ML20151D458

Monthly Operating Rept for June 1988 for Millstone Unit 2.W/

ML20151D458
Person / Time
Site:	Millstone
Issue date:	06/30/1988
From:	Keenan J, Neron G NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
MP-12039, NUDOCS 8807250128
Download: ML20151D458 (5)

Text

e, AVERAGE DAILY UNIT POWER LEVEL 00CKET NO.

50-336 UNIT Millstone Unit 2 DATE 880708 COMPLETED BY G. Neron TELEPHONE (203)447-1791 Extension 4417 HONTH June 1988 OAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 863 17 864 2

863 18 866 3

863 19 866 4

863 20 865 5

863 21 865 6-813 22 865 7

200 23 865 8

0 24 866 9

0 25 866 10 0

26 865 11 0

27 866 12 0

28 866 13 0

29 867 14 0

30 867 _

15 320 31 16 813 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

hI 8807250120 000630 noOcx Oe-me 9 b ros

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OPERATINC DATA REPORT DOCKET NO.

50-336 DATE 880708 COMPLETED BY G. Neron TELEPHONE (203)447-1791 Extension 4417

~0PERATING STATUS

'1.

Unt; Name:. MILLSTONE UNIT 2

-l Notes: Items 21 and 22 are l

2.

. Reporting Period: JUNE 1988~

l weighted averages.

l 3.

Licensed Thermal Power (MWt): 2700 l

Unit operated at l

4-4.

Nameplate Rating (Gross MWe): 909 l

2560 MW thermal prior i

. 5.

Design Elec+.rical Rating (Net MWe): 870 l

.uprating to'the l

6.

Maximum Derandable Capacity (Gross MWe):893.88*l current 2700 MW l

7.

Maximum Dependable Capacity (Net MWe): 862.88* l thermal power level.**l 8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7)_

Since:Last Report, Give Reasons:

The change in capacity ratings is the result of secondary side efficiency work, i.e.,

replaced 1st, 5th and 6th point heaters, and condensers (work performed during the E0C 7 refuel outage).

9.

Power Level To Which Restricted, If Any (Net MWe):

N/A

10.. Reasons For-Restrictions, If Any:

N/A This Month Yr. - to-Date Cumulative 11.

Hours.In Reporting Period 720 4,367 109,703 12.

Number Of Hours Reactor Was Critical 533.?

2,562.0 79,942.3 13.

Reactor Reserve Shutdown Hours 0

0 2,205.5 14.

Hours Generator On-Line 527.0 2,430.5 75,683.5 15.

Unit Reserve Shutdown Hours 0

0 468.2 16.

Gross. Thermal Energy Generated (MWH) 1,400,732 6,297,945 210,860,207

17.

Gross Elec. Energy Generated (MWH) 463,678.5 2,076,461.0 62,948,040.0 18.

Het Electrical Eneggy Generated (MWH) 445,450.5 1,985,616.0 60,362,154.0 19.

Unit Service Factor 73.2 55.7 69.0 20.

Unit Availability Factor 73.2 55.7 69.4 l

21.

Unit Capacity Factor (Using MDC Net) 71.7 53.0 64.9 22.

Unit Capacity Factor (Using DER Net) 71.1 52.3 63.9 23.

Unit Forced Outage Rate 26.8 22.6 15.4 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

N/A 25.

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

N/A

-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

• • Item 21 Year-to-Date is a weighted average as a result of the capacity rating change.

DOCKET NO.

50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 880708 COMPLETED BY G. Neron REPORT MONTH June 1988 TELEPHONE (203)447-1791

~

Extension 4417 No.

Date Type Duration Reason 2 Method of Licensee System Component Cause & Corrective 2

(Hours)

Shutting Event Code' Code 5 Action to t

Down Reactor 3 Report #

Prevent Recurrence 88-03 060788 F

193.0 A

1 88-09 AA CL Initiated reactor power reduction from 10EE to < 70%

due to dropped CEA

1. 23; Commenced reactor shutdown from 70% power when CEA #23 was declared inoperable; Overheating of the CEDM upper gripper coil during the month of May, 1988 caused the subsequent coil failure, which resulted in the dropped CEA; Previous gripper coil failures (see April,1988 - LER #88-08) reinforced the decision to replace either the upper gripper coil or complete coil stack of all CEDM's on the reactor vessel head, with the exception of the CEA #14 CEDM, which had its upper gripper coil replaced during the May,1988 outage (see May,1988 Monthly Operating Report); Reactor criticality was achieved on 6/15/88; The Unit was also returned to service on 6/15/88.

See LER.

1 2

3 4

F:

Forced Reasen:

Method:

Exhibit C - Instructions S:

Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Mair,tenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-0161)

E-Operator Training & License Examination previous month F-Administrative 5-Power Reduction 5

G-Operational Error (Explain)

(Duration = 0)

Exhibit 1 - Same Source H-Other (Explain) 6-Other (Explain) e

t REFUELING INFORMATION REQUEST 1.

Name of facility:

Millstone 2 2.

Scheduled date for next refueling shutdown:

February, 1989 3.

Schedule date for restart following refueling: N/A 4.

Will refueling or resumption of operation thereaf ter require a t:chnical specification change or other license amendment?

^ Technical Specification changes will be necessary resulting from the change in fuel and safety analysis supplier for cycle 10 operation.

5.

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

The projected date is November 1988 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:

Cycle 10 will be unique in that it will be the first cycle where the fuel and safety anaiysis will be supplied by /.dvanced Nuclear Fuels for

, Millstone Unit 2 7.

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

(a)

In Core: (a) 217 (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:

Currently 1277 9.

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

1998 Core Full, Spent Fuel Pool Full 2009, Spent Fuel Pool, Full core off load capacity is reached

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9 % ) 665-5000 July 11, 1998 MP-12039 Re:

10CFR50.71(e)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Reference:

Facility Operating License No. OPR-65 Docket No. 50-336

Dear Sir:

This letter is forwarded to provide the report of operating and shutdown experience relating to Millstone Unit 2 Monthly Operating Report 88-06 in accordance with Appendix A Technical Specifications, Section 6.9.1.6.

One additional copy of the report is enclosed.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR:

Stephen E. Scace Station Superintendent Millstone Nuclear Power Station D, r s BY:

ohn S. Kee an nit 2 Superintendent Millstone Nuclear Power Station SES/GN:1js cc:

W,T. Russell, Region I Administrator W.J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3

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