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=Text=
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* Public Service-Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236  
  ~o PS~G
' ' Nuclear Business Unit U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERA TING REPORT SALEM UNIT NO. 1 DOCKET NO. 50-272 Gentlemen:
  '
OCT 121999 LR-N98-0478 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating report for September 1998 is attached.  
* Public Service- Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236
/rbk Enclosures C Mr. H.J. Miller s*ncerely, C. Bakken Ill eneral Manager -Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 r-----*-----
            '
9810190243 980930-. -----*-\ PDR ADOCK 05000272 R PDR The power is in your hands. I I ) 95*2168 REV. 6/94 Reporting Period: September 1998
Nuclear Business Unit OCT 121999 LR-N98-0478 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 Gentlemen:
* DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10/15/98 COMPLETED BY: R. Knieriem TELEPHONE:
In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating report for September 1998 is attached.                         I s*ncerely, C. Bakken Ill eneral Manager -
(609) 339-1782 OPERATING DATA REPORT Design Electrical Rating (MWe-Net) 1115 Maximum Dependable Capacity (MWe-Net) 1106 Month Year-to-date Cumulative No. of hours reactor was critical 720 4231 108612 No. of hours generator was on line (service 720 3990 104379 hours) Unit reserve shutdown hours 0 0 0 Net Electrical Energy (MWH) 734538 4057387 104193930 UNIT SHUTDOWNS NO. DATE TYPE F=FORCED S=SCHEDULED (1) Reason A -Equipment Failure (Explain) B -Maintenance or Test C -Refueling D -Regulatory Restriction DURATION (HOURS) E -Operator Training/License Examination F -Administrative G -Operational Error (Explain)
Salem Operations I      )
H -Other Summary: REASON METHOD OF (1) SHUTTING DOWN THE REACTOR (2) (2) Method 1 -Manual 2 -Manual Trip/Scram 3 -Automatic Trip/Scram 4 -Continuation 5 -Other (Explain)
    /rbk Enclosures C        Mr. H.J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road r-----*-----
CORRECTIVE ACTION/COMMENT Salem Unit 1 began the month of September 1998 operating at full power. Full power operation continued until September 19, when power was reduced to 92% to address abnormal vibration in the 13 Heater Drain pump. The unit returned to full power on the following day. Full power operation continued until September 22, when power was
King of Prussia, PA 19046 9810190243 980930-. - - - - - * - \
* DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10715798 COMPLETED BY: R. B. Knieriem TELEPHONE:
PDR ADOCK 05000272 R                         PDR The power is in your hands.
(609) 339-1782 reduced to 25% to address high vibration in the 12 Steam Generator Feed pump and Reactor Coolant pump lube oil alarms. Full power operation was restored on September 24, but was reduced again that day to 65% to again address abnormal vibration in the 13 Heater Drain pump. Salem Unit 1 returned to full power on September 25, and operated at full power for the remainder of the month.
95*2168 REV. 6/94
* DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: September 1998 OPERATING DATA REPORT Design Electrical Rating (MWe-Net)                       1115 Maximum Dependable Capacity (MWe-Net)                     1106 Month         Year-to-date     Cumulative No. of hours reactor was critical                         720             4231           108612 No. of hours generator was on line (service               720             3990           104379 hours)
Unit reserve shutdown hours                                 0               0               0 Net Electrical Energy (MWH)                             734538           4057387         104193930 UNIT SHUTDOWNS NO. DATE       TYPE               DURATION  REASON        METHOD OF        CORRECTIVE F=FORCED           (HOURS)    (1)          SHUTTING        ACTION/COMMENT S=SCHEDULED                                 DOWN THE REACTOR (2)
(1) Reason                                     (2) Method A - Equipment Failure (Explain)                 1 - Manual B - Maintenance or Test                         2 - Manual Trip/Scram 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 Summary:
Salem Unit 1 began the month of September 1998 operating at full power. Full power operation continued until September 19, when power was reduced to 92% to address abnormal vibration in the 13 Heater Drain pump. The unit returned to full power on the following day. Full power operation continued until September 22, when power was
* DOCKET NO.:
UNIT:
50-272 Salem 1 DATE:     10715798 COMPLETED BY:       R. B. Knieriem TELEPHONE:       (609) 339-1782 reduced to 25% to address high vibration in the 12 Steam Generator Feed pump and Reactor Coolant pump lube oil alarms. Full power operation was restored on September 24, but was reduced again that day to 65% to again address abnormal vibration in the 13 Heater Drain pump. Salem Unit 1 returned to full power on September 25, and operated at full power for the remainder of the month.
 
,_
,_
* DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10715798 COMPLETED BY: R. B. Knieriem TELEPHONE:
DOCKET NO.:
(609) 339-1782  
* UNIT:
50-272 Salem 1 DATE:   10715798 COMPLETED BY:         R. B. Knieriem TELEPHONE:       (609) 339-1782


==SUMMARY==
==SUMMARY==
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH: September 1998 The following items completed during September 1998 have been evaluated to determine:
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH: September 1998 The following items completed during September 1998 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 1 OCFR50.59 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 1 OCFR50.59 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 There were no changes in this category implemented during September 1998. Temporary Modifications  
: 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
-Summary of Safety Evaluations There were no changes in this category implemented during September 1998. Procedures  
: 3. If the margin of safety as defined in the basis for any technical specification is reduced.
-Summary of Safety Evaluations TSC.CH-AB.CN-1169 (Q), Steam Generator Carryover Testing This safety evaluation reviewed a procedure to be used for the conduct of steam generator carryover testing. This change was evaluated in accordance with 1 OCFR50.59 because the proposed testing methodology would use lithium hydroxide as the test medium vice sodium 24, and because installation of the test medium injection system required a change to the plant configuration as described in the SAR.
The 1OCFR50.59 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 1OCFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.
* ' The proposed procedure did not involve an unreviewed safety question because . the proposed test methodology and the proposed change to the plant configuration did not increase the probability of a steam generator tube rupture or introduce an accident or malfunction of a different type. In addition, because the test would not result in primary-to-secondary leakage, the margin of safety as defined in the Technical Specifications would not be reduced. SC.MD-CM.ZZ-0024 (Q) -Revision 3, In-service Single Cell Battery Charging This safety evaluation reviewed Revision 3 to the procedure used during maintenance to connect a single cell battery charger to the station non-vital batteries.
Design Changes - Summary of Safety Evaluations There were no changes in this category implemented during September 1998.
This evaluation determined that because the charger was to be used on non-vital batteries, failure of the charger would not increase the probability or consequences of an accident already analyzed; nor create an accident of a different type. Additionally, since the procedure involved non-vital equipment, the change would not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR or reduce the margin of safety as defined in the basis for any Technical Specifications.
Temporary Modifications - Summary of Safety Evaluations There were no changes in this category implemented during September 1998.
UFSAR Change Notices -Summary of Safety Evaluations There were no changes in this category implemented during September 1998. Deficiency Reports -Summary of Safety Evaluations There were no changes in this category implemented during September 1998. Other -Summary of Safety Evaluations There were no changes in this category implemented during September 1998.}}
Procedures - Summary of Safety Evaluations TSC.CH-AB.CN-1169 (Q), Steam Generator Carryover Testing This safety evaluation reviewed a procedure to be used for the conduct of steam generator carryover testing. This change was evaluated in accordance with 1OCFR50.59 because the proposed testing methodology would use lithium hydroxide as the test medium vice sodium 24, and because installation of the test medium injection system required a change to the plant configuration as described in the SAR.
 
                        *                                       '
The proposed procedure did not involve an unreviewed safety question because
    . the proposed test methodology and the proposed change to the plant configuration did not increase the probability of a steam generator tube rupture or introduce an accident or malfunction of a different type. In addition, because the test would not result in primary-to-secondary leakage, the margin of safety as defined in the Technical Specifications would not be reduced.
SC.MD-CM.ZZ-0024 (Q) - Revision 3, In-service Single Cell Battery Charging This safety evaluation reviewed Revision 3 to the procedure used during maintenance to connect a single cell battery charger to the station non-vital batteries. This evaluation determined that because the charger was to be used on non-vital batteries, failure of the charger would not increase the probability or consequences of an accident already analyzed; nor create an accident of a different type. Additionally, since the procedure involved non-vital equipment, the change would not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR or reduce the margin of safety as defined in the basis for any Technical Specifications.
UFSAR Change Notices - Summary of Safety Evaluations There were no changes in this category implemented during September 1998.
Deficiency Reports - Summary of Safety Evaluations There were no changes in this category implemented during September 1998.
Other - Summary of Safety Evaluations There were no changes in this category implemented during September 1998.}}

Revision as of 07:51, 21 October 2019

Monthly Operating Rept for Sept 1998 for Salem,Unit 1.With 981012 Ltr
ML18106A913
Person / Time
Site: Salem PSEG icon.png
Issue date: 09/30/1998
From: Bakken A, Knieriem R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0478, LR-N98-478, NUDOCS 9810190243
Download: ML18106A913 (5)


Text

-. e

~o PS~G

'

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

'

Nuclear Business Unit OCT 121999 LR-N98-0478 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 Gentlemen:

In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating report for September 1998 is attached. I s*ncerely, C. Bakken Ill eneral Manager -

Salem Operations I )

/rbk Enclosures C Mr. H.J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road r-----*-----

King of Prussia, PA 19046 9810190243 980930-. - - - - - * - \

PDR ADOCK 05000272 R PDR The power is in your hands.

95*2168 REV. 6/94

  • DOCKET NO.: 50-272 UNIT: Salem 1 DATE: 10/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: September 1998 OPERATING DATA REPORT Design Electrical Rating (MWe-Net) 1115 Maximum Dependable Capacity (MWe-Net) 1106 Month Year-to-date Cumulative No. of hours reactor was critical 720 4231 108612 No. of hours generator was on line (service 720 3990 104379 hours)

Unit reserve shutdown hours 0 0 0 Net Electrical Energy (MWH) 734538 4057387 104193930 UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE F=FORCED (HOURS) (1) SHUTTING ACTION/COMMENT S=SCHEDULED DOWN THE REACTOR (2)

(1) Reason (2) Method A - Equipment Failure (Explain) 1 - Manual B - Maintenance or Test 2 - Manual Trip/Scram 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 Summary:

Salem Unit 1 began the month of September 1998 operating at full power. Full power operation continued until September 19, when power was reduced to 92% to address abnormal vibration in the 13 Heater Drain pump. The unit returned to full power on the following day. Full power operation continued until September 22, when power was

  • DOCKET NO.:

UNIT:

50-272 Salem 1 DATE: 10715798 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782 reduced to 25% to address high vibration in the 12 Steam Generator Feed pump and Reactor Coolant pump lube oil alarms. Full power operation was restored on September 24, but was reduced again that day to 65% to again address abnormal vibration in the 13 Heater Drain pump. Salem Unit 1 returned to full power on September 25, and operated at full power for the remainder of the month.

,_

DOCKET NO.:

  • UNIT:

50-272 Salem 1 DATE: 10715798 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 1 GENERATING STATION MONTH: September 1998 The following items completed during September 1998 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 1OCFR50.59 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 1OCFR50.59 Safety Evaluations determined that no unreviewed safety or environmental questions are involved.

Design Changes - Summary of Safety Evaluations There were no changes in this category implemented during September 1998.

Temporary Modifications - Summary of Safety Evaluations There were no changes in this category implemented during September 1998.

Procedures - Summary of Safety Evaluations TSC.CH-AB.CN-1169 (Q), Steam Generator Carryover Testing This safety evaluation reviewed a procedure to be used for the conduct of steam generator carryover testing. This change was evaluated in accordance with 1OCFR50.59 because the proposed testing methodology would use lithium hydroxide as the test medium vice sodium 24, and because installation of the test medium injection system required a change to the plant configuration as described in the SAR.

  • '

The proposed procedure did not involve an unreviewed safety question because

. the proposed test methodology and the proposed change to the plant configuration did not increase the probability of a steam generator tube rupture or introduce an accident or malfunction of a different type. In addition, because the test would not result in primary-to-secondary leakage, the margin of safety as defined in the Technical Specifications would not be reduced.

SC.MD-CM.ZZ-0024 (Q) - Revision 3, In-service Single Cell Battery Charging This safety evaluation reviewed Revision 3 to the procedure used during maintenance to connect a single cell battery charger to the station non-vital batteries. This evaluation determined that because the charger was to be used on non-vital batteries, failure of the charger would not increase the probability or consequences of an accident already analyzed; nor create an accident of a different type. Additionally, since the procedure involved non-vital equipment, the change would not increase the probability of occurrence of a malfunction of equipment important to safety previously evaluated in the SAR or reduce the margin of safety as defined in the basis for any Technical Specifications.

UFSAR Change Notices - Summary of Safety Evaluations There were no changes in this category implemented during September 1998.

Deficiency Reports - Summary of Safety Evaluations There were no changes in this category implemented during September 1998.

Other - Summary of Safety Evaluations There were no changes in this category implemented during September 1998.