ML20045D173

From kanterella
Revision as of 21:10, 11 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Monthly Operating Repts for May 1993 for Diablo Canyon,Units 1 & 2
ML20045D173
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 05/31/1993
From: Bourgo E
PACIFIC GAS & ELECTRIC CO.
To:
Shared Package
ML20045D093 List:
References
NUDOCS 9306280055
Download: ML20045D173 (12)
v • d • e


Text

.

MONTHLY NARRATIVE REPORT ,

OF OPERATION AND MAJOR MAINTENANCE EXPERIENCE This repon describes the operating and major maintenece experience for the month of May 1993. This narrative report was prepared by the Plant Staff and is submitted in accordance with Section 6.9.1.7 of the Units 1 and 2 Technical Specifications.

Narrative of Daily Signi6 cant Plant Events On May 1,1993: Unit I started the month in Mode 1 (Power Operation) at 100%

power, and Unit 2 started the month in Mode 2 (Stanup) following the fifth refueling outage.

Unit 2 entered Mode 1 (Power Operation) and paralleled to the grid.

On May 10,1993: Unit 2 increased power to 100%. I On May 31,1993: Unit I and Unit 2 ended the month in Mode 1 (Power Operation) at 100% power.

Summarv of Plant Operating CJjaracteristics. Power Reductions and Unit Shutdowns Unit 1 operated this month with a unit availability factor of 100.0% and a unit capacity factor (using MDC Net) of 100.0%. Unit I did not reduce power by more than 20% this month.

Unit 2 operated this month with a unit availability factor of 97.7% and a unit capacity factor i (using MDC Net) of 87.0%. Unit 2 did not reduce power by more than 20% this month.

Summary of Signi6 cant Safety Related Maintenance  ;

i No significant safety related maintenance activities took place this month.

]

l Actuations of Steam Genemtor Safety or Pressurizer Power Operated Relief Valves i There were no challenges to the steam generator safety valves or the pressurizer power operated relief valves.

i 9306280055 930615 PDR ADOCK 05000275 R PDR

Report of Breakwater Survey Inspections Required by Technical Specifications 4.7.13.1 The breakwaters were inspected during the months of November to April in accordance with Technical Specifications 4.7.13.1 and 4.7.13.2. Results from this year's survey were verified against the survey performed in 1984. Changes in the positions of the breakwater survey monuments are given below:

Easting coordinates = .06 feet Northing coordinates = .06 feet Elevation = +.2 feet These differences are so small as to be considered negligible and indicative that'no appreciable breakwater displacement or settlement has occurred. Breakwater survey results and pictures taken during the survey are provide in Enclosures 1 and 2.

OPERATING DATA REPORT DOCKET NO. 50-275 UNIT 1 DATE 06/01/93 COMPLETED BY E. Bourgo TELEPHONE (805) 545-3035 OPERATING STATUS

1. Unit Name: Diablo Canyon Unit 1
2. Reporting Period: May 1993
3. Licensed Thermal Power (MWt): 3338
4. Nameplate Rating (Gmss MWe): 1137
5. Design Electrical Rating (Net Mwe): 1086
6. Maximum Dependable Capacity (Gross Mwe): 1124
7. Maximum Dependable Capacity (Net MWe): 1073.4
8. If changes occur in capacity ratings (items 3 through 7) since last repon, give reasons: N/A
9. Power level to which restricted, if any (Net MWe): N/A
10. Reasons for restrictions, if any: N/A This Month YTD Cumulative i1. Hours In Reponing Period 744.0 3623.0 70725.3
12. Number Of Hours Reactor Was Critical 744.0 3623.0 59235.1
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 744.0 3623.0 58335.6
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 2481334 11771314 183512616
17. Gross Electrical Energy Generated (MWH) 837900 3966800 61757832
18. Net Electrical Energy Generated (MWH) 798921 3779379 58567927
19. Unit Service Factor 100.00 100.00 82.48
20. Unit Availability Factor 100.00 100.00 82.48
21. Unit Capacity Factor (Using MDC Net) 100.04 97.18 77.15
22. Unit Capacity Factor (Using DER Net) 98.88 96.06 76.25
23. Unit Forced Outage Rate 0.00 0.00 3.27
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): None.
25. If Shut Down At End Of Repon Period, Estimate Date of Stanup: Not applicable

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-275 UNIT 1 DATE 06/01/93 COMPLETED BY E. Bourgo TELEPHONE. (805) 545-3035 May 1993 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

I 1071 2 1076 3 1076 4 1075 5 1076 6 1076 7 -1076 8 1078 9 1077

-10 1077 11 1073 12 1077 13 1073 14 1077 15 1077 16 -1077 17 1061 18= 1073 19 1077 20 1073 21 1072 22 1073 23 1077 24 1073' 25- 1077.

26 1069 27 1%8 -

-28 1072 29 1069 30 1073 31 1069 The average monthly Electrical Power Level for May 1993 = 1073.8 MWe-Net

i l

l UNIT SHUTDOWNS AND POWER REDUCTIONS l .

l DOCKET NO. 50-275 UMT 1 i

DATE 06/01/93 COMPLETED BY P.G. DAHAN TELEPHONE (805) 545-4054 REPORT MONTH: May 1993 LICENSEE CAUSE & CORRECTIVE .

NO. DATE TYPE' DURATION REASON 2 METHOD OF EVENT SYSTEM COMPONENT ACI' ION TO PREVENT (HOURS) SHUTDOWN' REPORT CODE' CODES RECURRENCE None 1 2 3 4 Type: Reason: Method: Ells Systems List, Table 1 F-Forced A-Equipment Failure (Explain) 1-Manual S-Scheduled B-Maintenance or Test 2-Manual Scram 5 C-Refueling 3-Automatic Scram IEEE Std. 803A-1983, "IEEE D-Regulatory Restriction 4-Continuation from Recommended Practice for Unique E-Operator Training & License Examination previous month Identification in Power Plants and F-Administrative 5-Power reduction . Related Facilities - Table 2" G-Operational Error (Explain) 6-Other H-Other (Explain) 4

i OPERATING DATA REPORT DOCKET NO. 50-323 UNIT 2 DATE 06/01/93 COMPLETED BY E. Bourgo TELEPHONE (805) 545-3035 OPERATING STATUS

1. Unit Name: Diablo Canyon Unit 2
2. Reponing Period: May 1993
3. Licensed Thermal Power (MWt): 3411
4. Nameplate Rating (Gross MWe): 1164
5. Design Electrical Rating (Net MWe): 1i19
6. Maximum Dependable Capacity (Gross MWe): 1137
7. Maximum Dependable Capacity (Net MWe): 1087
8. If changes occur in capacity ratings (items 3 through 7) since last report, give reasons: N/A
9. Power level to which restricted, if any (Net MWe): N/A
10. Reasons for restrictions, if any: N/A This Month YTD Cumulative
11. Hours In Reponing Period 744.0 3623.0 63284.0
12. Number Of Hours Reactor Was Critical 744.0 2247.8 53082.8
13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
14. Hours Generator On-Line 726.6 2189.2 52194.5
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thennal Energy Generated (MWH) 2210729 7099590 170401411
17. Gross Electrical Energy Generated (MWH) 739700 2368900 56714299
18. Net Electrical Energy Generated (MWH) 703409 2244365 53877966
19. Unit Service Factor 97.66 60.42 82.48
20. Unit Availability Factor 97.66 60.42 82.48
21. Unit Capacity Factor (Using MDC Net) 86.98 56.99 78.45
22. Unit Capacity Factor (Using DER Net) 84.49 55.36 76.09
23. Unit Forced Outage Rate 0.00 3.27 4.28
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): None.
25. If Shut Down At End Of Report Period, Estimate Date of Startup: Not applicable.

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-323 UNIT 2 DATE 06/01/93 COMPLETED BY E. Bourgo TELEPHONE (805) 545-3035 May 1993 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 -10 2 171 3 224 4 308 5 486 6 773 7 1010 8 1013 9 1080 10 1100 11 1104 12 1108 13 1105 14 1104 15 1108 16 1109 17 1104 18 1105 19 1105 20 1105 21 1101 22 1105 23 1101 24 1105 25 1097 26 1097 27 1101 28 1096 l 29 1101 30 1093 31 1101 I

The average monthly Electrica' Power Ixvel for May 1993 = 945.4 MWe-Net l

l i

UNIT SHUTDOWNS AND POWER REDUCTIONS i DOCKET NO. 50-323 , -:

UNIT 2 DATE 06/01/93 COMPLETED BY P.G.DAHAN 1

TFI.FPHONE (805) 545-4054 REPORT MONTH- May 1993

, LICENSEE CAUSE &

NO. - DATE . TYPE' DURATION ' REASON 2 METHOD OF EVENT' -SYSTEM- COMPONENT CORRECTIVE

) (HOURS) _ SHUTDOWN' REPORT CODE' CODES ACTION TO PREVENT '

. RECURRENCE 4

.I 930501 S 17.4 C 4 None AB RCT Unit 2 was continuing the fifth refueling outage.

4 1 2 3 4 i Type: Reason: Method: Ells Systems List, Table 1 F-Forced A-Equipment Failure (Explain) 1-Manual S-Scheduled B-Maintenance or Test 2-Manual Scram 5 C-Refueling 3-Automatic Scram IEEE Std. 803A-1983, "IEEE

D-Regulatory Restriction 4-Continuation from Recommended Practice for Unique

! E-Operator Training & License Examination previous month Identification in Power Plants and i- F- Administrative 5-Power reduction- Related Facilities - Table 2" G-Operational Error (Explain) 6-Other i H-Other (Explain) .

i k

__m..z__ . _ .._.m..._

...-____2___m_ _ _ _ _ _ . _ . . _ . . _ _ _ _ . _ _ ____m._________ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _-- - _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _, -

se ._. _ ___ _ ______

i REFUELING INFORMATION REQUEST DOCKET NO. 50-275 UNIT 1 l DATE 06/01/93 l COMPLETED BY M. L. Mayer TELEPHONE (805) 545-4674 1

1. Name of facility: Diablo Canyon Unit 1 l
2. Scheduled date for next refueling shutdown: March 5,1994 (estimated).
3. Scheduled date for restart following refueling: May 2,1994 (estimated).

l 4. Will refueling or resumption of operation thereafter require a technical specification

! change or other license amendment? If answer is yes, what, in general, will there be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)7 If no such review has taken place, when is it scheduled?

No. The PSRC is scheduled to review the cycle 7 core reload on April 4,1994 (estimated).

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

N/A

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: N/A
7. As of May 31,1993, the number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool were:

(a) 193 (b) 376

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

Present 1324 Increase size by 0

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2006 (Loss of full core offload capability)

f 1

REFUELING INFORMATION REQUEST DOCKET NO. 50-323 I

UNIT 2 DATE 06/01/93 COMPLETED BY M. L. Mayer TELEPHONE (805) 545-4674

1. Name of facility: Diablo Canyon Unit 2
2. Scheduled date for next refueling shutdown: September 15,1994 (estimated).

4

3. Scheduled date for restart following refueling: November 6,1994 (estimated).
4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? If answer is yes, what, in general, will there be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)? If no such review has taken place, when is it scheduled?

No. The PSRC reviewed and approved the cycle 6 core reload on March 10, 1993.

5. Scheduled date(s) for submitting proposed licensing action and supporting information:  ;

1 N/A

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: NA
7. As of May 31,1993, the number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool were: 1 (a) 193 (b) 396
8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

Present 1324 Increase size by 0

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2006 (Loss of full core offload capability)

Breakwater Survey r

The periodic intake structure breakwater survey is included as an attachment to this mo'nthly- ,

report. There was no significant chanFe in the position of the breakwater.

i

'i l

l l

)

I 1

i 4

l-  ;

1 i 1

-i

'l i )

-l

, s n -- a a a m J ;oae u -.

h b l

  • 1 4

t l

1 I

i t

4 J

f 1

1 1

1 e

l

(

i t

4 t

a 4

1 I

1 l

Enclosure 1 e

d h

l 4

1 i

Retrieved from "https://kanterella.com/w/index.php?title=ML20045D173&oldid=2556350"