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{{#Wiki_filter:e ! , Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit ... AUG l.5 1997 LR-N970517 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 July, 1997, is attached.
{{#Wiki_filter:.~*                                  e
RAR:tcp Enclosures c Mr. H. J. Miller David F. Garchow General Manager -Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 9708250113 970731 PDR ADOCK 05000272 R . PDR The power is in your hands. ----------------....--..
        *ops~G
I llllll lllll lllll llllll llll llllll Ill llll .sasc1A*, I 95-2168 REV. 6/94 DOCKET NO.: UNIT: DATE: COMPLETED BY: TELEPHONE:  
        , Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit
                                                      . . AUG l.5 1997 LR-N970517 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 July, 1997, is attached.
                                                        <:f]f.~
David F. Garchow I
General Manager -
Salem Operations RAR:tcp Enclosures c         Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046
!          9708250113 970731 PDR ADOCK 05000272 R                   . PDR                               --------- --                 ~-   -----....--..
Illllll lllll lllll llllll llll llllll Ill llll
                                                                              .sasc1A*,
The power is in your hands.
95-2168 REV. 6/94
 
DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 08/15/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445


==SUMMARY==
==SUMMARY==
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH JULY 1997 50-272 Salem 1 08/15/97 R. Ritzman (609) 339-1445 The following items completed during July 1997 have been evaluated to determine:
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH     JULY 1997 The following items completed during July 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 increasedi 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 createdi 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 increasedi 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&deg;F. Raising the low lube oil temperature from 80&deg;F to 100&deg;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 createdi 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.
lEC-3438, Pkg. 1, "A" Emergency Diesel Generator Circuit Breaker Voltage Permissive Relay Installation and Indication Modifications.
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.
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.
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&deg;F. Raising the low lube oil temperature from 80&deg;F to 100&deg;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 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 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-3453, Pkg. 1, "A" Emergency Diesel Generator Fuel Oil Day Tank Setpoint Change. This design change adjusted the level switch setpoints associated with the fuel oil day tank. This design change allows the Emergency Diesel Generator to run longer after the receipt of the low level alarm and before it runs out of fuel. This change also mitigates the consequences of a loss of the fuel oil transfer pump. This design change does not negatively impact any accident response.
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) .
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.
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-3453, Pkg. 1, "A" Emergency Diesel Generator Fuel Oil Day Tank Setpoint Change. This design change adjusted the level switch setpoints associated with the fuel oil day tank. This design change allows the Emergency Diesel Generator to run longer after the receipt of the low level alarm and before it runs out of fuel. This change also mitigates the consequences of a loss of the fuel oil transfer pump.
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-3533, Pkg. 1, "A" Emergency Diesel Generator Starting and Turbo-Boost Air Compressor Start/Stop Pressure Switches.
lEC-3533, Pkg. 1, "A" Emergency Diesel Generator Starting and Turbo-Boost Air Compressor Start/Stop Pressure Switches.
This design change replaces pressure control switches for the Emergency Diesel Generator starting and turbo-boost air compressors.
This design change replaces pressure control switches for the Emergency Diesel Generator starting and turbo-boost air compressors. This design change also revises the auto stop setpoint for the air compressors to increase the margin prior to safety relief valve operation.
This design change also revises the auto stop setpoint for the air compressors to increase the margin prior to safety relief valve operation.
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.
SEC-0008, Pkg. 1, Hand Geometry Access Project. This design change installs a hand geometry reader system in the Security Center, enables the elimination of the badge issue and retrieval from the Security Center, and relocates the accountability computer terminals.
SEC-0008, Pkg. 1, Hand Geometry Access Project. This design change installs a hand geometry reader system in the Security Center, enables the elimination of the badge issue and retrieval from the Security Center, and relocates the accountability computer terminals.
This design change was reviewed with regard to the Design Basis Security Threat. Nothing in this design change was determined to contribute to an increased vulnerability to a design basis threat. The use of hand geometry is a program enhancement in that it reduces the possibility of human error in badge issuance and improves Security Center lobby management.
This design change was reviewed with regard to the Design Basis Security Threat. Nothing in this design change was determined to contribute to an increased vulnerability to a design basis threat. The use of hand geometry is a program enhancement in that it reduces the possibility of human error in badge issuance and improves Security Center lobby management.
This design change does not negatively impact any accident response.
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 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 97-020, 4KV "A" Vital Bus Undervoltage Relay Tie-Ins.
Temporary Modifications Summary of Safety Evaluations TMR 97-020, 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 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 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.
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.
Therefore, this temporary modification does not involve an Unreviewed Safety Question.
Procedures Summary of Safety Evaluations Sl.MD-CM.CAV-0004(Q), Rev. 0, Alternate Feed for 11 Control Room Emergency Air Conditioning System. This new maintenance procedure was written to provide an alternate 230V AC power feed to the 11 Control Room Emergency Air Conditioning System. The normal supply is from the lA vital ventilation MCC. This procedure allows the 11 Control Room Emergency Air Conditioning System to temporarily be powered from the lB vital ventilation MCC during lA vital bus outages with the unit in Mode 5, 6, or undefined.
Procedures   Summary of Safety Evaluations Sl.MD-CM.CAV-0004(Q), Rev. 0, Alternate Feed for 11 Control Room Emergency Air Conditioning System. This new maintenance procedure was written to provide an alternate 230V AC power feed to the 11 Control Room Emergency Air Conditioning System. The normal supply is from the lA vital ventilation MCC. This procedure allows the 11 Control Room Emergency Air Conditioning System to temporarily be powered from the lB vital ventilation MCC during lA vital bus outages with the unit in Mode 5, 6, or undefined.
The safety evaluation concluded that this new procedure does not present any new challenges to the involved systems. The procedure connects the "A" and "B" trains, and there is sufficient independence from the "c" train such that no single failure will result in less than the required power distribution system. 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.
The safety evaluation concluded that this new procedure does not present any new challenges to the involved systems. The procedure connects the "A" and "B" trains, and there is sufficient independence from the "c" train such that no single failure will result in less than the required power distribution system.
UFSAR Change Notices Summary of Safety Evaluations There were no changes in this category implemented during July, 1997. Deficiency Reports Summary of Safety Evaluations Other There were no changes in this category implemented during July, 1997. Summary of Safety Evaluation There were no changes in this category implemented during July, 1997.
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.
OPERATING DATA REPORT Docket No: Date: completed by: Robert Phillips Telephone:
Therefore, this procedure revision does not involve an Unreviewed Safety Question.
Operating Status 1. Unit Name Salem No. 1 Notes 2. Reporting Period July 1997 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) Report, Give Reason NA 9. Power Level to Which Restricted, if any (Net MWe) 50-272 .. 08/10/97 339-2735 since Last N/A 10. Reasons for Restrictions, if any
UFSAR Change Notices     Summary of Safety Evaluations There were no changes in this category implemented during July, 1997.
: 11. Hours in Reporting Period 12. No. of Hrs. Rx. was Critical 13. Reactor Reserve Shutdown Hrs. 14. Hours Generator On-Line 15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MWH) 17. 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 N'et) 22. Unit Capacity Factor (using DER Net) 23. Unit Forced Outage Rate This Month 744 0 0 0 0 0 0 -2868 0 0 0 0 100 Year to Date 5087 0 0 0 0 0 0 -18813 0 0 0 0 100 Cumulative 186862 104380.45 0 100338.27 0 31806229.
Deficiency Reports     Summary of Safety Evaluations There were no changes in this category implemented during July, 1997.
2' 105301000 100155923 53.7 53.7 48.4 48.1 35.5 24. Shutdowns scheduled over next 6 months (type, date and duration of each) NA 25. If shutdown at end of Report Period, Estimated Date of Startup: Under review. 8-1-7.R2 AVERA<4tnAILY UNIT POWER LEVEL Docket No.: 50-272 Unit Name: Salem #1 Date: 08/10/97 Completed by: Robert Phillips Telephone:
Other    Summary of Safety Evaluation There were no changes in this category implemented during July, 1997.
339-2735 Month July 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 P. 8.1-7 Rl NO. DATE 3859 7-1-97 F 1 2 F: Forced S: Scheduled DURATION TYPE 1 (HOURS) REASON 2 744 F.C Reason A-Equipment Failure (explain)
 
B-Maintenance or Test C-Refuel ing D-Requlatory Restriction 4 UNIT SHUTDOWN AND POWER REDUCTIONS REPORT MONTH July 1997 METHOD OF SHUTTING DOWN REACTOR LICENSE EVENT REPORT # -----------
OPERATING DATA REPORT Docket No: 50-272 ..~
zz 3 Method: 1-Manual 2-Manual Scram SYSTEM CODE 4 E-Operator Training & License Examination F-Administrative 3-Automatic Scram 4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-Operational Error (Explain)
Date:       08/10/97 completed by:     Robert Phillips                   Telephone: 339-2735 Operating Status
H-Other (Explain)
: 1. Unit Name                         Salem No. 1     Notes
COMPONENT CODE 6 '. .* DOCKET NO.: 50-272 UN IT NAME: Sal DATE:
: 2. Reporting Period               July       1997
__ _ COMPLETED BY: Robert Phillips TELEPHONE:
: 3. Licensed Thermal Power (MWt)             3411
609-339-2735 CAUSE AND CORRECTIVE ACTION TO PREVENT RECURRENCE zzzz Steam Generator Replacement 4
: 4. Nameplate Rating (Gross MWe)             1170
-Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG-0161) 5 Exhibit -Same Source Refueling Information July, 1997 Month: July, 1997 Docket No. Unit Name: Contact: Telephone:
: 5. Design Electrical Rating (Net MWe)       1115
50-272 Salem 1 D.Tisdel 609-339-1538
: 6. Maximum Dependable Capacity(Gross MWe) 1149
: 1. Refueling information has changed from last month: Yes: No: X 2. Scheduled date for next refueling:
: 7. Maximum Dependable Capacity (Net MWe)     1106
To Be Determined Scheduled date for restart following refueling:
: 8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason             NA
To Be Determined
: 9. Power Level to Which Restricted, if any (Net MWe)           N/A
: 10. Reasons for Restrictions, if any ~~~~--=N~A=-~~~~~~~~~~~~--
This Month    Year to Date  Cumulative
: 11. Hours in Reporting Period             744          5087        186862
: 12. No. of Hrs. Rx. was Critical           0              0      104380.45
: 13. Reactor Reserve Shutdown Hrs.           0              0          0
: 14. Hours Generator On-Line                 0              0      100338.27
: 15. Unit Reserve Shutdown Hours             0              0          0
: 16. Gross Thermal Energy Generated (MWH)                           0              0    31806229. 2'
: 17. Gross Elec. Energy Generated (MWH)                           0              0    105301000
: 18. Net Elec. Energy Gen. (MWH)         - 2868        -18813    100155923
: 19. Unit Service Factor                     0              0        53.7
: 20. Unit Availability Factor               0              0        53.7
: 21. Unit Capacity Factor (using MDC N'et)                   0              0        48.4
: 22. Unit Capacity Factor (using DER Net)                   0              0        48.1
: 23. Unit Forced Outage Rate               100           100         35.5
: 24. Shutdowns scheduled over next 6 months (type, date and duration of each)
NA
: 25. If shutdown at end of Report Period, Estimated Date of Startup:
Under review.
8-1-7.R2
 
AVERA<4tnAILY UNIT POWER LEVEL Docket No.:   50-272 Unit Name:     Salem #1 Date:         08/10/97 Completed by:     Robert Phillips                   Telephone:     339-2735 Month       July       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 P. 8.1-7 Rl
 
UNIT SHUTDOWN AND POWER REDUCTIONS                                                                          .*
REPORT MONTH July          1997                                          DOCKET NO.: 50-272 UN IT NAME: Sal em.~#1~--
DATE: _0=8~/~10~*1~9~7_ __
COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF SHUTTING        LICENSE DURATION                     DOWN            EVENT            SYSTEM    COMPONENT              CAUSE AND CORRECTIVE ACTION 2
NO.          DATE    TYPE 1 (HOURS)       REASON       REACTOR          REPORT #        CODE 4    CODE 6                    TO PREVENT RECURRENCE 3859      7-1-97    F          744           F.C           4                -----------      zz        zzzz            Steam Generator Replacement 1              2                                                        3                          4                                  5 F:  Forced      Reason                                                   Method:                    E~hibit'G - Instructions          Exhibit    - 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-Refuel ing                                             3-Automatic Scram          Event Report CLER) File D-Requlatory Restriction                                 4-Continuation of          (NUREG-0161)
E-Operator Training & License Examination                   Previous Outage F-Administrative                                         5-Load Reduction G-Operational Error (Explain)                             9-0ther H-Other (Explain)
 
Refueling Information                              Docket No. 50-272
~onth:   July, 1997                               Unit Name: Salem 1
 
==Contact:==
D.Tisdel Telephone: 609-339-1538 Month:    July, 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?
: 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: X No: Not Determined to Date:
Yes: No: X If no, when is it scheduled?
: b. Has the reload fuel design been reviewed by the Station Operating Review Committee?
To be Determined
Yes:   No: X   If no, when is it scheduled? To be Determined
: 4. Scheduled date (s) for submitting proposed licensing action: 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: b. In Spent Fuel Storage: 7. Present Licensed spent fuel storage capacity:
: a. Incore:                                                0
Future spent fuel storage capacity:
: b. In Spent Fuel Storage:                                953
0 953 1632 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
: 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  
 
SALEM GENERATING STATION MONTHLY OPERATING  


==SUMMARY==
==SUMMARY==
  -UNIT 1 JULY 1997 SALEM UNIT 1
  - UNIT 1 JULY 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:
* 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.}}

Latest revision as of 05:10, 3 February 2020

Monthly Operating Rept for Jul 1997 for Salem Generating Station,Unit 1.W/970815 Ltr
ML18102B524
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/31/1997
From: Garchow D, Phillips R, Ritzman R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N970517, NUDOCS 9708250113
Download: ML18102B524 (10)
v • d • e


Text

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, Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit

. . AUG l.5 1997 LR-N970517 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 July, 1997, is attached.

<:f]f.~

David F. Garchow I

General Manager -

Salem Operations RAR:tcp Enclosures c Mr. H. J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046

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95-2168 REV. 6/94

DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 08/15/97 COMPLETED BY: R. Ritzman TELEPHONE: (609) 339-1445

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH JULY 1997 The following items completed during July 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 increasedi 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 createdi 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-3453, Pkg. 1, "A" Emergency Diesel Generator Fuel Oil Day Tank Setpoint Change. This design change adjusted the level switch setpoints associated with the fuel oil day tank. This design change allows the Emergency Diesel Generator to run longer after the receipt of the low level alarm and before it runs out of fuel. This change also mitigates the consequences of a loss of the fuel oil transfer pump.

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-3533, Pkg. 1, "A" Emergency Diesel Generator Starting and Turbo-Boost Air Compressor Start/Stop Pressure Switches.

This design change replaces pressure control switches for the Emergency Diesel Generator starting and turbo-boost air compressors. This design change also revises the auto stop setpoint for the air compressors to increase the margin prior to safety relief valve operation.

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.

SEC-0008, Pkg. 1, Hand Geometry Access Project. This design change installs a hand geometry reader system in the Security Center, enables the elimination of the badge issue and retrieval from the Security Center, and relocates the accountability computer terminals.

This design change was reviewed with regard to the Design Basis Security Threat. Nothing in this design change was determined to contribute to an increased vulnerability to a design basis threat. The use of hand geometry is a program enhancement in that it reduces the possibility of human error in badge issuance and improves Security Center lobby management.

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 97-020, 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.MD-CM.CAV-0004(Q), Rev. 0, Alternate Feed for 11 Control Room Emergency Air Conditioning System. This new maintenance procedure was written to provide an alternate 230V AC power feed to the 11 Control Room Emergency Air Conditioning System. The normal supply is from the lA vital ventilation MCC. This procedure allows the 11 Control Room Emergency Air Conditioning System to temporarily be powered from the lB vital ventilation MCC during lA vital bus outages with the unit in Mode 5, 6, or undefined.

The safety evaluation concluded that this new procedure does not present any new challenges to the involved systems. The procedure connects the "A" and "B" trains, and there is sufficient independence from the "c" train such that no single failure will result in less than the required power distribution system.

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 July, 1997.

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

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

OPERATING DATA REPORT Docket No: 50-272 ..~

Date: 08/10/97 completed by: Robert Phillips Telephone: 339-2735 Operating Status

1. Unit Name Salem No. 1 Notes
2. Reporting Period July 1997
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) N/A
10. Reasons for Restrictions, if any ~~~~--=N~A=-~~~~~~~~~~~~--

This Month Year to Date Cumulative

11. Hours in Reporting Period 744 5087 186862
12. No. of Hrs. Rx. was Critical 0 0 104380.45
13. Reactor Reserve Shutdown Hrs. 0 0 0
14. Hours Generator On-Line 0 0 100338.27
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 0 31806229. 2'
17. Gross Elec. Energy Generated (MWH) 0 0 105301000
18. Net Elec. Energy Gen. (MWH) - 2868 -18813 100155923
19. Unit Service Factor 0 0 53.7
20. Unit Availability Factor 0 0 53.7
21. Unit Capacity Factor (using MDC N'et) 0 0 48.4
22. Unit Capacity Factor (using DER Net) 0 0 48.1
23. Unit Forced Outage Rate 100 100 35.5
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

NA

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

Under review.

8-1-7.R2

AVERA<4tnAILY UNIT POWER LEVEL Docket No.: 50-272 Unit Name: Salem #1 Date: 08/10/97 Completed by: Robert Phillips Telephone: 339-2735 Month July 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 P. 8.1-7 Rl

UNIT SHUTDOWN AND POWER REDUCTIONS .*

REPORT MONTH July 1997 DOCKET NO.: 50-272 UN IT NAME: Sal em.~#1~--

DATE: _0=8~/~10~*1~9~7_ __

COMPLETED BY: Robert Phillips TELEPHONE: 609-339-2735 METHOD OF SHUTTING LICENSE DURATION DOWN EVENT SYSTEM COMPONENT CAUSE AND CORRECTIVE ACTION 2

NO. DATE TYPE 1 (HOURS) REASON REACTOR REPORT # CODE 4 CODE 6 TO PREVENT RECURRENCE 3859 7-1-97 F 744 F.C 4 ----------- zz zzzz Steam Generator Replacement 1 2 3 4 5 F: Forced Reason Method: E~hibit'G - Instructions Exhibit - 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-Refuel ing 3-Automatic Scram Event Report CLER) File D-Requlatory Restriction 4-Continuation of (NUREG-0161)

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

Refueling Information Docket No. 50-272

~onth: July, 1997 Unit Name: Salem 1

Contact:

D.Tisdel Telephone: 609-339-1538 Month: July, 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 JULY 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.
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