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
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Text
/ ' . S-C-A900-NFD-077
,"REV. 0 Nuclear Department TITLE: USE OF THE MASTER EQUIPMENT LIST SALEM UNITS 1 & 2 1.0 PURPOSE Page 1 of 6 March 9*, 1983 The purpose of this Field Directive is to identify the Salem Master Equipment List (MEL), to .identify the extent to which MEL shall be used, and to cancel Project Directive No. 7 (PD-7). This Directive also augments the MEL with the of a systems listing. 2.0 SCOPE This Field Directive applies to the MEL and PD-7 for Salem units 1 & 2 *. *-:. ... . .O REFERENCES-3.1 -Quality Assurance Instruction 2-1, entitled, "Salem O-List". 3.2 -Regulatory Guide 1.33, entitled, Assurance Program Requirements (Operation)".
3.4 -Salem Administrative Procedure No. 19, entitled, "Material Procurement, Receiving, Storage, Issue, Transfer, Shipping, and Services Program".
3.5 -Salem Administrative Procedure No. 3, entitled, "Document Control Program".
3.6 -R.D. Rippe transmittal letter dated November 3, 1980 distributing the original issue of the Salem Unit 2 MEL. . 3.7 -R.D. Rippe transmittal letter dated January 27, 1981 distributing Revision One to the Salem Unit 2 MEL. 3.8 -R.D. Rippe transmittal letter dated July 15, 1981 distributing the original issue of the Salem Unit 1 MEL. 8303160615 830-314 _____ -----PDR ADOCK 05000272 S PDR The Energy People EDD-7 FORM l REV 0 10SEPT81 Page 2 REFERENCES
- 3.9 -Quality Assurance Instruction 7-1, entitled, "Procurement Control System". of 6 3.10 -Letter, J.T. Boettger to H.J. Midura, dated March 9, 1983 re MEL. 4.0 BACKGROUND Project Directive No. 7 (PD-7) was issued during construction of the Salem Units. It is a of safety-related . ment procurement data which was compiled from equipment curement documents in response to an NRC requirement that all subject to the Quality Assurance Program be identified.
The NRC requires in lOCFRSO that all activities which tribute to (a) preventing accidents that could cause undue risk to the health and safety of the public or (b) mitigating consequences of such accidents should occur, be performed in accordance with a quality assurance program. The necessary elements of such a program are described in lOCFRSO ApPendix B. The PSE&G Quality Assurance Program is described in the Quality Assurance Manual and the FSAR. The Salem Q-List identifies*
those systems and programs which are subject to the Operational Q.A. Program described above. Part of the Q-List is a document called the Master Equipment List (MEL). The.MEL lists specific plant equipment components which were procured and installed under the Q-Program.
It is not currently complete with respect to systems which have been to the Operational QA Program _subsequent to installation (e.g. spent fuel cooling).
-.The Salem MEL (one per unit) was developed to -supercede PD-7 and function as a continuously maintained document.
It is maintained by the Nuclear Engineering Department.
The MEL provides a component breakdown for the Q-Listed systems. The only official issue of the Salem Unit 1 MEL was made on July _15, 1981 3.8). The Salem Unit 2 MEL was originally issued on November 3, 1980 (Reference 3.6) and subsequently revised and reissued on January 27, 1981 (Refereence 3.7). The MEL is comprised of the following four (4)* major sections:
- ........ IEDD-7 FORM 1 REV 0 Controls Equipment Equipment Mechanical Equipment Structural Equipment 10SEPT81 Page 3 of 6 0
-Cont'd The Controls Equipment portion of MEL is comprised of three (3) distinct lists as follows: 1. Equipment List (i.e. equipment which does not have an associated instrument or valve number); 2. Instrument List; *3, Control Valve, Solenoid Valve, & Damper List. In addition to a component*breakdown of the systems fied in the Q-List, the controls, electrical and mechanical sections of the list provide compDnent breakdowns of addi-' tional systems. each listed component, the MEL identifies the nuclear class, seismic class., safety-related status, and Operational Quality Assurance Program applicability.
The Controls Equipment list also has a column designating if the item was procured as a Commercial Catalog Item (CCI) (Reference QAI-7-1) and a column for the items' environmental class. 0 ADDITION OF SYSTEM LISTING To facilitate utilization of the MEL and ensure proper . ment of 0-Listed equipment, a systems list is hereby porated into the MEL. The systems listing has been .abstracted from the Salem Q-List (Reference
- 1) and identifies all plant systems subject to the Operational Quality Assurance Program. The systems list differs in content from the Q-List only in that the Q-List includes in addition to systems. Note: The systems listing must be used in conjunction with the component listing, as described in the following section. 6.0 UTILIZATION OF MEL All organizational elements of the Nuclear Department with the exception of Nuclear Engineering may use the MEL as a source of system component purchasing data and classif tions subject to restrictions stated Nuclear Engineering personnel.must obtain.and document confirmation of component classifications from a source document (FSAR, System Description, etc.) prior to such utilization.
- EDD-7 FORM 1 REV 0 10SEPT81 Page 4 of 6 6.0 UTILIZATION OF MEL -Cont'd Only six columns may *be used as sources of information for decisions relative to Quality related activities by organizations other than Nuclear Engineering:
- 1. Safety-Related
- 2. QA Applicability
- 3. CCI. . 4. Nuclear Class 5. Seismic Class 6. Environmental Class All other fields are engineering data subject to tation by engineering.
For use in classifying work orders as to safety-related status and QA Program applicability, personnel shall consult the systems list of the MEL, the component listing. All work on any of the listed systems shall be performed based on the classification of the system as a whole, not the individual.component in question.
F.or use in cl*assifying items on procurement documents, both the MEL systems listing and the MEL component listing shall be Use of inf orma ti on shall be as. follows: -if the item is on the MEL component listing and its system is on the system list, the classification on the component list may be used on an MO/IC. if the i.tem is not on the component listing and its system is not onthe systems listing, the item may be be regarded as non-safety related with no QA program requirements.
- if the item is not on the component listing but its system is on the system listing, the Nuclear Engineering Department should be consulted *garding its true classification.
if an i tern is found on the ME.L c_omponent listing as Q-Program applicability "yes" but its system is not on the systems listing, Nuclear Engineering should be consulted for resolution and to effect MEL revision, if necessary.
For items on the MEL component listing, the safety-related and QA applicability columns may be used verbatim, unless the item ii listed CCI "Yes". In this case, care should be as the classification for safety-related and QA Program applicability*of
."No" refer only to procurement/supplier documentation requirements, and should .be regarded as "Yes" for all other This category EDD-7 FORM 1 REV 0 10SEPT81 *.
I. Page 5 of 6 6.0 UTILIZATION OF MEL -Cont'd. in the MEL will be revised to reflect "yes" designations for both safety related status and Q-Prograrn applicability for items haveing a CCI designation "yes". Although MEL is not broken down into sub-components, fication of sub-components shall be assumed to be the same as its associated component unless written direction is requested and received from the Nuclear Engineering Department.
Any question concerning a component classification in MEL shall be directed to the Nuclear Engineering Department.
Requests for classification of components not in MEL shall be directed to the Nuclear Engineering Department.
7.0 REQUIRED
ACTION The General Manager -Salem Operations is requested to revise Salem Administrative Procedures No. 9 and No. 19 and any other procedure referencing and _utilizing the MEL, to strongly emphasize to personnel that inquir.ie.s concerning tions on,. or not on, MEL shall be directed to the Nuclear Engineering Department.
Also, said procedures should refe.rence this Field Directive for instructions on. use of MEL. . ............::::
.. . In addition, Attachment 2 of Salem Administrative Procedure No. 3 identifies five (5) engineering documents which are under the-Station document control program, falling .under geheric of "Equipment Classification Lists". Certain information on these "Equipment tion Lists" is shared by MEL but may not be used as a source of any work order and/or procurement classifications due to considerations relating to frequency of updat"e. -In the *. future, this information*
will be deleted from the "Equipment Classification Lists". Please insure none of the "Equipment Classification Lists" are being used as a source for any work order or procurement activities.
All Station copies of Project Directive No. 7 (the predecessor to MEL) shall be discarded immediately.
Per this directive, Project Directive No. 7 is cancelled.
This Field Directive shall be attached to each Station copy of the MEL. It is requested the General Manager -Salem Operations provide written confirmation of a disposition of each of the above four action items. 8.0 ATTACHMENTS 8.1 -MEL Systems List '* ,I : '
- EDD-7 FORM l.REV 0 l0SEPT81 Page 6 of 6 SUPERCEDED DOCUMENTS 9.1 -Project Directive No. 7 -(PD-7) 10.0 APPROVAL SIGNATURES Verif 1er ngineering Manager -Nuclear Plant Engineering ic,.>J
Engineering Control -Engineering I :
-MASTER EQUIPMENT LIST SALEM GENERATING STATION This listing is incorporated into the Salem Master Equipment List (MEL) by Nuclear Engineering Department (NED) Field Directive S-C-A900-NFD-077,REV.O.
The below listed systems represent those systems whose components are covered by MEL. This system list should be used in determining classifications for work orders (per the detailed instructions in the above referenced NED Field Directive).
The detailed MEL component list should be used in conjunction with this systems list for procurement . activities (per the detailed instructions in the above referenced NED Field Directive);
The following is a list of Safety Related systems which are covered by the PSE&G QA Program: *
- A-C Control and Emergency Power Vital Buses (4kv, 460Vr 230V) including Inverters.
All Penetrations of the Containment Autj.lia:ry Building Ventilation System Auxiliary Feedwater*system Component Cooling System Containment Pressure Vacuum Relief System Control Area Ventilation System *Chilled Water D-C Power Supply System Diesel Generators and Associated Systems Diesel Area Ventilation System Containment Spray System Containment Ventilation System Safety Injection System RHR System eve system Feedwater System (to outermost isolation valves) Fuel Handling Building Ventilation System Fuel Handling System Hydrogen Recombiners Control Air System Leak Detection System .. Main Steam System (to isolation valves) Radiation Monitoring System Waste Gas System Reactor Protection System (including SSPS) Reactor Coolant System Sampling System (to outermost isolation valve) Service Water System Spent Fuel Cooling *System Ste?m Generator Blowdown System (to outermost . isolation valve) Switchgear Room Ventilation System ATTACHMENT I TO S-C-A900-NFD-077 r ! 77 0 Appendix I Administrative AP-9, Control of Station Maintenance AP-10, Inspection Order Program
