Justification for Operation of Units 1 & 2 W/Limited 4KV Loads.| ML18093A662 |
| Person / Time |
|---|
| Site: |
Salem  |
|---|
| Issue date: |
08/31/1986 |
|---|
| From: |
Public Service Enterprise Group |
|---|
| To: |
|
|---|
| Shared Package |
|---|
| ML18093A661 |
List: |
|---|
| References |
|---|
| S-C-E130-NSE-04, S-C-E130-NSE-0458-0, S-C-E130-NSE-4, S-C-E130-NSE-458, NUDOCS 8802250229 |
| Download: ML18093A662 (6) |
|
Similar Documents at Salem |
|---|
Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18107A3151999-04-30030 April 1999
Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1
ML18106A6821998-06-24024 June 1998
Revised Charting Our Future.
ML18106A6681998-06-17017 June 1998
Charting the Future.
ML18106A2571998-01-19019 January 1998
Nuclear Business Unit Future Objectives.
ML18106A2131997-12-15015 December 1997
Safety Evaluation Supporting Rev to TS to Adopt Option B of 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18102B3331997-02-28028 February 1997
Rev 0 to Cfcu Return Piping Inside CTMT,221F Temp Effect.
ML20133D2201996-12-0606 December 1996
Root Cause Analysis of Struthers-Dunn Operate-Reset Relay Latch Failures for Salem Generating Station
ML20133D2251996-10-30030 October 1996
Struthers-Dunn Model 255XCXP Relay Root Cause Evaluation for Salem Nuclear Generation Station
ML18102A3231996-07-0101 July 1996
Reg Guide 1.121 Assessment of Indications at Salem Unit 2.
ML18102A1591996-06-0404 June 1996
Fuel Handling Accident Analysis Radiological Evaluation.
ML20101M6601996-03-24024 March 1996
Supplemental Submittal in Response to NRC GL 87-02/USI A-46, 'Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.'
ML18102A1321996-03-15015 March 1996
Change 2EC-3332 to Rev 0 to Design Analysis, 125 Vdc Battery Charger Replacement.
ML18102B0201996-02-28028 February 1996
Rev 0 to Evaluation of Structures for Increased Temps Due to Updated Main Steam Line Break.
ML20129K1031995-07-10010 July 1995
Exam of Fasteners from Salem Nuclear Generating Station
ML18101A7481995-05-19019 May 1995
Safe Shutdown Equipment List Rept for Salem Generating Station Units 1 & 2
ML18101A7491995-04-25025 April 1995
Relay Evaluation Rept, Volumes 1 & 2, for Salem Generating Station Units 1 & 2
ML18101A7501995-04-20020 April 1995
Seismic Evaluation Rept, for Salem Generating Station
ML20134K1031995-03-24024 March 1995
Organizational Effectiveness Assessment Rept for Sngs,
ML18102B6541995-03-24024 March 1995
Organizational Effectiveness Assessment Rept for Plant, Redacted Version
ML18101A4391994-12-21021 December 1994
Fire Protection Review of Salem Reactor Coolant Pump Oil Collection Sys, Dtd 941221
ML20134C5791994-10-23023 October 1994
Salem/Maint SC.MD-GP.SW-0001(Q) Svc Water Silt Survey, Rev 5
ML18106B0541994-01-31031 January 1994
Criticality Analysis of Salem Units 1 & 2 Fresh Fuels Racks.
ML18100A7971993-12-23023 December 1993
Simulator Four-Year Certification Rept.
ML20069M2221993-10-15015 October 1993
Flux Thimble Thermocouple Ultrasonic Profilometry & Eddy Current Encircling Coil Insp of Stored Thimble Tubes Jul-Aug 1993
ML18100A6281993-09-16016 September 1993
Updated Page A4-4 of Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis, Changing Figure Numbers A5-1 & A5-2 to A4-1 & A4-2 at End of First Paragraph
ML18100A6801993-08-20020 August 1993
Engineering Evaluation of Sgs 1 & 2 Control Room Evacuation for Fire Induced MOV Hot Shorts as Discussed in NRC Info Notice 92-018.
ML20045B8801993-05-21021 May 1993
Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis for Salem Nuclear Generating Station, Units 1 & 2.
ML18100A3401993-04-28028 April 1993
Licensing Rept for Spent Fuel Storage Capacity Expansion Pse&G,Salem Generation Station,Units 1 & 2.
ML18096B3561993-02-11011 February 1993
Cycle 8 Peaking Factor Limit Rept.
ML20135A8141992-12-29029 December 1992
Control Room Overhead Annunciator Lock-Up of 921213
ML18096B1661992-11-13013 November 1992
Rev 1 to Fracture Toughness Analysis for Salem Units 1 & 2 Reactor Pressure Vessels to Protect Against Pressurized Thermal Shock Events,10CFR50.61.
ML18096B0081992-09-0202 September 1992
Analytical Data Rept, for Project 28173
ML18096A8061992-06-17017 June 1992
Rev 0 to Salem Unit 2 Response to Generic Ltr 92-01,Rev 1, 'Reactor Vessel Structural Integrity.'
ML18096A8051992-06-17017 June 1992
Rev 0 to Salem Unit 1 Response to Generic Ltr 92-01,Rev 1, 'Reactor Vessel Structural Integrity.'
ML18096A5831992-03-31031 March 1992
Rev 1 to Estimated Frequency of Loss of Off-Site Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations.
ML18095A5151990-07-31031 July 1990
Vol 1 to Spring 1990 NDE of Selected Class 1 & Class 2 Components of Salem Generating Station,Unit 2.
ML18095A3691990-07-26026 July 1990
Unit 1 Decommissioning Rept.
ML18095A3681990-07-26026 July 1990
Unit 2 Decommissioning Rept.
ML18095A3791990-07-20020 July 1990
Decommissioning Rept of Philadelphia Electric Co.
ML18094B2241989-12-28028 December 1989
Simulator NRC Certification, Vols I-III
ML18094A3551989-04-30030 April 1989
Assessment of Impacts of Salem & Hope Creek Generating Stations on Kemps Ridley (Lepidochelys Kempi) & Loggerhead (Carretta Caretta) Sea Turtles.
ML20086U2571989-03-31031 March 1989
Estimated Frequency of Loss of Offsite Power Due to Extremely Severe Weather & Severe Weather for Salem & Hope Creek Generating Stations
ML18093B2021988-09-30030 September 1988
Special Rept on Spare CRD Mechanism Weld Refurbishments.
ML18093A7601988-02-18018 February 1988
Appendix R/Breaker Coordination as-Found Review (Pre-Audit 1987).
ML18093A5471987-12-10010 December 1987
Breaker Coordination W/Respect to External & Internal Hazards.
ML18093A4531987-10-14014 October 1987
Justification for Continued Operation of Salem Units 1 & 2 W/Outstanding Fire Protection Concerns.
ML18093A4131987-10-0101 October 1987
Justification for Continued Operation of Salem Units 1 & 2 W/Outstanding Fire Protection Concerns.
ML18093A3781987-09-16016 September 1987
Rev 7 to, Westinghouse Engineering Svcs Rept for Salem Nuclear Generating Station Units 1 & 2 Concerning RHR Sys Mid-Loop Operation Re NRC Generic Ltr 87-12.
1999-09-30
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
ML18107A5581999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With 991014 Ltr
ML18107A5571999-09-30030 September 1999
Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With 991014 Ltr
ML18107A5301999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 990913 Ltr
ML18107A5311999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913
ML18107A5031999-08-26026 August 1999
LER 99-006-00:on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With 990826 Ltr
ML18107A5201999-08-12012 August 1999
Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#9) Second Interval,Second Period, First Outage (96RF).
ML18107A4811999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 1.With 990813 Ltr
ML18107A4821999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Salem,Unit 2.With 990813 Ltr
ML18107A4691999-07-28028 July 1999
LER 99-008-00:on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With 990728 Ltr
ML18107A4441999-07-0606 July 1999
LER 99-007-00:on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With 990706 Ltr
ML18107A4211999-07-0202 July 1999
LER 99-005-00:on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With 990702 Ltr
ML18107A4331999-07-0101 July 1999
LER 99-002-01:on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With 990701 Ltr
ML18107A4321999-07-0101 July 1999
LER 99-006-01:on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With 990701 Ltr
ML18107A5211999-07-0101 July 1999
Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO#10) Second Interval,Second Period,Second Outage (99RF).
ML18107A4351999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 1.With 990713 Ltr
ML18107A4341999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Salem,Unit 2.With 990713 Ltr
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
ML18107A3951999-06-17017 June 1999
LER 99-004-00:on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With 990617 Ltr
ML18107A3661999-06-0909 June 1999
LER 99-003-00:on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With 990609 Ltr
ML18107A3551999-06-0202 June 1999
LER 99-005-00:on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With 990602 Ltr
ML18107A3441999-06-0101 June 1999
Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716
ML18107A3541999-06-0101 June 1999
LER 99-006-00:on 990501,HHSI Flow Balance Discrepancy Was Noted During Surveillance.Caused by Sticking of Check Valve in SI Discharge Line to 21 Cold Leg.Valve 21SJ17,was Cut Out of Sys & Replaced.With 990601 Ltr
ML18107A3681999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With 990611 Ltr
ML18107A3721999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With 990611 Ltr
ML18107A2931999-05-12012 May 1999
LER 99-002-00:on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With 990512 Ltr
ML18107A2781999-05-10010 May 1999
LER 99-004-00:on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With 990505 Ltr
ML18107A2791999-05-0404 May 1999
LER 99-003-00:on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With 990504 Ltr
ML18107A2741999-05-0303 May 1999
LER 99-002-00:on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With 990504 Ltr
ML18107A3711999-04-30030 April 1999
Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1
ML18107A3151999-04-30030 April 1999
Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1
ML18107A2991999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Salem Unit 1.With 990514 Ltr
ML18107A2971999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Salem Unit 2.With 990514 Ltr
ML18107A2351999-04-23023 April 1999
LER 99-001-00:on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With 990423 Ltr
ML18107A2881999-04-0707 April 1999
Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11.
ML18107A1821999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With 990414 Ltr
ML18107A1831999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 990414 Ltr
ML18106B1471999-03-29029 March 1999
LER 99-001-00:on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with 990329 Ltr
ML18106B1021999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Salem Unit 2.With 990315 Ltr
ML18106B1011999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Salem Unit 1.With 990315 Ltr
ML18106B0931999-02-25025 February 1999
Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified
ML18106B0701999-02-16016 February 1999
LER 98-015-00:on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With 990216 Ltr
ML18106B0551999-02-0101 February 1999
Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl
ML18106B0561999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 2.With 990212 Ltr
ML18106B0571999-01-31031 January 1999
Monthly Operating Rept for Jan 1999 for Salem Generating Station,Unit 1.With 990212 Ltr
ML20205P1671999-01-31031 January 1999
a POST-PLUME Phase, Federal Participation Exercise
ML18106B0441999-01-29029 January 1999
Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables
ML18106B0491999-01-28028 January 1999
LER 98-007-01:on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With 990128 Ltr
ML18106B0401999-01-18018 January 1999
LER 98-016-00:on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With 990118 Ltr
ML18106B0251998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Salem Unit 2.With 990115 Ltr
1999-09-30
[Table view] |
Text
ATTACHMENT 1 Page 1 of 3 PS~G
/
S-C-El30-NSE-0458-0 Date: 8/31/86 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Department TITLE: JUSTH'ICATION FUR OPERATION OF UNITS 1 AND 2 WITH LIMITED 4KV LOADS
1.0 PURPOSE
This safety evaluation is being written to justify the continued safe operation of Salem Unit #1 and Unit #2 following the reactor trip/safety injection and subsequent loss of offsite power indication which occurred on Salem Unit #2 on August 26, 1986.
2.0 SCOPE
This safety evaluation is applicable to the operation of both Salem Unit #1 and Salem Unit #2.
3.0 REFERENCES
3.1 U.S. NRC letter "Adequacy of Station Electrical Distribution System Voltages at Salem Units 1 and 2" to F. W. Schneider, dated October 21, 1981.
3.2 "Adequacy of Station Electric Distribution System Voltages, Salem Nuclear Power Station Units 1 and 2".
Prepared for U.S. NRC by EG&G Idaho, Inc., June, 1981.
3.3 U.F.S.A.R., Section 8 and Section 3 3.4 Salem Nuclear Generating station Technical Specifi-cations bases.
3.~ G.o.c. 17, Electric Power Systems 3.6 Public Service Electric and Gas Company Drawings 203061 A8789 and 203062 A8789 4.U DISCUSSION:
Un August 26, 1986, Unit #2 experienced a reactor trip and safety injection tallowed shortly by a loss of offsite power to the 4KV vital A, B, & C electrical busses. Initially on the safety injection, all safeguards loads loaded simultaneously in accordance with the desiyn. Subsequent to the safety injection an indication of loss of offsite power was received. The "A" and "C" vital bus loads sequenced onto the diesels as per design. The "B" vital bus remained deenergized because the "B" diesel generator was tagged for 8802250229 860831 PDR ADOCK 05000272 p PDR L NED/~O 11.
- FORM l REV 0 1USEPT81 95-216811001\11 ;2-8J
Page 2 of 3 Date: 8/31/86 maintenance. (Two vital 4160 volt busses are required to provide minimum safeguards equipment). Upon investigation it was determined that equipment failures did not initiate the loss of offsite power event. The investigation revealed that a transient stability analysis had not been performed on the plant since June, 1981. Plant loads have been modified on the basis of a static loading analysis only.
The changes in plant loads may be found in Attachment #1.
The June, 1981 transient stability analysis was performed by Public Service Electric and Gas (PSE&G) and supplied to the U.S. NRC in accordance with a request dated August 8, 1979. The U.S. NRC then submitted this study to their contractor EG&G, Idaho, Inc. for review. The U.S. NRC then supplied PSE&G with a Safety Evaluation Report which approved the Salem Unit No. 1 and Unit No. 2 electric distribution system (Reference 3.2).
5.0 RECOMMENDATIONS Since a transient stability analysis has not been performed since June, 1981, operation of the Salem Unit #1 and Unit #2 plants may only be continued when the plant loads are returned to within the values identified in the study and approved by the NRC. In addition, the plant loads will be supplied from the station power transformers with the auxiliary power transformer group bus infeed breakers open.
This will further remove the potential transient load added to the station power transformers when a group bus transfers from the Auxiliary power transformer. The reduced loads identified in Attachment II will result in more conservative loads than that which were identified in the June 1981 study.
6.0 CONCLUSION
S:
The continued operation of Salem Units 1 & 2 is justified on the basis ot the discussion above. Implementation of the above recommendations do not constitute an Unreviewed Safety Question since, a) It does not involve a modification, test or experiment associated with equipment important to safety, but rather the administrative operation of balance of plant equipment, b) It is based on the results of analysis for a modification of a type previously approved by the NRC (Ref.
3.2), c) It recommends the administrative control of oper-ation of non-vital equipment that are not part of the basis for any Technical Specification (See attachment).
7.0 VENDOR MANUAL IMPACT None.
NED/50 11.*FORM 1 REV 0 10SEPT81
Page 3 of 3 Date : 8 I 3 1I8 6
8.0 SIGNATURES
~J
,ew. ~."-1L tJbJ/e<o
/)_;J ch~~ 9/:31/?6 Originator Date Verifier DbtJ
-!.~ ~er Group Head
/'M--v-. ~~/;,r Group Head System Analysis Manager - Date Plant Engineering NED/50 11.* FORM 1 REV 0 1 OS E.l?T81
ATTACHMENT I - Changes in plant loads Unit 1 11 Station Power Transformer 12 Station Power Transformer Group 2000 KVA ( 2 ) Cond. Pumps 1000 KVA ( 1 ) Cond. Pump Busses 333 KVA Misc. Subs. 333 KVA Misc. Subs.
Vital 833 KVA Mi SC. Subs 833 KVA Misc. Subs Buss es 3166 KVA Total 2166 KVA Total Unit 2 21 Station Power Trans former 22 Station Power Transformer Group 6000 KVA ( 3) Cond. Pumps 1000 KVA ( 1 ) Cond. Pump Busses 1000 KVA Non Rad Waste 333 KVA Misc. Subs.
333 KVA Mi SC. Subs Vital 833 KVA Mi SC. (Subs) 833 KVA Misc. Subs Buss es 8166 KVA Total 2166 KVA Total
ATTACHMENT II Equipment to be out of service to obtain reduction of Station Power Transformer Loads Unit #1 11 Station Power Transformer 12 Station Power Transformer must reduce by 3166 KVA, any must reduce by 2166 KVA, any of the following may be removed of the following may be removed from service to total 3166 KVA. from service to total 2166 KVA.
11 Cond. Pump - 4000 KVA* 13 Cond. Pump - 4000 KVA 12 Cond. Pump - 4000 KVA 12 Heater Drain Pump - 1000 KVA 11 Heater Drain Pump - 1000 KVA 13 Heater Drain Pump - 1000 KVA llA Circ. Water Pump - 2000 KVA llB Circ. Water Pump - 2000 KVA 12A Circ. Water Pump - 2000 KVA 12B Circ. Water Pump - 2000 KVA 13A Cond. Pump - 4000 KVA 13B Circ. Water Pump - 2000 KVA Unit #2 21 Station Power Transformer 22 Station Power Transformer must reduce by 8166 KVA, any must reduce by 2166 KVA, any of the following may be removed of the following may be removed from service to total 8166 KVA* from service to total 2166 KVA.
11 Cond. Pump - 4000 KVA** 23 Cond. Pump - 4000 KVA 21 Cond. Pump - 4000 KVA 22 Heater Drain Pump - 1000 KVA 22 Cond. Pump - 4000 KVA 23 Heater Drain Pump - 1000 KVA 21 Heater Drain Pump - 1000 KVA 218 Circ. Water Pump - 2000 KVA 21A Circ. Wat.er Pump - 2000 KVA 22B Circ. Water Pump - 2000 KVA 22A Circ. Water Pump - 2000 KVA 238 Circ. Water Pump - 2000 KVA 23A Circ. Water Pump - 2000 KVA
- - - - - - - - - - - - - - - - - - - - - - : - -*..... , .... ccc
.. ~-;--;:
...-;-;,,,...,,..~
ATTACHMENT 2
(
IMMEDIATE CORRECTIVE ACTIONS
- 1. Station electrical bus loadings will be reduced to levels consistent with those used in the Salem degraded grid voltage study performed by EG&G, Idaho, Inc. on behalf of the NRC. This condition shall be maintained until Item 1 under Long Term Corrective Actions is complete.
- 2. Procedures will be generated or revised as necessary to administratively control equipment removed from service in order to reach the reduced buss load levels.
- 3. Appropriate evaluations will be performed in accordance with the provisions of lDCFRS0.59 to justify continued operation.
- 4. The station electrical lineup will be shifted such that all station electrical loads are powered from the Station Power Transformers.
LONG TERM CORRECTIVE ACTIONS
- 1. PSE&G shall conduct a comprehensive design analysis of the Salem Generating Station electrical distribution system.
The analysis will include consideration of transients in accordance with appropriate regulatory criteria.
- 2. An analysis of the present protective and relaying and breaker scheme will be performed to determine the root cause of the vital bus multiple transfer phenomena and establish corrective actions to preclude recurrence.
- 3. Updated status reports shall be forwarded to the Regional Administrator on a monthly basis until such time as all corrective actions are complete.