ML20092G332

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Monthly Operating Repts for Aug 1995 for Limerick Nuclear Generating Station
ML20092G332
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 08/31/1995
From: Gallagher M, Henricks D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9509190241
Download: ML20092G332 (10)
v • d • e


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' PECO ENERGY- ;5ff";'s ""**

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T.S.6.9.1.6 September 14, 1995 Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 1

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 August 1995 forwarded pursuant to Technical Specification 6.9.1.6.

l Very truly yours, 4P.6Au.agheR.

Michael P. Gallagher Director - Site Engineering drh Enclosures cc: T. T. Martin, Administrator, Region I, USNRC N. S. Perry, USNRC Senior Resident Inspector LGS W. G. MacFarland, Vice President, LGS IS0123 ^

9509190241 DR-950831 t l

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- Docket No. 50-352

- Attachment to Monthly Operating Report for i August 1995 Umerick Generating Station Unit 1 August 1 through August 31,1995

i. Narrative Summarv of Ooerating Exoeriences Unit 1 began the month of August at a nominal 100% of rated thermal power (RTP).

l

- On August 1,2,3,4,5,12,14,16,17,1995, power was reduced slightly due to high turbine

! backpressure as a result of elevated outside air temperature. Power was restored to 100% )

RTP when turbine backpressure was retumed to acceptable values.

J

- On August 6,1995, at 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br />, power was reduced to 90% RTP for main turbine valve 2 testing and control rod exercise testing. Power was restored to 100% RTP at 0857 hours0.00992 days <br />0.238 hours <br />0.00142 weeks <br />3.260885e-4 months <br />.

- On August 8,1995, at 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br />, the A reactor feedwater pump minimum flow valve failed

open. This resulted in a reactor pressure vessel level decrease of 15". The RO responded ,

a by increasing flow to the vessel, however the B reactor feedpump tripped due to low 1 suction pressure and both reactor recirculation pumps ran back to their high flow limiter.

l Off-normal procedures were entered and appropriate actions taken. An operator was

- dispatched to close the A reactor feedpump minimum flow line manual isolation valve and the Unit was stabilized at 71% RTP. The failure of the minimum flow valve was the result l of a failed power supply. The Unit was retumed to 100% power on August 9,1995, at 1616 4

hours.

l - On August 13,1995, at 1325 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.041625e-4 months <br />, power was reduced to 95% RTP for control rod exercise testing. Power was restored to 100% RTP, at 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />. 1

- On August 20,1995, at 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />, power reductions began for a planned outage to

replace a failed fuel bundle. The main turbine was removed from service at 1316 hours0.0152 days <br />0.366 hours <br />0.00218 weeks <br />5.00738e-4 months <br />, and the unit was scrammed using the mode switch at 1401 hours0.0162 days <br />0.389 hours <br />0.00232 weeks <br />5.330805e-4 months <br />. The unit entered operational condition 4, cold shutdown, at 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br />, on August 21,1995. The leaking fuel bundle was replaced end the Unit entered operational condition 2, Startup, at 1520
hours, on August 27,1995. The unit went critical at 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br />.

I - On August 28, 1995, during startup activities, with the reactor pressure vessel at approximately 820 psig, an increase in drywell pressure was observed. Off-normal  ;

i procedures were entered and reactor pressure was reduced. However, there was Indication  ;

of unidentified leakage into the drywell and the reactor was manually shutdown at 0652 l 1

hours. An unusual event was declared at 0734 hours0.0085 days <br />0.204 hours <br />0.00121 weeks <br />2.79287e-4 months <br /> due to the unusual shutdown of the 1 unt. The unusual event was terminated at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> with the unit stable in hot shutdown. l l The leakage was due to a misaligned reactor pressure vessel instrument flange connection

, following fuel replacement actMties. The Unit entered operational condition 4 and the j flange connection was properly aligned.

Unit 1 ended this operating period in operational condition 4, cold shutdown.

II. Challences to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of August.

i i

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AVERAGE DAILY UNIT PCWER LEVEL DOCKET NO. 50 - 352 UNIT LIMERICK UNIT 1

---------~~~~~.

DATE SEPTEMBER 13. 1995 .

COMPANY PECO ENERGY COMPANY

~~~---------------------

OAVID R. HENRICKS .

REPORTS ENGINEER ,

SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 MONTH AUGUST 1995 DAY AVERAGE DAILY PCwER LEVEL DAY AVERAGE DAILY POWER LEVEL (MwE-NET) (MWE-NET) 1 1012 17 1002 2 1004 18 1039 3 1004 19 1039 4 1004 20 403 5 1024 21 0 6 1016 22 0 7 1045 23 0 8 1005 24 0 9 944 25 0 10 1029 26 0 11 1025 27 0 12 1020 28 0 13 1028 29 0 14 1024 30 0 15 1039 31 0 16 1023

- . .. _ . _ . . _ . . . _ . . . o. .mm om ...- - m ---- ~~. -.m_~. - _...._.m_ . _ . _ . . . _. .. . .. .,._ _.m__._ ._m._ ._ _ ... ,

OPERQTING DQTA REPORT DOCKET NO. 50 - 352 DATE SEPTEMBER 13 1995 COMPLETED BY PECO ENERGY COMPANY .

DAVID R. HENRICKS REPORTS ENGINEER SITE ENGINEERING .

LIMERICK GENERATING STATION ,

TELEPHONE (610) 718-3772 OPERATING STATUS 1 UNIT NAME: LIMERICK UNIT 1 NOTES: THERE WERE 2 LOAD DROPS

2. REPORTING PERIOD: AUGUST. 1995 GREATER THAN 20% THIS MONTH
3. LICENSED THERMAL POWER (MWT): 3293 DUE TO REACTOR FEED WATER PUMP 4 NAMEPLATE RATING (GROSS MWE): 1092 MIN FLOW VALVE FAILURE AND A
5. DESIGN ELECTRICAL RATING (NET MwE): 1055 PLANNED OUTAGE TO REPLACE A
6. MAXIMUM DEPENDABLE CAPACITY (GROSS.MwE): 1092 FAILED FUEL BUNDLE.
7. MAXIMUM DEPENDABLE CAPACITV (NET MWE): 1055 i
8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET MwE):
10. REASONS FOR RESTRICTIONS. IF ANY:

'i THIS MONTH YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744 5.831 83.975
12. NUMBER OF HOURS REACTOR WAS CRITICAL 480.1 5.466.4 69.574.7
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATOR ON-LINE 469.3 5.419.1 68.444.6
15. UNIT. RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

, 16. GROSS THERMAL ENERGY GENERATED (MWH) 1.516.442 17.620.112 211.936.650 17 GROSS ELECTRICAL ENERGY GENERATED (MWH) 492.300 5.742.300 68.926.580

18. NET ELECTRICAL ENERGY GENERATED (MwH) 471.205 5.542.451 66.186.457 PAGE 1 OF 2

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OPERQTING DQTA REPORT (CONTINUED) DOCKET NO. 50 - 333 .

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

DATE SEPTEMBER 13. 1995 THIS MONTH VR-TO-DATE CUMULATIVE .

19. UNIT SERVICE FACTOR 63.1 92.9 B1.5
20. UNIT AVAILABILITY FACTOR 63.1 92.9 81.5 .

21 UNIT CAPACITY FACTOR (USING MDC NET) 60.0 90.1 74.7

22. UNIT CAPACITY FACTOR (U5ING DER NET) 60.0 90.1 74.7
23. UNIT FORCED OUTAGE RATE O.0 0.7 4.0 24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):
1. PLANNED OUTAGE / REPLACE FAILED FUEL BUNDLE. 8/20/95 12 DAYS.
2. REFUELING OUTAGE. SCHEDULED FOR 1/26/96 LASTING 2' DAYS.
25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 09/01/95
26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 12/19/84 12/22/84 INITIAL ELECTRICITV MID APRIL 85 4/13/05 COMMERCIAL OPERATION 157 QTR 86 2/01/86 PAGE 2 OF 2

I UNIT SHUTDOWNS AND POWER REDUCTIONS- DOCKET NO. 50 - 352 *

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UNIT . NAME LIMERICK UNIT 1

=

DATE SEPTEMBER 13 1995 REPORT MONTH AUGUST. 1995 COMPLETED BY PECO ENERGY COMPAN DAVID R. HENRICKS -

REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION .

TELEPHONE (610) 718-3772- ,

_..----.-..---..- _..- -- __ - - - - - - . - - - - - - - - - - - - - - - - - . . . . . - . - - . . - - - - - - - - - - - - - --..--- -- =-

METHOD OF LICENSEE SYSTEM COMPONENT - CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE A CTION TO NO. DATE (1) (HOURS) (2) REACTOR (3) REPORT a (4) (5) PREVENT RECURRENCE 77 950806 S 000.0 B 4 N/A HA VALVEX REACTOR POWER WAS REDUCED TO 90% FOR 4 MAIN TURBINE VALVE TESTING AND CONTROL 4 ROD EXERCISE TESTING. 4 73 950808 F 000.0 A 4 N/A CH INSTRU REACTOR POWER WAS REDUCED TO 71% DUE TO 4 REACTOR FEEDwATER PUMP MIN FLOW VALVE 4 l FAILED OPEN DUE TO A FAILED POWER SUPPLY 4 73 950813 S 000.0 B 4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 95% DUE TO 4 CONTROL ROD EXERCISE TESTING. 4 8D 950820 S I 185.6 A 2 N/A RC FUELXX REACTOR WAS SHUTDOWN TO REPLACE A FAILED 4 FUEL, BUNDLE. 4 81 950828 S. 089.1 A 2 1-95-006 CA PIPEXX REACTOR WAS SHUTDOWN SHORTLY AFTER BEING 4 CRITICAL DUE TO LEAKAGE INTO THE DRvWELL 4 CAUSED BY A MISALIGNED REACTOR PRESSURE 4 VE5SEL INSTRUMENT FLANGE CONNECTION. 4 4

l 4 I 274.7 1

1

. (1) (2) (3) (4)

! 8 - 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)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN) FILE (NUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)

G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE w _..z_-_ -- ___.- - _ _ - - _ _ . _ - . - - _ _ - - - _ _ - - _ _ - _ - - _ - _ _ - a - - . rA et

i ..

Docket No. 50-353 Attachment to Monthly Operating Report for l August 1996 l Limerick Generating Station Unit 2

< August 1 through August 31,1996 i 1. Narrative Summary of Operating Experiences l Unit 2 began the month of August at a nominal 100% of rated thermal power (RTP).

! - On August 1,2,3,4,5,12,14,16,17,1996, power was reduced slightly due to high turbine backpressure as a result of elevated outside air temperature. Power was restored to 100%

i RTP when turbine backpressure was retumed to acceptable values.

1 j - On August 8,1996, at 1337 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.087285e-4 months <br />, an automatic scram occurred due to main turbine stop valve closure fdlowing the trip of the main turbine as a result of high reactor pressure i vessel water level of 54". The RO observed a signal lockout to the A reactor feedpump.

j The A and B reactor recirc pumps received automatic runbacks. Following the scram,

reactor pressure vessel water level decreased to a minimum of -33". Off-normal procedures 4 were entered and level was restored with the feedwater system aligned in startup level contrd. The cause of the transient was the result of a failed power supply in the feedwater l contrd system. The power supply was replaced and the Unit was placed in startup on j August 9,1995, at 0626 hours0.00725 days <br />0.174 hours <br />0.00104 weeks <br />2.38193e-4 months <br />, and the unit went critical at 1604 hours0.0186 days <br />0.446 hours <br />0.00265 weeks <br />6.10322e-4 months <br />. The Unit entered operational condition 1, Run, at 0636 hours0.00736 days <br />0.177 hours <br />0.00105 weeks <br />2.41998e-4 months <br />, on August 11, 1995, and the unit was synchronized to the grid at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br />. On August 12,1995, at 1143 hours0.0132 days <br />0.318 hours <br />0.00189 weeks <br />4.349115e-4 months <br />, the unit was

. retumed to 100% RTP.

?

- On August 13,1996, at 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, power was reduced to 96% RTP for a control rod

pattem adjustment. Power was restored to 100% RTP at 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br />.

- On August 14,1995, at 0017 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br />, power was reduced to 90% RTP for a contrd rod pattem adjuttment and main turbine valve exercise testing. Power was restored to 100%

l

RTP at 0628 hours0.00727 days <br />0.174 hours <br />0.00104 weeks <br />2.38954e-4 months <br />.

j - On August 20,1995, at 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br />, turbine bypass valves sporadically opened and closed.

Power was reduced, per procedures, and stabilized at 51% RTP. At 1602 hours0.0185 days <br />0.445 hours <br />0.00265 weeks <br />6.09561e-4 months <br /> the bypass j valves again opened and the Unit scrammed on high reactor pressure vessel pressure while j the reactor mode switch was placed in shutdown. The Unit entered operational condition 4, Cold Shutdown, at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br /> on August 21,1995. The most probable cause of the i

scram was that a high impedance had developed across a normally closed Electro-Hydraulle Control relay contact that resulted in downstream relays to momentarily de-energize. This resulted in an Instantaneous or sustained low turbine control valve demand signal that caused the valves to cicse. A modification was performed on the relay board.

l The mode switch was placed in startup at 0202 hours0.00234 days <br />0.0561 hours <br />3.339947e-4 weeks <br />7.6861e-5 months <br />, on August 22,1996, and the reactor was critical at 1214 hours0.0141 days <br />0.337 hours <br />0.00201 weeks <br />4.61927e-4 months <br />. The unit entered operational condition 1, Run, at 0104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />,

~

i on August 23,1995, and the unit was synchronized to the grid at 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br />. The unit was retumed to 100% RTP at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />.

- On August 24,1995, at 0740 hours0.00856 days <br />0.206 hours <br />0.00122 weeks <br />2.8157e-4 months <br />, power was reduced to 90% RTP for a control rod pattem adjustment. Power was restored to 100% RTP at 1201 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.569805e-4 months <br />.

Unit 2 ended this operating period at 100% of RTP.

I II. Challenges to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of August.

AVERAGE DAILV UNIT PO3ER LEVEL .

DOCKET NO. 50 - 353 UNIT LIMERICK UNIT 2 DATE SEPTEMBER 13, 1995 COMPANY PECO ENERGY COMPANY DAVID R. HENRICKS ,

REPORTS ENGINEER

  • SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) *i8-3772 MONTH AUGUST 1995 DAY AVERAGE DAILV POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (wwE-NET) (MwE-NET) 1 1090 17 1098 2 1074 18 1111 3 1069 19 1115 4 1065 20 724 5 1098 21 0 6 1106 22 0 7 1118 23 488 8 556 24 1090 9 0 25 1114 10 0 26 1106 11 202 27 1103 12 976 28 1106 13 1097 29 1106 14 1085 30 1107 15 1111 31 1102 16 1103

W e

  • OPERATING DATA REPORT .

DOCKET NO. 50 - 353 DATE SEPTEMBER 13 1995 COMPLETED BY PECO ENERGY COMPANY

  • DAVID R. HENRICKS REPORTS ENGINEER .

SITE ENGINEERING LIMERICK GENERATING STATION

  • TELEPHOFE (610) 718-3772 OPERATING STATUS
1. UNIT NAME: LIMERICK UNIT 2 NOTES: THERE WERE 2 LOAD DROPS
2. REPORTING PERIOD: AUGUST. 1995 GREATER THAN 20% THIS MONTH
3. LICENSED THERMAL POWER (MwT): 3450 DUE TO AUTOMATIC SCRAMS 4 NAMEPLATE RATING (GROSS MWE): 1163 CAUSED BY FEED WATER CONTROL
5. DESIGN ELECTRICAL RATING (NET MWE)s 1115 FAILURE AND EHC CONTROL RELAY
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1155 FAILURE.
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 11$5
8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET WWE):
10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH VR-TO-DATE CUMULATIVE 11 HOURS IN REPORTING PERIOD 744 5.831 49.487

12. NUMBER OF HOUnS REACTOR WAS CRITICAL 673.4 5.240.8 44.603.8
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14 HOURS GENERATOR ON-LINE 614.9 5.069.1 43.674.0
15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MWH) 2.141.542 16.118.097 138.347.680
17. GROSS ELECTRICAL ENERGY GENERATED (uWH) 676.500 5.318.700 45.702.280
18. NET ELECTRICAL ENERGY GENERATED (MWH) 649.583 5.131.644 44.033.844 PAGE 1 Or 2'
c. 6; OPERATING' DATA REPORT (CONTINUED) . DOCKET NO. 50'- 353. ,

DATE SEPTEMBER 13, 1995 THIS MONTH YR-TO-DATE . CUMULATIVE  :.. .[

19. UNIT SERVICE FACTOR ' 8 2. 6 - 86.9 88.3 20.' UNIT AVAILA8ILITY FACTOR 82.6 86.9 88.3 . . .[
21. UNIT CAPACITY FACTOR (USING MDC NET) 78.3 79.3 83.9
22. UNIT CAPACITY FACTOR (USING DER NET) 78.3 79.3 83.9 '[
23. UNIT FORCED OUTAGE RATE 10.3 2.9 3.4
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):

.-25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF .STARTUP-i

26. UNITS IN TEST STATUS'(PRIOR TO COMMERCIAL OPERATION): FORECAST ACHIEVED INITIAL CRITICALITY 08/12/89 08/12/89 INITIAL ELECTRICITY 09/01/89 09/01/89 COMMERCIAL OPERATION 02/01/90 01/08/90

.i P

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' UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 5O - 353 UNIT NAME LIMERICK UNIT 2 DATE SEPTEM9ER 13 1995 REPORT MONTH AUGUST. 1995 COMPLETED BY PECO ENERGY COMPANY

.--=_ --- - ,

DAVID R. HENRICKS ,

REPORTS ENGINEER SITE ENGINEERING

  • LIMERICK GENERATING STATION
  • l TELEPHONE (610) 718-3772: ,

METHOD OF l LICENSEE ISYSTEM! COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWNl EVENT l CODE CODE ACTION TO NO.

DATE (1) (HOURS)

(2) REACTOR (3) l REPORT

  • l (4) (5) PREVENT RECURRENCE 67' 950800 F 069.5 A 3 2-95-008 CH INSTRU REACTOR WAS SHUTDOWN DUE TO A FAILED 4 i POWER SUPPLY IN THE FEED WATER CONTROL 4 SYSTEM. 4 1

68 950813 5 000.0 B 4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 95% DUE TO. 4 CONTROL ROD PATTERN ADJUSTMENT. .4 ';

69- 950814 5 000.0 B 4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 90% DUE TO 4-CONTROL ROD PATTERN ADJUSTMENT AND MAIN ~4 TURBINE VALVE TESTING. 4 70 950820 F 059.6 A 3 2-95-010 HA INSTRU REACTOR WAS SHUTDOWN DUE TO A HIGH IMPED 4 i

-ANCE ACROSS THE EHC CONTROL RELAY 4 CONTACT RESULTING IN SPROADIC OPENING 4.

AND CLOSING TURBINE BYPASS VALVES. 4 71 950824 5 000.0 B 4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 90% DUE TO 4 CONTROL ROD PATTERN ADJUSTMENT. 4

! 4 l

l 129.1 (1) (2) (3) (4) -;

F - FORCED REASON MET HOD 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)

D- REGULATORY RESTRICTION 4 - OTHER (EXPLAIN) FILE (NUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION '

F - ADMINISTRATIVE (5)

G - OPERATIONAL ERROR ( EX PL'.I N )

H- OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE

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