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{{#Wiki_filter:. Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit SEP 15 1997 LR-N970620 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating Report for August, 1997, is attached.
{{#Wiki_filter:Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit SEP 15 1997 LR-N970620 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn:     Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating Report for August, 1997, is attached.
RBK/tcp Enclosures C Mr. H. J. Miller General Man ger -Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 -----9709230*178 q7oa31 PDR ADOCK 05000272 R PDR The power is in your hands. \ I IUlll lllll lllll lllll lll\11111111111111  
I General Man ger -
*&&63&E* I 95-2168 REV. 6/94
Salem Operations RBK/tcp Enclosures C       Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046
.----------------------------------------------
                                                      \
-----------
    --- - -9709230*178 q7oa31 PDR   ADOCK 05000272 R                       PDR IIUlll lllll lllll lllll lll\11111111111111
-Refueling Information Month: August, 1997 Docket No. Unit Name: 50-272 Salem 1 Contact: Telephone:
                                                            *&&63&E*
R. B. Knieriem 609-339-1782 Month: August, 1997 1. Refueling information has changed from last month: Yes: No: X 2. Scheduled date for next refueling:
The power is in your hands.
To Be Determined
95-2168 REV. 6/94
: 3. Scheduled date for restart following refueling:
~ .
To Be Determined
 
: a. Will Technical Specification changes or other license amendments be required?
Refueling Information                               Docket No. 50-272 Month: August, 1997                                 Unit Name: Salem 1
Yes: X No: Not Determined to Date: b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
 
Yes: No: X If no, when is it scheduled?
==Contact:==
To be Determined
R. B. Knieriem Telephone: 609-339-1782 Month:   August, 1997
: 4. Scheduled date (s) for submitting proposed licensing action: To be Determined
: 1. Refueling information has changed from last month: Yes:     No: X
: 2. Scheduled date for next refueling:   To Be Determined Scheduled date for restart following refueling: To Be Determined
: 3. a. Will Technical Specification changes or other license amendments be required?
Yes: X   No: Not Determined to Date:
: b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
Yes:   No:   X   If no, when is it scheduled? To be Determined
: 4. Scheduled date (s)   for submitting proposed licensing action: To be Determined
: 5. Important licensing considerations associated with refueling:
: 5. Important licensing considerations associated with refueling:
: 6. Number of Fuel Assemblies:
: 6. Number of Fuel Assemblies:
: a. Incore: 0 b. In Spent Fuel Storage: 953 7. Present Licensed spent fuel storage capacity:
: a. Incore:                                                   0
1632 Future spent fuel storage capacity:
: b. In Spent Fuel Storage:                                 953
1632 8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
: 7. Present Licensed spent fuel storage capacity:             1632 Future spent fuel storage capacity:                       1632
April 2012 SALEM GENERATING STATION MONTHLY OPERATING  
: 8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:         April 2012
 
SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
  -UNIT 1 AUGUST 1997 SALEM UNIT 1 The unit is in a refueling and steam generator replacement outage and remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the unit will remain shutdown pending completion of the following actions:
  - UNIT 1 AUGUST 1997 SALEM UNIT 1 The unit is in a refueling and steam generator replacement outage and remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the unit will remain shutdown pending completion of the following actions:
* Appropriately address long standing equipment reliability and operability issues.
* Appropriately address long standing equipment reliability and operability issues.
* After the work is completed, conduct a restart readiness review to determine for ourselves the ability of the unit to operate in a safe, event free manner.
* After the work is completed, conduct a restart readiness review to determine for ourselves the ability of the unit to operate in a safe, event free manner.
* After the restart review, meet with the NRC and communicate the results of that review.
* After the restart review, meet with the NRC and communicate the results of that review.
DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:
 
50-272 Salem l 09/15/97 R. B. Knieriem (609) 339-1782  
DOCKET NO.: 50-272 UNIT: Salem l DATE: 09/15/97 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782


==SUMMARY==
==SUMMARY==
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT l GENERATING STATION MONTH AUGUST 1997 The following items completed during August 1997 have been evaluated to determine:
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT l GENERATING STATION MONTH     AUGUST 1997 The following items completed during August 1997 have been evaluated to determine:
: 1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or 2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or 3. If the margin of safety as defined in the basis for any technical specification is reduced. The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
: 1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or
Design Changes Summary of Safety Evaluations lEC-3310, Pkg. 1, Emergency Diesel Generator Low Lube Oil Temperature Setpoint Change. This design change revises the Emergency Diesel Generator (EDG) lube oil low temperature setpoint to 100°F. Raising the low lube oil temperature from 80°F to 100°F is conservative and will more promptly alert the operators of a failed heater. This design change does not negatively impact any accident response.
: 2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
: 3. If the margin of safety as defined in the basis for any technical specification is reduced.
----------
The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
lEC-3438, Pkg. 1, "A'' Emergency Diesel Generator Circuit Breaker Voltage Permissive Relay Installation and Indication Modifications.
Design Changes       Summary of Safety Evaluations lEC-3310, Pkg. 1, Emergency Diesel Generator Low Lube Oil Temperature Setpoint Change. This design change revises the Emergency Diesel Generator (EDG) lube oil low temperature setpoint to 100°F. Raising the low lube oil temperature from 80°F to 100°F is conservative and will more promptly alert the operators of a failed heater.
This design change installs two voltage sensing relays and an auxiliary relay to monitor the output voltage of the "A" Emergency Diesel Generator (EDG) . Contacts from the auxiliary relay replace the voltage permissive contact in the closing circuit of the main circuit breaker for the EDG. The setpoints of the voltage sensing relays are at a higher voltage than the previous relays and will prohibit the EDG main circuit breaker from closing when the EDG output is less than the required voltage. This design change also installs indicating lights on the generator control panel to identify when the voltage and speed permissives are satisfied.
This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
This design change does not negatively impact any accident response.
 
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
lEC-3438, Pkg. 1, "A'' Emergency Diesel Generator Circuit Breaker Voltage Permissive Relay Installation and Indication Modifications. This design change installs two voltage sensing relays and an auxiliary relay to monitor the output voltage of the "A" Emergency Diesel Generator (EDG) .
lEC-3401, Pkg. 1, Emergency Diesel Generator Starting Air & Turbo Boost System Upgrade. This design change upgrades the Starting Air and Turbo Boost system by the installation of stainless steel piping and components for corrosion resistance.
Contacts from the auxiliary relay replace the voltage permissive contact in the closing circuit of the main circuit breaker for the EDG. The setpoints of the voltage sensing relays are at a higher voltage than the previous relays and will prohibit the EDG main circuit breaker from closing when the EDG output is less than the required voltage. This design change also installs indicating lights on the generator control panel to identify when the voltage and speed permissives are satisfied.
It also provides for replacement of obsolete components to upgrade the system to reflect current industry practice.
This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
This design change does not negatively impact any accident response.
lEC-3401, Pkg. 1, Emergency Diesel Generator Starting Air &
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
Turbo Boost System Upgrade. This design change upgrades the Starting Air and Turbo Boost system by the installation of stainless steel piping and components for corrosion resistance. It also provides for replacement of obsolete components to upgrade the system to reflect current industry practice.
lEC-3529, Pkg. 1, Modify Emergency Diesel Generators (EDG) To Increase Vibration Tolerance.
This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
This design change modifies EDG design by modifying EDG engine, generator, and auxiliary components to increase the EDG's tolerance to vibration.
lEC-3529, Pkg. 1, Modify Emergency Diesel Generators (EDG)
These changes include: (1) Installation of elastomeric flexhose on components with relative motion mounted on the engine, engine skid, and engine foundation, piping, or tubing, (2) Braces components with a configuration with a natural frequency near that of the engine dominant frequency of vibration, (3) Strengthens certain components to withstand vibration, (4) Relocates and rigidly mounts cantilever-mounted valves on the engine and auxiliary components, (5) Removes existing EDG engine and generator mounted vibration switches.
To Increase Vibration Tolerance. This design change modifies EDG design by modifying EDG engine, generator, and auxiliary components to increase the EDG's tolerance to vibration. These changes include:   (1) Installation of elastomeric flexhose on components with relative motion mounted on the engine, engine skid, and engine foundation, piping, or tubing, (2) Braces components with a configuration with a natural frequency near that of the engine dominant frequency of vibration, (3) Strengthens certain components to withstand vibration, (4) Relocates and rigidly mounts cantilever-mounted valves on the engine and auxiliary components, (5) Removes existing EDG engine and generator mounted vibration switches.
* This design change does not negatively impact any accident response.
 
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
lEC-3525, Pkg. 1, Relief Valve 1CV141 Replacement.
lEC-3525, Pkg. 1, Relief Valve 1CV141 Replacement. This design change replaces and relocates the No. 13 Positive Displacement Charging pump (PDP) discharge relief valve (1CV141) with a bellows style relief valve which is better suited for this application.
This design change replaces and relocates the No. 13 Positive Displacement Charging pump (PDP) discharge relief valve (1CV141) with a bellows style relief valve which is better suited for this application.
This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
This design change does not negatively impact any accident response.
lEE-0333, Pkg. 1, Replace Service Water Pump Strainer Backwash Valve 11SW24. This design change replaces the existing Service Water Pump Strainer Backwash Diaphragm Valve (11SW24) . The valve will be replaced with a ball valve which has a longer service life between preventive maintenance and is better suited for the frequent cycling of backwash service. The existing fast actuating air operator is being replaced with a Bettis piston type actuator to slow the closure time of the valve to mitigate existing water hammer in this portion of the system.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
lEE-0333, Pkg. 1, Replace Service Water Pump Strainer Backwash Valve 11SW24. This design change replaces the existing Service Water Pump Strainer Backwash Diaphragm Valve (11SW24) . The valve will be replaced with a ball valve which has a longer service life between preventive maintenance and is better suited for the frequent cycling of backwash service. The existing fast actuating air operator is being replaced with a Bettis piston type actuator to slow the closure time of the valve to mitigate existing water hammer in this portion of the system. This design change does not negatively impact any accident response.
lEE-0349, Pkg. 1, Replace Circulating Pump Bearing Lube Relief Valve. This design change replaces the existing Circulating Pump Bearing Lube Relief valve with a model of increased size and increased set pressure. The size of the relief valve will be increased to accommodate a higher calculated flow rate and the set pressure will be increased to ensure that the valve does not lift due to pressure surges and flow induced vibrations which occur when the screen wash pumps are used to supply Circulating pump bearing lubrication water.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
 
lEE-0349, Pkg. 1, Replace Circulating Pump Bearing Lube Relief Valve. This design change replaces the existing Circulating Pump Bearing Lube Relief valve with a model of increased size and increased set pressure.
This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
The size of the relief valve will be increased to accommodate a higher calculated flow rate and the set pressure will be increased to ensure that the valve does not lift due to pressure surges and flow induced vibrations which occur when the screen wash pumps are used to supply Circulating pump bearing lubrication water.
Temporary Modifications     Summary of Safety Evaluations TMR 97-023, 4KV "A" Vital Bus Undervoltage Relay Tie-Ins.
, This design change does not negatively impact any accident response.
This temporary modification installs steel plates, terminal blocks, circuit breakers, fuse holders, and wiring to eliminate the need for additional bus outages. The additional bus outages would be required to support the installation of the Service Water Accumulator Tank Discharge Valve modification.
This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.
This temporary modification does not negatively impact any accident response. This temporary modification does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
Temporary Modifications Summary of Safety Evaluations TMR 97-023, 4KV "A" Vital Bus Undervoltage Relay Tie-Ins. This temporary modification installs steel plates, terminal blocks, circuit breakers, fuse holders, and wiring to eliminate the need for additional bus outages. The additional bus outages would be required to support the installation of the Service Water Accumulator Tank Discharge Valve modification.
Therefore, this temporary modification does not involve an Unreviewed Safety Question.
This temporary modification does not negatively impact any accident response.
Procedures   Summary of Safety Evaluations Sl.OP-SO.ABV-OOOl(Q), Rev. 5, Auxiliary Building Ventilation (ABV) System Operation. This new maintenance procedure was written to allow the Unit 1 ABV system to be operated outside the normal arrangement to allow for equipment maintenance which cannot be performed effectively with the normal system operating (one supply and two exhaust fans in service). The building pressure will remain negative with respect to the atmosphere with no supply fan and only one exhaust fan operational.
This temporary modification does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this temporary modification does not involve an Unreviewed Safety Question.
Procedures Summary of Safety Evaluations Sl.OP-SO.ABV-OOOl(Q), Rev. 5, Auxiliary Building Ventilation (ABV) System Operation.
This new maintenance procedure was written to allow the Unit 1 ABV system to be operated outside the normal arrangement to allow for equipment maintenance which cannot be performed effectively with the normal system operating (one supply and two exhaust fans in service).
The building pressure will remain negative with respect to the atmosphere with no supply fan and only one exhaust fan operational.
Since any one of the three exhaust fans will be in service during this duration, the Auxiliary Building will continue to be maintained at a negative pressure and any source of contamination will be filtered through the ABV filtration units prior to being released offsite. Since the plant is defueled, the potential for increased contamination and the migration of any contamination will be minimized.
Since any one of the three exhaust fans will be in service during this duration, the Auxiliary Building will continue to be maintained at a negative pressure and any source of contamination will be filtered through the ABV filtration units prior to being released offsite. Since the plant is defueled, the potential for increased contamination and the migration of any contamination will be minimized.
This procedure revision does not negatively impact any accident response.
This procedure revision does not negatively impact any accident response. This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.
This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this procedure revision does not involve an Unreviewed Safety Question.
Therefore, this procedure revision does not involve an Unreviewed Safety Question.
* UFSAR Change Notices Summary of Safety Evaluations There were no changes in this category implemented during August, 1997. Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during August, 1997. Other Summary of Safety Evaluation There were no changes in this category implemented during August, 1997.
 
I I DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 9/11/ 97 COMPLETED BY: R. Phillips TELEPHONE:
UFSAR Change Notices     Summary of Safety Evaluations There were no changes in this category implemented during August, 1997.
(609) 339-2735 OPERATING DATA REPORT OPERATING STATUS 1 Reporting Period August 1997 Hours in Report Period 2 Currently Authorized Power Level (MWt) Max Dependable Capacity (MWe-Net)
Deficiency Reports     Summary of Safety Evaluations There were no changes in this category implemented during August, 1997.
Design Electrical Rating (MWe-Net) 3 Power level to which restricted (if any) (MWe Net) 4 Reason For Restriction (if any) This Month Yr To Date 5 No. of hours reactor was critical 6 Reactor reserve shutdown hours 7 Hours generator on line 0.0 0.0 0 8 Unit reserve shutdown hours 0.0 9 Gross thermal energy generated (MWH) 0 10 Gross electrical energy generated (MWH) 0 11 Net electrical energy generated (MWH) -3655 12 Unit Service Factor 13 Unit Availability Factor 14 Unit Capacity Factor (MDC) 15 Unit Capacity Factor (DER) 0.0% 0.0% 0.0% 0.0% 0.0 0.0 0 0.0 0 0 -22468 0.0% 0.0% 0.0% 0.0% 16 Unit Forced Outage Rate 100.0% 100.0% 17 Shutdowns scheduled over next 6 months (type, date, duration)
Other     Summary of Safety Evaluation There were no changes in this category implemented during August, 1997.
: 18 If shutdown at end of report period, estimated date of Startup: Under Review 744 3411 1106 1115 None Cumulati 104380.5 0. 0 100338.3 0.0 31806229 10530100 10015226 52.1% 52.1% 47.0% 46.6% 37.8%
 
* DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 9/11/97 COMPLETED BY: R. Phillips TELEPHONE:
I I
(609) 339-2735 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS MONTH AUGUST 1997 TYPE F=FORCED DURATION NO. DATE S=SCHEDULED (HOURS) 3859 8/1 F 744 -8/31 (1) Reason A -Equipment Failure (Explain) B -Maintenance or Test C -Refueling D -Regulatory Restriction REASON ( 1) F, c E -Operator Training/License Examination F Administrative G -Operational Error (Explain) H -Other METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING CORRECTIVE POWER ACTION/COMMENT (2) 4 Steam Generator Replacement (2) Method 1 -Manual 2 -Manual Trip 3 -Automatic Trip/Scram 4 -Continuation 5 -Other (Explain)
DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 9/11/ 97 COMPLETED BY: R. Phillips TELEPHONE: (609) 339-2735 OPERATING DATA REPORT OPERATING STATUS 1 Reporting Period August 1997             Hours in Report     744 Period 2 Currently Authorized Power Level (MWt)                         3411 Max Dependable Capacity (MWe-Net)                             1106 Design Electrical Rating (MWe-Net)                             1115 3 Power level to which restricted (if any)   (MWe Net)         None 4 Reason For Restriction (if any)
* DOCKET NO.: 50-272 UNIT: Salem 1 DATE : 9 I 11 I 9 7 COMPLETED BY: R. Phillips TELEPHONE:
This Month   Yr To   Cumulati Date 5 No. of hours reactor was critical         0.0          0.0    104380.5 6 Reactor reserve shutdown hours           0.0          0.0    0. 0 7 Hours generator on line                   0           0       100338.3 8 Unit reserve shutdown hours               0.0          0.0    0.0 9 Gross thermal energy generated (MWH)     0           0      31806229 10 Gross electrical energy generated (MWH)   0           0      10530100 11 Net electrical energy generated (MWH)     -3655       -22468  10015226 12 Unit Service Factor                       0.0%         0.0%   52.1%
(609) 339-2735 AVERAGE DAILY UNIT POWER LEVEL MONTH AUGUST 1997 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}}
13 Unit Availability Factor                  0.0%         0.0%   52.1%
14 Unit Capacity Factor (MDC)                0.0%        0.0%    47.0%
15 Unit Capacity Factor (DER)                0.0%         0.0%   46.6%
16 Unit Forced Outage Rate                   100.0%       100.0% 37.8%
17 Shutdowns scheduled over next 6 months   (type, date, duration) :
18 If shutdown at end of report period, estimated date of Startup:       Under Review
* DOCKET NO.:
UNIT:
50-272 Salem 1 DATE:   9/11/97 COMPLETED BY:     R. Phillips TELEPHONE:   (609) 339-2735 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS MONTH   AUGUST 1997 METHOD OF SHUTTING DOWN THE TYPE                                 REACTOR OR F=FORCED       DURATION   REASON    REDUCING    CORRECTIVE NO. DATE   S=SCHEDULED     (HOURS)  ( 1)      POWER        ACTION/COMMENT (2) 3859   8/1     F             744       F,  c    4            Steam
        -                                                       Generator 8/31                                                     Replacement (1) Reason                                         (2) Method A - Equipment Failure (Explain)                     1 - Manual B - Maintenance or Test                             2 - Manual Trip C - Refueling                                       3 - Automatic Trip/Scram D - Regulatory Restriction                         4 - Continuation E - Operator Training/License Examination           5 - Other (Explain)
F   Administrative G - Operational Error (Explain)
H - Other
* DOCKET NO.: 50-272 UNIT: Salem 1 DATE : 9 I 11 I 9 7 COMPLETED BY: R. Phillips TELEPHONE: (609) 339-2735 AVERAGE DAILY UNIT POWER LEVEL MONTH   AUGUST 1997 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}}

Latest revision as of 05:09, 3 February 2020

Monthly Operating Rept for Aug 1997 for Salem Unit 1.W/ 970915 Ltr
ML18102B584
Person / Time
Site: Salem PSEG icon.png
Issue date: 08/31/1997
From: Garchow D, Knieriem R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N970620, NUDOCS 9709230178
Download: ML18102B584 (11)
v • d • e


Text

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit SEP 15 1997 LR-N970620 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 1 DOCKET NO. 50-272 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating Report for August, 1997, is attached.

I General Man ger -

Salem Operations RBK/tcp Enclosures C Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

\

--- - -9709230*178 q7oa31 PDR ADOCK 05000272 R PDR IIUlll lllll lllll lllll lll\11111111111111

  • &&63&E*

The power is in your hands.

95-2168 REV. 6/94

~ .

Refueling Information Docket No. 50-272 Month: August, 1997 Unit Name: Salem 1

Contact:

R. B. Knieriem Telephone: 609-339-1782 Month: August, 1997

1. Refueling information has changed from last month: Yes: No: X
2. Scheduled date for next refueling: To Be Determined Scheduled date for restart following refueling: To Be Determined
3. a. Will Technical Specification changes or other license amendments be required?

Yes: X No: Not Determined to Date:

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

Yes: No: X If no, when is it scheduled? To be Determined

4. Scheduled date (s) for submitting proposed licensing action: To be Determined
5. Important licensing considerations associated with refueling:
6. Number of Fuel Assemblies:
a. Incore: 0
b. In Spent Fuel Storage: 953
7. Present Licensed spent fuel storage capacity: 1632 Future spent fuel storage capacity: 1632
8. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: April 2012

SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT 1 AUGUST 1997 SALEM UNIT 1 The unit is in a refueling and steam generator replacement outage and remained shutdown for the entire period. According to commitments from PSE&G and a subsequent confirmatory action letter from the NRC, the unit will remain shutdown pending completion of the following actions:

  • Appropriately address long standing equipment reliability and operability issues.
  • After the work is completed, conduct a restart readiness review to determine for ourselves the ability of the unit to operate in a safe, event free manner.
  • After the restart review, meet with the NRC and communicate the results of that review.

DOCKET NO.: 50-272 UNIT: Salem l DATE: 09/15/97 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT l GENERATING STATION MONTH AUGUST 1997 The following items completed during August 1997 have been evaluated to determine:

1. If the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased; or
2. If a possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report may be created; or
3. If the margin of safety as defined in the basis for any technical specification is reduced.

The 10CFR50.59 Safety Evaluations showed that these items did not create a new safety hazard to the plant nor did they affect the safe shutdown of the reactor. These items did not change the plant effluent releases and did not alter the existing environmental impact. The 10CFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Design Changes Summary of Safety Evaluations lEC-3310, Pkg. 1, Emergency Diesel Generator Low Lube Oil Temperature Setpoint Change. This design change revises the Emergency Diesel Generator (EDG) lube oil low temperature setpoint to 100°F. Raising the low lube oil temperature from 80°F to 100°F is conservative and will more promptly alert the operators of a failed heater.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEC-3438, Pkg. 1, "A Emergency Diesel Generator Circuit Breaker Voltage Permissive Relay Installation and Indication Modifications. This design change installs two voltage sensing relays and an auxiliary relay to monitor the output voltage of the "A" Emergency Diesel Generator (EDG) .

Contacts from the auxiliary relay replace the voltage permissive contact in the closing circuit of the main circuit breaker for the EDG. The setpoints of the voltage sensing relays are at a higher voltage than the previous relays and will prohibit the EDG main circuit breaker from closing when the EDG output is less than the required voltage. This design change also installs indicating lights on the generator control panel to identify when the voltage and speed permissives are satisfied.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEC-3401, Pkg. 1, Emergency Diesel Generator Starting Air &

Turbo Boost System Upgrade. This design change upgrades the Starting Air and Turbo Boost system by the installation of stainless steel piping and components for corrosion resistance. It also provides for replacement of obsolete components to upgrade the system to reflect current industry practice.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEC-3529, Pkg. 1, Modify Emergency Diesel Generators (EDG)

To Increase Vibration Tolerance. This design change modifies EDG design by modifying EDG engine, generator, and auxiliary components to increase the EDG's tolerance to vibration. These changes include: (1) Installation of elastomeric flexhose on components with relative motion mounted on the engine, engine skid, and engine foundation, piping, or tubing, (2) Braces components with a configuration with a natural frequency near that of the engine dominant frequency of vibration, (3) Strengthens certain components to withstand vibration, (4) Relocates and rigidly mounts cantilever-mounted valves on the engine and auxiliary components, (5) Removes existing EDG engine and generator mounted vibration switches.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEC-3525, Pkg. 1, Relief Valve 1CV141 Replacement. This design change replaces and relocates the No. 13 Positive Displacement Charging pump (PDP) discharge relief valve (1CV141) with a bellows style relief valve which is better suited for this application.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEE-0333, Pkg. 1, Replace Service Water Pump Strainer Backwash Valve 11SW24. This design change replaces the existing Service Water Pump Strainer Backwash Diaphragm Valve (11SW24) . The valve will be replaced with a ball valve which has a longer service life between preventive maintenance and is better suited for the frequent cycling of backwash service. The existing fast actuating air operator is being replaced with a Bettis piston type actuator to slow the closure time of the valve to mitigate existing water hammer in this portion of the system.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

lEE-0349, Pkg. 1, Replace Circulating Pump Bearing Lube Relief Valve. This design change replaces the existing Circulating Pump Bearing Lube Relief valve with a model of increased size and increased set pressure. The size of the relief valve will be increased to accommodate a higher calculated flow rate and the set pressure will be increased to ensure that the valve does not lift due to pressure surges and flow induced vibrations which occur when the screen wash pumps are used to supply Circulating pump bearing lubrication water.

This design change does not negatively impact any accident response. This design change does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety. Therefore, this design change does not involve an Unreviewed Safety Question.

Temporary Modifications Summary of Safety Evaluations TMR 97-023, 4KV "A" Vital Bus Undervoltage Relay Tie-Ins.

This temporary modification installs steel plates, terminal blocks, circuit breakers, fuse holders, and wiring to eliminate the need for additional bus outages. The additional bus outages would be required to support the installation of the Service Water Accumulator Tank Discharge Valve modification.

This temporary modification does not negatively impact any accident response. This temporary modification does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.

Therefore, this temporary modification does not involve an Unreviewed Safety Question.

Procedures Summary of Safety Evaluations Sl.OP-SO.ABV-OOOl(Q), Rev. 5, Auxiliary Building Ventilation (ABV) System Operation. This new maintenance procedure was written to allow the Unit 1 ABV system to be operated outside the normal arrangement to allow for equipment maintenance which cannot be performed effectively with the normal system operating (one supply and two exhaust fans in service). The building pressure will remain negative with respect to the atmosphere with no supply fan and only one exhaust fan operational.

Since any one of the three exhaust fans will be in service during this duration, the Auxiliary Building will continue to be maintained at a negative pressure and any source of contamination will be filtered through the ABV filtration units prior to being released offsite. Since the plant is defueled, the potential for increased contamination and the migration of any contamination will be minimized.

This procedure revision does not negatively impact any accident response. This procedure revision does not increase the probability or consequences of either an accident or a malfunction of equipment important to safety.

Therefore, this procedure revision does not involve an Unreviewed Safety Question.

UFSAR Change Notices Summary of Safety Evaluations There were no changes in this category implemented during August, 1997.

Deficiency Reports Summary of Safety Evaluations There were no changes in this category implemented during August, 1997.

Other Summary of Safety Evaluation There were no changes in this category implemented during August, 1997.

I I

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 9/11/ 97 COMPLETED BY: R. Phillips TELEPHONE: (609) 339-2735 OPERATING DATA REPORT OPERATING STATUS 1 Reporting Period August 1997 Hours in Report 744 Period 2 Currently Authorized Power Level (MWt) 3411 Max Dependable Capacity (MWe-Net) 1106 Design Electrical Rating (MWe-Net) 1115 3 Power level to which restricted (if any) (MWe Net) None 4 Reason For Restriction (if any)

This Month Yr To Cumulati Date 5 No. of hours reactor was critical 0.0 0.0 104380.5 6 Reactor reserve shutdown hours 0.0 0.0 0. 0 7 Hours generator on line 0 0 100338.3 8 Unit reserve shutdown hours 0.0 0.0 0.0 9 Gross thermal energy generated (MWH) 0 0 31806229 10 Gross electrical energy generated (MWH) 0 0 10530100 11 Net electrical energy generated (MWH) -3655 -22468 10015226 12 Unit Service Factor 0.0% 0.0% 52.1%

13 Unit Availability Factor 0.0% 0.0% 52.1%

14 Unit Capacity Factor (MDC) 0.0% 0.0% 47.0%

15 Unit Capacity Factor (DER) 0.0% 0.0% 46.6%

16 Unit Forced Outage Rate 100.0% 100.0% 37.8%

17 Shutdowns scheduled over next 6 months (type, date, duration) :

18 If shutdown at end of report period, estimated date of Startup: Under Review

  • DOCKET NO.:

UNIT:

50-272 Salem 1 DATE: 9/11/97 COMPLETED BY: R. Phillips TELEPHONE: (609) 339-2735 OPERATING DATA REPORT UNIT SHUTDOWNS AND POWER REDUCTIONS MONTH AUGUST 1997 METHOD OF SHUTTING DOWN THE TYPE REACTOR OR F=FORCED DURATION REASON REDUCING CORRECTIVE NO. DATE S=SCHEDULED (HOURS) ( 1) POWER ACTION/COMMENT (2) 3859 8/1 F 744 F, c 4 Steam

- Generator 8/31 Replacement (1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip C - Refueling 3 - Automatic Trip/Scram D - Regulatory Restriction 4 - Continuation E - Operator Training/License Examination 5 - Other (Explain)

F Administrative G - Operational Error (Explain)

H - Other

  • DOCKET NO.: 50-272 UNIT: Salem 1 DATE : 9 I 11 I 9 7 COMPLETED BY: R. Phillips TELEPHONE: (609) 339-2735 AVERAGE DAILY UNIT POWER LEVEL MONTH AUGUST 1997 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
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