96% DUE TO MAIN i
F-FORCED                                                                                                                         REASON                                                             METHOD S - SCHEDULED                                                                                                                   A- EQUIPMENT FAILURE (EXPLAIN)                                     1 - MANUAL B - MAINTENANCE OR TEST                                             2- MANUAL SCRAM C - REFUELING                                                       3 - AUTOMATIC SCRAM D- REGULATORY RESTRICTION                                           4- OTHER (EXPLAIN)
TURBINE VALVE TESTING i
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE G - OPERATIONAL ERROR (EXPLAIN)
352 990212 S
H - OTHER (EXPLAIN)
B 4
                                                                                                                                                                                                              . - , , -    -  ~ , , , , - _ - -}}
REACTOR POWER WAS REDUCED TO 90% DUE TO MAIN TURBINE VALVE TESTING AND REMOVAL OF STH FEEDWATER HEATERS FROM SERVICE 353 990220 S
B 4
REACTOR POWER WAS REDUCED TO 96% DUE TO MAIN TURBINE VALVE TESTING
{
354 990226 S
B 4
REACTOR POWER WAS REDUCED TO 70% DUE TO MAIN l
TURBINE VALVE TESTING AND ISOLATION OF MINOR STEAM
{
LEAK TOTAL HOURS i
I I
(1)
(2)
(3)
F-FORCED REASON METHOD S - SCHEDULED A-EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL B - MAINTENANCE OR TEST 2-MANUAL SCRAM C - REFUELING 3 - AUTOMATIC SCRAM D-REGULATORY RESTRICTION 4-OTHER (EXPLAIN)
E - OPERATOR TRAINING + LICENSE EXAMINATION l
F - ADMINISTRATIVE G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER (EXPLAIN) i b
~,,,
, - _ - -}}

Latest revision as of 20:56, 6 December 2024

Monthly Operating Repts for Feb 1999 for Limerick,Units 1 & 2.With
ML20207J746
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 02/28/1999
From: Grimes J, Hinchey P
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9903160372
Download: ML20207J746 (7)


Text

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Limerick Gener: ting Station

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A V

PECO NUCLEAR ecw eo-c-,

Po Box 2300 A Unit of PECO Energy Sanatoga, PA 19464 0920

+

l T.S.6.9.1.6 l

l March 12,1999 Docket Nos. 50-352 50-353 License Nos. NPF-39 l

NPF-85 l

U. S. Nuclear Regulatory Commission l

Atm: Document Control Desk Washington,DC 20555 l

Subject:

Limerick Generating Station Monthly Operating Report For Units 1 and 2 Enclosed are the monthly operating reports for Limerick Units 1 and 2 for the month of February 1999 forwarded pursuant to Technical Specification 6.9.1.6.

Very truly yours, Jos h P. Grimes Director - Site Engineering f

Enclosures cc:

H. J. Miller, Administrator, Region I, USNRC A. L. Burritt, USNRC Senior Resident Inspector LGS i

J. D. von Suskil, Vice President, LGS G. H. Stewart, LGS Experience Assessment Branch, SSB2-4 S. A. Auve, LOS ISEG Branch, SSB4-2 Ij 9903160372 9902283 2 m; PDR ADOCK 0 R

2

..r.

a Docket No. 50-352 Attachment to Monthly Operating Report for February 1999 i

j Limerick Generating Station Unit 1 l

February 1 through February 28,1999 i

I

- 1.

Narrative Summary of Operatino Experiences 1

Unit 1 began the month of February 1999 at 100% of rated thermal power (RTP).

On February 13,1999 at 0336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br />, power was reduced to 64% of RTP for control j

rod pattern adjustments. Power was raised to 98 % of RTP on February 14,1999 at 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> with MFLPD being monitored and tuning being performed. Power was restored to 100% of RTP on February 16,1999 at 2257 hours0.0261 days <br />0.627 hours <br />0.00373 weeks <br />8.587885e-4 months <br />.

On February 19,1999 at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />, power was reduced to 86% of RTP for control I

rod pattern adjustments. Power was restored to 100% of RTP on February 20,1999 at 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />.

On February 28,1999 at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, power was reduced to 85% of RTP to reduce the heat load in the drywell with a loop of drywell chilled water being isolated due to an inoperable PCIV. Power was further reduced to 27% power to maintain drywell temperature below 135 degrees.

Unit 1 ended this month at 27 % RTP.

11.

Challenoes to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of February. There have been no challenges to the Main Steam Safety Relief Valves year to date.

l 4

l l

.. ~.. _.. _. -. _ _. - - _ _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -. - - -. -

OPERATING DATA REPORT t

DOCKET NO. 50-352 DATE MARCH 12,1999 COMPLETED BY PECO ENERGY COMPANY P. A. HINCHEY REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3797 1

OPERATING STATUS

1. UNIT NAME: ______,______________________________________________,,_____________________________LIMERIC_K_U_ NIT _1,
2. REPORTING PERIOD:,____________________________________________________________________________FEBR_U_A_RY1_999 u
3. DESIGN ELECTRICAL RATING (NET MWE): ___________________,____________________________________________________1_1_34_
4. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): ____________,_____________________________________________________1174 S. MAXIMUM DEPENDABLE CAPACITY (NET MWE): _________________,._________________________________________,_________1134 l

THIS MONTH YR-TO-DATE CUMULATIVE

6. NUMBER OF HOURS REACTOR WAS CRITICAL 672.0 1,416.0 97,480.6
7. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
8. HOURS GENERATOR ON-LINE 672.0 1,416.0 95,771.8
9. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
10. NET ELECTRICAL ENERGY GENERATED (MWH) 765,074 1,637,319 95,247,013 l

3

UNIT SHUTDOWNS DOCKET NO. 50-352 UNIT NAME LNERICK UNIT 1 DATE MARCH 12,1999 COMPLETED BY PECO ENERGY COMPANY D. A. HINCHEY REPORTS ENGINEER SITE ENGINEERING UMERICK GENERATING STATION REPORT MONTH FEBRUARY,1999 TELEPHONE (610)7183797 METHOD OF CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN ACTION TO NO.

DATE (1)

(HOURS)

(2)

REACTOR (3)

PREVENT RECURRENCE 322 990213 S

B 4

REACTOR POWER WAS REDUCED TO 64% DUE TO SCRAM TIME TESTING AND CONTROL ROD PATTERN ADJUSTMENTS 323 990219 S

H 4

REACTOR POWER WAS REDUCED TO 86% DUE TO CONTROL ROD PATTERN ADJUSTMENTS 324 990228 F

A 4

REACTOR POWER WAS REDUCED TO 27% TO MAINTAIN DRYWELL TEMPERATURES DUE TO FAILURE OF DRYWELL CHILLEDWATER PCIV TOTAL HOURS (1)

(2)

(3)

F-FORCED REASON METHOD S-SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL B - MAINTENANCE OR TEST 2-MANUAL SCRAM C - REFUELING 3-AUTOMATIC SCRAM D - REGULATORY RESTRICTION 4-OTHER (EXPLAIN)

E - OPERATOR TRAIN!NG + LICENSE EXAMINATION F - ADMINISTRATIVE G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER (EXPLAIN)

~

i Docket No. 50-353 l

Attachment to Monthly Operating Report for February 1999

]

i Limerick Generating Station l

- Unit 2 February 1 through February 28,1999

)

l 1.

N_grrative Summarv of Operatina Experiences Unit 2 began the month of February 1999 at 100% rated thermal power (RTP).

On February 6,1999 at 2214 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.42427e-4 months <br />, power was reduced to 96 % of RTP for main turbine valve testing. Power was restored to 100% of RTP at 2321 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.831405e-4 months <br />.

On February 12,1999 at 2202 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.37861e-4 months <br />, power was reduced to 90 % of RTP for main turbine valve testing and to remove the 5* feedwater heaters. Power was restored to

' 100% of RTP on February 13,1999 at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />.

On February 20,1999 at 2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br />, power was reduced to 96 % of RTP for main turbine valve testing. Power was restored to 98% of RTP on February 21,1999 at 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br />.

On February 26,1999 at 2109 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.024745e-4 months <br />, power was reduced to 95 % of RTP for main turbine valve testing. Power was further reduced to 70% of RTP for entry into the main condenser area to close an instrument root valve and isolate a steam leak on February 26,1999 at 2327 hours0.0269 days <br />0.646 hours <br />0.00385 weeks <br />8.854235e-4 months <br />. Power was restored to 98% of RTP on February 27,1999 at i

0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br />.

Unit 2 ended this month at 95% of RTP in end of cycle coast down.

i ll.

Challenoes to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of February. There have been no challenges to the Main Steam Safety Relief Valves year to date.

Y OPERATING DATA REPORT DOCKET NO. 50 - 353 DATE MARCH 12,1999 COMPLETED BY PECO ENERGY COMPANY P. A. HiNCHEY REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3797 OPERATING STATUS 1.UNITNAME_________________________,________________________________,

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ LIMERIC_K_ UNIT _2

2. REPORTING PERIOD; _________________,_________________________,_________________________________FEB,RU_A_RY,i_999
3. DESIGN ELECTRICAL RATING (NET MWE): ________________________________________________________________________1_115
4. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

________________________,__,___________________________________,__11_55

5. MAXIMUM DEPENDABLE CAPACITY (NET MWE): _____________________________________________________________________1115_

THIS MONTH YR-TO-DATE CUMULATIVE

6. NUMBER OF HOURS REACTOR WAS CRITICAL 672.0 1,416.0 73,965.3
7. REACTOR RESERVE SHUTDOWN HOURS 0.0 00 0.0
8. HOURS GENERATOR ON-LINE 672.0 1,416.0 72,559.1
9. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
10. NET ELECTRICAL ENERGY GENERATED (MWH) 735,093 1,566,748 75,436,433

UNIT SHUTDOWNS DOCKET NO. 50-353 UNIT NAME LIMERICK UNIT 2 i

[

DATE MARCH 12,1999 COMPLETED BY PECO ENERGY COMPANY P. A. HINCHEY REPORTS ENGINEER SITE ENGINEERING LIMERICif GENERATING STATION REPORT MONTH FEBRUARY,1999 TELEPHONE (610)718-3797 i

METHOD OF CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN ACTION TO NO.

DATE (1)

(HOURS)

(2)

REACTOR (3)

PREVENT RECURRENCE s

351 990206 S

B 4

REACTOR POWER WAS REDUCED TO 96% DUE TO MAIN i

TURBINE VALVE TESTING i

352 990212 S

B 4

REACTOR POWER WAS REDUCED TO 90% DUE TO MAIN TURBINE VALVE TESTING AND REMOVAL OF STH FEEDWATER HEATERS FROM SERVICE 353 990220 S

B 4

REACTOR POWER WAS REDUCED TO 96% DUE TO MAIN TURBINE VALVE TESTING

{

354 990226 S

B 4

REACTOR POWER WAS REDUCED TO 70% DUE TO MAIN l

TURBINE VALVE TESTING AND ISOLATION OF MINOR STEAM

{

LEAK TOTAL HOURS i

I I

(1)

(2)

(3)

F-FORCED REASON METHOD S - SCHEDULED A-EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL B - MAINTENANCE OR TEST 2-MANUAL SCRAM C - REFUELING 3 - AUTOMATIC SCRAM D-REGULATORY RESTRICTION 4-OTHER (EXPLAIN)

E - OPERATOR TRAINING + LICENSE EXAMINATION l

F - ADMINISTRATIVE G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER (EXPLAIN) i b

~,,,

, - _ - -