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{{#Wiki_filter:AVERAGE DAILY UNIT POh1:R. LEVEL 50-311 OOCKET NO.
{{#Wiki_filter:M)NTI-J August 1980 DAY AVERAGE DAILY POWER LEVEL 1
UNIT   Salem #2 DATE September 10, 1980 COMPLETED BY     L. K. Miller TELEPHONE 609-365-7000 X507 M)NTI-J    August 1980 DAY AVERAGE DAILY   POWER LEVEL                  DAY AVERAGE DAILY      POhE LEVEL (MWe-NET)                                        (M.WE-l"i'ET) 1                0                              17               0 2                0                              18               0 3                0                              19               0 4                0                              20               0 5                0                              21               0 6                0                              22               0 7                0                              23               0 0                                                0 a                                                24 9                0                             25               0 10                  0                              26               0 11                  0                              27               0 12                  0                              28               0 13                  0                              29               0 0                                               0 14                                                30
2 3
: 15.                0                                                0 31 0
4 5
16 2 of 6
6 7
.P g.
a 9
8.1-7.Rl
10 11 12 13 14
: 15.
16 P
2 of 6
. g.
8.1-7.Rl (MWe-NET) 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
AVERAGE DAILY UNIT POh1:R. LEVEL 50-311 OOCKET NO.
UNIT Salem #2 DATE September 10, 1980 COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 X507 DAY AVERAGE DAILY POhE LEVEL (M.WE-l"i'ET) 17 0
18 0
19 0
20 0
21 0
22 0
23 0
24 0
25 0
26 0
27 0
28 0
29 0
30 0
31 0  


e           OPERATIOO   ~     REPORT e
is e
50-311 rx:x:::KET NJ.: _ _ _ _ _ _ _ _ __
OPERATIOO ~
CATE :  September 10, 1980 CXM?LE'.l'ED BY:    L. K. Miller
REPORT OPERM'lN'.; STATUS
                                                                                                ~:            609-365-7000 X507 OPERM'lN'.; STATUS
: l. Unit Naue:
: l. Unit Naue:         Salem #2                                             Notes:
Salem #2 Notes:
: 2. Reporting Period:             August 1980
: 2.
: 3. Licensed~ Power (Wit):
Reporting Period:
: 4. Nanepl.ate Rating (Gmss .t+E):
August 1980
                                          --.,.-..,-------
: 3.
3411 1162
Licensed~ Power (Wit):
: s. Design Electrical Rating (Net .t+E--)-               1"'"1....
3411
                                                ** -.....,,1.... 5____
: 4.
: 6. Max:imJm Dependable Capacity "(Gross KW!):             1149
Nanepl.ate Rating (Gmss.t+E):
: 7. Maximr.ml Dependable Capacity (Net MWe) :               1104
1162
: s.
Design Electrical Rating (Net.t+E--)-
** -.....,,1.... 1"'"1.... 5 ___ _
: 6. Max:imJm Dependable Capacity "(Gross KW!):
1149
: 7.
Maximr.ml Dependable Capacity (Net MWe) :
1104 e
50-311 rx:x:::KET NJ.: _________ _
CATE : September 10, 1980 CXM?LE'.l'ED BY:
L. K. Miller
~:
609-365-7000 X507
: a. If Changes Occur in Capacity Ratings (Ite!!S Nutti:er 3 'lllrcugh 7) Since Last Report, Give Reason:
: a. If Changes Occur in Capacity Ratings (Ite!!S Nutti:er 3 'lllrcugh 7) Since Last Report, Give Reason:
NONE
NONE
: 9. Power Level To Which Pastricted, If Arr:/ (Net ?fie):                       5% Thermal
: 9.
: 10. Reasons For Restrictions, If Aey:                               -------------------------------------------------
Power Level To Which Pastricted, If Arr:/ (Net ?fie):
Pending successful *completion of low power                       . I physics and natural . circulation testing programs.                                                                     I
5% Thermal
                                                                        '!bis lblth         Year to Date         Ctmll.ative 744                     3,240               3,240 ll. Hours In Reporting Period 268.2                    268.2                268.2
: 10.
: 12. NUntier Of Hours Reactor Was Critical l3. Reactor Reserve .Shutcbm !burs                                         0                         0                   0
Reasons For Restrictions, If Aey:
: 14. Hours Generator On-Line.                                               0                         0                   0
Pending successful *completion of low power physics and natural.. circulation testing programs.  
: 15. Unit Reserve Shutdown Hours                                                                       0                   0
'!bis lblth Year to Date Ctmll.ati ve 744 3,240 3,240 ll. Hours In Reporting Period
: 16. GJ:Oss 'llleJ:mal Energy Generated (!-fiH)                               0                         0
: 12.
: 17. GJ:Oss Electrical Energy Generated (mli)                                 0                         0                   0
NUntier Of Hours Reactor Was Critical 268.2 268.2 268.2 l3.
: 18. Net Electrical Energy Generated (M'IH)                                   0                         0                   0
Reactor Reserve. Shutcbm !burs 0
: 19. Unit Service Factor                                                     0                         0                   0
0 0
: 20. Unit Availahiljty Factor                                                 0                         0                   0
: 14.
: 21. Unit Capacity Factor (Using MOC Net)                                     0                         o.                 0 is
Hours Generator On-Line.
: 22. Unit Capacity Factor (Using DER Net)                                   0                         0                   0
0 0
: 23. Unit Forced Ol.ttage Rate                                               0                         0                   0
0
: 24. Shutdowns Scheduled Over Next 6 Mcnths (Type, Date, and Duration of Each) :
: 15. Unit Reserve Shutdown Hours 0
                                                                                          -
0
: 25. I f Shut Down At End of Report Period! Estimated Ila.te of Startup: - - - - - - - - - - - - - - - - - -
: 16.
: 26. Units In Test Status (Prior tc Camercial Operation) :
GJ:Oss 'llleJ:mal Energy Generated (!-fiH) 0 0
Forecast              Achieved INITIAL CRITICALITY                                           6/30/80               *8/02/8o INITIAL ~CI'IY                                                9/01/80                   N/A 8-l-7.R2
: 17.
                            ~          OPERATION                                              N/A                   N/A Pg.3 of 6
GJ:Oss Electrical Energy Generated (mli) 0 0
__J
0
: 18.
Net Electrical Energy Generated (M'IH) 0 0
0
: 19. Unit Service Factor 0
0 0
: 20. Unit Availahiljty Factor 0
0 0
: 21. Unit Capacity Factor (Using MOC Net) 0
: o.
0
: 22. Unit Capacity Factor (Using DER Net) 0 0
0
: 23. Unit Forced Ol.ttage Rate 0
0 0
: 24.
Shutdowns Scheduled Over Next 6 Mcnths (Type, Date, and Duration of Each) :
: 25. If Shut Down At End of Report Period! Estimated Ila.te of Startup: ------------------
: 26.
Units In Test Status (Prior tc Camercial Operation) :
8-l-7.R2 Pg.3 of 6 INITIAL CRITICALITY INITIAL ~CI'IY
~
OPERATION Forecast 6/30/80 9/01/80 N/A Achieved
*8/02/8o N/A N/A
_ _J


UNIT SllUTIXMNS l\ND PCMER REOOcrIONS 50-311 DOCKET NO.:~~~~~~~~~~
NJ.
REPORI' MJlmI  August 1980                    UNIT 'NAME:   Salem 112 DATE:   September 10' 198 0 COMPLETED BY:     L. K. Miller
1 DATE F: Forced S:
                                                                                                                              ~~~~~~~~~~
Scheduled Page 4 of 6 B-1-7.Rl TYPE1 2
TELEPHONE:   609-365- 7000 X507 ME.l'llOD OF OORATIOO                SllUITI~      LICENSE      SYSTEM CXMPOOENl'            CAUSE 1\ND CORRECI'IVE NJ.        DATE  TYPE1    (11.XJRS)    ~            ln'IN          EVEN!'    CODE4    CODES                    ACTION TO REAC'IOR      REPORI' I                                  PREVENT RIDJRRENCE N/A 1                    2                                                    3                    4                              5 F: Forced          . Reason:                                            Method:              Exhibit G - Instructions       Exhibit 1-Sane for Preparation of Data       Source S: Scheduled          A-Equipment Failure(Explain)                      1-Manual B-Maintenance or Test                                                    Entry Sheets for Licensee C-Refueling                                      2-Manual Scram.        Event Report (LER) File trRegulatory Restriction                          3-Automatic Scram.      (NUREI}-0161)
UNIT SllUTIXMNS l\\ND PCMER REOOcrIONS REPORI' MJlmI August 1980 ME.l'llOD OF OORATIOO
E--Operator Training & License Examination        4-Continuation of F-J\dministrative                                    Previous Outage
~
                            ~ational Error(Explain)
SllUITI~
H-other (Explain)                                5-Load Reduction Page 4 of 6                                                            9-0ther B-1-7.Rl
(11.XJRS) ln'IN REAC'IOR
. Reason:
A-Equipment Failure(Explain)
B-Maintenance or Test C-Refueling trRegulatory Restriction LICENSE EVEN!'
REPORI' I E--Operator Training & License Examination F-J\\dministrative
~ational Error(Explain)
H-other (Explain)
SYSTEM CXMPOOENl' CODE4 CODES 3
Method:
1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4
50-311 DOCKET NO.:~~~~~~~~~~
UNIT 'NAME:
Salem 112 DATE:
September 10' 198 0 COMPLETED BY: L. K. Miller  
~~~~~~~~~~
TELEPHONE:
609-365-7000 X507 CAUSE 1\\ND CORRECI'IVE ACTION TO PREVENT RIDJRRENCE N/A Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREI}-0161) 5 Exhibit 1-Sane Source


DOCKET NO.:      50-311
-MAJdR PLANT MODIFICATI.
-MAJdR PLANT MODIFICATI.                                     Salem t/2 UNIT N.41l:
REPORT MONTH August l  
REPORT MONTH     August l
~~~~~~~~~~~  
              ~~~~~~~~~~~
*DCR NO.
DATE:   September 10, 1980 COMPLETED BY:     L. K. Miller TELEPHONE:   609-365- 7000 X507
PRINCIPLE SYSTEM 2ET-0630 Leak Detection 2EC-0800 Lighting 2EC-0821 Structural 2EC-0957 Radiation Monitoring 2ET-0970 Inverters 2EC-0987 Control Air 2SC-0162 Waste Disposal
    *DCR NO.      PRINCIPLE SYSTEM                    SUBJECT 2ET-0630  Leak Detection              Data Required to Satisfy NRC 2EC-0800  Lighting                    Add Two Lights in Parking Let 2EC-0821  Structural                  Add 4" cp Core Bore - TGA 2EC-0957  Radiation Monitoring System Modify 2Rl8 Sampler Tubing 2ET-0970  Inverters                    Perform E-154 Test 2EC-0987  Control Air                Add 1-1/2" Check Valve 2SC-0162  Waste Disposal Liquid        Resin Decant Filter
* DESIGN CHANGE REQUEST 8-1-7.Rl Liquid System DOCKET NO.:
* DESIGN CHANGE REQUEST                            Pg. 5 of 6 8-1-7.Rl
50-311 UNIT N.41l:
Salem t/2 DATE:
September 10, 1980 COMPLETED BY:
L. K. Miller TELEPHONE:
609-365-7000 X507 SUBJECT Data Required to Satisfy NRC Add Two Lights in Parking Let Add 4" cp Core Bore -
TGA Modify 2Rl8 Sampler Tubing Perform E-154 Test Add 1-1/2" Check Valve Resin Decant Filter Pg. 5 of 6  


DOCKET NO.:        50-311 MAJOR PLANT MODIFICAT.S REPORT MONTH   August 1980 UNIT ~:           Salem 112 DATE:      September 10, 1980 COMPLETED BY:       L. K. Miller TELEPHONE:       609-365-7000 X507
50-311 MAJOR PLANT MODIFICAT.S REPORT MONTH August 1980 DOCKET NO.:
  *DCR NO.      1OCFRS0. 5 9.                   SAFETY EVALUATION 2ET-0630  The purpose of this DCR is the accumulation of data for the refinement of the Salem Leak Detectio_n Curves. No change to any system or operating procedure is required. This DCR does not impact any safety related system. Data will be acquired from equipment already installed at Salem.
UNIT ~:
2EC-0800  This DCR covers the addition of two lighting standards in the parking lot.
DATE:
Salem 112 September 10, 1980  
*DCR NO.
2ET-0630 2EC-0800 2EC-0821 2EC-0957 2ET-0970 2EC-0987 2:SC-0162 COMPLETED BY:
L. K. Miller TELEPHONE:
609-365-7000 X507 10CFRS0. 5 9.
SAFETY EVALUATION The purpose of this DCR is the accumulation of data for the refinement of the Salem Leak Detectio_n Curves.
No change to any system or operating procedure is required.
This DCR does not impact any safety related system.
Data will be acquired from equipment already installed at Salem.
This DCR covers the addition of two lighting standards in the parking lot.
This DCR will not affect any safety function of the system involved.
This DCR will not affect any safety function of the system involved.
The proposed changes do not involve any of the criteria associated with an unresolved safety question.
The proposed changes do not involve any of the criteria associated with an unresolved safety question.
2EC-0821  The addition of a 4" 0 Core Bare Hole in the north exterior stair.: of the T.G.A. will not require a change to the SAR or Technical Specifications and will not present an unreviewed safety question. There is no change in the fire safety features of the station.
The addition of a 4" 0 Core Bare Hole in the north exterior stair.: of the T.G.A. will not require a change to the SAR or Technical Specifications and will not present an unreviewed safety question.
2EC-0957  Change required to assure that radiation monitor: -performs as intended ..
There is no change in the fire safety features of the station.
by design. The function of the monitor .has not :*been .changed. No safety analysis are affected. No fire hazard is created - just adding process tubing to radiation sampler. Penetration through fire barriers will be resealed to maintain fire protection requirements.
Change required to assure that radiation monitor: -performs as intended..
2ET-0970  This procedure improves maintenance -- does not affect design.
by design.
2EC-0987  The additional check valve and downstream piping will be Seismic Class I.
The function of the monitor.has not :*been.changed.
No safety analysis are affected.
No fire hazard is created - just adding process tubing to radiation sampler.
Penetration through fire barriers will be resealed to maintain fire protection requirements.
This procedure improves maintenance -- does not affect design.
The additional check valve and downstream piping will be Seismic Class I.
This new flow path will not permit flow from safety related header to non safety related.
This new flow path will not permit flow from safety related header to non safety related.
2:SC-0162 This DCR does not present an unreviewed safety question and is in no way related uo any safety related system. Its operability is not essential for the operation or shutdown of the plant.
This DCR does not present an unreviewed safety question and is in no way related uo any safety related system.
Its operability is not essential for the operation or shutdown of the plant.
Pa.ge 6 of 6
Pa.ge 6 of 6
* DES!GN CHANGE REQUEST}}
* DES!GN CHANGE REQUEST}}

Latest revision as of 05:31, 6 January 2025

Monthly Operating Rept for Aug 1980
ML18082B187
Person / Time
Site: Salem 
Issue date: 09/10/1980
From: Miller L
Public Service Enterprise Group
To:
Shared Package
ML18082B186 List:
References
NUDOCS 8009180257
Download: ML18082B187 (5)


Text

M)NTI-J August 1980 DAY AVERAGE DAILY POWER LEVEL 1

2 3

4 5

6 7

a 9

10 11 12 13 14

15.

16 P

2 of 6

. g.

8.1-7.Rl (MWe-NET) 0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

AVERAGE DAILY UNIT POh1:R. LEVEL 50-311 OOCKET NO.

UNIT Salem #2 DATE September 10, 1980 COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 X507 DAY AVERAGE DAILY POhE LEVEL (M.WE-l"i'ET) 17 0

18 0

19 0

20 0

21 0

22 0

23 0

24 0

25 0

26 0

27 0

28 0

29 0

30 0

31 0

is e

OPERATIOO ~

REPORT OPERM'lN'.; STATUS

l. Unit Naue:

Salem #2 Notes:

2.

Reporting Period:

August 1980

3.

Licensed~ Power (Wit):

3411

4.

Nanepl.ate Rating (Gmss.t+E):

1162

s.

Design Electrical Rating (Net.t+E--)-

    • -.....,,1.... 1"'"1.... 5 ___ _
6. Max:imJm Dependable Capacity "(Gross KW!):

1149

7.

Maximr.ml Dependable Capacity (Net MWe) :

1104 e

50-311 rx:x:::KET NJ.: _________ _

CATE : September 10, 1980 CXM?LE'.l'ED BY:

L. K. Miller

~:

609-365-7000 X507

a. If Changes Occur in Capacity Ratings (Ite!!S Nutti:er 3 'lllrcugh 7) Since Last Report, Give Reason:

NONE

9.

Power Level To Which Pastricted, If Arr:/ (Net ?fie):

5% Thermal

10.

Reasons For Restrictions, If Aey:

Pending successful *completion of low power physics and natural.. circulation testing programs.

'!bis lblth Year to Date Ctmll.ati ve 744 3,240 3,240 ll. Hours In Reporting Period

12.

NUntier Of Hours Reactor Was Critical 268.2 268.2 268.2 l3.

Reactor Reserve. Shutcbm !burs 0

0 0

14.

Hours Generator On-Line.

0 0

0

15. Unit Reserve Shutdown Hours 0

0

16.

GJ:Oss 'llleJ:mal Energy Generated (!-fiH) 0 0

17.

GJ:Oss Electrical Energy Generated (mli) 0 0

0

18.

Net Electrical Energy Generated (M'IH) 0 0

0

19. Unit Service Factor 0

0 0

20. Unit Availahiljty Factor 0

0 0

21. Unit Capacity Factor (Using MOC Net) 0
o.

0

22. Unit Capacity Factor (Using DER Net) 0 0

0

23. Unit Forced Ol.ttage Rate 0

0 0

24.

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

25. If Shut Down At End of Report Period! Estimated Ila.te of Startup: ------------------
26.

Units In Test Status (Prior tc Camercial Operation) :

8-l-7.R2 Pg.3 of 6 INITIAL CRITICALITY INITIAL ~CI'IY

~

OPERATION Forecast 6/30/80 9/01/80 N/A Achieved

  • 8/02/8o N/A N/A

_ _J

NJ.

1 DATE F: Forced S:

Scheduled Page 4 of 6 B-1-7.Rl TYPE1 2

UNIT SllUTIXMNS l\\ND PCMER REOOcrIONS REPORI' MJlmI August 1980 ME.l'llOD OF OORATIOO

~

SllUITI~

(11.XJRS) ln'IN REAC'IOR

. Reason:

A-Equipment Failure(Explain)

B-Maintenance or Test C-Refueling trRegulatory Restriction LICENSE EVEN!'

REPORI' I E--Operator Training & License Examination F-J\\dministrative

~ational Error(Explain)

H-other (Explain)

SYSTEM CXMPOOENl' CODE4 CODES 3

Method:

1-Manual 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4

50-311 DOCKET NO.:~~~~~~~~~~

UNIT 'NAME:

Salem 112 DATE:

September 10' 198 0 COMPLETED BY: L. K. Miller

~~~~~~~~~~

TELEPHONE:

609-365-7000 X507 CAUSE 1\\ND CORRECI'IVE ACTION TO PREVENT RIDJRRENCE N/A Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREI}-0161) 5 Exhibit 1-Sane Source

-MAJdR PLANT MODIFICATI.

REPORT MONTH August l

~~~~~~~~~~~

  • DCR NO.

PRINCIPLE SYSTEM 2ET-0630 Leak Detection 2EC-0800 Lighting 2EC-0821 Structural 2EC-0957 Radiation Monitoring 2ET-0970 Inverters 2EC-0987 Control Air 2SC-0162 Waste Disposal

  • DESIGN CHANGE REQUEST 8-1-7.Rl Liquid System DOCKET NO.:

50-311 UNIT N.41l:

Salem t/2 DATE:

September 10, 1980 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 SUBJECT Data Required to Satisfy NRC Add Two Lights in Parking Let Add 4" cp Core Bore -

TGA Modify 2Rl8 Sampler Tubing Perform E-154 Test Add 1-1/2" Check Valve Resin Decant Filter Pg. 5 of 6

50-311 MAJOR PLANT MODIFICAT.S REPORT MONTH August 1980 DOCKET NO.:

UNIT ~:

DATE:

Salem 112 September 10, 1980

  • DCR NO.

2ET-0630 2EC-0800 2EC-0821 2EC-0957 2ET-0970 2EC-0987 2:SC-0162 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 10CFRS0. 5 9.

SAFETY EVALUATION The purpose of this DCR is the accumulation of data for the refinement of the Salem Leak Detectio_n Curves.

No change to any system or operating procedure is required.

This DCR does not impact any safety related system.

Data will be acquired from equipment already installed at Salem.

This DCR covers the addition of two lighting standards in the parking lot.

This DCR will not affect any safety function of the system involved.

The proposed changes do not involve any of the criteria associated with an unresolved safety question.

The addition of a 4" 0 Core Bare Hole in the north exterior stair.: of the T.G.A. will not require a change to the SAR or Technical Specifications and will not present an unreviewed safety question.

There is no change in the fire safety features of the station.

Change required to assure that radiation monitor: -performs as intended..

by design.

The function of the monitor.has not :*been.changed.

No safety analysis are affected.

No fire hazard is created - just adding process tubing to radiation sampler.

Penetration through fire barriers will be resealed to maintain fire protection requirements.

This procedure improves maintenance -- does not affect design.

The additional check valve and downstream piping will be Seismic Class I.

This new flow path will not permit flow from safety related header to non safety related.

This DCR does not present an unreviewed safety question and is in no way related uo any safety related system.

Its operability is not essential for the operation or shutdown of the plant.

Pa.ge 6 of 6

  • DES!GN CHANGE REQUEST