ML20083L937

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Mar 1984
ML20083L937
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/31/1984
From: Miller L, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8404170413
Download: ML20083L937 (8)


Text

-.

AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-272 Unit Name Salem # 1 Date April 10, 1984 Completed by L.

K. Miller Telephone 609-935-6000 Extension 4455 Month March 1984 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 0

17 0

1 2

0 18 0

.3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

P.

8,1-7 Rl-B404170413 840331 Page 2 of 8 f -

='"

[

PDR ADOCK 05000272

.R

..PDR

.._ a _

4 OPERATING DATA REPORT Docket No.50-272 r

Date April 10, 1984 Telephone 935-6000

-Completed by L.

K. Miller Extension 4455 i

Operating Status j

1.

Unit Name Salem No. 1 Notes 2.

Reporting. Period March 1984 3.

Licensed Thermal Power (MWt) 3338 4.

Nameplate Rating (Gross MWe) 1135 5.

Design Electrical Rating (Net MWe) 1090 6.

Maximum Dependable Capacity (Gross MWe)1124 1

7.

Maximum Dependable Capacity (Net MWe) 1079 8.

If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A l

9.

Power Level to Which Restricted, if any (Net MWe)

N/A i

10. Reasons for Festrictions, if any N/A This Month Year to Date Cumulative
11. Hours in Reporting Period 744 2184 59209
12. No. of Hrs. Reactor was Critical 0

1237.6-34388.8

13. Reactor Reserve Shutdown Hrs.

0 54.5 3088.4

14. Hours Generator On-Line 0

1197.8 32975.7

-15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated

-99619394.

(PHGI) 0 3800023

17. Gross Elec. Energy Generated (MWH) 0 1281380 32896480 j
18. Net Elec. Energy Generated (MWH)

(6306) 1217458 31188770

19. Unit Service Factor 0

54.8 55.-7

20. Unit Availability Factor 0

54.8 55.7.

21. Unit Capacity Factor j

(using MDC Net) 0 51.7 48.8

22. Unit Capacity Factor-(using. DER Net) 0 51.1 48.3
23. Unit Forced Outage Rate 100 45.2 129.8
24. Shutdowns scheduled over next 6 mohths -(type, -date and duration of-each)

Re fueling 3-1-84

'25..If shutdown at'end of Report Period, Estimat'ed Date of.Startup:

9-1-84:

26. Units in Test Status (Prior to Commercial Operation) :

Forecast Achieved

. Initial-Criticality

-9/30/76;

_12/11/76

Initial Electricity

.12/20/76 11/1/76; 12/25/76-Commercial Operation'.

8-1-7.R2 6/30/77 Page of Page.3 of.8-T P

T rS-7

UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50 -272 REPORT MONTH March 1984 Unit Name Salem No.1 Date April 10, 1984 Completed bT L.K. Miller Telephone 609-935-6000 Extension 4455 Method of Duration Shutting License Cause and Corrective No.

Date Type Hours Paason Down Event System Component Action to 1

2 Reactor Report Code 4 Code 5 Prevent Recurrence Other HA GENERA Generator Problems84-172 02-24 F

744 A

3 4

~

l 2 Reason-3 Method 4 Exhibit G S Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Scram.

for Prepara-Source C-Refueling 3-Automatic Scram. tion of Data

' D-Regulato ry ' Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-Other (LER) File

.H-Other-explain (NUREG 0161)

Page 4 of 8

DOCKET NO:

50-272 MAJOR PLANT MODIFICATIONS REPORT MONTH MARCH 1984 UNIT NAME:

SALEM 1 DATE:

APRIL 10, 1984 COMPLETED BY:

L.

K.

MILLER fx TELEPHONE:

(609) 339-4455 3

O

  • DCR NO.

PRINCIPLE SYSTEM SUBJECT ISC-1362 Fuel Transfer Upgrade the Fuel Transfer System per Westinghouse recommendations.

(-U

(

.) -

l x y'

  • DESIGN CHANGE REOUEST 8-1-7.R1 Page 5 of 8

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-272

' REPORT MONTH MARCH 1984 UNIT NAME:

Salem 1-DATE:

April 10, 1984 i

COMPLETED BY:

L.K. Miller TELEPHONE:

609/339-4455 I

  • DCR NO.

SAFETY EVALUATION 10 CFR 50.59 ISC-1362 The implementation of this DCR does not involve any safety related systems.

Additionally, implementation of this DCR will not compromine the functioning of the fuel handling system.

No unreviewed safety or environmental questions are involved.

  • DCR - Design Change Request I

1 i

1 4

Page 6-of'8-

--a.-


s--,----a,---


w--

s- - - - - - - - - - -

--a

SALEM UNIT 1 OPERATIONS

SUMMARY

REPORT MARCH 1984 Unit No. I began the period shutdown as the fifth refueling outage continues.

The Unit No. 1 generator was partially disassembled to allow removal of the rotor and completion of the damage assessment.

Following testing, the generator coils were completely removed.

Eight top coils and four bottom coils are to be saved.

The generator rotor was shipped off site to be refurbished and repaired.

Loop testing of the generator iron revealed no major problems.

The decision to repair or replace the generator is under consideration.

All low pressure turbine rotor NDE examinations of the L-O stages were performed.

The results are under evaluation.

Disassembly of No. 12 Low Pressure Turbine is in progress to allow further evaluation.

Inspections of the Moisture Separator Reheaters (MSR) disclosed significant degradation, requiring replacement of the chevron separators.

Reactor disassembly and unloading of the fuel was completed on March 20, 1984.

Radiography of No.,12 Component Cooling Water Heat Exchanger service water piping welds was completed.

Approximately 75% of the welds inspected show evidence of pitting and linear corrosion in the base metal adjacent to the welds.

Engineering Department is evaluating several options to correct the situation.

Radiography was performed on all RTD loop bypass valves.

Ten of the twenty valves have their disks separated from the stems.

One valve has a disk which is only partially separated from the stem.

All of the RTD bypass valves will be replaced.

Preparations are in progress to remove No. 11, 13 and 14 RCP motors for design modifications, and to perform seal inspections on No. 11 and 13 RCPs.

Page 7 of 8

REFUELING INFORMATION DOCKET NO.:

50-272 COMPLETED BY:

L.K.

Miller UNIT NAME:

Salem 1 DATE:

April 10, 1984 TELEPHONE:

609/935-6000 EXTENSION:

4455 Month March 1984 1.

Refueling information has changed from last month:

YES X

NO 2.

Scheduled date for next refueling:

February 24, 1984 3.

Scheduled date for restart following refueling: September 1,1984 4.

A)

Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO DATE 4/1/84 B)

Has the reload fuel design been rev.iewed by the Station Operating Review Committee?

YES NO X

If no, when is it scheduled?

May 1984 5.

Scheduled date (s) for submitting proposed licensing action:

May 1984 (if required) 6.

Important licensing considerations associated with refueling:

NONE 7.

Number of Fuel Assemblies:

A)

Incore 0

B)

In Spent Fuel Storage 489 8.

Present licensed spent fuel storage capacity:

1170 Future spent fuel storage capacity:

1170 9.

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

September 1996 8-1-7.R4 Page 8 of 8

O PSEG Pubhc Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station April 10, 1984 Director, Office of Inspection and Enforcement U.S.

Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In Compliance with Section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of March 1984 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Operating Summary Refueling Information Sincerely yours, J

M.

upko, Jr.

General Manager - Salem Operations LKM:sbh cc:

Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control U.S.

Nuclear Regulatory Commission Washington, DC 20555 Enclosures Page lof 8 8-1-7.R4 Z82.*/

IE I The Energy People p

,m _

d