ML19343A783

Monthly Operating Rept for Oct 1980

ML19343A783
Person / Time
Site:	Millstone
Issue date:	11/06/1980
From:	Howlett G NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML19343A780	List: ML19343A778 ML19343A783
References
NUDOCS 8011210400
Download: ML19343A783 (7)

Text

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l OPERATING DATA REPORT DOCKETNO. 50-336 DATE November T), 1980.

CO.\\lPLETED BY - G.H. Howj,ett 1ELEPHONE (203)447-_1791X364.

OPERATING STA TUS

1. Unit Name: Millstone 2 Notes

• Items 21 & 22

2. Reporting Period: _0ctober 1980

~

cumulative are computed

3. Licensed Thermal Power (>!Wil: _2700 using a weighted average.

4. Nameplate Rating (Gross SIWel:

909

5. Design Electrical Rating (Net afwe): 870

6. Staximum Dependable Capacity (Gross 31We): 895

7. Staximum Dependable Capacity (Net StWe): R64

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report None

9. Power Lese! To Which Restricted. If Any (Net 31We):None

10. Reasons For Restrictions. If Any: --done This.\\lonth Yr.-to.Date Cumulative

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 745 429.5 _

7.320 _

42,528 4,706.2 42,/db.3

13. Reactor Reserve Shutdown Hours 4.5

14. Ilours Generator On.Line 4.5 2,076.9 301.2 4,404 M

15. Unit Reserve Shutdown Hours 28,305 132.8 132.8 460.2

16. Gross Thermal Energy Generated O!WH) 659.001

17. Gross Electrical Energy Cenerated OtWH) 215.600,_,, - 11,679,277 __ __69,377,905 3,829,672 22,414,317 ]

18. Net Electrical Energy Generated OlhH) 200.139 3,668.534 21.448,792

19. Unit Senice Factor 40.4 61.3_

20. Unit Availability Factor 58.3 63.I 67.7 66.6

21. Unit Capacity Factor (Using if f>C Net t

22. Unit Capacity Factor (Using DER Net) 31.1

23. Unit Forced Outage Rare '

30_9 _

56.0

• bl.1 57.6

• 60.0 0

22.4 23.6

24. Shutdowns Scheduled Over Next 6.\\lonths IType. Date,and Duration of Each1:

None

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

N/A

26. Units in Test Status (Prior to Commercial Operationi:

Forecast

.chies ed INITIA L CRITICA LITY N/A N/A INITIA L ELECTRICITY

__N/A N/A COSI\\lERCI A L OPERA TION

_N/A N/A (9/ m 8011210

'f C C

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' AVER ACE DAILY UNIT POWER LEVEL -

b DOCKET NO.

__50-335 UNIT Millstone 2 DATE November 6, 1980

.B1PLETED BY G.H. Howlett TELEPHONE (203)447-1791X364 October 1980 SiONE DAY AVERAGE DAILY POWER LEVEL DAY-AVERAGE DAILY POWER LEVEL

~ _- (NtWe-Net) -

(5fWe-Net) 3 O

(-4)

'O

(-27)

,7 2

0

(-4) 0

(-27) is 3

0

(-4) 58 39 4

0-(-4) 289

,o 5

0

'(-4) 404

,3 6

0

(-5) 428 7.

0

(-4) 735

~3 0

(-5) 8 826 24 9

-0

(-4) 826

,5 0

(-5)

-791 to 0

(-14) 827 27 0

(-26) 840 12

's 13 0

(-27) 853 29 14 0

(-27) 852 3a 0

(-28) 852 15 3,

16 0

(-28)

INSTRUCTIONS On :hn format.!!st' the nerage da0y unit power leselin S!We Net for each day in the repuriin; month Compuie to the f.earcil whole megaw.*t.

(9/77)

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50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. Millstone 2 UNIT NAME DATE November 12. 1980 COMPLETED BY G - 11 linwlett REPORTMONTH 0ctober 1980 TELEPHONE (?n'tidd7 1741 Y'464 "i

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Licensee 3

5%

g.

Cause & Correceive No

• Date E.

S5

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4 yj g

-5 j x Event f,3 gU3 Action to i Di y Report

• nU p,cvent Recurrence C-2 g

d 13 800816 S

442.5 C

1 Cycle 4 Refuel Outage 14 8010 S

1.3 B

4 Power was manually reduced to approx-imately 8% at which time a Turbine-overspeed trip test was conducted with the reactor remaining at power, Summary: Cycle 4 refuel outage concluded with the reactor being brought critical on the 13th.

Low Power Physics te:ng was conducted through the 18th with the unit being brought on line on the 19th.

100% power operations was achieved on the 29th.

Power Ascension testing is still ongoing at the end,0f this reporting period.

k i

Dockit No. 50-336 Page 1 of 3 Dato novemoer it, 1960 Unit Name Mi11stnnn ?

Completed By n n_ innw19et Telephone (203)447-1791X364 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month September 1980 DATE SYSTEM COMPONENT MAINTENANCE ACTION 9/2/80

. Main Steam Main Steam Safety Valves Removed off site for overhaul setup and testing.

9/3/80 Main Steam Steam Driven Aux, feed Pump H-21, Overhauled valve.

Trip Valve 9/3/00 Diesel Generator 130, Emergency Diesel Generator Annual overhaul 9/4/80 Main Steam Main Steam Isolation Valve Changed out air operated valve actuators.

2-MS-64A 9/5/80 High Pressure Safety HPSI Pump P-41C Realigned pump to notor per vendor recommendations.

Injection 9/6/80 Safety Injection Loop 1A.S.I. Header Check valve Rebuilt valve.

leak drain, 2-SI-618 9/11/80 Ma i'i Steam

1. 1 Steam Generator Surface Blow Rebuilt valve Stop Valve 2-MS-llA 9/11/80 Main Steam

1. 1 Steam Generator Bottom Blow Rebuilt valve Stop Valve 2-MS-12A 9/12/80 Reactor Coolant R.C.S. Flow transmitter PDT-lllB Replaced and calibrated transmitter 9/13/80 Main Steam

1. 2 Steam Generator Surface Blow Rebuilt valve.

Stop Valve 2-MS-118 9/13/80 Main Steam

1. 2 Steam Generator Bottom Blow Rebuilt valve.

Stop Valve 2-MS-128 O

Docket Ns. 50-336 Page 2 of.

3 Date-november 12, 1960 Unit Name Millstone 2-Completed By G.H. Howlett Telephone (703)447-1791X364' CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month September 1980 DATE SYSTEM COMTONENT MAINTENANCE ACTION 9/15/80 Reactor' Coolant RCS flow transmitter PDT-lllA

' Replaced and calibrated transmitter.

9/16/80 Diesel Generator' 120, Emergency Diesel Generator Replaced thrust bearing and re-coated heat exchanger heads.

9/17/80 Reactor Protection Trip circuit breakers 1-10 Rebuilt breakers.

9/17/80 Reactor Protection R.P.S. Ch. "A" Scaling Amplifier Replaced scaling amplifier.

CPC-2-F4.5 Module 9/20/60 Reactor Protection R.P.S. Ch. "A" Comparator Replaced comparator CPC-1-G4.5 Module 9/22/80 Reactor Building CAR Cooler ' A' RBCCW Normal outlet Rebuilt valve operator.

Cooling Water valve 2-RB-28.2 A 9/24/80 Main Steam S/G #1 Blowdown Stop Valve Rebuilt valve.

2-MS-220A i

9/24/80 Main Steam S/G #2 Blowdown Stop Valve Rebuilt valve.

2-MS-2208 9/24/80 Incore Nuclear Incore Instruments (12 total)

Replaced failed detectors.

Monitoring Locations; Nil, Ll6, L6, R6, T9, V15, T16, CIS, B15, L4, W6 & X7.

9/26/80 Reactor Coolant Pressurizer Relief valves.

Removed, overhauled, set-up and tested installed valves.

DockGt No. 50-336 Pag 2 3 of 3 Date November 12, 1980 Unit Nane Millstono ?

Completed By G.H. Howlett Telephone (203)447-1791X364 CCRRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month September 1980 DATE SYSTEM COMPONENT MAINTENANCE ACTION 9/27/80 Reactor Coolant Low temperature, overpressure Repaired bistable.

relief control bistable PC-103-1 9/29/80 Reactor Coolant Reactor Coolant Pump P-40C Repaired pump vapor seal.

9/30/80 Auxi.!ary Feed Aux. Feed Pump P-9A Replaced bearings.

Dockst N3..

50-336 Date:

November 12, 1980 Completed By: G.H. Howlett III Telephone: 203/447-197) X364 REFUELING INFORMATION REQUEST 1.

Name of facility:

Hillstone 2-2.

Scheduled date for next refueling shutdown:

Commenced refuel outage November 28, 1981.

3.

Schedule date for restart following refueling: January 16, 1982 4.

Will refueling or-resumption of operation thereafter require a technical specification change or other license amendment?

It is not anticipated that cycle 5 operations will require Technical' Specification changes or other License amendments.

5.

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

Licensing documentation will be provided a minimum of 90 days prior to start-up of Cycle 5 or as documented in the R.A. Clark letter to W.G. Counsil, dated 10/6/80, authorizing Cycle 4 operation.

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.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

(a)

In Core:

217 (b) 21 6 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

66~

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

1985, Spent Fuel Pool, full core off load capability is reached.

1987, Core Full, Spent Fuel Pool contains 648 bundles.