ML20155D851

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for May 1988 for Millstone 2
ML20155D851
Person / Time
Site: Millstone 
Issue date: 05/31/1988
From: Neron G
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20155D855 List:
References
NUDOCS 8806150433
Download: ML20155D851 (4)


Text

_

OPERATING DATA REPORT DOCKET N0. 50-336 OATE 6/8/88 COMPLETED BY G. Neron TELEPHONE (203) 447-1791

. Extension 4417 OPERATING STATUS 1.

Unit Name:. Millstone Unit 2 l Notes:

Items 21 and 22 cumulative l 2.

Reporting Period: May 1988 l

are weighted averages.

l 3.

Licensed Thermal Power (MWt): 2700 l

Unit operated at.2560 MW l 4.

Nameplate Rating (Gross MWe): 909 l

thermal prior to its

.l S.

Design Electrical Rating (Net MWe): 870 l

uprating to the current l

6.

Maximum Dependable Capacity (Gross MWe):888.75]

2700 MWTH power level.

l 7.

Maximum Dependable Capacity (Net MWe): 857.25 l l

8.

If Changes Occur in Capacity Ratings (Items Number 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 Yr.-to-Date Cumulative 11.

Hours In Reporting Period 744 3,647 108,983 12.

Number Of Hours Reactor Was Critical 395.1 2,028.8 79,409.1 13.

Reactor Reserve Shutdown Hours 0

0 2,205.5 14.

Hours Generator On-Line 364.5 1,903.5 75,156.5 15.

Unit Reserve Shutdown Hours 0

0 468.2 16.

Gross Thermal Energy Generated (MWH) 956,578 4,897,213 209,459,475 17.

Gross Elec. Energy Generated (MWH) 314,784.0 1,612,782.5 62,484,361.5 18.

Net Electrical Energy Generated (MWH) 299,836.0 1,540,165.5 59,916,703.5 19.

Unit Service Factor 49.0 52.2 69.0 20.

Unit Availability Factor 49.0 52.2 69.4 21.

Unit Capacity Factor (Using MDC Net) 47.0 49.3 64.8 22.

Unit Capacity Factor (Using DER Net) 46.3 48.5 63.8 23.

Unit Forced Outage Rate 51.0 21.4 15.3 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 32 8806150433 880531

//

PDR ADOCK 05000336 i

R nrn

_.. _....... _... _ -. _ _ _ _ _. ~,.._ _ _ _ __ _,

4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-336 UNIT Millstone 2 DATE 6/8/88 l

COMPLETED BY G. Neron TELEPHONE (203) 447-1791 Extension 4417 MONTH May 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 865 17 0

2 864 18 0

3 865 19 0

4 865 20 0

1 5

866 21 0

6 812 22 5

7 0

23 630 8

0 24 841 9

0 25 860 10 0

26 831 11 0

27 862 12 0

28 863 13 0

29 864 14 0

30 864 15 0

31 864 16 0

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Het for each day in the reporting month.

Com

'a to the nearest whole megawatt.

r DOCKET NO. 50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 2 DATE 6/8/88 COMPLETED BY G. Neron

~

REPORT MONTH MAY 1988 TELEPHONE (203) 447-1791 Extension 4417 l

No.

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

Shutting Event Code 4 Code 5 Action to Down Reactor 3 Report #

Prevent Recurrence 88-02 050788 5

379.5 8

1 N/A AB SEAL Initiated reactor shutdown from 100% power for a planned maintenance outage to investigate a reactor coolant system leak -

leak rate was less than amount specified in Technical Specifications; Visual inspections of the reactor coolant system revealed a leak in the proximity of the reactor vessel flange region; Removal of the reactor vessel head revealed the failure of the two (2) reactor vessel head "O"-rings; The two (2) failed "0"-rings were replaced; Reactor criticality was achieved on 5/21/88 and the Unit returned to service on S/22/88.

1 2

3 4

F:

Forced Reason:

Method:

Exhibit G - Instructions S:

Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance 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)

o 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 thereafter require a technical sps;ification 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 analysis will be supplied by Advanced Nuclear Fuels for Millstone Unit 2 go 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 - On March 31, 1988, License Amendment #128 was issued to Millstone Unit 2 which allows the full scale storage of consolidated fuel in the Spent Fuel Pool.

DOCKET NO. 50-336 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstona 2 DATE 05-06-88 COMPLETED BY G. Neron REPORT MONTH APRIL 1988 TELEPHONE (203) 447-1791 Extension 4417 l

No.

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

Shutting Event Code' Code 5 Action to Down Reactor 3 Report #

' Prevent Recurrence 88-01 040888 5

138.8*

B 1

88-08 AA CD CL,CCL Initiated reactor power reduction from 100% power for planned maintenance outage; CEA #22 dropped and power was reduced to ~70%; Continued reactor shutdown

- unable to recover the dropped CEA; CEA #4 also dropped before reactor was sub-critical; The dropping of CEA's #4 and #22 was determined to have been caused by major loss of upper gripper coil resistance due to overheating; In addition, a high resistance of the CEA #5 upper gripper coil was found, and was determined to have been caused by a loose coil stack connection; Overheating was caused by the reduction of the CEDM Cooler efficiency due to boron clogging of the fan intakes; New CEDM Coil Stacks were installed for CEA's #4, #5, and #22; The CEDM Cooler intakes were cleaned; Determination of the boron source is still under investigation.

See LER.

1 2

3 4

F:

Forced Reason:

Method:

Exhibit G - Instructions S:

Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance 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 S-Power Reduction 5

G-Operational Error (Explain)

(Duration = 0)

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

  • Corrected duration i

i

5 a.ner i Orric... s ioon sir.i. seriin. Connecticui em cowcecv, we woma cw=

wi.i v*sse.weisuc= ccww P.O. BOX 270 e + * *'ta =< = ce~

H ARTFORD. CONNECTICUT 06141-0270 L

L J Ul~/$ ($,N,"w~~~

(203) 665-5000 l

June 9, 1988 MP-11929 l

l Re:

10CFR50.71(a)

U.S. Nuclear Regulatory Commission Document Control Desk Washingtoo, D.

C. 20555

Reference:

Facility Operating License No. DPR-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 88-05 i

in accordance with Appendix A Technical Specifications, Section 6.9.1.6.

One additional copy of the report is enclosed.

Also attached is a revision for the April 1988 Unit Shutdown and Power Reductions sheet.

j Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

/)h670mco Stephen E. Scace Station Superintendent Millstone Nuclear Power Station SES/GN:faj cc:

W.T.

Russell, Region I Administrator W.J.

Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 & 3 lja