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{{#Wiki_filter:*.4: """ Edison e-m PILGRIM NUCLEAR POWER STATION RFD # 1 rocky HILL HOAD PLYMOUTH. mas 3ACHUsETrs 02360 July 12, 1979 BECo Ltr #79-141 Director Office of Managenert Information and Program Control U.S. Nuclear Regulatory Cotnission Uanhingten, DC 20555 Docket No. 50-293 License DPR-35 Subj ec t : | {{#Wiki_filter:* | ||
June, 1979 Monthly Report | . | ||
4: | |||
""" Edison e-m PILGRIM NUCLEAR POWER STATION RFD # 1 rocky HILL HOAD PLYMOUTH. mas 3ACHUsETrs 02360 July 12, 1979 BECo Ltr #79-141 Director Office of Managenert Information and Program Control U.S. Nuclear Regulatory Cotnission Uanhingten, DC 20555 Docket No. 50-293 License DPR-35 Subj ec t : June, 1979 Monthly Report | |||
==Dear Sir:== | ==Dear Sir:== | ||
In accordance with PNPS Technical Specification 6.9. A.3, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning. | |||
In accordance with PNPS Technical Specification 6.9. A.3, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning. . | |||
J.E. Howard M. T. McLoughlin D. G. Stoodley G. C. Andognini J. A.Murphy R. Tis H.R. 3alfour J. W. Nicholson C. K. Vantrease R. A. Canalas, G.E. | Respectfully submitted, | ||
C. S. Ondash F. J. Wiedennann E. L. Cobb S. L. Rosen' Document Control Center Mrs.C. M. Gaffney R. J.Schug PJM (LB)R.S. Hahn J. A.Seery M. G. Hensch R. J. Sevigny 7gg | * P. J. McGuire Station Manager Nuclear Operations GGH:dl cc: Director Office of Inspection and Enforcement Of fice of Nuclear Regulatory Commission U. S. Nuclear Regulatory Consission Washington, DC 20555 Director of Region I Office of Inspection and Enforce =ent U. S. Nuclear Regulatory Consission 631 Park Avenue King of Prussia, PA 19406 cc: MessrJ: J. E. Howard M. T. McLoughlin D. G. Stoodley G. C. Andognini J. A. Murphy R. Tis H. R. 3alfour J. W. Nicholson C. K. Vantrease R. A. Canalas, G.E. C. S. Ondash F. J. Wiedennann E. L. Cobb S. L. Rosen' Document Control Center Mrs. C. M. Gaffney R. J. Schug PJM (LB) | ||
.OPERATING DATA REPORT DOCKET NO. | R. S. Hahn J. A. Seery M. G. Hensch R. J. Sevigny 7gg C. J. Mathis W. M. Sides JUU jn0 i6 7 9072 0 0 A fE2: | ||
50-293 DATE 7/9/79 CO\tPLETED llY G.G. 'Piitney TELEPflONE 1-617-746-7900 OPER ATING STATUS N '" 1. Unit Name: Pilcri'. I | |||
. | |||
OPERATING DATA REPORT DOCKET NO. 50-293 DATE 7/9/79 CO\tPLETED llY G. G. 'Piitney TELEPflONE 1-617-746-7900 OPER ATING STATUS N '" | |||
: 1. Unit Name: Pilcri'. I | |||
: 2. Reporting Period; hne - 1979 | : 2. Reporting Period; hne - 1979 | ||
: 3. Licensed Thermal Powei Otht): | : 3. Licensed Thermal Powei Otht): 19C8- | ||
19C8-4. Nameplate Rating (Gross StWe). | : 4. Nameplate Rating (Gross StWe). 678. | ||
678. | : 5. D: sign Electrical Ratmg (Net \tWe): 655. | ||
: 6. Stasimum Dependab!e Capacity (Gross 31We): | : 6. Stasimum Dependab!e Capacity (Gross 31We): 600. | ||
600. | : 7. Stasimum Dependable Capacity (Net .\1We): 670. | ||
, 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Sinte Last 1:eport. Gise Reasons: | , | ||
None 9. Power Lesel To which Restricted. If Any (Net %!We): | : 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Sinte Last 1:eport. Gise Reasons: | ||
None | |||
N/A This 51onth Yr to-Date Cumalatise | : 9. Power Lesel To which Restricted. If Any (Net %!We): _None | ||
*11. Hours in Reporting Period 720.0 4343.0 57479.0 12. Number Of Hours Reactor Was' Critical 688.0 3791.9 40839.6 13. Reactor Reserve Shutdown liours 0.0 0.0 0.0 14. IIours Generator Or .Line 679.9 3755.3 39477.9 15. Unit Resene Shutdown Hours 0.0 0.0 0.0 16. Gross Thermal Energy Generated O!WH) 1314336.0 7318090.0 65750880.0 7 Gross Electrical Energy Generated 15tWH) 452420.0 , _ , 2515430.0 21645904.0 | : 10. Reasons For Restrictions. lf Any: N/A This 51onth Yr to-Date Cumalatise | ||
* | |||
: 11. Hours in Reporting Period 720.0 4343.0 57479.0 | |||
Ncne 25. If Shut Down At End Of Report Period. Estimated Date of Startup: _ | : 12. Number Of Hours Reactor Was' Critical 688.0 3791.9 40839.6 | ||
Cnit Operating | : 13. Reactor Reserve Shutdown liours 0.0 0.0 0.0 | ||
: 26. Units in Test Status (F rior to Commercial Operation): | : 14. IIours Generator Or .Line 679.9 3755.3 39477.9 | ||
Forecast Achieved. | : 15. Unit Resene Shutdown Hours 0.0 0.0 0.0 | ||
.AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. | : 16. Gross Thermal Energy Generated O!WH) 1314336.0 7318090.0 65750880.0 7 Gross Electrical Energy Generated 15tWH) 452420.0 , _ , | ||
50-293 s UNIT Filgrim I.DATE 7/9/79-CO\tPLETED BY G.G. Whitnev TELEP110NE 1-617-746-7900 MONT11 June, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL ( M We-Net) | 2515430.0 21645904.0 __ | ||
OtWe Net)1 530.17 6 !. .2 63_2.13 436.3 A64-19 333.4 662.-20 656.5 662.21 663.6 6A'5664 33 7 AA1.23 665.3 662.24 663.9^^*25 663.10 666-26 663.11 AAS.664 | Nct Electrical Energy Generated 01% H) 435472.0 _ | ||
N/77)366 182 | 2420387.0 20781951.0 | ||
=>C.a v".?=- | /. Unit Senice Factor 94.& 36.5 63.7 | ||
: 20. Unit Asailability Factor 94.4 86.5 63.7 | |||
O Di. | : 21. Unit Capacity Factor (Using SIDC Net) 90.3 83.2 - | ||
'.=. | 54.0 | ||
%)w --~ | : 22. Unit Capacity Factor (Using DER Net) 92.3 _ | ||
($jl){Ill | 85.1 55.2 | ||
: m. -n -1,a .u m- | : 23. Unit Forced Outage Rate 0.0 12.7 10.y | ||
: 24. Shutdowns Scheduled Oser Next 6.\1onths (Type Date, and Duration of Each1: | |||
Ncne | |||
: 25. If Shut Down At End Of Report Period. Estimated Date of Startup: _ Cnit Operating | |||
: 26. Units in Test Status (F rior to Commercial Operation): Forecast Achieved | |||
. | |||
INITIAL CRITIC / .TY ' | |||
INITIAL ELECTRICITY CONI \t ERCI A L OPER ATION 366 181 mm | |||
. | |||
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 s | |||
UNIT Filgrim I | |||
. DATE 7/9/79 | |||
- | |||
CO\tPLETED BY G. G. Whitnev TELEP110NE 1-617-746-7900 MONT11 June, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL | |||
( M We-Net) | |||
OtWe Net) 1 530. 17 6 !. . | |||
2 63_2. 13 436. | |||
3 A64- 19 333. | |||
4 662. - 20 656. | |||
5 662. 21 663. | |||
6 6A' 5664 33 7 AA1. 23 665. | |||
3 662. 24 663. | |||
9 ^^* 25 663. | |||
10 666- 26 663. | |||
11 AAS. 27 664 12 AA4- 23 665. | |||
13 664 _ ,9 gg4, la 661. 30 663. | |||
15 629. 31 0. | |||
16 1- | |||
. | |||
INSTRUCTIONS On tlu., tornut. !ist t."e averag . aa,1y .ani: power !; elin \twc-Net fer each day in the repertuig 'nt.oth. Compute to the reatest who;c megawan. | |||
N/77) 366 182 | |||
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f =J b 17- ,_ m-= ~- | |||
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L 366 183 | |||
BOSTON EDISON COMPAW PILCRIM NUCLFR POWER STATION | |||
==SUMMARY== | ==SUMMARY== | ||
OF OPERATIONS FOR JU':E, 1979 The station was recovering fren the snubter modification outage at the beginning of June. | OF OPERATIONS FOR JU':E, 1979 The station was recovering fren the snubter modification outage at the beginning of June. Reactor Pcwer was 85% on June 1 and increasing at 10MW /hr per PCICMR. | ||
Reactor Pcwer was 85% on June 1 and increasing at 10MW /hr per PCICMR. | |||
Reacter Power reached 100% on June 3, 1979 and continued at this level until June 16, 1979 except for minor power reductions to naintain main condenser delta temperature. On June 16, 1979, the unit was shutdown to replace a weeping safety relief valve and perform other planned =aintenance. | Reacter Power reached 100% on June 3, 1979 and continued at this level until June 16, 1979 except for minor power reductions to naintain main condenser delta temperature. On June 16, 1979, the unit was shutdown to replace a weeping safety relief valve and perform other planned =aintenance. | ||
The unit was started up on June 17, 1979 and synchronized to the systen at 1613 hours. | The unit was started up on June 17, 1979 and synchronized to the systen at 1613 hours. Reactor pcwer reached 100% again on June 21, 1979 and continued at this level for the remainder of the month. | ||
Reactor pcwer reached 100% again on June 21, 1979 and continued at this level for the remainder of the month. | . | ||
.366 134 REFUELING INFOrtCION The f ollowing refueling inf ormation is included in the Monthly Report as requested in a letter to Mr. G. C. Andognini dated January 18, 1978. | 366 134 | ||
REFUELING INFOrtCION The f ollowing refueling inf ormation is included in the Monthly Report as requested in a letter to Mr. G. C. Andognini dated January 18, 1978. | |||
For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request. | For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request. | ||
1.The name of this f acility is Pilgrim Nuclear Power Station, Docket No. 50-293 2.Scheduled date for next Refueling Shutdown: | : 1. The name of this f acility is Pilgrim Nuclear Power Station, Docket No. 50-293 | ||
January, 1980 3.Scheduled date for restart following refueling: April, 1980 4 5.Due to their similarity, requests 4, 5 and 6 are responded to collectively. | : 2. Scheduled date for next Refueling Shutdown: January, 1980 | ||
6.The fuel, which is presently expected to be loaded during the next scheduled shutdown, may be reload fuel of a new design and may therefore require a proposed license submittal and technical specification change. | : 3. Scheduled date for restart following refueling: April, 1980 4 | ||
It is not possible, however, to supply pertinent information on dates. | : 5. Due to their similarity, requests 4, 5 and 6 are responded to collectively. | ||
As information concerning fuel design, core configuration, Operational Review Committee determinations, proposed licensing action, and Technical Specification submittals becomes available, it will be forwarded to you. | : 6. The fuel, which is presently expected to be loaded during the next scheduled shutdown, may be reload fuel of a new design and may therefore require a proposed license submittal and technical specification change. It is not possible, however, to supply pertinent information on dates. As information concerning fuel design, core configuration, Operational Review Committee determinations, proposed licensing action, and Technical Specification submittals becomes available, it will be forwarded to you. | ||
7.(a) There are 580 fuel assemblies in the core.(b) There are 580 fuel assemblies in the spent fuel pool. | : 7. (a) There are 580 fuel assemblies in the core. | ||
8.(a) The station is presently licensed to store 2320 spent fuel assemblies. | (b) There are 580 fuel assemblies in the spent fuel pool. | ||
The actual spent fuel storage capacity is 1160 fuel assemblies and new high density fuel storage racks are in the process of being installed.(b) The planned spent fuel storage capacity is 2320 fuel assemblies. | : 8. (a) The station is presently licensed to store 2320 spent fuel assemblies. | ||
9.b'ith present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 580 fuel assemblies (one core). | The actual spent fuel storage capacity is 1160 fuel assemblies and new high density fuel storage racks are in the process of being installed. | ||
366 135 PII.CRIf1 tillCI. EAR POWER STATIOri Month . June, 1979 | (b) The planned spent fuel storage capacity is 2320 fuel assemblies. | ||
.MAlOR SAFETY REI.ATED MAINTENAtlCE | : 9. b'ith present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 580 fuel assemblies (one core). | ||
----CORRECTIVE ACTTON AS SOC TAT P.fi'~ ' | 366 135 | ||
SYSTE!!C0!!POtlErlT MAI.FUtlCT I O!1 calls E PIA l tit E? LANCE TO PREVENT RECURREf;CE 1.ER 1"i n" Relief Valve I.eaking Pilot Valve Leakage Replace with Modified Topworks on Order None rel>u il t valve 29'A'SSU Pump Bottom Bowl Worn Errosion and Corrosion Install New New Modified Assembly None Itowl Assemlil y 2 MOV-202-SA Possible deteriora-Exposure and Age Replaced Motors None None t1oV-202-5B tion of Teflon in-sulation on leads 29 Salt Service Corrosion Failure of Rubber Replaced '.in ing Inst alled flew Ruliber 1.Ined tion e | |||
_U;8.Le r P [p i ng___ _ | PII.CRIf1 tillCI. EAR POWER STATIOri Month . June, 1979 | ||
. | |||
l.I n ing Pipe:")Salt Service Errosion of Seat 6 Replaced Seat fl/A None Wa t e r I.eaks filse And Dise Pump Disc Check Valve. __ _ _ _ . . _. _ _ _ _ _ _ _ _ . _ __ . . _ _ _ | MAlOR SAFETY REI.ATED MAINTENAtlCE | ||
- - - - | |||
_ _ _ _ _ _ _ _ | CORRECTIVE ACTTON AS SOC TAT P.fi'~ ' | ||
-,%,.a--m-----w--.. | SYSTE!! C0!!POtlErlT MAI.FUtlCT I O!1 calls E PIA l tit E? LANCE TO PREVENT RECURREf;CE 1.ER 1 "i n" Relief Valve I.eaking Pilot Valve Leakage Replace with Modified Topworks on Order None rel>u il t valve 29 'A' SSU Pump Bottom Bowl Worn Errosion and Corrosion Install New New Modified Assembly None Itowl Assemlil y 2 MOV-202-SA Possible deteriora- Exposure and Age Replaced Motors None None t1oV-202-5B tion of Teflon in-sulation on leads 29 Salt Service Corrosion Failure of Rubber Replaced '.in ing Inst alled flew Ruliber 1.Ined | ||
m.em-w ew-*u m'-+ 6 =-we--*--*-- | . | ||
mewe.--e-_-N--g m e-w.wee----e me wwe--n_ | tion e | ||
m-s--e ON ON. - - _ _ _ . . . | - _ _ _ _ _ _ | ||
-- - . . - _ _ _ . _ | _U;8.Le r P [p i ng___ _ _ _ _ _ _ _ _ | ||
.-- | l.I n ing Pipe | ||
:") Salt Service Errosion of Seat 6 Replaced Seat fl/A None Wa t e r I.eaks filse And Dise Pump Disc Check Valve | |||
_ _ _ _ _ _ _ _ _ | . __ _ _ _ . . _ . _ _ _ _ _ _ _ _ . _ __ . . _ _ _ _ __ ___ _ | ||
-__. ..._ ___-- . - -., .._ | _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ | ||
__. __ _ _ _ _ - _ _ . . | -,%,.a--m -----w--. .m _ em- e-mmmmw- ee.=am--e. -Ne-w - = e-m-..mmm-+---mai.%-, -- w ._w-.- -- - - - , , , | ||
-- - . - . _ _ | -% - -. . - - - --- m. em -w ew-*u m'- + 6 =- we--*--*-- mewe.--e-_-N--g m e-w. wee ----e me wwe--n_ m-s--e ON ON | ||
. - - _ _ _ . . . -- - . . - _ _ _ . _ .--_ _ _ _ _ - - __ _ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ | |||
-__ . ... _ ___-- . - -., .._ __. __ _ _ _ _ - _ _ . . - - - . - . _ _ _ | |||
. . _ _ __ _ - . _ . . , _ _ . _ - - . _ . . | |||
ON J}} | ON J}} |
Revision as of 11:38, 19 October 2019
ML19225A790 | |
Person / Time | |
---|---|
Site: | Pilgrim |
Issue date: | 07/09/1979 |
From: | Whitney G BOSTON EDISON CO. |
To: | |
Shared Package | |
ML19225A789 | List: |
References | |
NUDOCS 7907200252 | |
Download: ML19225A790 (6) | |
Text
.
4:
""" Edison e-m PILGRIM NUCLEAR POWER STATION RFD # 1 rocky HILL HOAD PLYMOUTH. mas 3ACHUsETrs 02360 July 12, 1979 BECo Ltr #79-141 Director Office of Managenert Information and Program Control U.S. Nuclear Regulatory Cotnission Uanhingten, DC 20555 Docket No. 50-293 License DPR-35 Subj ec t : June, 1979 Monthly Report
Dear Sir:
In accordance with PNPS Technical Specification 6.9. A.3, a copy of the Operational Status Summary for Pilgrim Nuclear Power Station is attached for your information and planning. .
Respectfully submitted,
- P. J. McGuire Station Manager Nuclear Operations GGH:dl cc: Director Office of Inspection and Enforcement Of fice of Nuclear Regulatory Commission U. S. Nuclear Regulatory Consission Washington, DC 20555 Director of Region I Office of Inspection and Enforce =ent U. S. Nuclear Regulatory Consission 631 Park Avenue King of Prussia, PA 19406 cc: MessrJ: J. E. Howard M. T. McLoughlin D. G. Stoodley G. C. Andognini J. A. Murphy R. Tis H. R. 3alfour J. W. Nicholson C. K. Vantrease R. A. Canalas, G.E. C. S. Ondash F. J. Wiedennann E. L. Cobb S. L. Rosen' Document Control Center Mrs. C. M. Gaffney R. J. Schug PJM (LB)
R. S. Hahn J. A. Seery M. G. Hensch R. J. Sevigny 7gg C. J. Mathis W. M. Sides JUU jn0 i6 7 9072 0 0 A fE2:
.
OPERATING DATA REPORT DOCKET NO. 50-293 DATE 7/9/79 CO\tPLETED llY G. G. 'Piitney TELEPflONE 1-617-746-7900 OPER ATING STATUS N '"
- 1. Unit Name: Pilcri'. I
- 2. Reporting Period; hne - 1979
- 3. Licensed Thermal Powei Otht): 19C8-
- 4. Nameplate Rating (Gross StWe). 678.
- 5. D: sign Electrical Ratmg (Net \tWe): 655.
- 6. Stasimum Dependab!e Capacity (Gross 31We): 600.
- 7. Stasimum Dependable Capacity (Net .\1We): 670.
,
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Sinte Last 1:eport. Gise Reasons:
None
- 9. Power Lesel To which Restricted. If Any (Net %!We): _None
- 10. Reasons For Restrictions. lf Any: N/A This 51onth Yr to-Date Cumalatise
- 11. Hours in Reporting Period 720.0 4343.0 57479.0
- 12. Number Of Hours Reactor Was' Critical 688.0 3791.9 40839.6
- 13. Reactor Reserve Shutdown liours 0.0 0.0 0.0
- 14. IIours Generator Or .Line 679.9 3755.3 39477.9
- 15. Unit Resene Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated O!WH) 1314336.0 7318090.0 65750880.0 7 Gross Electrical Energy Generated 15tWH) 452420.0 , _ ,
2515430.0 21645904.0 __
Nct Electrical Energy Generated 01% H) 435472.0 _
2420387.0 20781951.0
/. Unit Senice Factor 94.& 36.5 63.7
- 20. Unit Asailability Factor 94.4 86.5 63.7
- 21. Unit Capacity Factor (Using SIDC Net) 90.3 83.2 -
54.0
- 22. Unit Capacity Factor (Using DER Net) 92.3 _
85.1 55.2
- 23. Unit Forced Outage Rate 0.0 12.7 10.y
- 24. Shutdowns Scheduled Oser Next 6.\1onths (Type Date, and Duration of Each1:
Ncne
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: _ Cnit Operating
- 26. Units in Test Status (F rior to Commercial Operation): Forecast Achieved
.
INITIAL CRITIC / .TY '
INITIAL ELECTRICITY CONI \t ERCI A L OPER ATION 366 181 mm
.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-293 s
UNIT Filgrim I
. DATE 7/9/79
-
CO\tPLETED BY G. G. Whitnev TELEP110NE 1-617-746-7900 MONT11 June, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL
( M We-Net)
OtWe Net) 1 530. 17 6 !. .
2 63_2. 13 436.
3 A64- 19 333.
4 662. - 20 656.
5 662. 21 663.
6 6A' 5664 33 7 AA1. 23 665.
3 662. 24 663.
9 ^^* 25 663.
10 666- 26 663.
11 AAS. 27 664 12 AA4- 23 665.
13 664 _ ,9 gg4, la 661. 30 663.
15 629. 31 0.
16 1-
.
INSTRUCTIONS On tlu., tornut. !ist t."e averag . aa,1y .ani: power !; elin \twc-Net fer each day in the repertuig 'nt.oth. Compute to the reatest who;c megawan.
N/77) 366 182
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L 366 183
BOSTON EDISON COMPAW PILCRIM NUCLFR POWER STATION
SUMMARY
OF OPERATIONS FOR JU':E, 1979 The station was recovering fren the snubter modification outage at the beginning of June. Reactor Pcwer was 85% on June 1 and increasing at 10MW /hr per PCICMR.
Reacter Power reached 100% on June 3, 1979 and continued at this level until June 16, 1979 except for minor power reductions to naintain main condenser delta temperature. On June 16, 1979, the unit was shutdown to replace a weeping safety relief valve and perform other planned =aintenance.
The unit was started up on June 17, 1979 and synchronized to the systen at 1613 hours0.0187 days <br />0.448 hours <br />0.00267 weeks <br />6.137465e-4 months <br />. Reactor pcwer reached 100% again on June 21, 1979 and continued at this level for the remainder of the month.
.
366 134
REFUELING INFOrtCION The f ollowing refueling inf ormation is included in the Monthly Report as requested in a letter to Mr. G. C. Andognini dated January 18, 1978.
For your convenience, the information supplied has been enumerated so that each number corresponds to equivalent notation utilized in the request.
- 1. The name of this f acility is Pilgrim Nuclear Power Station, Docket No. 50-293
- 2. Scheduled date for next Refueling Shutdown: January, 1980
- 3. Scheduled date for restart following refueling: April, 1980 4
- 5. Due to their similarity, requests 4, 5 and 6 are responded to collectively.
- 6. The fuel, which is presently expected to be loaded during the next scheduled shutdown, may be reload fuel of a new design and may therefore require a proposed license submittal and technical specification change. It is not possible, however, to supply pertinent information on dates. As information concerning fuel design, core configuration, Operational Review Committee determinations, proposed licensing action, and Technical Specification submittals becomes available, it will be forwarded to you.
- 7. (a) There are 580 fuel assemblies in the core.
(b) There are 580 fuel assemblies in the spent fuel pool.
- 8. (a) The station is presently licensed to store 2320 spent fuel assemblies.
The actual spent fuel storage capacity is 1160 fuel assemblies and new high density fuel storage racks are in the process of being installed.
(b) The planned spent fuel storage capacity is 2320 fuel assemblies.
- 9. b'ith present spent fuel in storage, the spent fuel pool now has the capacity to accommodate an additional 580 fuel assemblies (one core).
366 135
PII.CRIf1 tillCI. EAR POWER STATIOri Month . June, 1979
.
MAlOR SAFETY REI.ATED MAINTENAtlCE
- - - -
CORRECTIVE ACTTON AS SOC TAT P.fi'~ '
SYSTE!! C0!!POtlErlT MAI.FUtlCT I O!1 calls E PIA l tit E? LANCE TO PREVENT RECURREf;CE 1.ER 1 "i n" Relief Valve I.eaking Pilot Valve Leakage Replace with Modified Topworks on Order None rel>u il t valve 29 'A' SSU Pump Bottom Bowl Worn Errosion and Corrosion Install New New Modified Assembly None Itowl Assemlil y 2 MOV-202-SA Possible deteriora- Exposure and Age Replaced Motors None None t1oV-202-5B tion of Teflon in-sulation on leads 29 Salt Service Corrosion Failure of Rubber Replaced '.in ing Inst alled flew Ruliber 1.Ined
.
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l.I n ing Pipe
- ") Salt Service Errosion of Seat 6 Replaced Seat fl/A None Wa t e r I.eaks filse And Dise Pump Disc Check Valve
. __ _ _ _ . . _ . _ _ _ _ _ _ _ _ . _ __ . . _ _ _ _ __ ___ _
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