ML20137T144

Monthly Operating Repts for Mar 1997 for Beaver Valley Power Station Units 1 & 2

ML20137T144
Person / Time
Site:	Beaver Valley
Issue date:	03/31/1997
From:	David Jones, Legrand R DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9704160002
Download: ML20137T144 (12)

Text

~

d%.

7%

4 Telephone (412) 393-6000

""o!' 3

• Shippingport. PA 15077-0004 April 4,1997 i

Beaver Valley Power Station Unit 1 - Docket No. 50-334, License No. DPR-66 Unit 2 - Docket No. 50-412, License No. NPF-73 Monthlv Operating Report U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

In accordance with Appendix A, Technical Specifications, the Monthly Operating Report is submitted for Unit 1 and Unit 2 for the month of March,1997.

Respectfully, ,

On a e --c.

R. L. LeGrand Division Vice President, Nuclear Operations /

Plant Manager i

Enclosures  :

cc: NRC Regional Office O King ofPrussia, PA 150147 The Nuclear Professionals 9704160002 970331 Illl3ll!lllllIIl$lllh5!!!!

PDR ADOCK 05000334 '

R PDR ,

- - J

i NARRATIVE

SUMMARY

OF

.. .. MONTHLY OPERATING EXPERIENCE UNIT 1 l

MARCH 1997 March 1 The Unit operated at a nominal value of 100% output through March 18 March 19 The Unit experienced a Reactor Trip from 100% output at 0606 hours0.00701 days <br />0.168 hours <br />0.001 weeks <br />2.30583e-4 months <br /> when the Main Unit Generator output breakers opened due to inadvertent operation of a bus backup timer relay in the 345 KV distribution system. Just prior to the event, a phase-to-ground fault occurred on a 345 KV line in the Ohio Edison System. The fault was sensed by the Beaver Valley switchyard electrical protection circuitry that inadvertently operated causing a Main Unit Generator / Turbine Trip and subsequent Reactor Trip. The Unit was subsequently stabilized in Mode 3.

March 20 The Unit commenced a plant cooldown to Mode 5 at 1843 hours0.0213 days <br />0.512 hours <br />0.00305 weeks <br />7.012615e-4 months <br /> to repair a secondary side leak at the "C" Steam Generator hand hole flange.

March 21 Mode 4 was entered at 0513 hours0.00594 days <br />0.143 hours <br />8.482143e-4 weeks <br />1.951965e-4 months <br /> as the plant cooldown continued. i i

March 22 Mode 5 was entered at 0326 hours0.00377 days <br />0.0906 hours <br />5.390212e-4 weeks <br />1.24043e-4 months <br /> to enable repair of the secondary side leak at the "C" Steam Generator hand hole flange.

March 23 The Unit remained shutdown in Mode 5 to perform repair of the secondary side leak through at the "C" Steam Generator hand hole flange. During this time period, a small leak March 26 was also found at the "A" Steam Generator hand hole flange and was repaired. In addition, a body-to-bonnet flange joint leak was discovered on the "A" Reactor Coolant Loop Cold Leg Isolation Valve.

March 27 The Unit remained shutdown in Mode 5 for the remainder of the report period to through continue with repair of the "A" Reactor Coolant Loop Cold Leg Isolation Valve.

March 31

. NARRATIVE

SUMMARY

OF

, MONTHLY OPERATING EXPERIENCE UNIT 1 MARCH 1997 (Continued)

In addition to the above, the following event which also occurred during the report period is being

reported as required by Technical Specifications.

March 1 The Automatic Rod Position Deviation Monitor, although still functional, was not through considered operable per Technical Specifications. The limiting condition for March 31 operation as specified in the Technical Specifications was met because the deviations

! between the indicated rod positions were verified to be within their 12 step limits by 4

obtaining analog / digital rod positions at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

t

AVERAGE DAILY UNIT POWER LEVEL 4

DOCKET NO. 50-334 UNIT BVPS Unit 1 DATE April 2,1997 COMPLETED BY David T. Jones TELEPHONE (412) 393-4962 MONTH March 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 818 17 826 2 823 18 826 3 829 19 826 4 826 20 0 5 825 21 0 6 827 22 0 7 829 23 0 8 825 24 0 9 828 25 0 l 10 827 26 0 11 831 27 0 12 831 28 0 13 830 29 0 14 824 30 0 15 830 31 0 l

16 830 j INSTRUCTIONS On this form, list the average daily unit power level MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

l OPERATING DATA REPORT DOCKET NO. 50-334 REPORT DATE: 04/03/97 COMPLETEL BY: DAVID T. JONES TELEPHONE: (412) 393-4962 OPFRATING STATUS

1. UNIT NAME: BEAVER VALLEY POWER STATION, UNIT 1

• Notes

• l

2. REPORTING PERIOD: MARCH 1997 * *

3. LICENSED THERMAL POK'ER (MWt). 2652 * *

4. NAMEPLATE RATING (Gross MWe)- 923 * *

5. DESIGN ELECTRICAL RATING (Net MWe) : 835 * * ,

6. MAX. DEPENDABLE CAPACITY (Gross MWe): 860 *

• I i 7. MAX. DEPENDABLE CAPACITY (Net MWe). 810 ********** * * *

• I 1

8. IF CHANGES OCCUR IN CAPACITY RATINGS SINCE LAST REPORT, GIVE REASONS:

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (Net MWe): None

10. REASONS FOR RESTRICTIONS, IF ANY: N/A 1 l

THIS MONTH YEAR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD: 744.0 2160.0 183360.0

12. NO. OF HRS. REACTOR WAS CRITICAL: 438.1 1854.1 122502.0

13. REACTOR RESERVE SF.UTDOWN HOURS: 0.0 0.0 4482.8

14. HOURS GENERATOR WAS ON LINE: 438.1 1854.1 120340.7

15. UNIT RESERVE SHUTDOWN HOURS: C.0 0.0 0.0

16. GROSS THERMAL ENERGY GEN. (MWH): 1153954.0 4855766.0 292129508.5

17. GROSS ELECT. ENERGY GEN. (MWH): 383153.0 1619643.0 94487235.0

18. NET ELECTRICAL ENERGY GEN. (MWH) : 357853.0 1527253.0 88388822.0

19. UNIT SERVICE FACTOR: (PERCENT) 58.9 85.8 67.4 1

20. UNIT AVAILABILITY FACTOR: (PERCENT) 58.9 85.8 67.4

21. UNIT CAPACITY FACTOR (MDC) : PCT 29.4 87.3 61.8

22. UNIT CAPACITY FACTOR (DER) : PCT 57.6 84.7 60.0

23. UNIT FORCED OUTAGE RATE: (PERCENT) 41.1 14.2 15.0

24. SHUTDOWNS SCHEDULED OVER NEXT SIX MONTHS (TYPE,DATE,AND DURATION OF EACH)'

THE UNIT'S 45 DAY 12TH REFUELING OUTAGE IS SCHEDULED TO BEGIN ON 9/S/97 THE UNIT IS CURRENTLY SHUTDOWN TO REPAIR THE "A" RCS COLD LEG _ ISOLATION VALVE.

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 4/10/97

26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

UNIT SHUIDOWNS AND POWER REDUCTIONS (220%) Docket No. 50-334  :

Unit Name BVPS Unit #1 ,

Date April 2,1997 Completed By David T. Jones - ,

REPORT MONT11 March 1997 Telephone (412)393-4 % 2 No. Date Typel Duration Reason 2 Method of Liansee System Component Cause & Corrective Action to Prevent .

(Hours) Shuning Event Report # Code 4 Code 5 Rocm.uu Down Reactor 3 I 970319 F 36.6 A 3 1-97-005 EA RELAYX . The Unit experienced a R,.cear Trip tran 100% output when the Main Unit Generator output breakers opened due to inadvettent operation of a bus backw timer relay in the 345 KV distribution system followmg a  ;

phase-to-ground fault on a 345 KV line in the .

Ohio Edison System. The inadvertent operation of the bus backup timer relay was  ;

due to incorrect wiring in the field and on the wiring diagram. Both have been modified and the relay has been proof tested i satisfactory.

j i

2 970320 F 145.8 A 9 N/A Cil IITEXCll Subsequent to the Reactor Trip, the Unit cooled down to cold shutdowri conditions to

• repair a secondary side leak at both the "A" and "C" Steam Generator hand hole flanges

• 3 970326 F 123.5 A 9 N/A CB VALVEX The Unit remamed in cold shutdown to repair r a body-to-bonnet flange joint leak on the "A" Reactor Coolant loop Cold leg Isol Valve. t 1 2 3 4 F-Forad Reason- Method. Exhibit F-Inseruction for Preparation of Data Esery S-Sduduled AF. . ^ Failure (Explain) 1-Manual Shries far Lacensee Event Report (IIR) File [

B-Maintenance or Test 2-Manual Screen (NURE00161).  ;

C-Refueling 3-Autosnatic Scrmen D-Regulatory Restrictice 4-Cosat froen Previous Month -

FA)perator Training & IJcause Exarn 3-Reduason 5 F-Ashisnistrative 94)ther Exhibit H-Sarne Source G-Operstional Enur (Explain)  !

Il4)ther(Explain)  !

f ,

NARRATIVE

SUMMARY

OF

.- .- MONTHLY OPERATING EXPERIENCE UNIT 2 l

MARCH 1997 i

! March 1 The Unit operated at a nominal value of100% output.

! through j March 18

. March 19 The Unit experienced a Reactor Trip from 100% output at 0607 hours0.00703 days <br />0.169 hours <br />0.001 weeks <br />2.309635e-4 months <br /> when the i Main Unit Generator output breakers opened due to inadvertent operation of a bus l backup timer relay in the 345 KV distribution system. Just prior to the event, a

}

phase-to-ground fault occurred on a 345 KV line in the Ohio Edison System. The fault was sensed by the Beaver Valley switchyard electrical protection circuitry that inadvertently operated causing a Main Unit Generator / Turbine Trip and subsequent i

Reactor Trip. The Unit was subsequently stabilized in Mode 3. A plant cooldown to l Mode 5 was commenced at 1256 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.77908e-4 months <br /> to investigate the cause for low Auxiliary l Feedwater System flow to the "B" Steam Generator observed following the Reactor i Trip. Mode 4 was entered at 1731 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.586455e-4 months <br /> as the plar*. cooldown continued.

I 1 March 20 Mode 5 was entered at 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> to enable investigation of the cause for the low-Auxiliary Feedwater (AFW) System flow to the "B" Steam Generator. The

. investigation determined that the seat to the "B" AFW to Steam Generator nozzle

check valve had dislodged, thereby minimizing the amount of AFW System flow to I. the "B" Steam Generator, l March 21 The Unit remained in Mode 5 to repair / modify the "B" AFW to Steam Generator j through nozzle check valve. Similar modifications to the "A" and "C" AFW to Steam March 27 Generator nozzle check valves were also performed during this time period.

} March 28 Following satisfactory completion of repairs / modifications and testirg of the "A",

f "B" and "C" APW to Steam Generat' or nozzle check valves, the Unit began to heat up and entered Mode 4 at 2004 hours0.0232 days <br />0.557 hours <br />0.00331 weeks <br />7.62522e-4 months <br />.

I March 20 Mode 3 was entered at 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br />.

March 30 The Unit entered Mode 2 at 1215 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.623075e-4 months <br />. The Reactor was taken critical at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />. Mode I was entered at 1616 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.14888e-4 months <br />. The Main Unit Generator was synchronized to the electrical grid at 2236 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.50798e-4 months <br />, and output was escalated towards full power.

NARRATIVE

SUMMARY

OF MONTHLY OPERATING EXPERIENCE l

UNIT 2 '

i MARCH 1997 l

(Continued) l March 31 At 0601 hours0.00696 days <br />0.167 hours <br />9.937169e-4 weeks <br />2.286805e-4 months <br /> with the Unit at approximately 37% output, the "B" Heater Drain Pump was shutdown due to elevated bearing temperatures. At 1028 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91154e-4 months <br />, the Unit I resumed power escalation to 45% output while evaluation of the "B" Heater Drain ,

Pump bearing temperatures continued. The Unit achieved an output of j approximately 45% at 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br />. Upon satisfactory evaluation of the "B" Heater '

Drain Pump bearing temperatures, the Unit resumed power escalation at 1831 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.966955e-4 months <br />.

At 2024 hours0.0234 days <br />0.562 hours <br />0.00335 weeks <br />7.70132e-4 months <br />, power escalation was halted at approximately 59% output. The Unit remained at approximately 59% output for the remainder of the report period to complete repair of the mechanical seal on the "A" Main Feedwater Pump.

4 l

l l

l l

l l

l

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-412 UNIT BVPS Unit 2 DATE April 3,1997 COMPLETED BY David T. Jones TELEPHONE (412) 393-4962 MONTH March 1997 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 832 17 835 2 839 18 837 3 843 19 839 4 839 20 0 5 838 21 0 6 845 22 0 7 845 23 0 8 842 24 0 9 843 25 0 i

10 842 26 0 11 840 27 0 12 839 28 0 13 839 29 0 14 836 30 34 15 841 31 281 16 838 I

INSTRUCTIONS i l

On this form, list the average daily unit power level MWe-Net for each day in the reporting month. !

Compute to the nearest whole megawatt.

l l

. ,. OPERATING DATA REPORT DOCKET NO.- 50-412 REPORT DATE: 04/03/97 COMPLETED BY: DAVID T. JONES TELEPHONE: (412) 393-4962 OPERATING STATUS

1. UNIT NAME: BEAVER VALLEY POWER STATION, UNIT 2

• Notes *

2. REPORTING PERIOD: MARCH 1997 * *

3. LICENSED THERMAL POWER (!fNt) : 2652 * *

4. NAMEPLATE RATI!!G (Gross MWe)r 923 * *

5. DESIGN ELECTRICAL RATING (Net MWe); 836 * *

6. MAX. DEPENDABLE CAPACITY (Gross MWe). 870 * *

7. MAX. DEPENDABLE CAPACITY (Net MWe)- 820 ********* * * * * *

8. IF CHANGES % CUR IN CAPACITY RATINGS SINCE LAST REPORT, GIVE REASONS:

9. POWER LEVEb TO WHICH RESTRICTED, IF ANY (Net MWe): None

10. REASONS FGR RESTRICTIONS, IF ANY: N/A THIS MONTH YEAR TO DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD: 744.0 2160.0 82143.0

12. NO. OF HRS. REACTOR WAS CRITICAL: 472.0 1682.7 69403.7

13. REACTOR RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0

14. HOURS GENERATOR WAS ON LINE: 463.5 1656.3 68921.0

15. UNIT RESERVE SHUTDOWN HOURS: 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GEN. (MWH) : 1186074.0 4192035.0 171403878.0

17. GROSS ELECT, ENERGY GEN. (MWH). 394465.0 1394591.0 55891014.0

18. NET ELECTRICAL ENERGY GEN. (MHH) : 369684.0 1312451.0 52801047.0

19. UFsr SERVICE FACTOR: (PERCENT) 62.3 76.7 83.9

20. UNIT AVAILABILITY FACTOR: (PERCENT) 62.3 76.7 83.9

21. UNIT CAPACITY FACTOR (MDC) : PCT 60.6 74.1 78.0

22. UNIT CAPACI77 FACTOR (DER) : PCT 59.4 72.7 76.9

23. UNIT FORCED OUTAGE RATE: (PERCENT) 37.7 23.3 5.0

24. SHUTDOWNS SCHEDULED OVER NEXT SIX MONTHS (TYPE,DATE,AND DURATION OF EACH):

25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION) :

FORECAST ACHIEVED INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A

9 UNIT SHl.TIDOWNS AND POWER REDUCTIONS (220%) Docket No. __50-412 .

Unit Name BVPS Unit #2 Date April 2,1997 REPORT MONTH Completed By _ David T. Jones -

March 1997 Telephone _ (412) 393-4%2 No. Date Typel Duration Reamn2 Method of Licensec System Component (llours) Shutting Event Report # Cause & Corrective Action to Prevent Code 4 Code 5 Down Recurrence

- Reactor 3 5 970319 F j 6.8 A 3 1-97-005 EA RELAYX The Unit experienced a Reactor Trip from 100% output when the Main Unit Generator output breakers opened due to inadvertent operation of a bus backup timer relay in the 345 KV distribution system following a phase-to-ground fault on a 345 KV line in the Ohio Edison System. The inadvertent operation of the bus backup timer relay was due to incorrect wiring in the field and on the wiring diagram. Both have been modified and the relay has been proof 6 tested satisfactery.

970319 F 237.2 A 9 N/A 'WG VALVEX Subsequent to the Reactor Trip, the IJnit cooled down to cold shutdown conditions to repair / modify the Auxiliary Feedwater 7 970330 F to Steam Generator nozzle check vahts.

36.5 H 9 N/A ZZ 777777 The Unit remained shutdown to complete preparations for startup.

I 2

F-Fwced Reason: 3 S&heduled .

Method- 4 A-Equiprnmt Failure (Explain)

B-Maintenarum or Test 1-Manual Exhibit F-Intions for thparatmn ofData Entry C-Refuelmg 2-Manual Saarn Sheets for imensee Evern Report (tIR) File D-Regulatay Resencton 3-Autornatic Saam (NUREG0161).

E-operator Trammg & tiense Exam 4 Ocws4 frorn Previous Month F-Aammstrative 5-Reduction 9-Other 5 l Goperathnal Errw(Explam)

II4)ther(Explain) Exhibit Il-Same Source

~

UNIT SHlIIDOWNS AND POWER REDUCI'lONS (220%) Docket No. 50-412 i Unit Name BVPS Unit #2 .

1' Date April 2,1997 ,

Completed By David T. Jones '

REPORT MONTH March 1997 Telephone (412)393-4 % 2 No. Date Typel Duraten Reason 2 Method of Licensee Sysem Component Cause & Corrective Achon to Prevent (Hours) Shutting Event Report # Code 4 Code 5 Recurrena i Down Reactor 3 8 970331 F 0 H 9 N/A HH PUMPXX The Unit halted escalation to full power  !

at approximately 45% output to evaluate i elented bearing temperatures on the "B"  ;

Heater Drain Pump. The temperatures were subsequently evaluated as acceptable.

9 970331 F 0 H 9 N/A CH PUMPXX The Unit halted escalation to full power at approximately 59% output to repair i the mechamcal seal on the "A" Min Feedwater Pump.

[

i I 2 3 4 ,

F-Forced Researc Methat: Exhant F-Instruchons for Preparahan of Data Faery  !

S.Sduduled A-Equipenent Failure (Explem) 1-Manual Sheets for tuensee Event Report (LER) File B-Maissenance er Test 2-Manual Scraen (NUREG01611 C-Refueling 3-Automaine Saaru ,

i D Regulatory Resenction 44'ern'd. freen Pwwous Morah E Operstar Training & License Exam 5-Reduction 5 ,

F-Adeninistrative 94%er Exhiint II-Same Source i Goperational Enor (Explain) i llother(Explain) i 6

i I

L UNIT SHUTDOWNS AND POWER REDUC 1' IONS (220%) Docket No. 50-412 . I Unit Name BVPS Unit #2 Date April 2,1997 Completed By David T. Jones .

REPORT MONTH March 1997 Telephone (412) 393-4962 No. Date Typel Duration Reason 2 Method of Licensee System Component Cause & Corrective Action to Prevent (Hours) Shutting Event Report # Code 4 Code 5 Recum.cc Down '

- Reactor 3 t

5 970319 F 6.8 A 3 1-97-005 EA RELAYX 'llic Unit experienced a Reactor Trip from 100% output when the Main Unit Generator output breakers opened due to inadvertent operation of a bus backup '

timer relay in the 345 KV distribution system following a phase-to-ground fault on a 345 KV line in the Ohio Edison System. The inadvertent operation of the i bus backup timer relay was due to '

incorrect wiring in the field and on the wiring diagram. Both have been ,

modified and the relay has been proof l i

tested satisfactory.

6 970319 F 237.2 A 9 N/A WG VALVEX Subsequent to the Reactor Trip, the Unit cooled down to cold shutdown conditions to repair / modify the Auxiliary Feedwater to Steam Generator nozzle check valves. ,

7 970330 F 36.5 H 9 N/A ZZ mm The Unit remained shutdown to complete preparations for startup. l 1 2 3 4 F-Forced Reason: . Method- Exhibit F-Indruanens for Preparation of Data Entry S-Sdieduled A-Equipment Failure (Emplain) 1-Manuel Sheets fer Immamee Evers Report (LER) File B-4taintenana or Test 2-Manual Screen (NUREG0161). i C-Refueling 3-Automatic Saarn  ;

D-Regulatory Restrictuwe 4 Cat'd from Previous Month ,

E44=rator Training & tianse Exam 5-Redtution 5  !

F-Admirustrative 9-Other Exhibit II-Same source I

G44eratamal Error (Euplain)

Il4Rher(Explain) ,

9

~

' Docket No. 50-412 i UNIT SHUTDOWNS AND POWER REDUCTIONS (220%) .

Unit Name BVPS Unit #2 Date April 2,1997 . i Completed By David T. Jones

• REPORT MONTH March 1997 Telephone (412)393-4 % 2

• i i

No. Date Typel Durauon Reason 2 Method of lacensee System Component Cause & Corrective Acton to Prevent ,

(Hours) Shutting Event Report # Code 4 Code 5 Recunence i Down  :

Reactor 3 8 970331 F 0 H 9 N/A HH PUMPXX The Unit halted escalation to full power j at approximately 45% output to evaluate  !

elevated bearing to..w..iores on the "B" .

Heater Drain Pump. The temperatures were subsequently evaluated as maptable.

9 970331 F 0 H 9 N/A CH PUMPXX The Unit halted escalation to full power at approximately 59% output to repair the mechanical seal on the "A" Main Feedwater Pump.  ;

i I

1 2 3 4 F-Forced Reason: Method. Exhibit F-Instructens for Preparassen of Dean Enary S-Sdwikaled A-F+ipment Failure (Explain) 1-Manual Sheses for Lacensee Ewnt Repet (ER) File B-Maineenanz or Test 2-Masusal Sanni (NURE00161) i C-Refuehng 3-Automatic Saarn D-Regulescry Resenction 4-Cont 1 freen Freneus Month E-Operator Training A ticense Exam 5-Reduction 5 F-Adminnierative 9-Other Exhibit H-Same Sourm G4hwational Error (Explain)

Il4hhrt(Explain)

_ _ _ _- i._ ___ _ _ _ _ _ _ _ _ __