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{{#Wiki_filter:( I DAILY UNIT POWER LE .. Completed by: Mike Morroni Month January 1995 Day Average Daily Power Level (MWe-NET) 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 P. 8.1-7 Rl 9502210277 950214 PDR ADOCK 05000311 R PDR Docket No.: 50-311 Unit Name: Salem #2 Date: 02-10-95 Telephone:
{{#Wiki_filter:~RAGE DAILY UNIT POWER LE. .
339-2122 Day Average Daily Power Level (MWe-NET) 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 OPERATING DATA REPORT Docket No: 50-311 Date: 02/10/95 Completed.
Docket No.:    50-311 Unit Name:    Salem #2 Date:          02-10-95 Completed by:     Mike Morroni                     Telephone:    339-2122 Month     January     1995 Day Average Daily Power Level             Day Average Daily Power Level (MWe-NET)                              (MWe-NET) 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 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
by: Mike Morroni Telephone:
(  9502210277 950214 I  PDR ADOCK 05000311 R               PDR
339-2122 Operating Status 1. Unit Name Salem No. 2 Notes 2. Reporting Period January 1995 3. Licensed Thermal Power (MWt) 3411 4. Nameplate Rating (Gross MWe) 1170 5. Design Electrical Rating (Net MWe) 1115 6. Maximum Dependable Capacity(Gross MWe) 1149 7. Maximum Dependable Capacity (Net MWe) 1106 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA 9. Power Level to Which Restricted, if any (Net MWe) NIA 10. Reasons for Restrictions, if any
 
: 11. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown
                        ~      OPERATING DATA REPORT ~
: 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) Gross Elec. Energy Generated (MWH) 18. Net Elec. Energy Gen. (MWH) 19. Unit Service Factor 20. Unit Availability Factor 21. Unit Capacity Factor (using MDC Net) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate This Month 744 0 0 0 0 0 0 -17867 0 0 0 0 0 Year to Date Cumulative 744 116617 0 75615.2 0 0 0 72967.9 0 0 0 180973784.2 0 76450008 -17867 72705677 0 62.6 0 62.6 0 56.4 0 55.9 0 21. 8 24. Shutdowns scheduled over next 6 months (type, date and duration of each) We are presently in a maintenance outage. 25. If shutdown at end of Report Period, Estimated Date of Startup: 2 12 95. 8-1-7.R2 NO. DATE 2078 1-1-95 1 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 s 744 c UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JANUARY 1995 METHOD OF SHUTTING LICENSE DOWN EVENT REACTOR REPORT # 4 --------RC SYSTEM CODE 4 2 3 Reason A-Equipment Failure (explain)
Docket No:   50-311 Date:         02/10/95 Completed. by:   Mike Morroni                       Telephone:   339-2122 Operating Status
B-Maintenance or Test C-Refueling D-Requlatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)
: 1. Unit Name                         Salem No. 2     Notes
H-Other (Explain)
: 2. Reporting Period               January     1995
Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther COMPONENT CODE 5 DOCKET NO.:
: 3. Licensed Thermal Power (MWt)               3411
UNIT NAME: Salem #2 DATE: 2-10-95 COMPLETED BY: Mike Morroni TELEPHONE:
: 4. Nameplate Rating (Gross MWe)               1170
339-5142 L CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE FUELXX NORMAL REFUELING 4 Exhibit G -Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File CNUREG-0161) 5 Exhibit 1 -Same Source * * 
: 5. Design Electrical Rating (Net MWe)         1115
*
: 6. Maximum Dependable Capacity(Gross MWe) 1149
* 10CFR50.59 EVALUATIONS MONTH: JANUARY 1995 DOCKET NO: UNIT NAME: 50-311 SALEM2 02/10/95 R.HELLER 609-339-5162 DATE: COMPLETED BY: TELEPHONE:
: 7. Maximum Dependable Capacity (Net MWe) 1106
The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
: 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason     NA
The Station Operations Review Committee has reviewed and concurs with these evaluations.
: 9. Power Level to Which Restricted, if any (Net MWe)             NIA
: 1. Design Change Packages (DCP) 2EX-2139, Pkg. 1 2EE-0077, Pkg. 1 "Temporary Load Balance Test for 2PR5 Discharge Piping" Rev. 0 -The objectives of this test are to record data and ascertain the impact of the variation in discharge piping loading upon 2PR5 seat leakage at NOP/NOT conditions.
: 10. Reasons for Restrictions, if any   ~~~~N~A=--~~~~~~~~~~~~~~-
This Month    Year to Date    Cumulative
: 11. Hours in Reporting Period               744          744          116617
: 12. No. of Hrs. Rx. was Critical             0            0          75615.2
: 13. Reactor Reserve Shutdown Hrs~            0            0              0
: 14. Hours Generator On-Line                   0            0          72967.9
: 15. Unit Reserve Shutdown Hours               0            0              0
: 16. Gross Thermal Energy Generated (MWH)                             0            0      180973784.2 Gross Elec. Energy Generated (MWH)                             0            0      76450008
: 18. Net Elec. Energy Gen. (MWH)         -17867          -17867      72705677
: 19. Unit Service Factor                       0            0            62.6
: 20. Unit Availability Factor                 0            0            62.6
: 21. Unit Capacity Factor (using MDC Net)                     0            0            56.4
: 22. Unit Capacity Factor (using DER Net)                     0            0            55.9
: 23. Unit Forced Outage Rate                   0             0           21. 8
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
We are presently in a maintenance outage.
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
2 12 95.
8-1-7.R2
 
UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JANUARY 1995                                               DOCKET NO.: -'5::..:0:....-..::.27:....:2=-----
UNIT NAME: Salem #2 DATE: 2-10-95 COMPLETED BY: Mike Morroni TELEPHONE: 339-5142 METHOD OF SHUTTING        LICENSE                                                                                        L DURATION                      DOWN            EVENT            SYSTEM    COMPONENT              CAUSE AND CORRECTIVE ACTION NO.        DATE      TYPE 1      (HOURS)      REASON 2      REACTOR        REPORT #        CODE 4    CODE 5                    TO PREVENT RECURRENCE 2078    1-1-95    s          744            c              4              --------        RC        FUELXX         NORMAL REFUELING
* 1              2                                                        3                        4                                 5 F:  Forced      Reason                                                  Method:                  Exhibit G - Instructions         Exhibit 1 - Same S:  Scheduled  A-Equipment Failure (explain)                            1-Manual                  for Preparation of Data           Source B-Maintenance or Test                                    2-Manual Scram            Entry Sheets for Licensee
* C-Refueling                                              3-Automatic Scram        Event Report CLER) File D-Requlatory Restriction                                4-Continuation of        CNUREG-0161)
E-Operator Training & License Examination                  Previous Outage F-Administrative                                        5-Load Reduction G-Operational Error (Explain)                            9-0ther H-Other (Explain)
* 10CFR50.59 EVALUATIONS
* DOCKET NO:            50-311 MONTH: JANUARY 1995                                   UNIT NAME:           SALEM2 DATE:        02/10/95 COMPLETED BY:              R.HELLER TELEPHONE:            609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations.
: 1. Design Change Packages (DCP) 2EX-2139, Pkg. 1         "Temporary Load Balance Test for 2PR5 Discharge Piping" Rev. 0 - The objectives of this test are to record data and ascertain the impact of the variation in discharge piping loading upon 2PR5 seat leakage at NOP/NOT conditions.
These results will be used to provide a basis for a potential future design change to piping supports so that discharge nozzle loads at the PR 3, 4 and 5 valves are minimized with the end result of achieving their task leak tight operation.
These results will be used to provide a basis for a potential future design change to piping supports so that discharge nozzle loads at the PR 3, 4 and 5 valves are minimized with the end result of achieving their task leak tight operation.
All of the conclusions of the UFSAR Chapter 15 licensing basis safety analysis remain valid and thus the margin of safety is not reduced. The pressurizer safety valves (2PR3, 4 &5) will be operable with the required lift setpoints along with the PORV s (2PR1 & 2) during the Mode 3 operation. (SORC 95-002) "2PR 3, 4 and 5 Valve Bonnet Leak-Off Line Elimination" Rev. 0 -The proposed modification entails decoupling the 3/4" valve bonnet leak-off lines from the valve bonnets on the Pressurizer Safety Relie(Valves 2PR3, 4 and 5. The purpose of this change is to alleviate the potential for inducing stresses from the leak-off piping system into the valve bonnets/bodies.
All of the conclusions of the UFSAR Chapter 15 licensing basis safety analysis remain valid and thus the margin of safety is not reduced. The pressurizer safety valves (2PR3, 4 &5) will be operable with the required lift setpoints along with the PORVs (2PR1 & 2) during the Mode 3 operation.
Operability of the Pressurizer Safety Relief valves is required by Technical Specifications to provide RCS overpressure protection.
(SORC 95-002) 2EE-0077, Pkg. 1      "2PR 3, 4 and 5 Valve Bonnet Leak-Off Line Elimination" Rev. 0 - The proposed modification entails decoupling the 3/4" valve bonnet leak-off lines from the valve bonnets on the Pressurizer Safety Relie(Valves 2PR3, 4 and 5. The purpose of this change is to alleviate the potential for inducing stresses from the leak-off piping system into the valve bonnets/bodies. Operability of the Pressurizer Safety Relief valves is required by Technical Specifications to provide RCS overpressure protection. The proposed modification represents only a minor configuration change to enhance the long term reliability of the safety relief valves. Since the vent path from the valve bonnets remains unchanged, the design function of the Pressurizer Safety Relief Valves is not affected. There will be no impact on
The proposed modification represents only a minor configuration change to enhance the long term reliability of the safety relief valves. Since the vent path from the valve bonnets remains unchanged, the design function of the Pressurizer Safety Relief Valves is not affected.
* 10CFR50.59 EVALUATIONS
There will be no impact on
* DOCKET NO:          50-311 MONTH: JANUARY 1995                                   UNIT NAME:           SALEM 2 DATE:        02/10/95 COMPLETED BY:              R.HELLER TELEPHONE:          609-339-5162 the margin of safety as defined in the basis for any Technical Specification. (SORC 95-004)
*
: 2. Temporary Modifications (T-Mods) 95-005               "Pressurizer Safety Relief Valve Piping Instrumentation" Rev. 0 - The purpose of this T-Mod is to provide instrumentation (displacement transducers, strain gauges, thermocouples) downstream of the discharge flanges of valves 2PR3, 4 and 5 and recording system response using a separate, dedicated data acquisition system. The acceptance criteria for design basis accidents will continue to be met, and the existing margins of safety established by UFSAR safety analyses will not be affected. This proposal will not exceed the design limits of any systems, components or structures. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
* 10CFR50.59 EVALUATIONS MONTH: JANUARY 1995 DOCKET NO: UNIT NAME: 50-311 SALEM 2 02/10/95 R.HELLER 609-339-5162 DATE: COMPLETED BY: TELEPHONE:
(SORC 95-004) 95-013              "2SJ7, Cut and Cap Piping Downstream of Valve to Eliminate Leakage" Rev. 0 - The purpose of this T-Mod is to cut and cap the piping downstream of valve 2SJ7 to eliminate leakage. This will eliminate the contribution of this piping to the unidentified RCS leak rates. The proposed change does not affect the operability or availability of the Emergency Core Cooling System (ECCS) subsystem or the ECCS in general. The piping integrity is still maintained. The acceptance criteria for design basis accidents will continue to be met, and the existing margin of safety as defined by the Technical Specifications will not be affected. (SORC 95-012)
the margin of safety as defined in the basis for any Technical Specification. (SORC 95-004) 2. Temporary Modifications (T-Mods) 95-005 95-013 "Pressurizer Safety Relief Valve Piping Instrumentation" Rev. 0 -The purpose of this T-Mod is to provide instrumentation (displacement transducers, strain gauges, thermocouples) downstream of the discharge flanges of valves 2PR3, 4 and 5 and recording system response using a separate, dedicated data acquisition system. The acceptance criteria for design basis accidents will continue to be met, and the existing margins of safety established by UFSAR safety analyses will not be affected.
* 10CFR50.59 EVALUATIONS                                 DOCKET NO:          50-311 MONTH: JANUARY 1995                                     UNIT NAME:         SALEM2 SUPPLEMENT                                                      DATE:       02/10/95 COMPLETED BY:             R. HELLER TELEPHONE:          609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed .and concurs with these evaluations.
This proposal will not exceed the design limits of any systems, components or structures.
: 1. Design change Packages 2EC-3025, Pkg. 1       ''New Operator's Ready Room" Rev. 0 - The purpose of this design change is to convert an existing janitors closet and maintenance room at elevation 122' -0" in the Unit 2 auxiliary Building into a new Operators Ready Room.
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 95-004) "2SJ7, Cut and Cap Piping Downstream of Valve to Eliminate Leakage" Rev. 0 -The purpose of this T-Mod is to cut and cap the piping downstream of valve 2SJ7 to eliminate leakage. This will eliminate the contribution of this piping to the unidentified RCS leak rates. The proposed change does not affect the operability or availability of the Emergency Core Cooling System (ECCS) subsystem or the ECCS in general. The piping integrity is still maintained.
These changes do not affect the allowable design limits addressed in the Technical Specifications. The Control Area Air Conditioning System (CAACS) multipurpose system is not discussed in either the Unit 1 or Unit 2 Technical Specifications and the changes involved do not conflict with or have any bearing on the Emergency Air Conditioning System or the Control Room pressure requirements. The changes to the fire detection system do not affect the bases for fire detection instrumentation addressed in the Technical Specifications. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 90-153) 2SA-00101, Pkg. 1     "Chilled Water and Service Water Update" Rev. 0 - This as-built DCP updates service water and chilled water drawings to bring them into conformance with the actual plant design. Discrepancies were found in an SRG HVAC review documented in NSR REC SRGC 87-084, Task 36 and 37 dated 8/21/87. This DCP will make a number of reference changes in order to add consistency between the drawings and make the drawings easier to read; document removal of analog temperature devices and change component ID for temperature test connections which exist
The acceptance criteria for design basis accidents will continue to be met, and the existing margin of safety as defined by the Technical Specifications will not be affected. (SORC 95-012)
* 10CFR50.59 EVALUATIONS
* 10CFR50.59 EVALUATIONS MONTH: JANUARY 1995 SUPPLEMENT DOCKET NO: UNIT NAME: DATE: 50-311 SALEM2 02/10/95 COMPLETED BY: TELEPHONE:
* DOCKET NO:          50-311 MONTH: JANUARY 1995                                     UNIT NAME:           SALEM 2 SUPPLEMENT                                                    DATE:         02/10/95 COMPLETED BY:             R. HELLER TELEPHONE:          609-339-5162 (Cont'd) in the field but were not documented on the P&ID drawings or instrument schematics; and will document the removal of air regulators which did not exist in field. The proposal does not reduce the margin of safety as defined in the bases for any Technical Specification since the changes documented in this DCP are not described in the Salem Technical Specifications. The changes which are documented in this DCP are sound engineering changes and serve only to increase the overall margin of safety since the design is better. (SORC 90-03 5)
R. HELLER 609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59.
: 2.       Temporary Modifications (T-Mods) 90-105             "Ductwork Access Door Modifications" Rev. 0 - This T-Mod allows the opening of an access door on the riser to provide for redirection of air from the Containment Ring Duct, for personnel safety and comfort during work on the 22 Containment Fan Coil Unit (CFCU) motor replacement.
The Station Operations Review Committee has reviewed .and concurs with these evaluations.
This T-Mod also allows for installation ofherculite over the scaffolding to form a tent. This T-Mod does not impact the operability of any of the CFCUs. The safety function of the system is unchanged and unaffected by the installation of this T-Mod. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.
: 1. Design change Packages 2EC-3025, Pkg. 1 ''New Operator's Ready Room" Rev. 0 -The purpose of this design change is to convert an existing janitors closet and maintenance room at elevation 122' -0" in the Unit 2 auxiliary Building into a new Operators Ready Room. These changes do not affect the allowable design limits addressed in the Technical Specifications.
(SORC 90-130)
The Control Area Air Conditioning System (CAACS) multipurpose system is not discussed in either the Unit 1 or Unit 2 Technical Specifications and the changes involved do not conflict with or have any bearing on the Emergency Air Conditioning System or the Control Room pressure requirements.
 
The changes to the fire detection system do not affect the bases for fire detection instrumentation addressed in the Technical Specifications.
REFUELING INFORMATION
There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 90-153) 2SA-00101, Pkg. 1 "Chilled Water and Service Water Update" Rev. 0 -This as-built DCP updates service water and chilled water drawings to bring them into conformance with the actual plant design. Discrepancies were found in an SRG HV AC review documented in NSR REC SRGC 87-084, Task 36 and 37 dated 8/21/87. This DCP will make a number of reference changes in order to add consistency between the drawings and make the drawings easier to read; document removal of analog temperature devices and change component ID for temperature test connections which exist
* DOCKET NO:           50-311 MONTH: JANUARY 1995                                   UNIT NAME:         SALEM2 DATE:         02/10/95 COMPLETED BY:            R.HELLER TELEPHONE:          609-339-5162 MONTH: JANUARY 1995
*
: 1. Refueling information has changed from last month: YESJ_NO _ _
* 10CFR50.59 EVALUATIONS MONTH: JANUARY 1995 SUPPLEMENT DOCKET NO: UNIT NAME: DATE: 50-311 SALEM 2 02/10/95 (Cont'd) COMPLETED BY: TELEPHONE:
: 2. Scheduled date for next refueling: October 14. 1994
R. HELLER 609-339-5162 in the field but were not documented on the P&ID drawings or instrument schematics; and will document the removal of air regulators which did not exist in field. The proposal does not reduce the margin of safety as defined in the bases for any Technical Specification since the changes documented in this DCP are not described in the Salem Technical Specifications.
: 3. Scheduled date for restart following refueling: February 14. 1995
The changes which are documented in this DCP are sound engineering changes and serve only to increase the overall margin of safety since the design is better. (SORC 90-03 5) 2. Temporary Modifications (T-Mods) 90-105 "Ductwork Access Door Modifications" Rev. 0 -This T-Mod allows the opening of an access door on the riser to provide for redirection of air from the Containment Ring Duct, for personnel safety and comfort during work on the 22 Containment Fan Coil Unit (CFCU) motor replacement.
: 4. a. Will Technical Specification changes or other license amendments be required?
This T-Mod also allows for installation ofherculite over the scaffolding to form a tent. This T-Mod does not impact the operability of any of the CFCU s. The safety function of the system is unchanged and unaffected by the installation of this T-Mod. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 90-130)
YES       NO ____x_
* REFUELING INFORMATION MONTH: JANUARY 1995 MONTH: JANUARY 1995 DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
NOT DETERMINED TO DATE - -
50-311 SALEM2 02/10/95 R.HELLER 609-339-5162
: b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
: 1. Refueling information has changed from last month: YES J_NO __ 2. Scheduled date for next refueling:
October 14. 1994 3. Scheduled date for restart following refueling:
February 14. 1995 4. a. Will Technical Specification changes or other license amendments be required?
YES NO ____x_ NOT DETERMINED TO DATE --b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES_X_NO If no, when is it scheduled?
YES_X_NO If no, when is it scheduled?
: 5. Scheduled date(s) for submitting proposed licensing action:
: 5. Scheduled date(s) for submitting proposed licensing action: ---~N~/~A.......__ __
__ _ 6. Important licensing considerations associated with refueling:
: 6. Important licensing considerations associated with refueling:
: 7. Number ofFuel Assemblies:
: 7. Number ofFuel Assemblies:
: a. Incore b. In Spent Fuel Storage 8. Present licensed spent fuel storage capacity:
: a. Incore                                                                 193
Future spent fuel storage capacity:
: b. In Spent Fuel Storage                                                   556
: 9. Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
: 8. Present licensed spent fuel storage capacity:                             1632 Future spent fuel storage capacity:                                       1632
8-l-7.R4 193 556 1632 1632 March2012 
: 9. Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:               March2012 8-l-7.R4
*
 
                      *
* SALEM GENERATING STATION MONTHLY OPERATING  
* SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
  -UNIT 2 JANUARY 1995 SALEM UNIT NO. 2 The Unit remained shutdown throughout the entire period as the 2R8 Refueling Outage activities continued.
  - UNIT 2 JANUARY 1995 SALEM UNIT NO. 2 The Unit remained shutdown throughout the entire period as the 2R8 Refueling Outage activities continued.
* PORV & SAFETY VALVE ACTUATIONS MONTH: JANUARY 1995
 
* DOCKET NO: UNIT NAME: DATE: COMPLETED BY: TELEPHONE:
PORV & SAFETY VALVE ACTUATIONS
50-311 SALEM2 02/10/95 R. HELLER 609-339-5162 I::,:,:,*,:,*,*,*,*,*,*,**,::,:*,:,*,:,:,:,:,*,*,:,:,:,:,:,:,::,**,:*,',:,**,:,:,:,:,:,*,:,*,*.:.*,:.*.**,:,:,*,:,:,*,:,*,*,*,*.*
* DOCKET NO:
.. *.*.:.:*,*,*,*,*,*.*.:.:.:*,:,:,:,*,*,:,*,*,:,:,*,*,*,:,*,:,*,:,*,:,:,:,:
* 50-311 MONTH: JANUARY 1995                                                                                                                                                                                                                                                                                                                                                                                                                        UNIT NAME:                                                                               SALEM2 DATE:                                                             02/10/95 COMPLETED BY:                                                                                            R. HELLER TELEPHONE:                                                                                  609-339-5162
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-
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::=:=:. ::::::*:*:*::
PRESSURIZER OVERPRESSURE PROTECTION SYSTEM ACTUATION On January 25, 1995, upon securing the only operating Reactor Coolant Pump (RCP), the Pressurizer Overpressure Protection System (POPS) actuated. The POPS sensed an apparent pressure increase (or spike) when No. 21 RCP was secured. Reactor Coolant System temperature was at l 80&deg;F and a pressure of 350 psig when the POPS actuated. The setpoint for the POPS relief valves (PRl
*.*.**: .... *:::::::::::::::;::::::-
                                                                            & PR2) is 375 psig. Both valves were open for about 20 to 30 seconds. RCS pressure was being maintained by a bubble in the Pressurizer. No change was seen in the pressurizer level or any increase in the Pressurizer Relief Tank (PRT) level.
.. *:::::.:::::::::::::::::-:-:
Wide range reactor coolant pressure indication increased from 350 psig to 368 psig after No. 21 RCP was secured.}}
:::::;:;:::::;:;:::-:-:-:-:-*  
] PRESSURIZER OVERPRESSURE PROTECTION SYSTEM ACTUATION On January 25, 1995, upon securing the only operating Reactor Coolant Pump (RCP), the Pressurizer Overpressure Protection System (POPS) actuated.
The POPS sensed an apparent pressure increase (or spike) when No. 21 RCP was secured. Reactor Coolant System temperature was at l 80&deg;F and a pressure of 350 psig when the POPS actuated.
The setpoint for the POPS relief valves (PRl & PR2) is 375 psig. Both valves were open for about 20 to 30 seconds. RCS pressure was being maintained by a bubble in the Pressurizer.
No change was seen in the pressurizer level or any increase in the Pressurizer Relief Tank (PRT) level. Wide range reactor coolant pressure indication increased from 350 psig to 368 psig after No. 21 RCP was secured.}}

Revision as of 10:17, 21 October 2019

Monthly Operating Rept for Jan 1995 for Salem Unit 2
ML18101A548
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/31/1995
From: Morroni M
Public Service Enterprise Group
To:
Shared Package
ML18101A545 List:
References
NUDOCS 9502210277
Download: ML18101A548 (10)
v • d • e


Text

~RAGE DAILY UNIT POWER LE. .

Docket No.: 50-311 Unit Name: Salem #2 Date: 02-10-95 Completed by: Mike Morroni Telephone: 339-2122 Month January 1995 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 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 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

( 9502210277 950214 I PDR ADOCK 05000311 R PDR

~ OPERATING DATA REPORT ~

Docket No: 50-311 Date: 02/10/95 Completed. by: Mike Morroni Telephone: 339-2122 Operating Status

1. Unit Name Salem No. 2 Notes
2. Reporting Period January 1995
3. Licensed Thermal Power (MWt) 3411
4. Nameplate Rating (Gross MWe) 1170
5. Design Electrical Rating (Net MWe) 1115
6. Maximum Dependable Capacity(Gross MWe) 1149
7. Maximum Dependable Capacity (Net MWe) 1106
8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason NA
9. Power Level to Which Restricted, if any (Net MWe) NIA
10. Reasons for Restrictions, if any ~~~~N~A=--~~~~~~~~~~~~~~-

This Month Year to Date Cumulative

11. Hours in Reporting Period 744 744 116617
12. No. of Hrs. Rx. was Critical 0 0 75615.2
13. Reactor Reserve Shutdown Hrs~ 0 0 0
14. Hours Generator On-Line 0 0 72967.9
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 180973784.2 Gross Elec. Energy Generated (MWH) 0 0 76450008
18. Net Elec. Energy Gen. (MWH) -17867 -17867 72705677
19. Unit Service Factor 0 0 62.6
20. Unit Availability Factor 0 0 62.6
21. Unit Capacity Factor (using MDC Net) 0 0 56.4
22. Unit Capacity Factor (using DER Net) 0 0 55.9
23. Unit Forced Outage Rate 0 0 21. 8
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

We are presently in a maintenance outage.

25. If shutdown at end of Report Period, Estimated Date of Startup:

2 12 95.

8-1-7.R2

UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH JANUARY 1995 DOCKET NO.: -'5::..:0:....-..::.27:....:2=-----

UNIT NAME: Salem #2 DATE: 2-10-95 COMPLETED BY: Mike Morroni TELEPHONE: 339-5142 METHOD OF SHUTTING LICENSE L DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION NO. DATE TYPE 1 (HOURS) REASON 2 REACTOR REPORT # CODE 4 CODE 5 TO PREVENT RECURRENCE 2078 1-1-95 s 744 c 4 -------- RC FUELXX NORMAL REFUELING

  • 1 2 3 4 5 F: Forced Reason Method: Exhibit G - Instructions Exhibit 1 - Same S: Scheduled A-Equipment Failure (explain) 1-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee
  • C-Refueling 3-Automatic Scram Event Report CLER) File D-Requlatory Restriction 4-Continuation of CNUREG-0161)

E-Operator Training & License Examination Previous Outage F-Administrative 5-Load Reduction G-Operational Error (Explain) 9-0ther H-Other (Explain)

  • DOCKET NO: 50-311 MONTH: JANUARY 1995 UNIT NAME: SALEM2 DATE: 02/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed and concurs with these evaluations.
1. Design Change Packages (DCP) 2EX-2139, Pkg. 1 "Temporary Load Balance Test for 2PR5 Discharge Piping" Rev. 0 - The objectives of this test are to record data and ascertain the impact of the variation in discharge piping loading upon 2PR5 seat leakage at NOP/NOT conditions.

These results will be used to provide a basis for a potential future design change to piping supports so that discharge nozzle loads at the PR 3, 4 and 5 valves are minimized with the end result of achieving their task leak tight operation.

All of the conclusions of the UFSAR Chapter 15 licensing basis safety analysis remain valid and thus the margin of safety is not reduced. The pressurizer safety valves (2PR3, 4 &5) will be operable with the required lift setpoints along with the PORVs (2PR1 & 2) during the Mode 3 operation.

(SORC 95-002) 2EE-0077, Pkg. 1 "2PR 3, 4 and 5 Valve Bonnet Leak-Off Line Elimination" Rev. 0 - The proposed modification entails decoupling the 3/4" valve bonnet leak-off lines from the valve bonnets on the Pressurizer Safety Relie(Valves 2PR3, 4 and 5. The purpose of this change is to alleviate the potential for inducing stresses from the leak-off piping system into the valve bonnets/bodies. Operability of the Pressurizer Safety Relief valves is required by Technical Specifications to provide RCS overpressure protection. The proposed modification represents only a minor configuration change to enhance the long term reliability of the safety relief valves. Since the vent path from the valve bonnets remains unchanged, the design function of the Pressurizer Safety Relief Valves is not affected. There will be no impact on

  • DOCKET NO: 50-311 MONTH: JANUARY 1995 UNIT NAME: SALEM 2 DATE: 02/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 the margin of safety as defined in the basis for any Technical Specification. (SORC 95-004)
2. Temporary Modifications (T-Mods)95-005 "Pressurizer Safety Relief Valve Piping Instrumentation" Rev. 0 - The purpose of this T-Mod is to provide instrumentation (displacement transducers, strain gauges, thermocouples) downstream of the discharge flanges of valves 2PR3, 4 and 5 and recording system response using a separate, dedicated data acquisition system. The acceptance criteria for design basis accidents will continue to be met, and the existing margins of safety established by UFSAR safety analyses will not be affected. This proposal will not exceed the design limits of any systems, components or structures. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 95-004)95-013 "2SJ7, Cut and Cap Piping Downstream of Valve to Eliminate Leakage" Rev. 0 - The purpose of this T-Mod is to cut and cap the piping downstream of valve 2SJ7 to eliminate leakage. This will eliminate the contribution of this piping to the unidentified RCS leak rates. The proposed change does not affect the operability or availability of the Emergency Core Cooling System (ECCS) subsystem or the ECCS in general. The piping integrity is still maintained. The acceptance criteria for design basis accidents will continue to be met, and the existing margin of safety as defined by the Technical Specifications will not be affected. (SORC 95-012)

  • 10CFR50.59 EVALUATIONS DOCKET NO: 50-311 MONTH: JANUARY 1995 UNIT NAME: SALEM2 SUPPLEMENT DATE: 02/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 The following items were evaluated in accordance with the provisions of the Code of Federal Regulations 10CFR50.59. The Station Operations Review Committee has reviewed .and concurs with these evaluations.
1. Design change Packages 2EC-3025, Pkg. 1 New Operator's Ready Room" Rev. 0 - The purpose of this design change is to convert an existing janitors closet and maintenance room at elevation 122' -0" in the Unit 2 auxiliary Building into a new Operators Ready Room.

These changes do not affect the allowable design limits addressed in the Technical Specifications. The Control Area Air Conditioning System (CAACS) multipurpose system is not discussed in either the Unit 1 or Unit 2 Technical Specifications and the changes involved do not conflict with or have any bearing on the Emergency Air Conditioning System or the Control Room pressure requirements. The changes to the fire detection system do not affect the bases for fire detection instrumentation addressed in the Technical Specifications. There is no reduction in the margin of safety as defined in the basis for any Technical Specification. (SORC 90-153) 2SA-00101, Pkg. 1 "Chilled Water and Service Water Update" Rev. 0 - This as-built DCP updates service water and chilled water drawings to bring them into conformance with the actual plant design. Discrepancies were found in an SRG HVAC review documented in NSR REC SRGC 87-084, Task 36 and 37 dated 8/21/87. This DCP will make a number of reference changes in order to add consistency between the drawings and make the drawings easier to read; document removal of analog temperature devices and change component ID for temperature test connections which exist

  • DOCKET NO: 50-311 MONTH: JANUARY 1995 UNIT NAME: SALEM 2 SUPPLEMENT DATE: 02/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162 (Cont'd) in the field but were not documented on the P&ID drawings or instrument schematics; and will document the removal of air regulators which did not exist in field. The proposal does not reduce the margin of safety as defined in the bases for any Technical Specification since the changes documented in this DCP are not described in the Salem Technical Specifications. The changes which are documented in this DCP are sound engineering changes and serve only to increase the overall margin of safety since the design is better. (SORC 90-03 5)
2. Temporary Modifications (T-Mods)90-105 "Ductwork Access Door Modifications" Rev. 0 - This T-Mod allows the opening of an access door on the riser to provide for redirection of air from the Containment Ring Duct, for personnel safety and comfort during work on the 22 Containment Fan Coil Unit (CFCU) motor replacement.

This T-Mod also allows for installation ofherculite over the scaffolding to form a tent. This T-Mod does not impact the operability of any of the CFCUs. The safety function of the system is unchanged and unaffected by the installation of this T-Mod. There is no reduction in the margin of safety as defined in the basis for any Technical Specification.

(SORC 90-130)

REFUELING INFORMATION

  • DOCKET NO: 50-311 MONTH: JANUARY 1995 UNIT NAME: SALEM2 DATE: 02/10/95 COMPLETED BY: R.HELLER TELEPHONE: 609-339-5162 MONTH: JANUARY 1995
1. Refueling information has changed from last month: YESJ_NO _ _
2. Scheduled date for next refueling: October 14. 1994
3. Scheduled date for restart following refueling: February 14. 1995
4. a. Will Technical Specification changes or other license amendments be required?

YES NO ____x_

NOT DETERMINED TO DATE - -

b. Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES_X_NO If no, when is it scheduled?

5. Scheduled date(s) for submitting proposed licensing action: ---~N~/~A.......__ __
6. Important licensing considerations associated with refueling:
7. Number ofFuel Assemblies:
a. Incore 193
b. In Spent Fuel Storage 556
8. Present licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632
9. Date oflast refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: March2012 8-l-7.R4
  • SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 2 JANUARY 1995 SALEM UNIT NO. 2 The Unit remained shutdown throughout the entire period as the 2R8 Refueling Outage activities continued.

PORV & SAFETY VALVE ACTUATIONS

  • DOCKET NO:
  • 50-311 MONTH: JANUARY 1995 UNIT NAME: SALEM2 DATE: 02/10/95 COMPLETED BY: R. HELLER TELEPHONE: 609-339-5162

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  • .*.**:....*:::::::::::::::;::::::-..*:::::.:::::::::::::::::-:-: :::::;:;:::::;:;:::-:-:-:-:-* ]

PRESSURIZER OVERPRESSURE PROTECTION SYSTEM ACTUATION On January 25, 1995, upon securing the only operating Reactor Coolant Pump (RCP), the Pressurizer Overpressure Protection System (POPS) actuated. The POPS sensed an apparent pressure increase (or spike) when No. 21 RCP was secured. Reactor Coolant System temperature was at l 80°F and a pressure of 350 psig when the POPS actuated. The setpoint for the POPS relief valves (PRl

& PR2) is 375 psig. Both valves were open for about 20 to 30 seconds. RCS pressure was being maintained by a bubble in the Pressurizer. No change was seen in the pressurizer level or any increase in the Pressurizer Relief Tank (PRT) level.

Wide range reactor coolant pressure indication increased from 350 psig to 368 psig after No. 21 RCP was secured.

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