ML18102B691
| ML18102B691 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 01/31/1997 |
| From: | COLEY W E, EUBANK T, POWERS R P PACIFIC GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| DCL-97-020, DCL-97-20, NUDOCS 9702250104 | |
| Download: ML18102B691 (13) | |
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- Gas and Electric Company February 18, 1997 PG&E Letter DCL-97-020 Diablo Canyon Power Plant P.O. Box 56 Avila Beach, CA 93424 805/545-6000 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C. 20555 Docket No. 50-275, DPR-80 Docket No. 50-323, DPR-82 Diablo Canyon Units 1 and 2 Monthly Operating Report for January 1997 Dear Commissioners and Staff: Robert P. Powers Vice President-Diablo Canyon Operations and Plant Manager are the monthly operating report forms for Diablo Canyon Power Plant, Units 1 and 2, for January 1997. This report is submitted in accordance with Section 6.9.1.7 of the Units 1and2 Technical Specifications.
Sincerely, Robert P. Powers Enclosure WEC/1713 250073 -----------9702250104 970131 PDR ADOCK 05000275 R PDR
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- 18, 1997 * *Page 2 cc: Mr. Steven D. Bloom U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 13 E16 Washington, DC 20555 Mr. James E. Dyer, Acting Regional Administrator U.S. Nuclear Regulatory Commission, Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 Ms. Liz Hannon, President Utility Data Institute, Inc. 1700 K Street, NW, Suite 400 Washington, DC 20006 Mr. Kurt Larson American Nuclear Insurers Towne Center, Suite 300 South 29 South Main Street W. Hartford, Connecticut 06107-2430 Mr. Kenneth E. Perkins U.S. Nuclear Regulatory Commission, Region IV, Branch Office 1450 Maria Lane Walnut Creek, CA 94596-5268 INPO Record Center 700 Galleria Parkway Atlanta, GA 30339-5957
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Control Des.
18, 1997 :Page 3 bee: R. D. Glynn G. M. Rueger NRC Resident 77/832 77/814A 104/5/538
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- I' .. ,,. * .. MONTHLY NARRATIVE REPORT OF OPERATION AND MAJOR MAINTENANCE EXPERIENCE The monthly report describes the operating and major maintenance experience for Diablo Canyon Power Plant for the month of January 1997. This narrative report was prepared and submitted in accordance with Section 6.9.1.7 of the Units 1and2 Technical Specifications.
Narrative of Daily Significant Plant Events January 1, 1997: January 3, 1997: January 10, 1997: January 12, 1997: January 31, 1997: Units 1 and 2 started the month in Mode 1 (Power Operation) at 1 00 percent power. An Unusual Event (UE) was declared at 1115 PST, due to a mudslide on the public access road just outside the main gate. The mudslide blocked normal access to and from the plant. The alternate access to and from the plant was verified available through the dirt road north of the site. The UE was terminated at 1430 PST after county work crews had sufficiently removed the mudslide to allow access to and from the plant through the normal route. At approximately 1800 PST, a 24-hour nonemergency report was made to the NRC in accordance with Section 4.1 of the Environmental Protection Plan. At approximately 1000 PST, biologists had observed a green seaturtle between the seawall and the 1-2 bar rack at the seawater Intake Structure.
The turtle was removed by divers, examined by biologists, and released 1/4 mile outside the intake cove. Units 1 and 2 reduced power to 80 percent for modification to the discharge piping on two Unit 1 and one Unit 2 main steam safety valves (MSSVs). (For details, see Summary of Significant Safety-Related Maintenance.)
Units 1 and 2 were returned to 1 00 percent power. At 1220 PST, a 1-hour, nonemergency report was made to the NRC in accordance with 10 CFR 50.72(b)(1)(ii)(B).
PG&E determined that subsequent to a loss-of-coolant accident, an outside design basis condition could occur when separating cooling water trains in accordance with Emergency Operating Procedure (EOP) E-1.4, "Transfer to Hot Leg Recirculation," concurrent with loss of electrical power to a vital bus. As a conservative measure during the evaluation of this issue, EOP E-1.4 was revised to no longer require immediate train separation after the transfer to hot leg recirculation.
The
- . . * ... ' . r: * . . January 31, 1997: decision to separate was transferred to the Technical Support Center, where it will be decided after an evaluation of plant conditions.
This action precludes the postulated event from occurring.
Licensee Event Report 1-97-001 will be submitted by March 3, 1997, to provide additional information on this condition.
Units 1 and 2 ended the month in Mode 1 at 100 percent power. Summary of Plant Operating Characteristics.
Power Reductions.
and Unit Shutdowns Unit 1 operated this month with a unit availability factor of 100 percent and a unit capacity factor (using MDC Net) of 100.43 percent. Unit 1 reduced power once this month to 80 percent for modification to the discharge piping of two MSSVs. Unit 2 operated this month with a unit availability factor of 100 percent and a unit capacity factor (using MDC Net) of 100.64 percent. Unit 2 reduced power once this month to 80 percent for modification to the discharge piping of a MSSV. Summary of Significant Safety-Related Maintenance Units 1 and 2: Modifications were made to the discharge piping on two Unit 1 and one Unit 2 MSSVs. Material was removed from the drip pans, welded to the outside diameter of the discharge piping, to provide clearance between the drip pans and the vent stacks. The added clearances prevent excessive load transfer from the discharge stack to the safety valve discharge piping and ultimately to the safety valve during differential movement as a result of seismic events, thermal changes, and jet reaction during valve actuation.
Excessive loading of the safety valve discharge piping results in valve body distortion and could have an adverse impact on valve performance.
Actuation of Steam Generator Safety or Pressurizer Power Operated Relief Valves There were no challenges to the steam generator safety or pressurizer power operated relief valves.
, . 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18. 19. 20. 21. 22. 23. 24. 25. '.
- OPERATING DATA REPORT OPERATING STATUS Unit Name: Reporting Period: Licensed Thermal Power (MWt): Nameplate Rating (Gross MWe): Design Electrical Rating (Net MWe): Maximum Dependable Capacity (Gross MWe): Maximum Dependable Capacity (Net MWe): If Changes Occur In Capacity Ratings (Items 3 Through 7) Since Last Report, Give Reasons: Power Level To Which Restricted, If Any (Net MWe): Reasons For Restrictions, If Any: Hours In Reporting Period: Number Of Hours Reactor Was Critical:
Reactor Reserve Shutdown Hours: Hours Generator On-Line: Unit Reserve Shutdown Hours: Gross Thermal Energy Generated (MWH): Gross Electrical Energy Generated (MWH): Net Electrical Energy Generated (MWH): Unit Service Factor: Unit Availability Factor: Unit Capacity Factor (Using MDC Net): Unit Capacity Factor (Using DER Net): Unit Forced Outage Rate: Shutdowns Scheduled Over Next 6 Months DOCKET NO.: UNIT: DATE: 50-275 1 02/18/97 COMPLETED BY: T. Eubank/W.
E. Coley (805) 545-4867/4741 TELEPHONE:
Diablo Canyon Power Plant Unit 1 January 1997 3338 1137 1086 1124 1073.4 N/A N/A N/A This Month YTD Cumulative 744.0 744.0 102910.3 744.0 744.0 87642.3 0.0 0.0 0.0 744.0 744.0 86572.9 0.0 0.0 0.0 2391047 2391047 275811828 840700 840700 92936032 802031 802031 88222288 100.00 100.00 84.12 100.00 100.00 84.12 100.43 100.43 79.87 99.26 99.26 78.94 0.00 0.00 3.64 (Type, Date, & Duration of Each): Eighth refueling outage (1 RB), April 19, 1997, scheduled 36 days. If Shut Down At End Of Report Period, Estimate Date of Startup: N/A l (. .. . .. -,. , . . ,,. January 1997
- AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:
50-275 1 02/18/97 T. Eubank/W.
E. Coley (805) 545-4867/4741 DAY AVERAGE DAILY POWER LEVEL 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 (MWe-Net) 1081 1085 1081 1082 1086 1082 1081 1085 1081 1086 1086 919 1081 1080 1081 1085 1086 1086 1081 1086 1081 1087 1081 1082 1086 1086 1082 1081 1086 1081 1086 The average monthly electrical power level for January 1997 = 1078.00 MWe-Net UNIT SHUTDOWNS AND POWER REDUCTIONS 1 01/12/97 s N/A 1 Type: F-Forced S-Scheduled 2 Reason: A-Equipment Failure (Explain)
B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
H REPORT MONTH: January 1997 5 N/A 3 4 DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:
SB RV 5 50-275 1 02/18/97 W. E. Coley (805) 545-47 41 Reduced power to modify discharge piping for two MSSVs. See Summary of Significant Related Maintenance for description of A action taken.
- Method: EllS Systems List, Table 1 IEEE Std. 803A-1983, "IEEE Recommended Practice for Unique Identification in Power Plants and Related Facilities
-Table 2" 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from previous month 5-Power reduction 6-0ther
. ..-... ' . .. _, 1. 2. 3. 4. 5. 6. 7. 8. 9. 10. 11. 12. 13. 14. 15. 16. 17. 18. 19. 20. 21. 22. 23. 24. 25.
- OPERATING DATA REPORT OPERATING STATUS Unit Name: Reporting Period: Licensed Thermal Power (MWt): Nameplate Rating (Gross MWe): Design Electrical Rating (Net MWe): Maximum Dependable Capacity (Gross MWe): Maximum Dependable Capacity (Net MWe ): If Changes Occur In Capacity Ratings (Items 3 Through 7) Since Last Report, Give Reasons: DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:
50-323 2 02/18/97 T. Eubank/W.
E. Coley (805) 545-4867/4741 Diablo Canyon Power Plant Unit 2 January 1997 3411 1164 1119 1137 1087 N/A Power Level To Which Restricted, If Any (Net MWe): N/A Reasons For Restrictions, If Any: . N/A This Month YTD Cumulative Hours In Reporting Period: 744.0 744.0 95469.0 Number Of Hours Reactor Was Critical:
744.0 744.0 82606.7 Reactor Reserve Shutdown Hours: 0.0 0.0 0.0 Hours Generator On-Line: 744.0 744.0 81406.3 Unit Reserve Shutdown Hours: 0.0 0.0 0.0 Gross Thermal Eriergy Generated (MWH): 2531071 2531071 268055603 Gross Electrical Energy Generated (MWH): 850610 850610 89226442 Net Electrical Energy Generated (MWH): 813866 813866 84885675 Unit Service Factor: 100.00 100.00 85.27 Unit Availability Factor: 100.00 100.00 85.27 Unit Capacity Factor (Using MDC Net): 100.64 100.64 81.90 Unit Capacity Factor (Using DER Net): 97.76 97.76 79.46 Unit Forced Outage Rate: 0.00 0.00 4.00 Shutdowns Scheduled Over Next 6 Months (Type, Date, And Duration Of Each): N/A If Shut Down At End Of Report Period, Estimate Date of Startup: N/A
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- I. t{ January 1997
- DAY 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:
50-323 2 02/18/97 T. Eubank/W.
E. Coley (805) 545-4867 /4997 AVERAGE DAILY POWER LEVEL (MWe-Net) 1097 1096 1098 1097 1099 1098 1094 1101 1098 1098 1099 1014 1086 1087 1097 1096 1098 1098 1096 1099 1097 1098 1096 1098 1096 1097 1096 1096 1097 1096 1096 The average monthly electrical power level for January 1997 = 1093.91 MWe-Net UNIT SHUTDOWNS AND POWER REDUCTIONS 1 01/12/97 s N/A 1 Type: F-Forced S-Scheduled 2 Reason: A-Equipment Failure (Explain) 8-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
H-Other (Explain)
H REPORT MONTH: January 1997 5 N/A 3 4 DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:
SB RV 5 50-323 2 02/18/97 W. E. Coley (805) 545-4741 :*:*:*:*:*:*:*:***:*:*:*:*:*.;:::::::::::::::::::::::::::;:;:;::::::
Reduced power to modify discharge piping for one MSSV. See Summary of Significant Related Maintenance for description of ace taken. Method: EllS Systems List, Table 1 IEEE Std. 803A-1983, "IEEE Recommended Practice for Unique Identification in Power Plants and Related Facilities
-Table 2" 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from previous month 5-Power reduction 6-0ther
* REFUELING INFORMATION REQUEST DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:
- 1. Name of facility:
Diablo Canyon Power Plant Unit 1 2. Scheduled date for next refueling shutdown:
April 19, 1997 3. Scheduled date for restart following refueling:
May 24, 1997 50-275 1 02/18/97 D. Farrer/W.
E. Coley (805) 545-4438/4741
- 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 Staff Review Committee (PSRC) 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 review should occur in April or May of 1997 before reloading the core. 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 January 31, 1997, the number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool were: (a) 193 (b) 548 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).
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- REFUELING INFORMATION REQUEST DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:
- 1. Name of facility:
Diablo Canyon Power Plant Unit 2 2. Scheduled date for next refueling shutdown:
February 7, 1998 3. Scheduled date for restart following refueling:
March 14, 1998 50-323 2 02/18/97 D. Farrer/W.
E. Coley (805) 545-4438/4741
- 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 Staff Review Committee (PSRC) 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 review should occur in January or February of 1998 before reloading the core. 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 January 31, 1997, the number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool were: (a) 193 (b) 580 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 he present licensed capacity:
2006 (loss of full core offload capability).
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