Similar Documents at Salem |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9
ML20211Q8771999-08-27027 August 1999
Rev 0 to Inservice Testing Manual for Pumps & Valves Program
ML18107A5171999-08-25025 August 1999
Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2
ML18107A5121999-08-23023 August 1999
Procedure 71151, Performance Indicator Verification.
ML18107A5091999-08-23023 August 1999
Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability.
ML18107A4961999-08-23023 August 1999
Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys.
ML18107A4671999-07-29029 July 1999
Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements
ML18107A4601999-07-23023 July 1999
Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown
ML18107A4241999-07-0202 July 1999
Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR
ML18107A3811999-06-10010 June 1999
Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means
ML18107A3601999-06-0404 June 1999
Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC
ML18107A2961999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9
ML18107A2131999-04-14014 April 1999
Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431
ML18106B1591999-03-31031 March 1999
Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918
ML18106B0801999-02-22022 February 1999
Proposed Tech Specs Re CR Emergency Air Conditioning Sys
ML18106B0641999-02-0808 February 1999
Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing
ML18106B0611999-02-0808 February 1999
Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions.
ML18106B0531999-02-0202 February 1999
Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel
ML18106B0431999-01-19019 January 1999
Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys
ML18106B0241999-01-15015 January 1999
Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1
ML18106A9231998-10-12012 October 1998
Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03
ML18106A9181998-10-12012 October 1998
Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10
ML18106A8941998-09-29029 September 1998
Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch
ML18106A8781998-09-17017 September 1998
Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity
ML18106A8371998-08-12012 August 1998
Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door
ML18106A7931998-07-30030 July 1998
Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase
ML18106A6961998-07-0707 July 1998
Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan
ML18106A6631998-06-17017 June 1998
Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements
ML20216B0641998-05-0101 May 1998
Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page
ML18106A5571998-04-16016 April 1998
Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents
ML20239A1251998-03-31031 March 1998
Rev 11 to Salem Nuclear Generating Station Odcm
ML18106A4241998-03-26026 March 1998
Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters.
ML18106A4291998-03-26026 March 1998
Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2
ML18106A3921998-03-13013 March 1998
Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency.
ML18106A8281998-03-0404 March 1998
Rev 1 to Reactivity Manipulations Documentation Guide.
ML18106A3221998-02-18018 February 1998
Marked-up TS Pages for Section 4.2.1 of App B
ML18106A3091998-02-0202 February 1998
Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation
ML18106A2541998-01-0808 January 1998
Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page
ML18106A2141997-12-15015 December 1997
Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18106A1961997-12-11011 December 1997
Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4
ML18102B6791997-11-14014 November 1997
Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels
ML18102B6751997-11-14014 November 1997
Proposed Tech Specs Re Administrative & Editorial Corrections
ML18102B6591997-11-0404 November 1997
Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid
ML18102B6631997-11-0404 November 1997
Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown
ML18102B6431997-10-29029 October 1997
Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing
ML18102B6391997-10-29029 October 1997
Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10
ML18102B6491997-10-24024 October 1997
Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases
ML18102B6461997-10-24024 October 1997
Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1
ML18102B6321997-10-21021 October 1997
Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position
ML18102B6201997-10-14014 October 1997
Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2
1999-09-10
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18107A5291999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9
ML20211Q8771999-08-27027 August 1999
Rev 0 to Inservice Testing Manual for Pumps & Valves Program
ML18107A5121999-08-23023 August 1999
Procedure 71151, Performance Indicator Verification.
ML18107A5091999-08-23023 August 1999
Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability.
ML18107A2961999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9
ML20216B0641998-05-0101 May 1998
Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page
ML18106A5571998-04-16016 April 1998
Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents
ML20239A1251998-03-31031 March 1998
Rev 11 to Salem Nuclear Generating Station Odcm
ML18106A3921998-03-13013 March 1998
Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency.
ML18106A8281998-03-0404 March 1998
Rev 1 to Reactivity Manipulations Documentation Guide.
ML18102B6681997-10-0101 October 1997
Rev 8 to Inservice Testing Manual for Pumps & Valves Program.
ML18106A8291997-09-0404 September 1997
Rev 2 to Reactivity Manipulations Documentation Guide. Page to Training Manual NC.TQ-TP.ZZ-0302,encl
ML18102A7941997-01-21021 January 1997
Event Classification Guide,Technical Basis, for Hope Creek Generating Station & Salem
ML18102A7931997-01-21021 January 1997
Event Classification Guide,Technical Basis, Salem Generating Station
ML18102A6661996-11-19019 November 1996
Rev 2 to Pse&G Simulation Facility Certification Program.
ML20115B7791996-07-0303 July 1996
Final Draft, Hope Creek Event Classification Guide, Sections 1-9
ML18101B1141995-11-14014 November 1995
Revised Salem Generating Station Event Classification Guide, Including Rev 46 to Table of Contents,Rev 37 to Attachments Signature Page,Rev 26 to Attachment 6,Rev 25 to Attachment 7 & Rev 24 to Attachment 9
ML20091M9911995-10-15015 October 1995
Event Classification Guide HCGS, Including Revised Eals, Technical Basis Document & NUMARC EAL-to-Hope Creek Comparison Summary
ML18101A6911995-05-31031 May 1995
Nbu Issue Mgt & Prioritized Action Plan, Dtd May 1995
ML18101A7711995-05-11011 May 1995
Rev 1A to Vol a of Salem Generating Station Unit 2 Second 10-Yr Insp Interval ISI Program Plan.
ML20134K0831995-02-27027 February 1995
Pse&G/Nuclear Business Unit Organizational Effectiveness Assessment Plan,
ML18101A6751995-02-16016 February 1995
Rev 11 to EOP 1-EOP-TRIP-1, Reactor Trip or Safety Injection.
ML18101A6761995-02-16016 February 1995
Rev 12 to EOP 1-EOP-TRIP-2, Reactor Trip Response.
ML18101A5381995-01-27027 January 1995
Revised Salem Generating Station Event Classification Guide.
ML18101A2111994-08-17017 August 1994
Revised Salem Event Classification Guide.
ML18101A6771994-07-11011 July 1994
Rev 10 to EOP 1-EOP-TRIP-3, Safety Injection Termination.
ML20147B1601994-04-23023 April 1994
Rev 3 to S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation
ML18100A8081994-01-0707 January 1994
Rev 30 to Salem Generating Station Event Classification Guide.
ML20147B1491993-11-0202 November 1993
Rev 2 to Procedure S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation
ML18100A4201993-06-15015 June 1993
Justification for Sgs Units 1 & 2 Restart & Operation Rod Control Sys Failures.
ML18100A3771993-05-0505 May 1993
Rev 27 to Salem Generating Station Event Classification Guide.
ML18100A3661993-04-27027 April 1993
Rev 8 to Section 18 to Event Classification Guide, Correcting Typo on Pages 3 & 5 of 6
ML20147B1171993-04-13013 April 1993
Rev 1 to Procedure NC.NA-AP.ZZ-0015(Q), Safety Tagging Program
ML18096B3251993-02-26026 February 1993
Integrated Scheduling Program.
ML18096B2911993-02-10010 February 1993
Revised Event Classification Guide,Including Rev 25 to Table of Contents,Rev 14 to Attachment 6,Rev 13 to Attachment 7, Rev 8 to Attachment 8,Rev 13 to Attachment 9,Rev 3 to Section 10,Rev 4 to Section 17 & Rev 7 to Section 18
ML20147B1021993-01-21021 January 1993
Rev 5 to Procedure NC.NA-AP.ZZ-0009(Q), Work Control Process
ML20135B6521992-12-29029 December 1992
Rev 0 to Loss of Overhead Annunciator Sys
ML20147B1371992-12-22022 December 1992
Rev to Procedure SC.RP-TI.ZZ-0209(Q), Release of Items from Rca
ML20147B2051992-09-21021 September 1992
Rove Time Keeping Procedure
ML18096A9601992-08-28028 August 1992
Electrical Distribution Sys Functional Insp (Edsfi) Methodology & Plan.
ML18100A3151992-07-28028 July 1992
Rev 1 to Process Computer Maint & Mod Control Program.
ML18096B3191992-07-17017 July 1992
Rev 8 to Salem Nuclear Generating Station Odcm.
ML20147B1691992-05-0707 May 1992
Rev 1 to Procedure NC.NA-AP.ZZ-0013(Q), Control of Temporary Modifications
ML18096A6791992-04-30030 April 1992
Vols A-D of Salem Generating Station Unit 2 Inservice Insp Program (Second Insp Interval) Long-Term Plan.
ML18096A4421992-01-15015 January 1992
Rev 17 to Salem Generating Station Event Classification Guide
ML18096A3211991-10-0404 October 1991
Rev 13 to Event Classification Guide,Including Table of Contents,Section Signature Pages,Spill/Discharge Notification Form & Related Pages
ML18096A1431991-06-28028 June 1991
Rev 12 to Salem Generating Station Event Classification Guide.
ML18095A9661991-05-30030 May 1991
Artificial Island Salem Event Classification Guide, Rev 11
ML18096A1191991-05-28028 May 1991
Rev 2 to NFU-0039, Salem Reactor Physics Methods.
ML18095A9391991-05-16016 May 1991
Revised Replacement Pages to Facility Inservice Testing Program
1999-09-10
[Table view] |
Text
NOTE: PRESS HARD YOU ARE MAKING FIVE (5) COPIES ADMINISTRATIVE PROCEDURE 3 CHANGE TYPE:
ON-THE-SPOT CHANGE rt7t L.l:::i- PERMANENT (GREEN)
D *TEMPORARY (ORANGE)
! PROCEDURE TITLE SS Br *EXPIRES:
ALL ON-THE-SPOT CHANGES TO BE CONSIDERED FOR APPLICABILITY TO BOTH UNITS.
~UNIT! PROCEDURE No. _\_-_P_~_-_1_~_,__\__,_o_o_S-=--- REV. NO. _ _.\_ _ _ CHANGE NO. _ _ __
ISlJ UNIT Z PRocEDURE No.~2.-=-~P~.b~-__;_1g=-:..,~l~,~o::;....:::o~~-=-~~ REV. No. _ _.___ CHANGE NO._.....__ _
PROPOSED CHANGE:
Co ue-r- Sh..ee...t""
J) e ..Je. te. ,, r "- i s REASON FOR CHANGE:
To ACTION TAKEN FOR OTHER UNIT:
AUTHORIZATION:
'**SUPERVISOR IN CHARGE
//lz~'- \.
CATE OR SHIFT SUPERVISOR
- SIGNATURE ALSO VERIFIES THAT APPLICABILITY TO BOTH UNITS HAS BEEN CONSIOEREO.
ACCEPTABLE: POST CHANGE-REVIEW/APPROVAL o~
YES NO fi_§'L-1zpir;;
I MANAG~* SALEM GENERATING STATION 1-i.-/~/~
r ATE RETURN COMPLETED OR REJECTED FORM TO DEPARTMENT REQUESTING CHANGE.
FOLLOW-UP TO REJECTED ON-THE-SPOT CHANGE ACTION TAKEN:
~ -930316056f-830314 PDR ADDCK 05000272 S PDR PERFORMED BY:
SIGNATURE CATE RETURN TO DEPARTMENT HEAD FOR ROUTING THROUGH POST CHANGE-REVIEW/APPROVAL CYCLE.
FORM AP*3*t REV. 9
SALEM NUCLEAR GENERATING STATION PUBLIC SERVICE ELECTRIC & GAS COMPANY ELECTRIC GENERATION DEPARTMENT PROCEDURE APPROVAL COVER SHEET SAFETY RELATED lPD-18.1.005 SOLID STATE PROTECTION SYSTEM PROCEDURE:
REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST - TRAIN B REMARKS:
REV. 1 - General Revision to incorporate On-The-Spot-Changes.
EEO QA PERF. ENGR. SORC STA. SUPT.
REV SUBMITTED APPROVED .REVIEWED APPROVED REVIEWED APPROVED
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~~-::..:._*.**-*.**-;r.--:* ......-,-:.*0-:-;,..~)1"1;<~'"1";1:*~-"'*~--.--- .... - . - . - . -.. . - -...... ~---* .. *"-***_***_**_ _ _. : . _ __ _ _ _ : _ - - ' - - - - - - - - - - - - - - - - - -
.SALEM GENERATING STATION NUMBER - lPD-18 .1. 005 PERFORMANCE DEPARTMENT (I & C) REV.NO. ~l~~~~~~-
DATE 6/25/82
' TEST PROCEDURE PAGE 1 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST - TRAIN B 1.0 Purpose 1.1 To verify the operability of the Reactor.Trip Breakers to satisfy requirements of ~he Technical Specifications.
1.2 To verify the operability of the Reactor Trip Breaker/
Reactor Bypass Breaker P-4 permissive switches.
l.~ To satisfy the recommendations of Westinghouse Lett~r PSE-80-14 *.
2.0 References 2.1 Solid State Protection System Manual 2.2 Westinghouse Letter PSE-80-14 (2/22/80) 2.3 Wiring Diagrams - 203688, 222885, 224325, 203646 2.4 Technical Specifications 3.0 Precautions 3.1 Insure that all required safety precautions and tagging procedures have been complied with as stated in the Performance Department Manual.
I & C - 001
x SALEM GENERATING STATION NUMBER -
lPD-18.1.005 REV. NO. l PERFORMANCE DEPARTMENT (I & C)
DATE 6/25/82 TEST PROCEDURE PAGE 2 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST - TRAIN B
- 4. 0 Limitations and A.ctions 4.1 If, at any time during the performance of this test, there is any reason to suspect that the test equipment being used may not be performing properly, a comparison check shall be performed with a similar device or the device shall be checked for calibration against a standard. This shall be done prior to taking any other corrective action.
4.2 If, during the performance of this test, the "As Found" data does not meet the requirements of the specified accurac"y, the Job Supervisor shall be notified immediately and PD_-14.1. 001 shall be performed.
4.3 If, during the performance of this* procedure, the required status indication cannot be obtained, the Job Supervisor shall be notified immediately. Exceptions to the required indication, due to plant conditions at the time of the test, may be made by the Job Supervisor.
Any exceptions of this nature must be indicated and explained in Section 10.0 of this procedure.
I & C - 001
SALEM GENERATING STATION NUMBER - lPD-18 .1. 005 REV. NO. 1 PERFORMANCE DEPARTMENT (I & C)
DATE 6/25/82 TEST PROCEDURE PAGE 3 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST - TRAIN B 5.0 Test Equipment DEVICE NAME PD. NO. RECAL. DATE Fluke DVM I.'.:! C-001
- .-~~--~ .... - ***- .... ****-**-** *******-_*.*_*_ '_ _ _ _ __
x SALEM GENERATING STATION NUMBER - lPD-18. 0. 0 05 REV. NO. . l PERFORMANCE DEPARTMENT (I & C) ~~~~~--~
DATE 6/25/82 TEST PROCEDURE 4 PAGE OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST - TRAIN B 6.0 Prerequisites 6.1 The individual assigned to perform this procedure is qualified to do so in accordance .with the Solid State Protection System Qualification Card.
Job Supervisor *
.6.2. T:Q.e Senior Shift Superv~sor/Shift Supervisor has granted permission to perform this procedure *.
- Senior Shift Supervisor/Shift Supervisor Date/Time 6.3 The Control Operato~ is aware of all the alarms and indications that will be affected by the performance of this procedure.
Control Operator I & C
- .:~-~.-..._~--*!'"*,.-***;.:,.,..* ***.. ...,,.......,.:-~-.. -:-?.---~-*- -** : -- --.- .** ~--,,. ,. ;***.r:*"'-* ....,. **.- ** ***** ***** **.***,,.-:"**
x SALEM GENERATING STATION NUMBER - lPD-18 .1. 005 REV. NO. 1 PERFORMANCE DEPARTMENT (I & C) ~~~~~~~~
DATE 6/25/82 TEST PROCEDURE 5 PAGE OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST - TRAIN B 7.0 System Line-Up: Initial The following conditions must be established and/or verified by the Control Operator.
7 .1 Verify. the following breaker line-up:
7 .1.1 Reactor Trip Breaker B CLOSED.
7 .1. 2 Reactor Bypass Breaker B RACKED OUT.
7 .1. 3 Reactor Bypass Breaker A RACKED OUT.
I*~ C - 001
x SALE;M GENERATING STATION NUMBER - lPD-18 .1. 005
- PERFORMANCE DEPARTMENT (I & C)
TEST PROCEDURE REV.NO.
DATE
_l_ _ _ _ _ __
PAGE 6/25/82
--6
- OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST - TRAIN B
8.0 Instructions
Initial 8.1 Connect the digital voltmeter as follows:
8.1.l Reactor Trip Breaker B Cubicle TB7-l (+).
8.1. 2 Reactor Trip Breaker B Cubicle TB 7-3 C-) .-
8.2 The DVM should read approximately 48 VDC.
8.3 Have the Control Operator RACK IN and CLOSE Reactor Bypass Breaker B.
8.4 Verify on the Control Board that Reactor Bypass Breaker B is CLOSED.
8.5 The DVM should read 0 VDC.
8.6 ~ave the Control Operator OPEN Reactor Trip Br~aker B.
8.7 At the Control Board, verify Reactor Trip Breaker B is OP.EN
x SALEM GENERATING STATION NUMBER- lPD-18.1.005 REV. NO. 1 PERFORMANCE DEPARTMENT (I & C) ~~~~~~~~-
0 ATE 6/25/82 TEST PROCEDURE PAGE 7 OF 10 I*
I TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER &*PERMISSIVE P-4 TEST - TRAIN B
8.0 Instructions
(Continued) Initial 8.8 Connect the digital voltmeter as follows:
.8. 8 .1 Reactor Trip Breaker B Cubicle TB7-3 (+)
- 8.8.2 Reactor Bypass Breaker B Cubicle TBl0-8 (-).
8.9 The DVM should read approximately 48 VDC.
8.10 Have the Control Operator CLOSE Reactor Trip Breaker B.
8.11 The DVM should read 0 VDC.
8.12 Verify on the Control Board, Reactor Trip Breaker B is CLOSED.
8.13 Have the Control Operator OPEN Reactor Bypass Breaker B.
8.14 Connect the digital voltmeter as follows:
8.14.l Reactor Trip Breaker B Cubicle TB7-l (+).
,. 8.14.2 Reactor Trip Breaker B Cubicle TB7-3 (-).
I & C -001
x.
NUMBER~
SALEM GENERATING STATION lPD-18.1. 005 REV. NO. 1 PERFORMANCE DEPARTMENT (I.& C)
DATE 6/25/82 TEST PROCEDURE PAGE 8 -
-- OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST - TRAIN B
8.0 Insteuctions
(Continued) Initial 8.15 The DVM should read approximately 48 VDC.
8.16 Have the Control Operator RACK OUT Reactor Bypass Breaker B.
8.17 The DVM should read approximately 48 VDC *
8 .19 If the Shift Supervisor wants .the Safety Injection Block reinstalled for this train, jumper terminals 2 and 6 on TDl and have the*control.Operator depress the S.I. Reset for this train.
Senior Shift Supervisor/Shift Supervisor Date/Time
- 8. 20 If necessary, remove the jumper placed in Step 8.19.
x SALEM GENERATING STATION NUMBER- lPD-18.1.005 REV. NO. 1 PERFORMANCE DEPARTMENT (I & C)
DATE 6/25/82 TEST PROCEDURE PAGE
--9
- OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST - TRAIN B 9.0 System Return To Normal:
The following conditions must be established and/or verified by the Control Operator:
9.1 None Required *
.....!j.
I Iii C-001
x SALEM GENERATING STATION NUMBER - lPD-18 .1. 005 REV. NO. 1 PERFORMANCE DEPARTMENT (I & C)
DATE 6/25/82 TEST PROCEDURE PAGE 10 OF 10 TITLE SOLID STATE PROTECTION SYSTEM REACTOR TRIP BREAKER & PERMISSIVE P-4 TEST - TRAIN B 10.0 Remarks: I .O. # w.o. #
- 11. 0 Completion 11.1 Completed By:
Technician Date Time 11.2 Approved By:
Supervisor Date Time I & C -001
