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| issue date = 07/31/1998
| issue date = 07/31/1998
| title = Monthly Operating Rept for July 1998 for Salem,Unit 2. W/980817 Ltr
| title = Monthly Operating Rept for July 1998 for Salem,Unit 2. W/980817 Ltr
| author name = BAKKEN A C, KNIERIEM R B
| author name = Bakken A, Knieriem R
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:*
{{#Wiki_filter:-~
* Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 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. 2 DOCKET NO. 50-311 Gentlemen:
OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit AUG 1 7 1998 LR-N98-0393 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 2 DOCKET NO. 50-311 Gentlemen:
AUG 1 7 1998 LR-N98-0393 In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating report for July 1998 is attached.  
In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating report for July 1998 is attached.                             I Sincerely,
/rbk Enclosures C Mr. H.J. Miller Sincerely, A. C. Bakken Ill General Manager -Salem Operations Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 9aoa21oi6a 9ao73i ___
                                                        ~A. C. Bakken Ill General Manager -
PDR ADOCK 05000311 R PDR The power is in your hands. I 95-2168 REV. 6/94
Salem Operations
* Reporting Period: July 1998
  /rbk Enclosures C      Mr. H.J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 9aoa21oi6a 9ao73i___ ~--~--------,
* DOCKET NO.: 50-311 UNIT: Salem 2 DA TE: 8/15/98 COMPLETED BY: R. Knieriem TELEPHONE:  
PDR     ADOCK 05000311 R                         PDR The power is in your hands.
(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 581 4191 85397 No. of hours generator was on line (service 579 4099 82163 hours) Unit reserve shutdown hours 0.0 0.0 0.0 Net Electrical Energy (MWH) 620164 4371557 81547142 UNIT SHUTDOWNS NO. DATE TYPE F=FORCED S=SCHEDULED 4 7/25/98 F -7/31/98 (1) Reason A -Equipment Failure (Explain) B -Maintenance or Test C-Refueling D -Regulatory Restriction DURATION (HOURS) 165 E -Operator Training/License Examination F -Administrative G -Operational Error (Explain) H -Other Summary: REASON METHOD OF (1) SHUTTING DOWN THE REACTOR (2) B 1 (2) Method 1 -Manual 2 -Manual Trip/Scram 3 -Automatic Trip/Scram 4 -Continuation 5 -Other (Explain)
95-2168 REV. 6/94
CORRECTIVE ACTION/COMMENT Pressurizer Safety Valve Replacement Salem Unit 2 began the month of July 1998 operating at full power. Full power operation continued until July 25, 1998 when the unit was removed from service to replace three pressurizer safety valves and to conduct various technical specification surveillances.
 
This shutdown continued through' the end of the month. -
DOCKET NO.:
. * *
UNIT:
* DOCKET NO.: 50-311 UNIT: Salem 2 DATE: 8/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE:  
DATE:
(609) 339-1782  
50-311 Salem 2 8/15/98 COMPLETED BY:         R. Knieriem TELEPHONE:       (609) 339-1782 Reporting Period: July 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                         581             4191                 85397 No. of hours generator was on line (service               579             4099                 82163 hours)
Unit reserve shutdown hours                               0.0             0.0                   0.0 Net Electrical Energy (MWH)                             620164           4371557               81547142 UNIT SHUTDOWNS NO. DATE       TYPE             DURATION  REASON      METHOD OF        CORRECTIVE F=FORCED         (HOURS)    (1)          SHUTTING        ACTION/COMMENT S=SCHEDULED                             DOWN THE REACTOR (2) 4     7/25/98             F             165        B              1        Pressurizer Safety Valve
          -                                                                   Replacement 7/31/98 (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 2 began the month of July 1998 operating at full power. Full power operation continued until July 25, 1998 when the unit was removed from service to replace three pressurizer safety valves and to conduct various technical specification surveillances. This shutdown continued through' the end of the month.
 
DOCKET NO.:
UNIT:
DATE:
50-311 Salem 2 8/15/98 COMPLETED BY:         R. B. Knieriem TELEPHONE:         (609) 339-1782


==SUMMARY==
==SUMMARY==
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH: July 1998 The following items completed during July 1998 have been evaluated to determine:.  
OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH: July 1998 The following items completed during July 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 July 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 July 1998. Procedures  
: 3. If the margin of safety as defined in the basis for any technical specification is reduced.
-Summary of Safety Evaluations There were no changes in this category implemented during July 1998. UFSAR Change Notices -Summary of Safety Evaluations There were no changes in this category implemented during July 1998. Deficiency Reports -Summary of Safety Evaluations There were no changes in this category implemented during July 1998.
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 There were no changes in this category implemented during July 1998.
* Other -Summary of Safety Evaluations
Temporary Modifications - Summary of Safety Evaluations There were no changes in this category implemented during July 1998.
* There were no changes in this category implemented during July 1998. '}}
Procedures - Summary of Safety Evaluations There were no changes in this category implemented during July 1998.
UFSAR Change Notices - Summary of Safety Evaluations There were no changes in this category implemented during July 1998.
Deficiency Reports - Summary of Safety Evaluations There were no changes in this category implemented during July 1998.
 
                                            -~.-
Other - Summary of Safety Evaluations There were no changes in this category implemented during July 1998.
          '}}

Latest revision as of 04:52, 3 February 2020

Monthly Operating Rept for July 1998 for Salem,Unit 2. W/980817 Ltr
ML18106A815
Person / Time
Site: Salem PSEG icon.png
Issue date: 07/31/1998
From: Bakken A, Knieriem R
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N98-0393, LR-N98-393, NUDOCS 9808210168
Download: ML18106A815 (4)
v • d • e


Text

-~

OPS~G Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit AUG 1 7 1998 LR-N98-0393 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Attn: Document Control Desk MONTHLY OPERATING REPORT SALEM UNIT NO. 2 DOCKET NO. 50-311 Gentlemen:

In compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original Monthly Operating report for July 1998 is attached. I Sincerely,

~A. C. Bakken Ill General Manager -

Salem Operations

/rbk Enclosures C Mr. H.J. Miller Regional Administrator USNRC, Region 1 475 Allendale Road King of Prussia, PA 19046 9aoa21oi6a 9ao73i___ ~--~--------,

PDR ADOCK 05000311 R PDR The power is in your hands.

95-2168 REV. 6/94

DOCKET NO.:

UNIT:

DATE:

50-311 Salem 2 8/15/98 COMPLETED BY: R. Knieriem TELEPHONE: (609) 339-1782 Reporting Period: July 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 581 4191 85397 No. of hours generator was on line (service 579 4099 82163 hours)

Unit reserve shutdown hours 0.0 0.0 0.0 Net Electrical Energy (MWH) 620164 4371557 81547142 UNIT SHUTDOWNS NO. DATE TYPE DURATION REASON METHOD OF CORRECTIVE F=FORCED (HOURS) (1) SHUTTING ACTION/COMMENT S=SCHEDULED DOWN THE REACTOR (2) 4 7/25/98 F 165 B 1 Pressurizer Safety Valve

- Replacement 7/31/98 (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 2 began the month of July 1998 operating at full power. Full power operation continued until July 25, 1998 when the unit was removed from service to replace three pressurizer safety valves and to conduct various technical specification surveillances. This shutdown continued through' the end of the month.

DOCKET NO.:

UNIT:

DATE:

50-311 Salem 2 8/15/98 COMPLETED BY: R. B. Knieriem TELEPHONE: (609) 339-1782

SUMMARY

OF CHANGES, TESTS, AND EXPERIMENTS FOR THE SALEM UNIT 2 GENERATING STATION MONTH: July 1998 The following items completed during July 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 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 There were no changes in this category implemented during July 1998.

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

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

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

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

-~.-

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

'

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