ML20078R595

Forwards Response to 830708 Generic Ltr 83-28 Re Required Actions Based on Generic Implications of Salem ATWS Events

ML20078R595
Person / Time
Site:	Brunswick
Issue date:	11/07/1983
From:	Howe P CAROLINA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
GL-83-28, LAP-83-513, NUDOCS 8311150220
Download: ML20078R595 (352)

Text

-

SERIAL: LAP-83-513

Carolina Power & Light Company NOV 07198I Mr. Darrell G. Eisenhut,-Director Division of Licensing thited States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 AND 2 DOCKET NOS. 50-325 AND 50-324 LICENSE NOS. DPR-71 AND DPR-62 GENERIC IMPLICATIONS OF SALEM ATWS EVENTS

/

Dear Mr. Eisenhut:

Carolina Power & Light Company (CP&L) has received your letter, Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events, dated July 8, 1983. Your letter requested CP&L to furnish "the status of current conformance with the positions contained" in your letter, "and plans and schedules for any needed improvements for conformance with the positions." In April 1983, the management at the Brunswick Nuclear Project created the Salem Response Task Force comprised of on-site CP&L and contract personnel to address the implications of the Salem event. Pursuant to Generic Letter 82-14, CP&L hereby transmits one original and forty copies of the Salem Response Task Force Report which incorporates our. response to Generic Letter 83-28.

Representatives of CP&L are participating in the Nuclear Utility Task Action Committee (NUTAC), sponsored by the Institute of Nuclear Power Operations (INPO), concerning Section 2.2.2 of your letter and in the BWR Owners' Group's (BWROG) generic evaluation of the positions stated in your letter. Based on our participation in these industry groups, revisions to the schedule provided in the task force report may be necessary as we consider the results of these studies.

8311150220 831107 DR ADOCK 05000324 PDR

\

. , , ,.,.,,... s,,... . m - , ss , . . c_

m1

@*@?

A .,

NOV 7 1983 Darrell G. Eisenhut If you have any questions regarding our response, please do not hesitate to call a member of our Licensing staff.

Yours very t y, P. W. owe Vice President Brunswick Nuclear Project DCW/cce (8371DCW)

Attachnent cc: Mr. D. O. Myers (NRO-BSEP)

Mr. J. P. O'Reilly (NRC-RII)

Mr. S. D. Ma cKay (NRC)

A 6. daner, f p" P. ". "cre, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power & Light Company.

Y $A4&t44' Notary (Seal) unis,,,,,

My commission expires: October 4,1986

$.UN

{ [60TARy

: A  :  :

t* yBLIC l 5 l

p,,,,uv.p'

,,,,,,,o s p I

l l

I l

l l

L

l l

l l

SALEM RESPONSE TASK FORCE REPORT NRC Generic Letter 83-28 Response .

November 5,1983 Written By: A, William M. fogle &

Task Force (

Project Manager l

1.

f l

i i

• I

SALEM RESPONSE TASK FORCE William M. Hogle,' Project Manager Senior Engineer--Technical Support Michael A. Jones Principal Engineer--On-Site Nuclear Safety, Martin B. Kesmodel Supervisor--Document Control / Administration Peter H. Koder Storekeeper A--Materials Department for Purchasing and Requisition Timothy T. Marron Engineer (GE--Contract)--Operations Sidney W. Morgan Senior Specialist--Training David Rudoff Project Engineer--Quality Assurance Alfred W. Stevens Electrical Foreman--I&C Maintenance Daniel Webster Engineer (GE--Contract)--Operations Supppet Group Douglas N. Allen Project Engineer--On-Site Nuclear Safety Charles R. Drew Engineer--I&C Maintenance Eugene 0. Eagle, Jr.

Project Engineer--Computer

-Leslie P. Hewlett Project Engineer--Plant Performance and Reliability Robert A. Jernigan Start-up and Testing Supervisor (UE&C--Contract)--Technical Support Brian P. Newell Engineer (GE--Contract)--Operations Bennie L. Parks Engineering Supervisor--Technical Support i

i

Acronyms ac alternating current ADS Automatic Depressurization System ADSB Adsorption AI Administrative Instruction ANS American Nuclear Society ANSI American National Standards Institute A0G Augmented Off-Gas APRM Average Power Range Monitor ASME American Society of Mechanical Engineers ATWS Anticipated Transient Without Scram B&W Babcock and Wilcox BESU Brunswick Engineering Support Unit BIP Brunswick Improvement Plan BKR Breaker BNP Brunswick Nuclear Project BOP Balance of Plant BRG Bearing BSEP Brunswick Steam Electric Plant BWR Boiling Water Reactor BWROG Boiling Water Reactor Owners' Group CC Cycle CFR Code of Federal Regulations CKT Circuit i

CMMS Corporate Materials Management System CONTMT Containment CP&L Carolina Power & Light Compa~ny ii

Acronyms (cont.)

cps. cycles per second CQAD Corporate. Quality Assurance Department CRD Control Rod Drive ,

CRT Cathode Ray Tube CW Circulating Water de direct current DFS Digital Fast Scram DW Drywell E&RC Environmental & Radiation Control ECCS Emergency Core Cooling System EI Emergency Instructions ,

ENP Engineering Procedure ERFIS Emergency Response Facility Information System EXT Extraction FDI Field Disposition Information (GE)

FDR Feeder FP Foreign Prints FPE&CD Fossil Plant Engineering & Construction Department .

FSAR Final Safety Analysis Report FW Feedwater 4

GE General Electric GEPAC General Electric Process Analog Computer GESSAR General Electric Standard Safety Analysis Report KD Heater Drain HTR Heater HXS Heat Exchanger HYD Hydraulic iii

Acronyms (cont.)

H2 Hydrogen I&C Instrumentation and Control ID Identification IEB Inspection and Enforcement Bulletin IEC Inspection and Enforcement Circular IEN Inspection and Enforcraent Notice INPO Institute for Nuclear Power Operations IRM Intermediate Range Monitor LCO Limiting Condition of Operation LER Licensee Event Report lpa lines per minute LTG Lighting MCC Motor Control Center MEL Master Equipment List MI Maintenance Instruction MLB/HR Pounds Mass Per Hour MP Maintenance Procedure MSIV Main Steam Isolation Valve MSL Main Steam Line NC Normally Closed NCR Non-Conformance Report NEB 0D Nuclear Energy Business Operation Division (GE)

NEMA National Electric Manufacturers Association NEPD Nuclear Energy Products Division (GE)

No Normally Open NPCD Nuclear Plant Construction Department NPED Nuclear Plant Engineering Department iv

Acronyms (cont.)

NPRD Nuclear Plant Reliability Department NPRDS Nuclear Plant Reliability and Data System NRC Nuclear Regulatory Commission NSS Nuclear Steam System NSSS Nuclear Steam Supply System NUREG Nuclear Regulatory Enforcement Guide NUTAC Nuclear Utility Task Action Committee (INPO)

O&MR Operating and Maintenance Reminders OB Operating Bulletin (GE)

OEF Operating Experience Feedback OER Operating Experience Report (INPO)

OI Operating Instruction OIEP Operating Information Exchange Program ONS On-Site Nuclear Safety

, OWP Operations Work Procedure P&ID Piping and Instrument Drawing PAT Performance Appraisal Team PM Plant Modification PNSC Plant Nuclear Safety Committee P0 Purchase Order PPP Plant Performance Procedure PRI. Primary PSE&G Public Service Electric and Gas of New Jersey PSIL Product Service Information Letter (GE)

PT Periodic Test PWR Pressurized Water Reactor QA Quality Assurance v

_ . ~ . _ _ , _ - . . _ _ _ _ . . _ , . . . _ _ _ _ _ _ . _ . , . . . . . . - . - _ _._., _.

Acronyms (cont.)

QC Quality Control RBCCW Reactor Building Closed Cooling Water RBM Rod Block Monitor RCPB Reactor Coolant Pressure Boundary RFP Reactor Feed Pump RFPT Reactor Feed Pump Turbine RHR Residual Heat Removal RMI Records Management Instruction RNA Reactor Non-Interruptible Instrument Air RPIS Rod Position Information System RPS Reactor Protection System RPT Recirculation Pump Trip RTD Resistive Temperature Device RTS Reactor Trip System RWCU Reactor Water Clean-Up RWM Rod Worth Monitor RX Reactor -

SAL Service Advise Letter (GE)

SALP Systematic Assessment of Licensee Performance (NRC)

SD System Description SDV Scram Discharge Volume Seq Sequence SER Significant Event Report (INPO)

SHNPP Shearon Harris Nuclear Power Plant SIL Services Information Letter (GE)

SK Storekeeper SOER Significant Operating Expierence Report (INPO) vi

Acronyms (cont.)

SPDS Safety Parameter Display System SRI Select Rod Insert SRM Source Range Monitor SRV Safety Relief Valve STA Shift Technical Advisor SW Service Water SWGR Switchgear TAR Task Assistance Request TB Turbine Building TCV Turbine Control Valve TI Training Instruction TIL Technical Information Letter (GE)

TIP Traveling Incore Probe TP Transfer Procedure TS Technichl Specification TSV Turbine Stop Valve TT Trouble Ticket .

UAT Unit Auxiliary Transformer UE&C' United Engineers and Constructors UFSAR Updated Final Safety Analysis Report UPS . Uninterruptible Power Supply WR&A Work Request and Authorization XMFR Transformer ,

vii

CONTENTS 1 Page Task Force Members................................................. i Acronyms........................................................... ii - vii Table of Contents.................................................. viii - xi I. Executive Summary........................................ 1 II. Introduction............................................. 1 III. Background--BSEP Salem Response Task Force.............. 2 IV. NRC Generic Letter 83-28 Response........................ 3 A. S umm a ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-B. Response............................................ 3 1.1 Post-Trip Review (Program Description and Procedoro)..................................... 3 1.1.1 Criteria for Determining the Acceptability of Restart............. 4 1.1.2 Responsibilities and Authorities of Personnel......................... 4 1.1.3 Qualification and Training........... 6 1.1.4 Sources.............................. 8 1.1.5 Methods and Criteria for Comparing Event Information. . . . . . . . . . 9 1.1.6 Criteria for Determining Need for Independent Assessment of an Event................................ 10 1.1.7 Procedure............................ 10 1.2 Post-Trip Review (Data and Information Capability).................................... 11 1.2.1 Capability for Assessing Sequence of Events (On-Off Indicators--Digital)... 11 1.2.1.1 Brief Description of Equipment.................. 11 viii n

TABLE OF CONTENTS (Cont'd)

Page 1.2.1.2 Parameters Monitored....... 11 1.2.1.3 Time Discrimination Between Events............. 12 1.2.1.4 - Format for Displaying Data and Information....... 12 1.2.1.5 Capability for Retention of Data and Information............ 12 1.2.1.6 Power Source............... 12 1.2.2 Capability for Assessing the Time History of Analog Variables.......... 13 1.2.2.1 Brief Description of Equipment.................. 13 1.2.2.2 Parameters Monitored, Sampling Rate, and Basis for Selecting Parameters and Sampling Rates............. 15 1.2.2.3 Duration of Time History.................... 16 1.2.2.4 Format for Displaying Data (Readability) of Time Histories............. 16 1.2.2.5 Capability for Retention of Data.......... 17 1.2.2.6 Power Source............... 17 1.2.3 Other Data and Information........... 17 1.2.4 Schedule of Improvements............. 18 2.1 Equiprent Classification and Vendor Interrace (Reactor Trip System Components)..... 18 2.2 Equipment Classification and Vendor Interface (Programs for Safety-Related Components)............................ 20 2.2.1 Program Description.................. 20 ix

, - - . - , , . , , - . ----rr-- . , ,e, - - -- ----n,<w -, ,-- , ,,.g,,-- , - ,-, - - -, , , - - - - - ,

TABLE OF CONTENTS (Cont'd)

Page 2.2.1.1 Criteria for Component Identification............. 20 2.2.1.2 Information Handling System..................... 22 2.2.1.3 Information Handling System Use................. 23 2.2.1.4 Management Controls........ 24 2.2.1.5 Design and Qualification Verification............... 24 2.2.1.6 Equipment Classifi-cation Program............. 25 2.2.2 Vendor Interface Program............. 26 3.1 Post-Maintenance Testing (Reactor Trip System Components)............................. 30 3.1.1 Test and Maintenance Procedure Review............................... 31 3.1.2 Vendor and Engineering Recommendations...................... 31 3.1.3 Post-Maintenance Testing Require-ments-Technical Specification Related.............................. 33 3.2 Post-Maintenance Testing (All Other Safety-Related Components)............................ 33 3.2.1 Test and Maintenance Procedure Review............................... 33 3.2.2 Vendor and Engineering Recom-mendations........................... 33 3.2.3 Post-Maintenance Testing Require-ments-Technical Specification Review............................... 33 4.1 Reactor Trip System Reliability (Vendor-Related Modifications)......................... 34 X

TABLE OF CONTENTS (Cont'd)

Page 4.2 Reactor Trip System Reliability (Preventive Maintenance and Surveillance Program for Reactor Trip System Components)................ 34 4

4.3 Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)................... 34 4.4 Reactor Trip System Reliability (Improve-ments in Maintenance and Test Procedures for B&W Plants)................................ 34 4.5 Reactor Trip System Reliability (System Functional Testing)............................ 34 4.5.1 Diverse Trip Testing................. 34 4.5.2 On-Line Testing...................... 35 4.5.3 Test Intervals....................... 36 V. References............................................... 36 VI. Appendices............................................... 45 APPENDIX A--NRC Generic Letter 83-28 APPENDIX B--Operating Instruction OI-22 APPENDIX C--Action Plans and Schedules APPENDIX D--UPS System Diagram APPENDIX E--Process Computer Parameters APPENDIX F--Control Room Strip Charts APPENDIX G--Post-Maintenance Testing Requirement Routing Process APPENDIX H--Vendor Recommendation Processing Routing Diagram APPENDIX I--Volume XI, Book 2: Q-list Program APPENDIX J--General Electric Service Information Letters (Review in Accordance with Section 3.1.2) xi

. _ . . _ .. _ . - . _ , _ _ _ _ _ .._.... _ ._. _. ~._ ..__.m._, . . . - , _ _ , _ - _ _ . .

.=

SALEM RESPONSE TASK FORCE REPORT I. -Executive Summary On February 22 and 26,-1983, an anticipated transient without scram (ATWS) occurred at the PSE&G Salem Unit No. I generating station. Carolina Power & Light Company recognized the implications of the event and on April 11, 1983, BSEP management established a Salem Response Team. The Task Force team's charter included the assessment of the generic implica-tians raised by the Salem incident with respect to Brunswick management controls and procedures. Using the project management approach, the Task Force developed a project plan and began a comprehensive review of past events and present controls and procedures relevant to the issues raised per NUREG-0977, NUREG-1000, Volume I, and NRC Generic Letter 83-28 (NUREG-1000, Volume II). This report encompasses the findings of the Task Force investigative efforts pertinent to the NRC Generic Letter 83-28 which was issued July 8, 1983.

1

The report includes positions on

1) post-trip review procedure and data handling capability, 2) equipment classification and vendor interface, 3) post-maintenance testing, and 4) reactor trip system reliability. Action plans and schedules are presented reflecting the outstanding items required to comply with the directives of the generic letter. These items include: 1) the upgrade of the Q-list procedure, 2) review of vendor recommendations with respect to post-maintenance testing require-ments, 3) assessment of whether existing post-maintenance testing degrades rather than enhances safety, and 4) implementation of backup scram pilot

. valve off-line testing. It should be noted that the schedules provided -

are preliminary and may require additional refinement in view of future regulatory actions and budgeting considerations. In addition, the BWR Owners Group and INPO are presently formulating generic positions on several of the issues contained in NRC Generic Letter 83-28 and revisions may be required to this report dependent upon the results of the INPO NUTAC and Owner's Group activities. The final schedules for implementation

, will be negotiated between the licensee and the NRC Project Manager consistent with the directive of NRC Generic Letter 83-28.

I II. Introduction An alert was declared at 1:30 a.m. on February 26, 1983, at the Salem Nuclear Generating Station when it was determined that an anticipated transient without scram (ATWS) condition had occurred at 12:21 a.m. A l low-low level condition developed in one of the steam generators which generated a reactor trip signal. Both reactor trip breakers (Westing-house Type DB-50) remained closed until subsequent operator action manually scrammed the unit about 30 seconds later, successfully bringing the reactor to a stable shutdown condition. It was determined by the licensee that the breakers failed to open due to mechanical binding of the latch mechanism in the undervoltage trip attachment on the breakers.

The manual signal operated a shunt trip attachment in addition to the j undervoltage trip mechanism which permitted the breakers to open.

I I

1 l I

l

Investigation into the cause of the February 26 incident determined that another ATWS had occurred for about three seconds at 9:55 p.m. on February 22, 1983. A transient initiated by the loss of the IF4-KV group bus during a transfer of the bus to the auxiliary power transformer resulted in a reactor trip signal. Coincidentally, the operator initiated a manual scram at the same time the transient condition was noted, thus unaware that an ATWS had occurred.

On March 1, 1983, NRC Region I established a Task Force to conduct a fact-finding study of the events which led to the ATWS conditions. The results of their investigation were published in NUREG-0977 and the generic implications presented in NUREG-1000, Volume I. Concerns were reported involving procurement, material transfer, storage, preventative maintenance, post-maintenance testing, training, and administrative and management controls. Subsequently the NRC issued NRC Generic Letter 83-28 (NUREG-1000, Volume II) which required licensees to provide information concerning conformance to positions involving post-trip review, equipment classification and vendor interface, post-maintenance testing, and reactor trip system reliability.

Tcis report provides the required response to NRC Generic Letter 83-28 for Carolina Power and Light Company's Brunswick Units 1 and 2. Enclosed are the status of current conformance with the positions dictated per the generic letter and action plans and schedules for implementation for improvements. The schedules are preliminary and may require additional refinement in view of future regulatory actions, the INP0 NUTAC on vendor recommendations, the BWR Owner's Groups efforts, and resource and priority considerations. The final schedules for implementation will be negotiated between the licensee and the NRC Project Manager consistent with the directive of NRC Generic Letter 83-28.

III. Background--BSEP Salem Response Task Force On April 11, 1983, BSEP management established a Salem Event Response Task Force whose charter included assessment of the issues raised by the Salem Event with respect to their applicability to BSEP management controls and procedures. The task force involved personnel from areas of Quality Assurance, Operations, On-Site Nuclear Safety, Engineering, Training, Administration, Maintenance, and Stores and subcommittees were formed to study the generic issues raised per NUREG-0977. Status reports were submitted periodically to Senior Management to gauge the progress of the group. Subsequently, additional personnel were required to address specific issues encountered upon issuance of NUREG-1000, Volume I and NRC Generic Letter 83-28. A listing of the major personnel involved in this effort appears in the preface of this report.

The Task Force's investigative efforts included a review of plant procedures, design documents, technical specifications, LERs, SALP audits, etc. A partial listing of the references used can be found in Section V.

4 2

t IV. NRC Generic Letter 83-28 Response A. Summary The following section encompasses the required response to NRC Generic  !

Letter.83-28 (reference Appendix A). The generic letter involves the required actions based on the generic implications of the Salem ATWS events and addresses the following items:

1. Section 1.1, Post-Trip Review (Program Descrip, tion and Procedure)

2. Section 1.2, Post-Trip Review (Data and Information Capability)

3. Section 2.1, Equipment Classification and Vendor Interface (Reactor Trip System Components)

4. Section 2.2, Equipment Classification and Vendor Interface (Programs

. for All Safety-Related Components) 4

5. Section 3.1, Post-Maintenance Testing (Reactor Trip System Components)

6. Section 3.2, Post-Maintenance Testing (All Other Safety-Related Components)

7. Section 4.1, Reactor Trip System Reliability (Vendor-Related Modifi-cations)

8. Section 4.2, Reactor Trip System Reliability (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)

9. Section.4.3, Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)

10. Section 4.4, Reactor' Trip System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)

11. Section 4.5, Reactor Trip System Reliability (System Functional Testing)

Sections 4.1, 4.2, 4.3, and 4.4 are not applicable to EVR reactors and no response is required. Action plans and schedules for ivprovement programs are located in Appendix C.

. B. Response 1.1 Post-Trip Review (Program Description and Procedure)

The Brunswick Steam Electric Plant has a program in effect for performing a review of unscheduled shutdowns and plant incidents. The procedure governing these reviews is 01-22: Plant Incident and Post-Trip Investigation (reference Appendix B). This document establishes a formal plant level 3

l instruction whereby plant incidents are properly investigated to ensure:

1) root causes are understood and properly documented, 2) incidents have not resulted in an unsafe or unacceptable condition for continued operation,

3) appropriate corrective action is provided to prevent recurrence, and

4) continued unanalyzed conditions do not exist. Included in this procedure are the criteria for determining the acceptability for restart, responsibilities of personnel involved in the review, definitions of plant incidents, and a sequence of event instruction. The following is a description of the. program and procedure pertinent to the line items listed in NRC Generic Letter 83-28.

1.1.1 Criteria for Determining the Acceptability of Restart.

In accordance with OI-22, the criteria for determining the accepta-bility of a restart are a) the root cause of the event resulting in an unscheduled reactor shutdown is known and understood, b) immediate corrective actions to reduce the probability of event recurrence are identified, c) there are no safety concerns, d) safety systems

. functioned as required, and e) an ATWS event was not hidden by quick operator action. Attachment 1: Immediate Incident Investigation to 01-22 assures that the above conditions are met.

In the event that cause of the unscheduled reactor shutdown cannot be determined, the General Manager may concur or approve a restart based on the following conditions:

1. Any further reasonable actions to determine cause is considered unproductive.

2. No physical damage was done by the event and a determination

, made that the plant had not operated beyond the boundaries established by approved plant safety and transient analysis.

3. Any reasonable action to gain additional information has been considered.

1.1.2 Responsibilities and Authorities of Personnel The specific responsibilities and authorities of personnel who will perform the review and analysis of these events are specifically delineated in OI-22. The Administrative Procedures of the Plant Operating Manual describe the general responsibilities and authorities of plant personnel. The investigation of transients is performed and reviewed by Operations personnel which include experienced licensed Senior Reactor Operators and Engineering level personnel.

These reviews are supplemented by Shift Technical Advisors, the Fire Protection Specialist, E&RC personnel, On-Site Nuclear Safety, and Technical Support Engineering personnel, as necessary, dependent on the nature of the transient. Follow-up reviews are conducted by PNSC and the plant General Manager (refer to Appendix B for detailed assessment).

4

_ ~ _ - . . _ _ _ _ . _ _ - . _ _ _ ._ _._ .._ _ _ _ . _ . . _ . _

The plant specific responsibilities of these plant personnel are as follows:

1. Shift Operating Supervisor: Provides central direction of incident investigation until relieved by the Engineer - Operations.

2. Engineer - Operations: Assumes direct responsibility for investigating plant incidents, except radiological incidents, and provides incident reports which are forwarded to the Manager - Operations. .

3. Principal Engineer - Operations: Reviews Immediate Incident Investigation report prepared by the Engineer - Operations and forwards it to the Manager - Operations.

4. Shift Technical Advisor: Assists the Shift Operating Supervisor and Operations Engineer with the incident investigation.

5. Manager - Operations: Determines when incident is tenminated, and if follow-up report is required, recommends restart (if applicable), and recommends incident reports to the Manager -

Plant Operations for approval.

6. Fire Protection Specialist: Provides fire report, as required, to the Engineer - Operations.

7. Manager - Environmental and Radiation Control (E&RC): Assumes responsibilities for radiological incidents and generates other written reports of incident as may be assigned by the plant General Manager.

8. Manager - Technical Support: Provides engineering support, as requested, to aid in determining root causes of occurrence and makes engineering recommendations.

9. Manager - Plant Operations: Provides final approval of initial and follow-up incident reports.

10. Plant Nuclear Safety Committee (PNSC): Reviews formal incident reports and forwards to plant General Manager for approval, reviews and accepts follow-up investigation reports, reviews safety evaluation related to ATWS events prior to restart, determines if additional detailed analysis is required, and determines final disposition of component (hardware).

11. Plant Performance and Reliability Rcview Group: Reviews copy of the SRV Failure / Challenge Report (Attachment 5 to 0I-22), if required. ,

5  ;

i l

.n- ., , -, .--- . .--c, - - ,. ,-. ,,, . . , - - , - - - -,,,, .. n -

e _

12. On-Site Nuclear Safety: Conducts independent assessment of the  ;

event if, in accordance with Attachment 1 of OI-22, the root '

cause is not determined, cause is determined to be repetitive, a potential safety concern regarding operation or restart exists, or where it is determined that a safety system did not function as required.

13. Plant General Manager: Approves return of unit (s) to service, determines deadlines for report submittals, reviews and approves follow-up reports, and forwards approved final investigative reports to the Vice Presidents of th~e Brunswick Nuclear Project, Corporate Nuclear Safety, and the Nuclear Generation Group. e i

i 1.1.3 Qualifications and Training

/

The general training and qualification criteria for the personnel involved in the review and analysis of plant incident reviews are outlined in ANSI 18.1-1971: Selection and Training of Nuclear Power Plant Personnel. These training and qualification criteria are reflected in BSEP administrative procedures (reference Volume I, Book 1 of the Plant Operation Manual).

PNSC members are appointed from the plant management group. The members are experienced management level personnel and represent the following plant units:

1. Maintenance

2. Technical Support <

3. Environmental and Radiation Control ,

n

4. Quality Assurance

5. Operations

6. Administrative Support Each reeting normally includes a representative from 'each of the units. The committee is chaired by the plant General Manager. Vice '

chairmen include the Manager - Operations, Managsr - Maintenance, Manager - Technical and Administrative Support, the Manager -

Technical Support, or Assistant to the General Manager.

ONS members are required to have a BS degree in Engineering or related field and five years related experience (three related years in Operations and/or design of nuclear power plants).' The Fire Protection Specialist must have three years minimum experience in

fire protection and complete a training program that meets or exceeds the requirements of Section 27 of the NFPA Code-1975.

6

.- -- . - .= .

Plant Performance and Reliability Engineers must have a BS degree in Engineering or related field or equivalent experience in basic system engineering. The Manager - E&RC must attain a bachelor's

, degree in Chemistry, Health Physics, or related disciplines or equivalent experience and 10 or more years of closely related experience. In addition, the Manager - E&RC shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The Shift Technical Advisors must attain a BS degree or equivalent in a scientific or engineering discipline. In addition, they will complete specific training in plant design and response and analysis of the plant for transients and accidents.

Training and qualifications of licensed personnel is covered.by BSEP Training Instructions 200, 201, and 202. A description of these programs is as follows:

Training Instruction TI-200: Brunswick Plant Operator Retraining Program establishes the requirements for a periodic retraining program for NRC licensed personnel at the Brunswick plant. This program meets or exceeds the requirements of 10CFR55, Appendix A, for operator training.

Training Instruction TI-201: Brunswick Plant Reactor Operator Replacement Trainint Program ensures that operator replacement personnel are proviced with sufficient formal and on-the-job training to meet or exceed the requirements of ANSI Standard N18.1-1971: Selection and Training of Nuclear Plant Personnel, and 10CFR55: Operator's Licenses. Graduates of this program are prepared to pass the NRC hot license examinations and operate the Brunswick plant in a safe and efficient manner.

Training Instruction TI-202: Replacement Training for Senior Licensed Operating Personnel ensures Senior Operator replacement personnel ~ receive sufficient training to meet or exceed the requirements of ANSI Standard N18.1-1971 and 10CFR55. Graduates of

this program are prepared to pass the NRC hot license examination for Senior Reactor Operator and to supervise the safe and efficient l

operation of the' Brunswick plant.

l In addition, the qualifications and training requirements of the I facility staff are outlined in Technical Specification Sections 6.3

and 6.4, and Volume I, Book 1, of the Plant Operating Manual.

l In summary, the reviews and analysis of plant incidents are performed by staff and management personnel who, by their position, t- have met the experience and educational requirements for those positions of responsibility.

O 7

i

1.1.4 Sources 01-22, Section 5.0, instructs personnel involved in the incident review to retrieve and adequately label pertinent data regarding the event (i.e., charts, computer printouts, log entires, etc.), and to take photographs of failed components, as applicable. Also, those personnel directly involved in the cause of the event must submit written statements to the Shift Operating Supervisor describing their observations and actions during the event.

The primary sources of information necessary to conduct the review and analysis are specifically delineated in Attachment 1 (Immediate Incident Investigation) and Attachment 3 (Scram Report) to 0I-22.

Information from the following Control Room instrument records are used to evaluate a transient:

A. Recirculation Pump Flow A and B ,

B. Core Flow and Core Delta-P C. APRM Power D. Main Steam Line Flow E. Feedwater Flow F. Reactor Water Level G. Reactor Pressure H. SRM Flux I. Main Condenser Vacuum J. Steam Jet Air Ejector Radiation Monitor K. Main Steam Line Radiation Monitor L. Reactor Building Ventilation Exhaust Radiation Monitor M. Drywell Pressure These sources of information are supplemented by the eyewitness accounts taken immediately after the transient and by the computer reports and logs. The eyewitness accounts generated as a result of the transient provide information gained from annunciators, automatic actions, and manual operator actions during the transient. The computer reports include the BOP post-trip log, NSS post-trip log, the sequence-of-events log (scram printout), and the printout depicting CRD position after scram. These computer printouts provide the sequence-of-events and pre- and post-trip values of key parameters. Further details are provided in Section 1.2.

8

,n- r. . - ,, -n , ,,, ,. . - . - , - _ , , - - - - , . . . _ . - - - . . , - , , , - - , . , - ,- -,

Together, the instrumentation charts, computer data, hardware inspection, and eyewitness accounts provide an extensive base of data from which the cause of the event can be determined, the proper functioning of automatic actions verified, and the consequences of the event determined to be acceptable.

1.1.5 Methods and Criteria for Comparing Event Information All unscheduled reactor shutdowns require a written assessment. A verification of proper safety system function and identification of significant safety concerns is required to be performed through the use of the following attachments to 0I-22:

1. Attachment 1: Immediate Incident Investigation

2. Attachment 2: Follow-Up Incident Investigation

3. i.ttachment 3: SCRAM Report

4. Attachment 4: Plant Incident Summary

5. Attachment 5: SRV Failure / Challenges Report

6. Attachment 6: -Screening Guidelines for Transients and Safety System Challenges

7. Attachment 7: PNSC Restart / Continued Operation Criteria

8. Attachment 8: Transient Response Verification These attachments provide a means of identification of incident cause and safety concerns and a basis for determination regarding continued operation or restart. Attachments 1, 3, 6, and 8 are required for unscheduled reactor shutdowns. Other attachments are used dependent upon the nature of the incident and the functioning of safety system equipment. If, upon completion of Attachment 1, there exists a safety concern and/or the cause is deemed repetitive or unknown, additional assessment is performed by the On-Site Nuclear Safety group for PNSC and General Manager approval. If an unanalyzed transient occurs, PNSC is instructed per Attachment 7 to

^

consider a detailed analysis including the following information as appropriate: 1) comparison to startup test data and past transients and 2) sequence risk analysis (a probabilistic analysis program ,

provided by INPO). Attachments 8 through 8h provide the specific guidelines for determining that safety-related equipment operates as required by technical specifications or other performance specifications.

This attachment involves transient response verification for the following parameters:

1. Reactor Vessel Water Level 9..

-- .= . . - - . . . _. . . _ -

2. Reactor Pressure

3. Reactor Power / Flux

4. Drywell Pressure i

5. Condenser Vacuum

6. Off-Gas Radioactivity

7. Loss of Electrical Power

8. Scram Setpoint Reached (Verification of Automatic Scram)

This system provides sufficient methods and criteria for comparing event information to assure that related safety functions performed per design.

1.1.6 Criteria for Determining Need for Independent Assessment of an ." vent In the process of performing the immediate incident investigation, OI-22 requires that the need for independent assessment be determined.

The criteria for determining the need for independent assessment of an event is: a) the cause is not understood, b) the cause is repetitive requiring more extensive corrective action, c) a potential safety concern exists, and d) safety systems did not function as required. The On-Site Nuclear Safety Committee (ONS) performs an independent assessment of events for PNSC and the plant General

~

Manager review and approval.

Paragraph 5.1.2 of 01-22 specifies the method for software preserva-tion, such as retrieval and labeling of pertinent data regarding the event (i.e. , charts, computer printouts, log entires, photographs of evidence, etc.) and Step 5 of the Immediate Incident Investigation (Attachment 1 of OI-22) also specifies retention of failed components for further assessment, if required. If the cause of the incident was component failure, the Plant Nuclear Safety Committee makes a determination for final disposition of the component.

1.1.7 Procedure Refer to Appendix B of this report for Operating Instruction OI-22:

Plant Incident and Post-Trip Investigation.

The procedure for post-trip review provides sufficient detail, documentation, and accountability for determining the cause of an unscheduled shutdown, and fully meets the criteria specified in Section 1.1 of NRC Generic Letter 83-28. No additional action is required.

i 10 l

, - ~ - - _ _ . ..-.i___.-.~__,-.._----. - , . , . _ _ , _ . - _ , , , . _ . _ _ _ . _ . , _ . . . _ . -

1.2 Post-Trip Review (Data and Information Capability)

The primary sources of information used in reviewing a scram and ascer-taining the proper function of safety-related equipment following un-scheduled reactor shutdowns are key Control Room instrumentation strip charts. An important source of the general sequence of events is provided by individual reports prepared by each operator immediately after a scram. These detail his observations and actions during the event. He becomes informed of the occurrence of specific events by a diverse and extensive array of annunciators, his initiation of manual actions and observations required by procedures, his verification of automatic actions required by procedures, and good operating practices developed from training and experience. Although this source many not provide extensive quantitative information, it is valuable in that it describes that information from which subsequent operator actions were based and identifies those operator actions taken. This information is not available from any other source. Additional information is obtained from the plant pro ga, _>puter logs and reports. These aid in determining the exact cine, direct cause, and detailed sequences relating to the scram.

1.2.1 Capability for Assessing Sequence of Events (On-Off Indications -

i Digital) 1.2.1.1 Brief Description of Equipment An extensive source of detailed unit sequence-of-events digital information is provided by the plant process computer. The computer is a Honeywell 4010 (GEPAC) upgraded with floating point hardware, fast core memory (800q sec), increased memory size (48K words),

large core store solid state fast bulk memory,160 cps dot matrix printers, and a 600 1pm line printer. There is one computer per unit.

There are two types of digital inputs. The normal scan group consists of 529 routine digital inputs. They are scanned once a second. A change in status is printed on the alarm typer in the Control Room after it is detected. The interrupt scan group of digital inputs consists of 92 key NSS and 46 key BOP digital contacts.

These automatically interrupt the normal scan points when a change of status occurs and are immediately printed on the alarm typer.

1.2.1.2 Parameters Monitored Parameters monitored include scram signals, reactor safety relief valve positions, major electrical breakers, major motor and turbine trips, etc. A listing of monitored parameters can be found in Appendix E--Figure 1.

11

., __._..____a_._._

1.2.1.3 Time Discrimination Between Events For normal scan digital contacts the time that a change of status occurs is printed in hours, minutes and seconds with the alarm message. Regular digital inputs can be resolved to within approx-imately one second. The sequence of events program prints the time of the change in state of the interrupt contacts in hours, minutes, seconds, and cycles. A sequence change of state can be resolved to within approximately 2 milliseconds. The computer also indicates which points it cannot determine the sequence on.

1.2.1.4 Format for Displaying Data and Information The computer alarms a contact status change of the normal scan points in the following format:

, Alarm Point 24 Character Contact Time Symbol ID Name Status M SS AAAA XXXX AA........AA AAAA where the time is recorded in hours, minutes, and seconds.

The format for the interrupt scan points are as follows:

Seq Point 24 Character Contact Time Cycle Symbol ID Name Status MSS CC SEQ R AA........AA AAAA There is a special sequence-of-events print out for the safety relief valves (SRV) as follows:

Seq 9 Character Reactor Time Cycle Symbol ID Valve Name Pressure MSS CC SEQ AXXX SRV F013A RXP=XXXX Number of Date Valve Openings Month-Day N=XXX XXXX 1.2.1.5 Capability for Retention of Data and Information Data is retained until printed. The last contact status is saved by the computer. OI-22 requires that the sequence-of-events printouts associated with a scram be included with the scram report.

1.2.1.6 Power Source The process computer receives power from the uninterruptible power supply (UPS) system. The UPS System consists of a vital bus, a power switching module, and two power converter modules, each supplied by divisionalized emergency ac and de sources (refer to Appendix D). Each power converter module is capable of supplying the total UPS load. Only one power converter module is in service, with the other module in standby.

12

The Power converter module takes power from a 480 Vac emergency bus and rectifies it to 250 Vdc as the normal power to its inverter. A ,

backup source of de is supplied to the inverter from the 250 V  ;

battery system. During normal operation, the rectifier voltage is l maintained approximately two volts higher than the battery voltage, i and the rectifier supplies power to the UPS inverter. Should the rectifier output fall below battery voltage, the battery will supply power to the inverter automatically, without interruption, until the rectifier output recovers. The inverter changes the de input to an ac output electronically.

The 120 Vac output of the in-service converter module is routed to a power switching module (static switch) as the normal source of power. An alternate source of 120 Vac power is supplied to the static switch from a 480 Vac emergency bus through a step down transformer. If the normal source of power from the power converter module is lost, the static switch will automatically transfer to the alternate hard source and continue feeding the UPS loads without interruption. When the normal supply to the static switch is reestablished, the normal lineup can be realigned by initiating a retransfer locally at the static switch.

A manual transfer switch is provided around the static switch which allows connecting the normal or alternate power supplies directly to the UPS loads. This is a manual operation and allows maintenance and testing to be performed on the power converter modules or static

. switch while maintaining the UPS loads energized. If the primary module fails, the backup can also be manually placed in service.

1.2.2 Capability for Assessing the Time History of Analog Variables 1.2.2.1 Brief Description of Equipment Strip chart recorders are provided for recording the signals from key instrument channels in the Control Room.

l Each unit has a dedicated upgraded Honeywell 4010 process computer.  !

The analog scanning hardware monitors 768 analog input points

- capable of monitoring square root analog, linear analog, RTD, thermal couples, and other type points. The scan software controls scanning, conversion to engineering units, averaging, and alarming points that are beyond a high or low limit. The software includes 4 features such as variable limits, dead band, reasonable limits, open thermocouple detection, composed points (calculated values), rate of change, and scan averaging. Analog points which exceed their associated limits are alarmed by printing on the alarm typer in the Control Room and by displaying on a CRT on the control board.

Each process computer has access to a vast amount of process data which it can scan and monitor. The following is a summary of the data arrays on bulk and those in core of each unit's process computer.

f 13

CORE: (1) Latest :: canned or calculated value for analog, digital, and composed points (calculated values).

(2) NSS post-trip log data tables.

(3) B0P post-trip log data tables.

(4) Sequence of events, point data tables.

(5) Control rod positions for the 137 control rods.

4 (6) Tables to hold temporary averages and rate of change data. ,

BULK: (1) Data base required to support nuclear programs.

(2) Traveling Incore Probe (TIP) data base.

(3) Exposure arrays including nodal fuel exposure, exposure voids, LPRM chamber exposure, and control rod exposure records.

(4) BOP data being collected for hourly and daily log.

(5) Average values required to support the BOP program run every ten minutes.

The system has the capability of providing three logs:

1. BOP log

2. NSS post-trip log

3. BOP post-trip log The function of the BOP log is to monitor data points which present an overall picture of plant operations and equipment performance.

The BOP log program records daily averages, hourly averages and instantaneous values. These values are then printed on a continuous roller log. A dedicated printer is used for the BOP log sheet. BOP performance calculation programs, together with supporting B0P subroutines, operate at 10-minute intervals.

The BOP and NSS post-trip logs are analysis tools for determining a time history of selected analog points immediately prior to and following a major plant trip event (e.g., a turbine trip, a

generator trip, a reactor scram). The B0P post-trip log contains values for the balance-of plant inputs, and the NSS post-trip log contains selected nuclear system inputs. Both logs are automatically initiated upon occurrence of predefined plant trips and either one can be demanded from the computer operator's console. The B0P post-trip log is initiated automatically following a reactor scram and turbine trip; the NSS post-trip log is initiated automatically only by a reactor scram.

14

1.2.2.2 Parameters Monitored, Sampling Rate, and Basis for Selecting Parameters and Sampling Rates Appendix F lists many of the instrument channels which are continuously recorded. Additional instrument channels are also continuously recorded in the Control Room or in remote locations.

These often provide pertinent information dependent on the nature of the shutdown. The selection of these recorded points was based on that information which needs to be trended to support plant operations or needs to be documented for future reference. Plant operating instruction 0I-22 requires that the following typical charts be included in a scram / incident report (refer to Appendix B, OI-22, page 10, for detailed listing):

1. Recirc Pump Flows - Loops A and B

2. Total Reactor Core Flow

3. Reactor Core Delta-P

4. APRM Power

5. Main Steam Flow

6. Feedwater Flow

7. Reactor Water Level

8. Reactor Pressure

9. SRM Flux

10. Main Condenser Vacuum

11. Steam Jet Air Ejector (SJAE) Radiation Monitor

12. Main Steam Line Radiation Monitor i

13. Reactor Building Vent Radiation Monitor

14. Drywell Pressure The computer log programs obtain information from the main scan program. It has scan intervals of 1, 5, 15, 30, 60, and 120 seconds with alarming capability on the analog points and the limit-checked calculated points. The BOP log has the capability of monitoring 160 analog points, although some of the points are of minimal benefit and not currently in use. A copy of the logs is provided in Appendix E.

Data values scanned and calculated by this program are stored for printout on the Balance-of-Plant hourly, daily, and monthly logs.

15

._ _ _ . . _ _ . , _ . _ . . _ _ _ _ o _, _ _ _ _ _ _ _____._ _ _ _ . _ _ _

The BOP hourly log contains instantaneous or 10 minute averaged values for the input points assigned to this log. The daily and monthly logs contain values that are averaged or accumulated over the respective daily and monthly logging periods.

The NSS post-trip log monitors 10 points, scanned once per second, as shown in Figure 2 of Appendix E.- The B0P post-trip log can monitor up to 40 points scanned once every 15 seconds. The post-trip log parameters were selected so as to provide the best indication of

, a problem, thus aiding in analysis.

1.2.2.3 Duration of Time History (Minutes Before Trip and Minutes After Trip)

The plant instrument recorders maintain a continuous record of the monitored parameters both during normal operation and operation during transients. The process computer retains the last good scanned value or substitute value in the core memory for the analog points. Alarm messages for analog points out-of-limits are printed on the alarm typer as they are detected by the computer scan program.

The BOP log provides long term averages of scan values that are averaged every 10 minutes, hourly, and daily (refer to Appendix E, Figure 3). The hourly values are printed on the BOP log each hour.

The NSS post-trip log saves and prints out one-second data one minute before and one minute after the event. The BOP post-trip log can save 15-second data five minutes before and five minutes after the event. Post-trip log data is not retained in the computer after

, printout.

, 1.2.2.4 Format for Displaying Data Including Scale (Readability) of Time Histories Instrument records record the information on charts whose range typically covers the full operating range. The normal chart speed is 1-inch per hour. Some key chart recorders can be set for higher speeds where helpful. Some examples of chart recorders with faster speeds are the SRM and IRM recorders.

The basic analog point alarm format is as follows:

Alarm Point Name High Low Time Symbol ID 24 Characters Value Limit Limit IUiHESS AAAA AXXX' AA........AA XX.E XX.XX XX.XX The BOP log and format is shown in Figure 3 of Appendix E. It is a continuous roll with 8 logs and preprinted headings. The NSS post-trip log format is depicted in Figure 2 of Appendix E. The time of the event is shown to the left of the title. The BOP

post-trip log is in the same general format.

16 I

-_ -. _ . , - _ _ - _ . _ . - - . - , , _ _ . _ . , . . _ . . . - . - . . . , - _ _ _ . _ . _ . _ . - _ _ _ _ _ . , . ~ . . - _ - - _ _ . - . . . , - _ . , . ~

1.2.2.5 Capability for Retention of Data The strip charts from recorders are numbered and stored in the vault. The main scan program alarms for analog points detected beyond their limits are printed on the alarm typer in the Control Room. This information is not retained in the computer. The B0P log edits provide a long-term storage of a number of points, such as, hourly averages, accumulations, calculated results and various instantaneous readings on permanent printed logs. Printouts from

.the alarm typer and the post-trip logs are included with the scram report which is maintained on file by Document Control.

Further long-term storage of data includes the twice weekly magnetic

, tape copies of the data base and the end-of-the-month magnetic tapes. When a magnetic tape of bulk memory is made, bulk data arrays are recorded as of that time. The Nuclear Data Base classi-fication information is recorded and preserved in the end-of-the-month magnetic tape.

1.2.2.6 Power Source Power for the computer, annunciators, and most strip charts and Control Room instrumentation is provided by either the uninterruptible power supply (UPS) or directly by the emergency power system. The

. normal off-site electrical feed for the safety-related emergency power system is backed up directly by the plant emergency generators.

Refer to Section 1.2.1.6 for a detailed description.

1.2.3 Other Data and Information Other sources of information used to assess the cause of an unscheduled reactor shutdown include-the eyewitness accounts taken immediately 4 after the transient. These accounts provide information gained from annunciators, automatic actions, and manual operator actions. Hard-ware inspection and analysis also provides a means for determining the cause of component failure. The process computer also has the capability of recording several analog signals on one of the several trend recorders. These may be set up to continuously record signals

of special interest during an interim period of time.

The utilization of instrumentation charts, computer data, hardware inspections, and eyewitness accounts provide an extensive base from which the event can be evaluated, the proper functioning of auto-matic actions verified, and the consequences of the event can be determined to be acceptable.

17

1.2.4 Schedule of Improvements Just as with the previous installation of additional core and bulk memory, further upgrades to tae process computer are continuously

-being implemented. Projects under consideration include: 1) enlargement of the sequence of events buffers in the core memory to retain additional points and storage of data on bulk memory as a backup, 2) modifying the BOP post-trip log to a five second interval data storage mode and rework point selection, and 3) expanding the NSS post-trip log from 10 to 15 points (refer to Appendix C, Item Nos. 1, 2, and 3).

The most ambitious project in this area is the implementation of the ERFIS/SPDS computer system required in response to TMI regulations.

The planned design will provide significant improvements in the following areas by adding new computers which will be able to access the existing process computer data base:

1. Faster scan rates

2. Additional safety related points Larger trending logs 3.

4. Larger historical logs

5. Improved display and replay of historical data

6. Color graphic displays

7. Improved point validation techniques The proposed action plan and schedule for implementation of the ERFIS/SPDS system is established in the NRC Generic Letter 82-33 response and is not included in this. report. Any further regulatory follow-up on this improvement should be monitored in accordance with the 82-33 response programs.

In summary, the referenced procedures and equipment demonstrates a capability to record, recall, and display data and information to permit diagnosing the causes of unscheduled shutdowns prior to i restart and for ascertaining the proper function of safety-related equipment. Submittal of the proposed action plans constitutes compliance to Section 1.2 of NRC Generic Letter 83-28.

2.1 Equipment Classification and Vendor Interface (Reactor Trip System Components)

Volume XI, Book 2 of the Plant Operating Manual identifies the nuclear safety-related (Q-list) portions of plant systems. This list is used as the reference for determining what plant components are nuclear safety-related. Activities which affect the function of Q-list components, such as maintenance and procurement, are required to be performed under the 18

control of procedures which reflect the requirements of the Corporate QA manual and which are intended for the control of Q-list related activities.

A review of the Q-list verified that the safety-related mechanical portions of the Reactor Protection System, the safety-related instrumentation of the Reactor Protection System, and the safety-related instrumentation of other systems which generate trip signals are listed in the Q-list within its guidelines as discussed in Section 2.2.1.2. Documents initiating design, maintenance, or procurement are required to identify whether the associated components are Q-list. A sample review of trouble tickets involving maintenance activities on the Reactor Protection System components revealed the appropriate Q-list designation and that appropriate safety-related procedures were referenced. The review included 100 of 491 randomly selected trouble tickets. A review of the pertinent maintenance instructions associated with the Reactor Protection System determined that Q-list was appropriately referenced either in the procedure, for recent ones, or in reference + a MP-04: General Maintenance Procedure, which references Q-list activities. Additional detail on the control of activities involving Q-list components is provided in Section 2.2.

l BSEP has in place several programs which provide for the evaluation, implementation, and control of vendor supplied information. Refer to Section 2.2.2 for a detailed discussion of these programs.

The General Electric (GE) Company designed and provided the major Reactor Protection System components Jor Unit Nos. I and 2 at Brunswick. GE currently utilizes a BWR Services Information Letter (SIL) System that documents recommended changes in equipment and procedures and conveys i information concerning unique operating conditions and experiences at other BWR plants. SILs and other vendor recommendations received by BSEP are processed in accordance with plant procedure PPP-02: Vendor Recommen-dation Processing.

General Electric services relating to the Reactor Protection System or any safety-related equipment are coordinated through General Electric

site representatives. The site representatives belong to the Domestic

; Apparatus and Engineering Service Operation Division of General Electric 4

and interface on safety-related NSSS issues with the Nuclear Energy

Business Operation Division (NEB 0D) in San Jose, California. The NEBOD personnel provide services related only to nuclear concerns while there exists numerous divisions that handle non-nuclear issues. The Nuclear Energy Products Division (NEPD) is responsible for the development and distribution of SILs. This divisional concept employed by GE ensures requisite control of nuclear versus non-nuclear work. In addition, safety-related work performed on site must be performed under the control of CP&L approved procedures.

The procedures and vendor interface program previously mentioned provides confidence that adequate controls are established for the Reactor Protection System components in determining that vendor information is appropriately incorporated in plant instructions and procedures.

19 ,

2.2 Equipment Classification and Vendor Interface (Programs for Safety-Related Components) 2.2.1 Program Description Volume XI, Book 2, of the Plant Operating Manual contains the Q-list procedure which defines the boundaries for which activities (design, procurement, maintenance, etc.) which are considered safety-related and required to be performed under the Corporate Quality Assurance program. This book provides: a) the general criteria for determining which plant items are Q-list (safety-related), and b) an identification of the portions of systems which are Q-list. This list is used as the basis for determining the need to identify documents and activities as Q-list and to evoke appropriate Q-list procedures.

2.2.1.1 Criteria for Component Identification The criteria for determining a Q-list plant item is as follows.

(excerpt from Volume XI, Book 2):

"The Q-list plant items for a nuclear power station are those structures, systems, and components (of both safety and non-safety systems) whose integrity or reliability is essential in preventing -

or mitigating the consequences of postulated accidents (i.e.,

limiting plant process conditions) that have the potential of causing injury to the public from substantial levels of radiation or release of substantial quantities of radioactive material from their intended place of confinement within the plant. To qualify as a Q-list plant item, the plant item in question must be necessary to:

a. Provide for structural integrity (or be a part) of the reactor coolant pressure boundary, or

b. Provide overpressure protection of the RCPB, or

c. Make and hold the reactor subcritical during the occurrence of frequent, infrequent, and limiting plant process conditions, or

d. Cool the core following normal reactor shutdown and during the occurrence of frequent, infrequent, and limiting plant process ,

conditions, or

e. Cool another safety system component during the occurrence of frequent, infrequent, and limiting plant process conditions, or i

! f. Provide essential services to the reactor containment during l

the occurrence of infrequent and limiting plant process condi-tions, or l

l g. Contain, control, or reduce the radioactivity release to the environment during the occurrence of frequent, infrequent, and limiting plant process conditions."

20

Tables I, II, and III of Volume XI, Book 2 identify the portions of systems and structures that are considered safety-related and which must be controlled in accordance with the requirements of the Corporate Quality Assurance program. When situations arise that require clarification of the actual physical boundary of a Q-list component, the following guidelines are used for interpretation (excerpt from Volume XI, Book 2): ,

"1) Mechanical Ccaponents

a. Q-list " fittings" includes all items which form part of or are installed in the pressure boundary such as branch outlet nozzles or nipples; instrument wells; reservoirs; blind flanges, studs and fasteners in flanged joints between pressure parts; traps, strainers, orifices, etc.

b. When a valve, which serves as an interconnection between Q-list and non-Q-list components, is welded on both sides, the weld on each side shall be treated as Q-list.

c. All instrument lines and fittings that are tapped off Q-list components are themselves Q-list items.

(1) If they lead to Q-list instruments.

(2) Up to and including the primary containment outer isolation valve if they lead to non-Q-list instruments and are tapped off RCPB components.

(3) Up to and including the first root valve (from the process side) if they lead to non-Q-list instruments.

d. All instrument lines and fittings that are tapped off non-Q-list components and lead to Q-list instruments are themselves Q-list items up to and including the first root valve (from the instrument side).

2) Instrumentation and Control Components

a. Instruments, controls, and their interconnecting wiring circuits that provide readouts and alarm functions which are the sole basis for correct manual initiation of nonautomatic safety system functions are Q-list items.

b. Instruments, controls, and circuitry between the process variable (s) sensors and the input terminals of the actuator systems involved in generating signals that initiate automatic safety action are Q-list items.

NOTE: The actuator system is that equipment which accepts safety system output signals and per-forms a safety action.

21

3) Elec il Components

a. .ose circuit elements (such as annunciators, relays, rwtors, indicating lights, ammeters, voltmeters, frequency meters, etc.) for safety system components, t' . failure of which could disable the accomplishment of a safety function,

, are Q-list items.

b. Circuit elements that are used either for information or analysis only (such as inputs to computer, rod position information circuit elements, etc.) are non-Q-list items.

c. Power supply and control supply circuit elements whose failure actuates the affected safety system (or its portions) in such a way as to put the reactor in a safe shutdown condition are non-Q-list items."

2.2.1.2 Information Handling System The Q-list identifies, in tables, the portions of systems, the instruments, and the special components of systems which are safety-

. related. These tables provide guidelines for identifying power and control circuit elements (breakers, switches, relays, etc.) that are also Q-list. Development of this document is based on information contained in the FSAR and guidance provided by ANSI /ANS-52.1-1978:

Ifuclear Safety Criteria for the Design of Stationary Boiling Water heactor Plants (which superceded ANS N-212-1974).

t The Q-list is a part of the Plant Operating Manual, and so is l considered a controlled document. It is the respnsibility of the l Technical Support unit to maintain and revise this document.

Revisions to the Q-list require a safety analysis and two party technical and safety review as well as Plant Nuclear Safety Committee and plant General Manager approval.

Improvements to the Q-list procedure are currently being formulated that will create a more detailed compnent level quality classifi-cation system for plant equipment. The computerized data base ,

l system for the control and dissemination of the quality classification l on a component level is being developed. A project plan is also l being created for the classification of equipment and loading of the information into the data base. It is intended that the first priority of the classification effort will be the Reactor Protection System.

Generally, the project plan will address the following:

a. Procedures required for development and control of the computerized quality classification data base.

b. The safety-related systems (or portion of systems) to be revised and more detailed components classified with priority j for each.

j 22 l

__ _ _ - _ - . . . _ . , - _ _ ~ _ , _ .

5

c. The process to be used to integrate the new component quality classification into the approved plant Q-list procedure on a system-by-system basis as we complete each system. This process is needed so that we can transition from our current process to the new component level data base as it is developed.

2

d. The process to be used in validating that the procurement, maintenance, and calibration activities are properly designated in the appropriate procedures.

e. A milestone schedule for completing the project.

The validation process will be performed on a system basis as each system is implemented. The plan for implementing the improvements is provided in Appendix C, Item No. 5. The present safety classification system is adequate until a detailed computerized quality classification data base is established. A review of 100 randomly selected trouble tickets associated with the Reactor Protection System found that proper Q-list classification is being utilized.

2.2.1.3 Information Handling System Use The plant procedures governing maintenance, modifications, and procurement activities provide for the determination of whether the '

intended actions affect or involve Q-list components or systems before any work begins. The results determine whether procedures '

and processes for the control of safety-related activities are required. If so, they must be implemented to control the process.

Maintenance procedure MP-14: Corrective Maintenance, provides administrative direction for corrective maintenance. It requires j that the Work Request and Authorization (trouble ticket), which identifies and is used to authorize specific maintenance of equipment,

identify on the trouble ticket if the affected components are Q-list and identify the specific maintenance instructions to be implemented.

Maintenance procedures MP-03: Calibration of Process Instruments, i MP-10: Preventive Maintenance Program, and MP-16: Writing Corrective Maintenance Instructions require that maintenance instructions be l written for maintenance on Q-list equipment except in specific i cases. These procedures require that new maintenance instructions j identify applicability to Q-list equipment. This designation is I included in new instructions and is being added to old ones as they are revised and converted to the new format. Some special maintenance activities are controlled by individual maintenance procedures.

While these do not always identify if they apply to Q-list activities, these procedures are always invoked by trouble tickets which identify whether the affected components are Q-list.

1 23 l

l _ _ . _ _ _ _ _ . _ _ _ _ _ _ ___ _ _ _

1 When the work involves a Q-list related component for which there is no procedure, the Maintenance Engineer prepares written work instruc-tions for the job in accordance with maintenance procedures MP-03, MP-10, MP-12, MP-16, HP-26, and MP-30 (or other approved procedures) as required.

Often, an approved work procedure exists which is applicable to the work being performed and is referenced accordingly on the WR&A.

Store procedure SK-01: Material Requisition and Reorder Procedures and Responsibilities, describes the controls imposed to ensure that plant procured Q-listed materials are properly identified, procured, received, inspected, and stored. Safety-related materials are identified by reference to the Q-list and are ordered on a color-coded requisition form which differentiates from non-Q requisition forms. The requisition is then subjected to the required reviews and approvals, including Quality Assurance and Quality Engineer /

Specialist reviews, to ensure appropriate design and inspection specifications are referenced and that the material is procured from a qualified vendor as established by the Corporate QA Manual.

Plant modification activities are controlled by engineering procedure ENP-03: Plant Modification Procedure. It requires that modifications affecting safety-related equipment be identified as Q-list and the requirements of the Corporate QA Manual and other applicable documents be implemented in the modification procedures.

s 2.2.1.4 Management controls Plant procedures and instructions controlling activities affecting Q-list equipment are a part of the Plant Operating Manual. As such, they are controlled documents and must receive certain reviews and approvals before implementation or revision to verify their technical correctness and conformance to applicable requirements. The basis

, for the change, a safety analysis, QA review, tw3 party technical and safety review, and required PNSC and plant General Manager approval are required for new or revised procedures.

QA reviews of maintenance work packages prior to closeout and record storage ensure that the maintenance activities were properly classified and that the work performed is in accordance with the correct

• procedure. These specific QA reviews are also supplemented by periodic QA surveillances and audits of the programs to provide further assurance of the correctness of the programs and their implementation.

2.2.1.5 Design and Qualification Verification Plant Q-list purchase requisitions are routed through a procurement support group in the plant's Technical Support unit for review by the Quality Engineer / Specialist. Their review verifies that the proper specification, technical requirements, and quality assurance require-24

ments are stipulated. Upon their approval, the requisition is forwarded to the Quality Assurance group for their review. Both groups must review a Q-list requisition before any order can be placed. This process ensures that parts are being properly specified when ordered.

Off-site procurement of safety-related material used at BSEP is controlled by the Standard Procedure Nos. NPCD-P-0066 for "Constructica Procurement," and NPCD-P-0075 for " Final Approval of Requisition for Site-Procured Items." These documents contain the guidelines used by Carolina Power & Light Company Nuclear Power Plant Construction Department, Brunswick Nuclear Project Department, Nuclear Plant Engineering Department, and Fossil Plant Engineering & Construction Department for final approval of requisitions for construction procured items. Directives are provided to ensure requisitions are prepared from approved drawings and specifications and that the preparation meets the project administrative procedures, particularly those related to specifications and quality assurance requirements. All safety-related purchase orders must be reviewed and approved by the Corporate Quality Assurance Department (CQAD). CQAD also approves the vendor selection. Items must include certification requirements and provisions of 10CFR Part 21 on the purchase order when required.

Plant modifications which are determined to affect Q-list components 1 receive the following reviews in addition to the routine management reviews to assure the appropriate procurement requirements are specified:

o Technical review o Safety analysis o QA review o Independent nuclear safety review by the On-Site Nuclear Safety group o Plant Nuclear Safety Committee review o General Manager approval o Corporate Nuclear Safety review of safety analysis 2.2.1.6 Equipment Classification Program Appendix I contains the Erunswick Q-list equipment classification program.

I At present, the industry and the NRC are debating whether there is a l

distinction between "important to safety" and " safety-related." We believe there was not originally any intent difference in the two terms and that each term is describing activities or equipment that directly affect a safety-related function. In this light, Brunswick does not feel that the concept of "important to safety" was intended to define a broader class of equipment for which " safety-related" equipment is a subset. Therefore, we believe that the provisions of 2.2.1.6 of the 83-28 letter is satisfied by our current program pending the NRC's establishment of a more structured definition.

The Atomic Industrial Forum is presently pursuing this issue.

25

2.2.2 Vendor Interface Program CP&L is supporting the INPO Nuclear Utility Task Action Committee (NUTAC) on NRC Generic Letter 83-28, which is currently focusing on industry-wide vendor information programs for safety-related equip-ment vendors other than NSSS vendors. We believe this prcgram will provide, when implemented, a practical industry-wide approach to assuring safety-related equipment reliability.

BSEP has in place a vendor interface program which provides for the evaluation of vendor information associated with safety-related components and the subsequent incorporation into plant instructions and procedures as appropriate. The vendor interface process, in combination with other plant and industry programs, provides assurance of the reliability of safety-related components commensurate with the safety functions.

Existing vendor interface procesa features include:

1) Control of vendor manualt oupplied with original plant equipment and with equipment installed as a result of design changes (RMI-01: Capture and Indexing of Correspondence and Plant Records; and RMI-03: Reproduction, Distribution, and Accountability of Plant Documents).

2) Use of vendor information in developing self-sufficient approved and controlled technical maintenance instructions (MP-3^:

Writing Corrective Maintenance Instructions).

3) Evaluation of vendor recommendations (PPP-02: Vendor Recommendation Processing).

Feature 1 is accomplished by incorporating vendor technical manuals in the document control process as controlled documents. Personnel requiring controlled copies of these manuals utilize the master copies of these documents and/or controlled drawings where determination of the as-built condition is required. New manuals and revisions resulting from changes to plant equipment are distributed upon Engineering approval or as part of the plant modification process.

Maintenance instructions are required for maintenance on safety-related equipment as discussed in Section 2.2.1.3. The technical manual is used as a source of reference material in preparing the maintenance instruction. The instructions are independently reviewed and approved by plant management and PNSC. This process provides for review and incorporation of technical manual information and the i added benefit of trained personnel input to the procedural steps to be utilized. Thus, the vendor input is evaluated before use and integrated with site specific conditions and experience. A self-sufficient, complete maintenance instruction is developed from the available pertinent information. Consequently, the vendor manual is 26

. - _ _ _ _ _ _ ._- _ _ ~ _ _ - .

usually of no further use. In some cases where the equipment is complex and the vendor manuals are suitable for direct use, the particular section of the manual that provides instruction for accomplishing the desired activity is directly referenced as part of the approved procedure. This constitutes Feature 2 of the process.

The last feature deals with the processing of vendor recommendations.

^

Vendor recommendations received are handled in accordance with Plant Procedure PPP-02: Vendor Recommendation Processing. By this proce-dure, recommendations are forwarded to the Performance and Reliability group. If the recommendation is applicable to BSEP and is safety-

~

related, it is forwarded to the On-Site Nuclear Safety (ONS) group.

. 0NS reviews the recommendations against ONSI-01: Operating Experience Feedback. An assessment is then conducted to assure that operating information pertinent to plant nuclear safety is supplied to the operating, maintenance, and training organizations. During this evaluation, ONS considers feedback based on elements of generic applicability such as:

a. Design of facility / component / system.

b. Vendor and likelihood of similar problems.

c. Addressed by CP&L procedures. ,

d. Addressed by CP&L training.

e. Item deemed isolated event or of minor significance. ,

f. Simil.; problem / event already addressed at CP&L plants.

g. Problem isolated to specific batch / production run not applicable to CP&L.

h. Item adequately addressed by another information system.

After their review, the recommendation is then forwarded to the '

responsible plant group for implementation along with an Operations Experience Feedback (0EF) report. If the recommendation is applicable to BSEP and is non-safety-related, it is forwarded directly to the applicable group. This program is also defined in Administrative Instruction AI-02: Feedback of Operating Experience.

Vendor recommendations are logged and tracked by the Performance and Reliability group. Recommendations must either be implemented or justification for not implementing provided with approval by senior site management as defined in the procedure. A diagram of this process it included in Appendix H.

27 i

P

- -,-y-- ,

" W v

Vendor information from General Electric (GE) is provided in the following ways:

1. Service Information Letters (SILs) are primarily for NSSS equipment and document changes in equipment and procedures.

2. Technical Information Letters (TILs) are primarily for turbine equipment and document changes in equipment and procedures.

3. Field Disposition Information (FDIs) for construction design changes.

4. Service Advise Letter (SALs) are primarily directed toward power delivery devices (switches, motors, relays, etc.) and document changes in equipment and procedures.

These items are processed at Brunswick in accordance with plant procedure PPP-02. Product Service Information Letters (PSILs),

Operating Experience Reports.(OERs), and Operating Bulletins (0Bs) were issued by GE prior to July 1973. Since that time, SILs have replaced these documents. A master status listing of the SILs is issued periodically to provide a feedback for both the vendor and client in monitoring the status of compliance to these NSSS vendor recommendations.

CP&L believes the program described above meets the requirements of Section 2.2.2 except for establishment of a working vendor interface and positive acknowledgement feedback upon receipt of vendor recommen-dations (excluding NSSS vendor). We believe, as a general rule, that these aspects of a program are not practical or cost effective as formal features, but rather, are inherent informal aspects of our parts procurement process and other plant and industry equipment performance and reliability reviews.

The surveillance testing program provides test and operational data which, in conjunction with equipment operating and maintenance history, provides a mechanism for early identification of equipment failure. Once identified, recurring equipment failure is addressed by Maintenance or Engineering personnel who utilize vendor contacts for determining corrective actions. Vendor interface is also presently established in our spare parts requisition process.

Vendors are contacted by' Store and Maintenance personnel when ordering replacement components and materials. Safety-related equipment vendors activities are controlled and monitored in accor-dance with Section 4 of the Corporate Quality Assurance Manual:

Procurement and Control. In addition, Section 5: Material and i

Equipment Control, enforces assurance that the vendor has completed j fabrication, inspection, and testing in accordance with specifications and proper documentation is supplied.

1 l

! 28

~ . ._ - _ .- _ . - . - . - ..

Additionally, the plant Performance and Reliability group utilizes information from INPO (NPRDS) in performing a quarterly equipment failure trending analysis on major components within the current

- scope of that system. This trending analysis is accomplished using plant procedure ENP-22: Equipment Failure Trending and Analysis which was initially approved on December 31, 1982 and is being imple-mented and expanded in conjunction with the current INPO rescoping effort. INPO's own trending of NPRDS data is being revised and may replace the BSEP program in the future if significant improvement is made. Significant events (without recommended action) are provided in INPO Significant Event Reports (SERs). In addition, operating and technical information is provided in the INPO Operating and Maintenance Reminders (0&MRs), Operating Experience Reports (OERs),

and Significant Operating Event Reports (SOERs). This information is reviewed by ONS and is processed in accordance with the Operating Experience Feedback (OEF) program.

NRC notification of safety-related concerns and regulatory requirements such as IE Bulletins, Notices, and Circulars, provide current information concerning component or design discrepancies that affect plant equipment and operating conditions. These notifications are further supported by the provision of Title 10, Chapter 1, CFR Part 21, which requires "that the directors and

. responsible officers of organizations that construct, own, operate, or supply components of a facility or activity that is licensed or otherwise regulated by the Nuclear Regulatory Commission inform the Commission if they obtain information reasonably indicating that

, such facility, activity, or basic component fails to comply with regulatory requirements relating to substantial safety hazards or li that such facility, activity, or basic component contains a' defect which could create a substantial safety hazard." This provides an effective additional safeguard for early identification of safety-related component failure or design discrepancy.

Since the existing vendor recommendation program PPP-02 was formally.

implemented in March,1982, BSEP plans to establish a program to review applicable historical safety-related equipment supplier recommendations relating to equipment problems issued since January, 1974. We believe that the most benefit would be achieved from focusing on these three sources of information. The focus of our review will be to determine if the recommendation was applicable to BSEP and if so, was it implemented or a basis for not implementing provided. Our plans for completing this review are provided in Appendix C, Item No. 9.

4 29

.-,...,,,,,,.e,.-..-.-...---__-,-..,-,,-m, ,,

' In combination with the vendor interface processes previously discussed, the following BSEP practices and controls provide adequate

assurance of safety-related component reliability commensurate with its safety function

1) Operating and maintenance procedures and instructions which reference or incorporate pertinent vendor technical information that has been received and evaluated for safety significance.

2) Surveillance testing program - procedures and test data.

3) Plant and industry equipment operation and maintenance history reviews with ongoing interface with vendors as required.

4) Quality Assurance programs applied to component procurement, operating, and maintenance procedures.

In summary, the vendor interface processes and the regulatory and '

industry notifications, in combination with BSEP's commitment to equipment preventive maintenance, surveillance testing, equipment corrective maintenance, and the quality assurance program, provide assurance of safety-related component reliability. This obviates the need for development of additional formal programs of periodic vendor contact or acknowledgement of feedback for other than the NSSS vendor as described in response to 2.1. For safety-related equipment vendors who have gone out of business or will not supply infonnation, such formal vendor contact programs would serve no

. purpose.

Thus, we do not plan to implement additional formal programs for

. periodic vendor contact or acknowledgement of feedback for other than the NSSS vendor as described in the response to Section 2.1.

The BSEP program provides assurance of sefety-related equipment reliability and cost-effective safety enhancement.

3.1 Post-Maintenance Testing (Reactor Trip System Components)

BSEP incorporates a post-maintenance testing program which requires that testing be performed following maintenance on safety-related components, including the Reactor Protection System, to verify their operability.

This procedure is outlined in maintenance procedures MP-10: Preventive Maintenance Program, and MP-14: Corrective Maintenance.

The specific test requirements are determined and reviewed by the Maintenance Planner, Operations personnel, and the Shift Operating Supervisor based upon the scope of the completed repair and whether technical specifi-cation surveillance or ASME,Section XI, Inservice Inspection directives are required.

30 9-.. .= +_m 7,,...-w,-~.m. , e _ , , , -, ,-,, , , , _. 4 .,,.9_.4,m. s._7v._ y y , , , ,yp,9p,. --7 mpy _.-w_y.7, p,,7-,, . ,, 3--.--.mm, 9

Surveillance requirements are identified through the use of technical specifications, administrative instruction AI-33: Surveillance Test Cross-Reference to the Technical Specifications, and engineering procedure ENP-16: Procedure for Administrative Control of Inservice Inspection Activities. The post-maintenance testing must be performed before returning the equipment to service.

Upon completion of the specified post-maintenance testing, the documen-tation is routed to Engineering for ISI and NPRD review and then to QA for final acceptance. A flowchart escribing the process is located in Appendix G of this report. Completion of this process provides a high level of assurance that safety-related components are tested after maintenance. The capability for performing their intended safety function is therefore reasonably demonstrated before being returned to service.

The testing which is performed after maintenance is determined from the scope of the maintenance and surveillance requirements of the technical specifications and ASME Section XI for verifying operability. These sources assure the adequacy of the tests performed for assuring the operability of the component. These various independent reviews further supports the concept that the required testing is properly referenced.

3.1.1 Test and Maintenance Procedure Review As previously stated, a post-maintenance test program is in effect-at BSEP. Maintenance and Engineering personnel have reviewed the periodic test program requirements associated with the Reactor Protection System as specified by AI-33, the technical specifications, and the applicable maintenance procedures and determined that an effective program exists for accomplishing post-maintenance testing on safety-related components in the Reactor Protection System.

The review of technical specifications also determined that testing of the Reactor Protection System trip function is required at least every 18 months (reference TS-4.3.1.3). This requirement provides for the testing of each logic train from the instrument sensing the measured parameter to the scram solenoids which includes the scram

[ *elays. A review of the surveillance procedures determined that they adequately meet the requirement of TS-4.3.1.3. The technical specification required test procedures separately test each logic

! channel verifying the condition of each redundant trip mechanism.

These surveillance procedures are the ones which were found to be typically used following maintenance to demonstrate the operability of the effected equipment.

3.1.2 ' Vendor and Engineering Recommendations

, A review was conducted of the GE Service Information Letters (SILs) l associated with the Reactor Protection System. The purpose of this review was to develop a plan for determining if vendor recommendations for the Reactor Protection System have been addressed in existing plant procedures.

31

A review was conducted of 395 General Electric Service Information Letters (SILs) to determine relevancy to the Reactor Protection System. This investigation identified 28 pertinenc SILs and supple-ments.which were initially considered as applicable to the Reactor Protection System. An evaluation was performed on these items to determine: 1) applicability to the Reactor Protection System, 2) need for expeditious implementation, 3) optimum time frame for implementation, and 4) need for sample inspections to confirm assessment. It was determined that SIL-308 (CR105D and/or NEMA 2 Contractor / Starter Contact Binding) should be implemented during the current unit shutdowns to confirm that no problem exists with contactor binding-in the Reactor Protection System K-14 and K-15 relays. In addition, SIL No. 360: CR2940 Tanden Block Switches, ar.d SIL No. 155: Inspection and Cleaning of General Electric Type SBN Control Switches (Unit No. 2 only) were identified as action items for implementation during the next refueling outage. In addition, the remaining SILs were found to either have been imple-mented with HIs and pts, appropriately justified if not implemented, or were determined not applicable to the Reactor Protection System.

It was also determined by this review that no obvious deletion of pertinent vendor recommendations existed in either the maintenance instructions or the surveillance periodic tests as specified in the technical manuals. The investigation consisted of the following process:

1) Identification of vendor recommendations.

2) Review of drawings, system descriptions, and design information associated with the Reactor Protection System.

3) Identification of pertinent teghnical manuals.

l 4) Identification of associated maintenance procedures.

5) Identification of associated surveillance periodic testing procedures.

6) Identification of NRC IE Bulletins, Circulars, Notices, and NUREGs associated with the Reactor Protection System components.

7) Verification that recommendations from the above sources were i

properly incorporated into plant procedures related to maintenance and testing.

System walkdown of components and interviews with system Engineers, Maintenance Foreman, Technicians, Planners, and vendors were utilized concerning implementation of vendor recommendations. An itemization of the items reviewed appears in Appendix J.

32

- - - . ..-_n_ - l

The action plan and schedule for accomplishing a review and implementation of recommendations from sources other than SILs is included in Appendix C, Item No. 6.

3.1.3- Post-Maintenance Testing Requirements - Technical Specification Related A review of BSEP Standard Technical Specifications was conducted by the On-Site Nuclear Safety department to determine if any specific post-maintenance test requirements relevant to the Reactor Protection System degraded rather than enhanced safety. The review identified no tests which tended to degrade safety.

The : cope of the review included only those requirements which were clearly defined in technical specifications au post-maintenance tests and not implied post-mainteaance tests indicated by the action statements, or reference to Technical Specification 4.0.5. An action plan and schedule for accomplishing this expanded review is located in Appendix C, Item No. 7.

3.2 Post-Maintenance Testing (All Other Safety-Related Components)

'The description of the post-maintenance testing program was previously presented in Section 3.1. Reactor Protection System components are not addressed any differently than other safety-related components.

3.2.1 Test and Maintenance Procedure Review '

i- ,

As outlined in Section 3.1, a post-maintenance testing program is in effect st BSEP. A review to verify that testing is performed after maintenance to demonstrate that safety-related equipment is capable of performing its safety functions will be performed as outlined in the project plan provided in Appendix C, Item No. 8.

3.2.2 Vendor and Engineering Recommendations (All Other Safety-Related l' Components):

, An assessment of safety-related vendor and engineering i

recommendations is planned. An action plan and schedule for

implementation of this effort is located in Appendix C, Item No. 9.

3.2.3 Post-Maintenance Testing Requirements - Technical Specification Review A review of BSEP Standard Technical Specificaticns was conducted by the On-Site Nuclear Safety department to determine if any specific post-maintenance test requirements relevant to safety-related j~ components degraded rather than enhanced safety. The review identi-fled no tests which tended to degrade safety.

33 -

i

>c

The scope of the review included only those requirements which were clearly defined in technical specifications as post-maintenance tests and not implied post-maintenance tests indicated by the action statements, or reference to Technical Specification 4.0.5. An action plan and schedule for accomplishing this expanded review is located in Appendix C, Item No. 10.

4.1 Reactor Trip System Reliability (Vendor-Related Modification)

Carolina Power & Light Company's Brunswick Unit Nos. I and 2 are boiling water reactors designed by the General Electric Company. Therefore, '

Section 4.1 is not applicable and no response is required. r 4.2 Reactor Trip System Reliability (Preventive Maintenance and Surveillance Program for Reactor Trip System Corponents) ,

Carolina Power & Light Company's Brunswick Unit Nos. I and 2 are boiling water reactors designed by the General Electric Company. Therefore, e Section 4.2 is not applicable and no response is required.

4.3 Reactor Trip System Reliability (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)

Carolina Power & Light Company's Brunswick Unit Nos. I and 2 are boiling water reactors designed by the General Electric Company and do not employ shunt trip attachments on the Reactor Protection System components.

Therefore, Section 4.3 is not applicable and no-response is required.

4.4 Reactor Trip System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)

Carolina Power & Light Company's Brunswick Unit Nos. I and 2 are. boiling water reactors designed by the General Electric Company, therefore

'Section 4.4 is not applicable and no response is required.

4.5 Reactor Trip System Reliability (System Functional Testing)

The Brunswick Unit Nos. I and 2 Reactor Protection System (RPS or Reactor Trip System) design complies with applicable regulatory requirements for the Reactor Protection System. A review of the Reactor Protection System on-line functional testing and testing intervals was performed and found to be consistent with achieving a high scram system reliability.

4.5.1 Diverse Trip Testing CP&L will perform surveillance of the backup scram solenoid valves to verify their proper operation by independent off-line testing of each valve during refueling outages. The acceptability of this level of testing was confirmed by the NRC's evaluation in NUREG-0979, Safety Evaluation Report Related to the Final Design Approval of the 34

GESSAR II, BWR-6 Nuclear Island Design. Carolina Power & Light Company is supporting the BWR Owner's Group activity which is pursuing this issue. Supplementary response to this section will be provided, if required, upon completion of the Owner's Group r assessment. Our plans for implementing testing of the backup scram valves are provided in Appendix C, Item No. 11.

4.5.2 On-Line Testing On-line testing of the Reactor Protection System is accomplished by-periodic functional channel tests, channel checks, and scram timing of control rods. On-line testing of the backup scram valves is not feasible due to the design of the system. The backup scram function I

is accomplished by two air operated solenoid valves which isolate the main air supply and vent the scram air supply header which connects to the individual Hydraulic Control Units. The b'ackup scram valves are redundant valves with redundant trip signals from both Reactor Protection System logic A and B. The logic is diverse from the primary Reactor Protection System since the backup scram valve solenoids are energized and de powered to trip versus the primary scram pilot valves which are deenergized to trip and ac powered.

Although one-half of the backup scram logic is actuated for each

- valve during channel functional tests, the only time the backup scram solenoids are actuated is when a complete scram signal is

' initiated. These valves cannot be tested on-line without scramming the plant. 'An independent test of each backup scram solenoid valve during each refueling outage is sufficient to assure the reliability of the Reactor Protection System >for the following reasons: -

1. The backup scram function was incorporated as an additional improvement in response to an already extremely remote event and~is not required by applicable regulatory requirements.

2. The backup scram function has been designed to be highly reliable by use of redundant valves and actuating logic.

3. Testing during operation would require a plant scram.

i 4. The primary scram pilot valve solenoids which are normally l

. energized and tested frequently are diverse to the backup scram solenoids which are normally deenergized and not cycled frequently.

Due to the lower testing frequency of the backup scram valves, the potential for a common cause or human error affecting the primary and backup Reactor Protection System is reduced.

35

For these reasons, on-line scram testing of the backup scram valves will not increase the reliability of the Reactor Protection System.

Therefore, the planned testing program is satisfactory.

)

4.5.3 Test Intervals A review of the Brunswick Unit Nos. I and 2 Reactor Protection '

System on-line functional testing intervals was performed and it was found that the frequency of tests was sufficient to ensure that an increase in failure rate due to a wearout condition or a common cause failure potential could be detected early and corrective action taken before the failure condition became systematic. The functional testing and testing intervals are consistent with achieving a high scram reliabilit.y. There is the potential for increased safety from less frequent testing due to a reduction in the possibility for human error and for challenges to safety systems due to spurious transients. If in the course of further reviews the determination is made that such a condition exists, a submittal will be made for a technical specification change.

The project plans and schedules for procedural development pertinent to testing backup scram valves is located in Appendix C, Item No.

11. Technical specifications will not be ammended to reflect this testing.

V. References The following is a partial listing of the references used in developing this report:

1. Administrative Instruction AI-02: " Feedback of Operating Experience," Revision 21, Volume I, Book 2, Plant Operating Manual.

2. Administrative Instruction AI-09: " Plant Nuclear Safety Committee Administration," Revision 13, Volume I, Plant Operating Manual.

3. Administrative Instruction: AI-21: " Technical Specification Surveillance Test Scheduling," Revision 5, Volume I, Plant Operating Manual.

4. Administrative Instruction AI-32: " Surveillance Test Scheduling and Tracking System," Revision 5, Volume I, Plant Operating Manual.

l 5. Administrative Instruction AI-33: " Surveillance Test l Cross-Reference to the Technical Specifications," Revision 7, Volume I, Plant Operating Manual.

i

6. Administrative Instruction AI-39: "BSEP Program for Compliance to 10CFR21," Revision 8, Volume I, Plant Operating Manual.

36 0

l l

7. Administrative Instruction AI-41: " Independent Evaluation of Procedures and Instructions," Revision 0, Volume I, Plant Operating Manual. i l

8. Administrative Instruction AI-43: "NRC Reporting Requirements Summary," Revision 1, Volume I, Plant Operating Manual. ,

9. Administrative Instruction AI-45: " Technical Specification Interpretation Feedback Procedure," Revision 0, Volume I, Plant Operating Manual.

6. Administrative Procedure AP: " Operating Manual," Revision 77, Volume I, Plant Operating Manual.

7. ANSI 18.1-1977: Selection and Training of Nuclear Power Plant Personnel."

10. " Brunswick Response to NUREG-0737, Supplement 1, Regulatory Guide 1.97 - Application to Emergency Response Facilities," Waldorf, J. M.,

- CP&L Report, August 9, 1983.

11. Brunswick Steam Electric Plant Final Safety Analysis Report.

12. Brunswick Steam Electric Plant Updated Safety Analysis Report.

13. CMMS Procedures and Operations Manual, Corporate Materials Management System.

4

14. Corporate Quality Assurance Manual, Section 4: " Procurement and Control."

15. Corporate Quality Assurance Manual, Section 5: "Haterial and Equipment Control." -

16. Emergency Instruction EI-02: " Loss of Control Rod Shutdown Capability," Revision 8, Volume VI, Plant Operating Manual.

, 17. Emergency Instruction EI-31: " Reactor Scram," Revision 25, Volume VI, Plant Operating Manual.

18. Emergency Instruction EI-49: " Anticipated Transients Without Scram," Revision 5, Volume VI, Plant Operating Manual.

19. Engineering Procedure ENP-03: " Plant Modification Procedure,"

Revision 22, Volume XX, Plant Operating Manual.

20. Engineering Procedure ENP-08: " Specification Preparation," Revision 1, Volume XX, Plant Operating Manual.

21. Engineering Procedure ENP-16: " Procedure for Administrative Control of Inservice Inspection Activities," Revision 13, Volume XX, Plant Operating Manual.

b 37

22. Engineering Procedure ENP-20: " Engineering Work Request,"

Revision 2, Volume XX, Plant Operating Manual.

23. Engineering Procedure ENP-22: " Equipment Failure Trending and Analysis," Revision 2, Volume XX, Plant Operating Manual.

25. Fire Protection Procedure FP-18: " Fire Protection Work Control,"

Revision 0, Volume XIX, Plant Operating Manual.

26. General Electric Service Information Letters (S1Ls) Numbers 1 to 395.

27. General Plant Operating Procedure GP-01: " General Plant Operating Procedure," Revision 88, Volume IV, Plant Operating Manual.

28. Maintenance Management System Procedure Manual.

29. Maintenance Procedure MP-03: " Calibration of Process Instruments,"

Revision 20, Volume XII, Plant Operating Manual.

30. Maintenance Procedure MP-04: " General Maintenance Procedure,"

Revision 9, Volume XII, Plant Operating Manual.

31. Maintenance Procedure MP-10: " Preventative Maintenance Program,"

-Revision 21; Volume XII, Plant Operating Manual.

32. Maintenance Procedure MP-12: " General Cleanliness Procedure,"

Revision 8; Volume XII, Plant Operating Manual.

i 33. Maintenance Procedure MP-14: " Corrective Maintenance," Revision 20, Volume XII, Plant Operating Manual.

34. Maintenance Procedure MP-16: " Writing Corrective Maintenance Instructions," Revision 9, Volume XII, Plant Operating Manual.

35. Maintenance Procedure MP-26: " Loop Calibration," Revision 5, Volume XII, Plant Operating Manual.

1

36. Maintenance Procedure MP-30: " General Welding Procedure,"

Revision 8, Volume XII, Plant Operating Manual.

(

" Standard Procedure for Final Approval of Requisitions

~

37. NPCD-P-0075:

for Construction-Procured Items." CP&L Nuclear Plant Construction Department, Fossil Plant Engineering & Construction Department, Nuclear Plant Engineering Department, and Brunswick Nuclear Project Deparbment.

38. NPCD-P-0066: " Standard Procedure for Construction Procurement."

CP&L Nuclear Plant Construction Department, Fossil Plant Engineering

& Construction Department, Nuclear Plant Engineering Department, and Brunswick Nuclear Project Department.

4 38

39. NRC Generic Letter 83-28: " Required Actions Based on Generic Implications of Salem ATWS Events," July 8, 1983. j

40. NRC Ins'pection Report No. 50-324/83-10. I

41. NRC Inspection Report No. 50-325/83-10.

42. NUREG-0977: "NRC Finding Task Force Report on the ATWS Events at the Salem Nuclear Generating Station, Unit 1, on February 22 and 25, 1983," U. S. Nuclear Regulatory Commission, March 1983.

43. NUREG-0979: " Safety Evaluation Report Related to the Final Design -

Approval of the GESSAR II, BWR-6 Nuclear Island Design," U. S.

Nuclear Regulatory Commission.

44. NUREG-1000, Volume I: " Generic Implications of ATWS Events at t.he Sales Nuclear Power Plant," U. S. Nuclear Regulatory Commission, April 1983.-

45. NUREG-1000, Volume II: " Generic Implications of ATWS Events at the Salen Nuclear Power Plant," U. S. Nuclear Regulatory Commission, August 1983.

46. On-Site Nuclear Safety Procedure ONSI-1: " Operating Experience Feedback," Corporate Nuclear Safety & Research Department.

47. On-Site Nuclear Safety Procedure ONSI-2: " Procedure Evaluation and Modification Review," Corporate Nuclear Safety & Research Department.

48. On-Site Nuclear Safety Procedure ONSI-3: "0NS Field Observations and Special Investigations," Corporate Nuclear Safety & Research Department.

49. " Operating Experience Feedback," Memorandum to C. R. Dietz from R. E. Helme, September 22, 1983.

50. Operating Guideline OG-01: " General Operating Instructions,"

Revision 5, Volume IV, Plant Operating Manual.

51. Operating Instruction 01-01: " Operating Principles and Philosophy,"

Revision 7, Volume VII, Plant Operating Manual.

52. Operating Instruction CI-12: " Scram Discharge Volume Vent and Discharge,"r Revision 2, Volume VII, Plant Operating Manual.

53. Operating Instruction 01-14: "10CFR21 Evaluation Records and Follow-Up," Revision 1, Volume VII, Plant Operating Manual.

54. Operating Instruction 0I-22: " Plant Incident and Post-Trip Investigation," Revision 4, Volume VII, Plant Operating Manual.

39

55. Operating Instruction 0I-23: " Trend Analysis," Revision 0, Volume VII, Plant Operating Manual.

56. Operations Procedure OP-03 (Unit 1): " Reactor Protection System,"

Revision 0, Volume III, Plant Operating Manual.

57. Operations Procedure OP-03 (Unit 2): " Reactor Protection System,"

Revision 10, Volume III, Plant Operating Manual.

so. Operations Procedure OP-55: " Process Computer," Revision 4, Volume III, Plant Operating Manual.

59. Operations Work Procedure 0WP-03/01: " Repair of Backup Scram Pilot Valve," Revision 0, Volume XII, Plant Operating Manual.

60. Operations Work Procedure 0WP-09/02: "APRM Failure Upscale and Downscale," Revision 0, Volume VII, Plant Operating Manual.

61. Periodic Test PT-A24: " Reactor Protection Instrument Test,"

Revision 0, Volume X, Plant Operating Manual.

62. Periodic Test PT-A24.1: " Reactor Protection Instrument Test,"

Revision 2, Volume X, Plant Operating Manual.

i

63. Periodic Test PT-A25: " Reactor Low Water Level No. 1 Channel Calibration and Functional Test," Revision 3, Volume X, Plant Operating Manual.

64. Periodic Test PT-A25.1: " Reactor Protectiou System," Revision 5, Volume X, Plant Operating Manual.

65. Periodic Test PT-A25.2: " Reactor Protection System," Revision 2, Volume X, Plant Operating Manual.

66. Periodic Test PT-A26: " Reactor High Pressure Trip Channel Calibration and Functional Test," Revision 7, Volume X, Plant Operating Manual.

67. Periodic Test PT-A26.1: " Reactor Protection System," Revision 2, l

Volume X, Plant Operating Manual.

68. Periodic Test PT-A26.2: " Reactor Protection System," Revision 2, Volume X, Plant Operating Manual.

69. Periodic Test PT-01.1.2P: " Reactor Protection Instrument Test,"

Revision 13, Volume X, Plant Operating Manual.

70. Periodic Test PT-01.1.2PC: " Reactor Protection Instrument Test,"

Revision 7., Volume X, Plant Operating Manual.

l l 40

71. Periodic Test PT-01.1.3.P: " Reactor Protection Instrument Test,"

Revision 18, Volume X, Plant Operating Manual.

72. ' Periodic Test PT-01.1.3PC: " Reactor Protection Instrument Test,"

Revision 5, Volume X, Plant Operating Manual.

73. Periodic Test PT-01.1.6: " Reactor Protection Instrument Check,"

Revision 7,' Volume X, Plant Operating Manual.

74. Periodic Test PT-01.1.7P: " Reactor Protection and Control Rod Block Test," Revision 31, Volume X, Plant Operating Manual.

75. Periodic Test.PT-01.1.7PC: "APRM," Revision 10, Volume X, Plant Operating Manual.

76. Periodic Test PT-01.1.10: " Reactor Protection Logic System Function Test," Revision 7, Volume X, Plant Operating Manual.

77. Periodic Test PT-01.1.11: " Reactor Protection Instrument Test,"

Revision 4, Volume X, Plant Operating Manual.

78. Periodic Test PT-01.1.13P: "High Steam Line Radiation Channel Alignment and Functional Test," Revision 9, Volume X, Plant Operating Manual.

79. Periodic Test PT-01.1.14P: " Reactor Protection System MG Set

' Electric Protection Assembly Functional Test," Revision 1, Volume X, Plant Operating Manual.

80. Periodic Test PT-01.1.14PC: " Reactor Pr'otection System MG Set Channel Calibration," Revision 3, Volume X, Plant Operating Manual.

81. Periodic Test PT-01.1.14PC-2: " Reactor Protection System Electric Power Monitoring Calibration," Revision 1, Volume X, Plant Operating Manual.

82. Periodic Test PT-01.2.3: " Average Power Range Monitor (15%),"

Revision 15, Volume X, Plant Operating Manual.

83. Periodic Test PT-01.2.3PC: " Average Power Range Monitor (15%)

Channel Calibration,". Revision 7, Volume X, Plant Operating Manual.

84. Periodic Test PT-01.3.1P: " Reactor Protection Instrument Test,"

Revision 24, Volume X, Plant Operating Manual.

85. Periodic Test PT-01.3.1PC: " Reactor Protection System," Revision 3, Volume X, Plant Operating Manual.

86. Periodic Test PT-01.3.2P-1: " Reactor Protection Instrument Test,"

Revision 9, Volume X, Plant Operating Manual.

41 I

, - - . ,- - , . _ .- . . , , . - . - . , . .-.- ----.--_.-.A

l l

87. Periodic Test PT-01.3.2P-2: " Reactor Protection Instrument Test,"

Revision 13, Volume X, Plant Operating Manual.

88. Periodic Test PT-01.3.2PC: " Reactor Protcction Instrument Test,"

Revision 5,' Volume X, Plant Operating Manual.

Periodic Test PT-01.9: "LPRM Calibration," Revision 12, Volume X, 89.

Plant Operating Manual.

90. Periodic Test PT-03.2.2: "End of Cycle - Reactor Recirculation Pump Trip Logic Functional Test," Revision 0, Volume X, Plant Operating Manual.

91. Periodic Test-PT-45.1.1: " Reactor Protection System," Revision 4, Volume X, Plant Operating Manual.

92. Periodic Test PT-45.1.4: " Reactor Protection System," Revision 5, Volume X, Plant Operating Manual.

93. Periodic Test PT-45.1.5: " Reactor Protection System," Revision 3, Volume X, Plant Operating Manual.

94. Periodic Test PT-45.1.6-1: " Reactor Protection System;" Revision 0, Volume X, Plant Operating Manual.

95. Periodic Test PT-45.1.6-2: " Reactor Protection System," Revision 2, Volume X, Plant Operating Manual.

96. Periodic Test PT-45.1.7: " Reactor Protection System," Revision 9, Volume X, Plant Operating Manual.

97. Periodic Test PT-45.1.8: " Reactor Recire," Revision 0, Volume X, Plant Operating Manual.

98. Periodic Test PT-72: " Main Steam Line Monitor Channel Calibration,"

Revision 2, Volume X, Plant Operating Manual.

99. Plant Notice PN-22: " Guidelines for Communication with NRC Inspectors for CP&L and Contract Employees," Revision 0, Volume XVIII, Plant Operating Manual.

100. Plant Performance Procedure PPP-01: "BSEP Performance Program,"

Revision 3, Volume V, Plant Operating Manual.

101. Plant P(rformance Procedure PPP-02: " Vendor Recommendation Processitg," Volume V, Plant Operating Manual.

I 102. Plant Performance Procedure PPP-03: " Performance Problems and Projects," Revision 0, Volume V, Plant Operating Manual.

103. Plant Performance Procedure PPP-07: " Review and Analysis of Routine Operating Data," Revision 0, Volume V, Plant Operating Manual.

42

104. Plant Performance Procedure PPP-12: " Performance Testing Development and Implementation Guidelines," Revision 1, Volume V, Plant Operating Manual.

105. Plant Performance Procedure PPP-14: " Plant Performance Data Analysis," Revision 0, Volume V, Plant Operating Manual.

106. Plant Performance Procedure PPP-15: " Plant Performance Trending and Analysis," Revision 0, Volume V, Plant Operating Manual.

107. Q-List, Volume XI, Book 2, Plant Operating Manual.

108. " Reactor Trip System Reliability Scram Testing Evaluation," Nuclear

. Energy Business Operations Department, General Electric Company, October 5,1983.

109. Record Management Instruction RMI-01: " Capture and Indexing of.

Correspondence and Plant Records," Revision 14, Volume I, Plant Operating Manual.

110. Record Management Instruction RMI-02: " Records Receipt and

. Storage," Revision 11, Volume I, Plant Operating Manual.

Ill.. Record Management Instruction RMI-03: " Reproduction, Distribution, and Accountability of Plant Documents," Revision 11, Volume I, Plant Operating Manual.

112. " Review of BNP Handling of Vendor and Engineering Recommendations with Regards to Implementation and/or Incorporation into mis, pts, PMTRs, or Technical Specifications," Memorandum from R. A. Jernigan to W. M. Hogle, October 5, 1983.

113. Sabin, William A., The Greg Reference Manual, McGraw-Hill, 1977.

114. "SIL, TIL, SAL," Memorandum from T. T. Marron to W. M. Hogle, October 26, 1983.

115. Special Procedure SP-82-036: "SRM/IRM Dry Tube Leakage Inspection Procedure." ,

116. Special Procedure SP-82-051: " Troubleshooting the Scram Discharge Volume High Level Instrumentation."

117. Special Procedure SP-83-036: " Time Response Testing of HFA Relays." ,

118. Special Procedure SP-83-190: " Intermediate Range Monitor (IRM) and Source Range Monitor (SRM)."

119. Storekeeper Instruction SK-01: " Material Requisition and Reorder Procedures and Responsibilities," Volume I, Plant Operating Manual.

1 i

i 43

120. Storekeeper Instruction SK-04: " Issuing of Materials and Tools,"

Revision 9, Volume I, Plant Operating Manual.

121. Storekeeper Instruction SK-05: " Packing of Q-list Items,"

Revision 0, Volume I, Plant Operating Manual.

122. Storekeeper Instruction SK-13: " Procedure for Updating Descriptions, Prices, and Parts Numbers," Revision 2, Volume I, Plant Operating Manual.

123.. System Description SD-03: " Reactor Protection System," Revision 8, Volume II, Plant Operating Manual.

124. System Description SD-52: "120 VAC Electrical System," Revision 3, Volume II, Plant Operating Manual.

125. System Description SD-55: " Process Computer System," Revision 2, Volume II, Plant Operating Manual.

126. Technical Specifications, Brunswick Steam Electric Plant, Unit No. 1.

127. Technical Specifications, Brunswick Steam Electric Plant, Unit No. 2.

128. Title 10, Chapter 1, Code of Federal Regulations, Part 21.

129. Title 10, Chapter 1, Code of Federal Regulations, Part 55.

130. Training Instruction TI-001: "Brun= wick Plant Training,"

Revision 2, Volume I, Plant Operating Manual.

131. Training Instruction TI-200: " Brunswick Plant Operator Retraining Program," Revision 7, Volume I, Plant Operating Manual.

132. Training Instruction TI-201: " Brunswick Plant Reactor Operator Replacement," Revision 4, Volume I, Plant Operating Manual.

1 133. Training Instruction TI-202: " Replacement Training for Senior Licensed Operating Personnel," Revision 2, Volume I, Plant Operating Manual.

134. Training Instruction TI-400: " Plant Management Training," Revision 2, Volume I, Plant Operating Manual.

135. Training Instruction TI-602: " Shift Technical Advisor (STA)

Training," Revision 2, Volume I, Plant Operating Manual.

44

VI. Appendices APPENDIX A--NRC Generic Letter 83-28 APPENDIX B--Operating Instruction 0I-22 APPENDIX C--Action Plans and Schedules APPENDIX D--UPS System Diagram APPENDIX E--Process Computer Parameters

. APPENDIX F--Control Room Strip Charts APPENDIX G--Post-Maintenance Testing Requirement Routing Process j APPENDIX H--Vendor Recommendation Processing Routing Diagram APPENDIX I--Volume XI, Book 2: Q-List Program APPENDIX J--General Electric Service Information Letters (Review in Accordance with Section 3.1.2) e 45

APPENDIX A NRC Generic Letter 83-28

/ .

g NUCLEAR REGULATORY COMMISSION um i cu s e m e ==

f -

a .

{ fr wAssimaTom o.c.2 ossa

,/ July 8, 1983 M I I 1"?3 TO ALL LICENSEES OF OPERATING REACTORS, APPLICANTS FOR OPERATING LICENSE, AND HOLDERS OF CONSTRUCTION PERMITS Gentlemen:

SUBJECT:

REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS OF SALEM A1WS EVENTS (Generic Letter 83-28) .

The Commission has recently reviewed intermediate-term actions to be taken by licensees and applicants as a result of the Salem anticipated transient without scram (A1WS) events. Thase actions have been developed by the staff based on infonnation contained in NUREG-1000, " Generic Implications of ATWS Events at the Salem Nuclear Power Plant." These actions address issues related to reactor trip system reliability and general management capability.

- The actions covered by this letter fall into the following four areas:

1. Post-Trip Review - This action addresses the program, procedures and data collection capability to assure that the causes for unscheduled 4 reactor shutdowns, as well as the response of safety-related equipment, are fully understood prior to plant restart.

2. Equipment Classification and Vendor Interface - This action addresses the programs for assuring that all components necessary for accomplishing required safety-related functions are properly identified in documents, procedures, and information handling systens that are used to control safety-related plant activities. In addition, this action addresses the establishment and maintenance of a program to ensure that vendor information for safety-related components is complete.

- 3. Post-Maintenance Testing - This action addresses post-maintenance operability testing of safety-related components.

4. Reactor Trip System Reliablity Improvements - This action is aimed at assuring that vendor-recommended reactor trip breaker modifications and associated reactor protection systen changes are completed in NRs, that a comprehensive program of preventive maintenance and surveillance testing is implemented for the reactor trip breakers in WRs, that the shunt trip attachment activates automatically in all PWRs that use circuit breakers in their reactor trip system, and to ensure that on-line functional testing of the reactor trip system is performed on all LWRs.

~ ~ ~

The enclosure to this letter breaks down these actions into several components.

You will find that all actions, except four (Action 1.2, 4.1, 4.3, and 4.5) ,

require software (procedures, training, etc.) changes and/or modifications and do not affect equipment changes or require reactor shutdown to complete.

Action 1.2 may result in some changes to the sequence of events recorder or existing plant cdeputers, but vd11 not result in a plant shutdown to implement.

Actions 4.1, 4.3 and 4.5.2, if applicable, would require the plant to be shutdown in order to implement.

The reactor trip system is fyndamental to reactor safety for all nuclear power plant designs. All transient and accident analyses are predicated on its successful operation to assure acceptable consequences. Therefore, the actions listeo below, which relate directly to the reactor trip system, are of the highest priority and should be integrated into existing plant schedules first.

1.1 Post-Trip Review (Program Description and Procedure) 2.1 Equipment Classification and Vendor Interface (Reactor Trip Systes Components) 3.1 Post-Maintenance Testing (Reactor Trip System Components) 4.1 Reactor Trip System Reliability (Vendcr-Related Modifications) 4.2.1 and 4.2.2 Reactor Trip System Reliability (Preventive Maintenance and Surveillance Program for Reactor Trip Breakers) 4.3 Reactor Trip System Reliability ( Automatic Actuation of Shunt-trip Attachment for Westinghouse and B&W plants)

Most of the remaining intermediate-term actions concern all other safety-related systems. These systems, while not sharing the same relative importance to safety as the reactor trip system, are essential in mitigating the conse-mnces of transients and accidents. Therefore. these actions should be l

Megrated into existing plant schedules over the longer-term on a medium oriority basis. Some of the actions discussed in the enclosure will best be served by Owners' Group participation, and this is encouraged to the extent practical.

Accordingly, pursuant to 10 CFR 50.54(f), operating reactor licensees and l

applicants for an operating license (this letter is for information only for those utilities that have ns*. applied for an operating license) are requested to furnish, under oath <nd affirmation, no later than 120 days from the date of this letter, the status of current conformance with the positions -

. contained herein, and plans and schedules for any needed improvements for conformance with the positions, The schedule for the implementation of these leprovements is to be negotiated with the Project Manager.

i e

i t

-+ . . _ _ _ . , ,.

Licensees and applicants may request an extension of time for submittals of the required information. Such a request must set forth a proposed schedule and justification for the delay. Such a request shall be directed to the Director, Division of Licensing, NRR. _ Any such request must be submitted no later than 60. days from the date of this letter < If a licensee or applicant does not intend to implement any of the enclosed items, the response should so indicate and a safety basis should be provided for each item not intended to be implemented. Value-impact analysis can be used to support such responses or to argue in favor of alternative positions that licensees might propose.

For Operating Reactors, the schedules for implementation of these actions shall be developed consistent with the staff's goal of integrating new requirements, considering th'e unique status of each plant and the relative safety importance of the improvements, combined with all other existing plant programs. Therefore, schedules for implementation of these actions will be negotiated between the MRc Project Manager ano ncensees.

For plants undergoing operating license review at this time, plant-specific schedules for the implementation of these requirements shall be developed in a manner similar to that being used for operating reactors, taking into consideration the degree of completion of the power plant. For construction permit holders not under OL review and for construction permit applicants, the requirements of this letter shall be implemented prior to the issuance of an operating license. '

This request for information was approved by the Office of Management and Budget under clearance number 3150-0011 which expires April 30, 1985.

Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, D. C. 20503.

Sincerely, s

l NW Darrell G. 'Eise , Director Division of Licensing l

Enclosure:

l Required Actions Based on Generic l Implications of Salem AWS Events 1

l f 1 1

1 b.. - . . . _ . . - . . - - - - . . - . . .- - - - - - - - . - - - - - - - - )

ENCLOSURE REQUIRED ACTIONS BASED ON GENERIC IMPLICATIONS OF SALEM ATWS EVENTS 1.1 POST-TRIP REVIEW (PROGRAM DESCRIPTION AND PROCEDURE)

Position Licensees and applicants shall describe their program for ensuring

- that unscheduled reactor shutdowns are analyzed and that a determination is made that the plant can be restarted safely. A report describing the program for review and analysis of such unscheduled reactor shutdowns should include, as a minimum:

1. The criteria for determining the acceptability of restart.

2. The responsibilities and authorities of personnel who will perform the review and analysis of these events.

3. The necessary qualifications and training for the responsible personnel .

4. The sources of plant information necessary to conduct the review and analysis. The sources of information should include the measures and equipment that provide the necessary detail and

. type of information to reconstruct the event accurately and in sufficient detail for proper understanding. (See Action 1.2)

5. The methods and criteria for comparing the event information with known or expected plant behavior (e.g., that safety-related equip-ment operates as required by the Technical Specifications or other performance specifications related to the safety function).

6. The criteria for determining the need for independent assessment of an event (e.g., a case in which the cause of the event cannot be positively identified, a competent group such as the l Plant Operations Review Connittee, will be consulted prior to authorizing restart) and guidelines on the preservation of physical evidence (both hardware and software) to support independent analysis of the event.

. 7. Items 1 through 6 above are considered to be the basis for the establishment of a systematic method to assess unscheduled reactor shutdowns. The systematic safety assessment procedures compiled from the above items, which are to be used in conducting the evaluation, should be in the report.

Applicability This position applies to all licensees and OL applicants.

s

- - . - . . - - - ..,,.,.-.,e . . , . _. .n , r. -. % n. . ., _ ___,_ ._,_._-..___?. _ _ _ _ . . _ -, , , , , _ _ ,, _ ..[_,

f*

I Type of Review l For licensees, a pos't-implementation review of the program and procedures will be conducted or the staff will perform a pre-implementation review l if desired by the licensee. NRR will perform the review and issue  !

Safety Evaluations. ' -

l For OL applicants, the NRR review will be performed consistant with the licensing schedule. .

Documentation Required Licensees and applicants shall submit a report. describing their program addressing all the items in the position.

Techncial Spec'ification Changes Required.

No changes te, Technical Specifications are required.

References Section 2.2 of NUREG-1000 Regulatory Guide 1.33 ANSI N18.7-1976/ANS-3.2 .

Item I.C.5 of NUREG-0660 10 CFR 50 - 50.72 O

e k

1

• ~

1.2 POST-TRIP REVIEW - DATA AND INFORMATION CAPABILITY Position Licensees and applic' a nts shall have or have planned a capability to record, recall and display data and information to permit diagnosing the causes of unscheduled reactor shutdowns prior to restart and for ascertaining the proper functioning of safety-related equipment. ,

, . Adequate data and information shall be provided to correctly diagnose the cause of unscheduled reactor shutdowns and the proper functioning  ;

of safety-related equipment during these events using systematic safety  !

assessment procedures (Action 1.1). The data and information shall be I displayed in a form that permits ease of assimilation and analysis by l persons trained in the use of systematic safety assessment procedures.

A report shall be prepared which describes and justifies the adequacy of equipment for diagnosing an unscheduled reactor shutdown. The report ,

shall describe as a minimum:

1. Capability for assessing sequence of events (on-off indications)

1. Brief description of equipment (e.g., plant computer, dedicated computer, strip chart)

2. Parameters monitored .

3. Time discrimination between events

4. Format for displaying data and information

5. Capability for retention of data and information

6. Power source ( ) (e.g., Class IE, non-Class IE, non-interruptable

2. Capability for assessing the time history of analog variables needed to determine the cause of unscheduled reactor shutdowns, and the functioning of safety-related equipment.

1. Brief description of equipment (e.g., plant computer, dedicated cmaputer, strip charts)

2. Parameters monitored, sampling rate, and basis for selecting parameters and sampling rate

3. Duration of time history (minutes before trip and minutes after trip) o f

b m '%e

• -++- -==~ w-- -. ---w-e'e-v r--r y -w- ---y

4. Format for displaying data including scale (readability) of time histories

5. Capability for retention of data, information, and physical eviddnce (both hardware and software)

6. Power source ( ) ~(e.g., Class IE, non-Class IE, non-interruptable

3. Other data and information provided to assess the cause of unscheduled reactor shutdowns.

4. Schedule for any planned changes to existing data and information capability. .

Applicability This position applies to all licensees and OL applicants.

Type of Review Data and information capability will be reviewed by NRR to determine whether adequate data and information will be available to support the systematic safety assessment of unscheduled reactor shutdowns. NRR.

will perform the reviews and issue a Safety Evaluation.

For licensees, a post implementation review of the program and procedures will be conducted by NRR or the staff will perform a pre-implementation review if desired by the licensee.

For OL applicants, the NRR review will be performed consistent with the licensing schedule.

Documentation Required Licensees and applicants shall submit a report describing their data and information capability for unscheduled reactor shutdowns.

Technical Specification Changes Required To be determined based on evaluation of required documentation.

References Section 2.2 of NUREG-1000. i

)

l l

l l

i l

" ~ ~ ~ ~ ' _ _ _ _ _ _ . _ _ _

_ __ _ _.__ _ ,_ 3 S = r . mm_

u-2.1 EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE (REACTOR TRIP SYSTEM COMPONENTS)

Position Licensees and applicants shall confirm that all components whose function-ing is required to trip the reactor are identified as safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities, including maintenance, work orders, and parts replacement. In addition, for these components, licensees and applicants shall establish, implement and maintain a continuing program to ensure that vendor information is complete, current and controlled throughout the life of

. the plant, and appropriately referenced or incorporated in plant instructions and procedures. Vendors of these components should be contacted and an inter-face established. Where vendors can not be identified, have gone out of business, or will not supply the information, the licensee or applicant shall assure that sufficient attention is paid to equipment maintenance, replacement, and repair, to compensate for the lack of vendor backup, to assure reactor trip system reliability. The vendor interface program shall include periodic communication with vendors to assure that all applicable information has been received. The program should use a system of positive feedback with vendors for mailings containing technical information. This could be accomplished by licensee acknowledgement for receipt of technical mailings. The program shall.also define the interface and division of responsibil~ities among the licensees and the nuclear and nonnuclear divisions of their vendors that provide service on reactor trip system components to assure that requisite control of and applicable instructions for maintenance

, work are provided.

Applicability This action applies to all licensees and OL applicants.

Type of Review For licensees, a post-implementation review will be conducted. NRR will

, perform these licensing reviews and issue a safety Evaluation.

For OL applicants, the NRR review will be performed consistent with the j licensing schedule. _

Documentation Required Licensees and applicants should submit a statement confirming that they have reviewed the Reactor Trip System components and conform to the position regarding equipment c.iassification. In addition, a summary report describing the vender interface program shall be submitted for staff review. Vendor lists of technical information, and the techncial information itself, shall be available for inspection at each reactor site.

9P-

,,-,--,-,....--N-.- ., ,--.n,y- , n-- ,---m-- ,, N- -,

e

a. .

- 6-Technical Specification Changes Required No changes to Technical Specifications are required.  ;

Reference Section 2.3.1 of NUREG-1000.

Section 2.3.2 of NUREG-1000.

9

/

O O

l

- - . _ , ..,N-.,--,__,-m, , , , , . _ , . _ ,, .-- . .._ , - _ - _ - -

- 7-2.2 EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE (PROGRAMS FOR ALL SAFETY-RELATED COMPONENTS)

Position Licensees a d applicants shall submit, for staff review, a description of their programs for safety-related* equipment classification and vendor interface as described below:

1. For equipment classification, licensees and applicants shall describe

~ their program for ensuring that all components of safety-related systems necessary for accomplishing required safety functions are identified as safety-related on documents, procedures, and information handling systems used in the plant to control safety-related activities, including maintenance, work orders and replacement parts. This description shall include:

1. The criteria for identifying components as safety-related within systems currently classified as safety-related.

This shall not be interpreted to require changes in safety classification at the systems level.

2. A description of the infonnation handling system used to identify safety-related components (e.g., computerized equipment list) and the methods used for its development and validation.

3. A description of the process by which station personnel

~

- use this information handling system to determine that an activity is safety-related and what procedures for main-tenance, surveillance, parts replacement and other activities defined in the introduction to 10 CFR 50, Appendix B, apply to safety-related components.

^

4. A description of the management controls utilized to verify that the procedures for preparation, validation and routine utilization of the information handling system have been followed.

5. A demonstration that appropriate design verification and j -

qualification testing is specified for procurement of safety-related components. The specifications shall include quali-fication testing for expected safety service conditions and provide support for the licensees' receipt of testing documen-tation to support the limits of life recousnended by the supplier. .

5afety-related structures, systems, and components are those that are relied upon to remain functional during and following design basis events to ensure:

(1) the integrity of the reactor coolant boundary, (2) the capability to shut down the reactor and maintain it in a safe shutdown condition, and (3) the

, capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guidelines of 10 CFR Part 100.

--n,,.,. , - , - - -.-,---,,,-----~~w--,

- 8-

6. Licensees and applicants need only to submit for staff review the equipnent classification program for safety-related components. Although not required to be submitted for staff review, your equipment classification program should  :

also include the broader class of structures, systems, and  !

components important to safety required by GDC-1 (defined in 10 CFR Part 50, Appendix A " General Design Criteria, Introduction").

2. For vendor interface, licensees and applicants shall establish, implement and maintain a continuing program to ensure that vendor information for safety-related components is complete, current and controlled throughout the life of their plants, and appropriately referenced or incorporated in plant instructions and procedures.

Vendors of safety-related equipment should be contacted and an interface established. Where vendors cannot be identified, have gone out of business, or will not supply information, the licensee or applicant shall assure that sufficient attention is paid to equipment maintenance, replacement, and repair, to compensate for the lack of vendor backup, to assure re11a' o 111ty conmensurate with its safety function (GDC-1). The program shall be closely coupled with action 2.2.1 above (equipment qualification). The program shall include periodic communication with vendors to assure that all applicable information has been received. The program should use a system of positive feedback with vendors for mailings containing technical information. This could be accomplished by licensee

' acknowledgment for receipt- of technical mailings. It shall also define the interface and division of responsibilities among the licensee and the nuclear and connuclear divisions of their vendors that provide, service on safety-related equipment to assure that requisite control of and applicable instructions for maintenance work on safety-related

. equipment are provided.

Applicability This action applies to all licensees and OL applicants.

Type of Review For licensees, a post-implementation review will be conducted. NRR will perform the review and issue a Safety Evaluation.

For OL applicants, the NRR review will be performed consistent with the licensing schedule.

Dobumentation Required Licensees and applicants should submit a report that describes the equipment classification and vendor interface programs outlined the position above.

J

- , - , ,- - , , _ _ , , , - . . , _ , ,_,y m,,_.,, __, ,,g,,, _,. __,_.___..,,,__m.___., , , , _ _ _ , _ _ _ ,,w__,,_y, _ _ . . , . , _ _ _ _ _ . . , _ _ ,

. 9_

Technical Specification Changes Required No changes tb the Technical Specifications are required.

. References .

Section 2.3.1 of NUREG-1000.

. Section 2.3.2 of NUREG-1000.

e 4

I

s 3.1 POST-MAINTENANCE TESTING (REACTOR TRIP SYSTEM COMPONENTS)

Position ,

1 The following actions are applicable to post-maintenance testing:

1

1. Licensees and applicants shall submit the results of their review of test and maintenance procedures and Technical Specifications to assure that post-maintenance operability testing of safety-related components in the reactor trip system is required to be conducted and that the testing demonstrates that the equipment is capable of performing its safety functions before being returned to service.

2. Licensees and applicants shall submit the results of their check of vendor and engineering recommendations to ensure that any appropriate test guidance is included in the test and maintenance procedures or the Technical Specifications, where required.

3. Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which can be demonstrated to degrade rather than enhance safety.

Appropriate changes to these test requirements, with supporting justification, shall be submitted for staff approval. (Note that action 4.5 discusses on-line system functional testing.)

Applicability This action applies to all licensees and OL applicants.

Type of Review For licensees, a post-implementation review will be conducted for actions 3.1.1 and 3.1.2 above. The Regions will perform these licensing reviews and issue Safety Evaluations. Proposed Technical Specification changes resulting from action 3.1.3 above will receive a pre-implementation review by NRR.

For OL applicants, the review will be performed consistent with the licensing schedule.

i Documentation Required Licensees and applicants should submit a statement confirming that actions 3.1.1 and 3.1.2 of the above position have been implemented.

Technical Specification Changes Required Changes to Technical Specifications, as a result of action 3.1.3. are to be detennined by the licensee or applicant and submitted for staff approval, as necessary.

Reference

,Section 2.3.4 of NUREG-1000.

I i

e

• ' ' * - * " * ' * " " . amee . en , , , _ ,

. \

1

, g .. .

3.2 POST-MAINTENANCE TESTING'(ALL OTHER SAFETY-RELATED COMPONENTS)

Position 1 The following actions are applicable to post-maintenance testing:

1. Licensees and applicants shall submit a report documenting the

, extending of test and maintenance procedures and Technical Specifications review to assure that post-maintenance operability testing of all safety-related equipment is required to be conducted ,

- and that the testing demonstrates that the equipment is capable of l perfonsing its safety functions before being returned to service.  ;

2. Licensees and applicants shall submit the results of their check  ;

of vendor and engineering recommendations.to ensure that any '

appropriate test guidance is. included in the test and maintenance l procedures or the Technical Specifications where required. l

3. Licensees and applicants shall identify, if applicable, any post-maintenance test requirements in existing Technical Specifications which are perceived to degrade rather than enhance safety. Appropriate changes to these test. requirements, with supporting justification, shall be submitted for staff approval.

Applicability This action appli,es.to all licensees and OL applicants.

Type of Review For licensees, a post-implementation review will be conducted for actions 3.2.1 and 3.2.2 above. The Regions will perform these licensing reviews and issue Safety Evaluations. Proposed Technical Specification changes resulting from action 3.2.3 above will receive a pre-implementation review by NRR.

For OL applicants, the review will be performed consistent with the licensing schedule.

Documentation Require'd l

l Licensees and applicants should submit a statement confirming that actions 3.2.1 and 3.2.2 of the above position have been implemented.

Technical Specification Changes Reouired l Changes to Technical Specifications, as a result of action 3.2.3, are to l be determined by the licensee or applicant for staff approval, as necessa ry.

Reference Section 2.3.4 of NUREG-1000.

~ "" * *+ . . . , , __

4.1 REACTOR TRIP SYSTEM RELIABILITY (VENDOR-RELATED MODIFICATIONS)

Position l

All vendor-recommended reactor trip breaker modifications shall be  !

reviewed f,o verify that either: (1) each modification has, in fact, '

been implemented; or (2) a written evaluation of the technical reasons i for not implementing a modification exists.

For example, the modifications recommended by Westinghouse in NCD-Elec-18 for the DB-50 breakers and a March 31, 1983, letter for the 05-416 breakers

~ shall be implemented or a justification for not implementing shall be made available. Modifications not previously made shall be incorporated or a written evaluation shall be provided. ,

Applicability This action applies to all PWR licensees and OL applicants.

Type of Review For licensees, a post-implementation review will be conducted. The Regions will perform these licensing reviews and issue Safety Evaluations.

For OL applicants, the NRR review will be performed consistent with the licensing schedule.

Documentation Required -

', Licensees and applicants should submit a statement confirwing that this action has been implemented.

Technical Specifications Required No changes to Technical Specifications are required.

Reference Section 3 of NUREG-1000.

I i

l J

l

-n9 e , , ,,--w-,--,-,r-e--,-- ' ~ ~ ~ " ' '

l

' - - na -

• . /e 4.2 REACTOR TRIP SYSTEM RELIABILITY (PREVENTATIVE MAINTENANCE AND SURVEILLANCE PROGRAM FOR REACTOR TRIP BREAKERS)

Position Licensees and applicants shall describe their preventative maintenance and surveillince program to ensure reliable reactor trip breaker operation.

The program shall include the following:

1. A planned program of periodic maintenance, including lubrication,

, housekeeping, and other items reconmended by the equipment supplier.

i 2. Trending of parameters affecting operation and measured during l

testing to forecast degradation of operability.

3. Life testing of the breakers (including the trip attachments) on an acceptable sample size.

4. Periodic r,eplacement of breakers or components consistent with demonstrated life cycles.

Applicability This action applies- to all PWR licensees and OL appif cants.

Type of Review' Actions 4.2.1 and 4.2.2 will receive a post-implementation review by NRR. A pre-implementation review will be performed by NRR for actions

- 4.2.3 and 4.2.4 (the circuit breaker life testing program and the com-ponent testing / replacement requirements based upon the life testing results). A Safety Evaluation will be issued.

For OL applicants, NRR will perform the reviews for actions 4.2.1 and 4.2.2 on a schedule consistent with the licensing schedule. NRR will perform a pre-implementation review for actions 4.2.3 and 4.2.4 (the circuit breaker life testing program and the component testing / replace-ment requirements based upon the life testing results). Safety Evaluations will be issued.

Documentation Required Licensees and applicants should submit descriptions of their programs to ensure compliance with this action.

Technical Specification Changes Required No changes to Technical Specifications are required.

Reference Section 3 of NUREG-1000.

s

• • • %*H v. e Q m'f , ,

. . - . _ , , . . _ . , . *4_,r

. , , - - ~ * -+ . c _;*, _ _ J; _~_. _ - _m7* _7_; , - _1*7'-**~'

)

~

. . 1 4.3 REACTOR TRIP SYSTEM RELIABILITY (AUTOMATIC ACTUATION OF SHUNT TRIP ATTACHMENT FOR WESTINGHOUSE AND B&W PLANTS)

Position Westinghouse and B&W reactors shall be modified by providing automatic reactor trip system actuatiori of the breaker shunt trip attachments.

The shunt trip attachment shall be considered safety related (Class IE).

Applicability This action applies to all Westinghouse and B&W licensees and OL applicants. l Type of Review For licensees, a pre-imp 1'ementation review shall be performed for the design modifications by NRR. A Safety Evaluation will be issued.

For OL applicants, the NRR review will be performed consistent with l the licensing schedule.

Technical Specification changes, if required, will be reviewed prior to implementation.

Documentation Recuired Licensees and applicants should submit a report' describing the modifications.

Technical Specification Changes Required i l

Licensees are to submit any needed Technical Specification change requests prior to declaring the modified system operable.

Reference Section 3 of NUREG-1000, i

i i

I l .

. .,. a.', .

4.4 REACTOR TRIP SYSTEM RELIABILITY (IMPROVEMENTS IN MAINTENANCE AND TEST PROCEDURES F0k B&W PLANTS)

Position Licensees and app 1'icants with B&W reactors shall apply safety-related maintenance and ' test procedures to the diverse reactor trip feature provided by interrupting power to control rods through the silicon

~

controlled rectifiers.

, This action shall not be interpreted to require hardware changes or additional envirormental or seismic qualification of these components.

Apolicability l This action applies to B&W licensees and OL applicants only.

Type of Review For licensees, a post-implementation review will be conducted. The Regions will conduct the licensing review and issue a Safety Evaluation.

For OL applicants, the review will be perfomed consistent with the licensing schedule.

Documentation Required Licensees and applicants should submit a statement confirming that this action has been implemented.

Technical Specification Changes Required Include the silicon controlled rectifers in the appropriate surveillance and test sections of the Technical Specifications.

Reference Section 3 of NUREG-1000.

/- .

- 16 - -

~

. 4.5 REACTOR TRIP SYSTEM RELIABfLITY (SYSTEM FUNCTf 0NAL TESTING)

Position on-line functional testing of the reactor trip system, including independent testin.g of the diverse trip features, shall be perfomed on all plants.

1. The diverse trip features to be tested include the breaker undervoltage and shunt trip features on Westinghouse, B&W (see Action 4.3 above) and CE plants; the circuitry used for power interruption with the silicon controlled rectifiers on B&W plants (see Action 4.4 above); and the scram pilot valve and backup scram valves (including all initiating circuitry) on GE plants.

2. Plants not currently designed to pemit periodic on-line testing shall justify not making modifications to pemit such testing.

Alternatives to on-line testing proposed by licensees will be '

considered where special circumstances exist and where the objective e of high reliability can be met in another way.

3. Existing intervals for on-line functional testing required by l Technical Specifications shall be reviewed to detemine that I the intervals are consistent with achieving high reactor trfp '

system availability when accounting for considerations such as-l

1. uncertainties in component failure rates

2. uncertainty in common mode failure rates

3. reduced redundancy during testing -

4. operator errors during testing

5. component " wear-out" caused by the testing ,

Licensees currently not perfoming periodic on-line testing shell detemine appropriate test intervals as described above. Changes to existing required intervals for on-line testing as well as the intervals to be detamined by licensees currently not perfoming on-line testing shall be justified by infomation on the sensitivity of rerte- +-ip =v=+== availmhilitv to parameters such as the test intervals, component failure rates, and common mode failure rates.

Applicablity This action applies to all licensees and OL applicants.

Type of Review For licensees, a post-implementation review will be conducted for action 4.5.1. The Regions will perfom these licensing reviews and issue Safety Evaluations. Actions 4.5.2 and 4.5.3 will require a pre-implemen-tation review by NRR. Results will be issued in a Safety Evaluation.

I

+ ~

ow. .. w4e we .. . e -+e = ewm>=* e.

_ . _ - _ . - . - - . - - - _ __-- . - . ..- n. .- . _ _ .- -..- -

For OL applicants, the NRR review should be performed consistent with the  !

licensing schedule.

Documentation Recuired For item 4.5.1, licensees and applicants should submit a statement confirming that this action has been implemented.

For item 4.5.2, licensees and applicants should submit a report describing

. the modifications for staff review.

For item 4.5.3, licensees and applicants should submit proposed Technical Specification changes for staff review. .

Technical Specification Changes Required For licensees, Technical Specification changes are required.

For OL applicants, Technical Specifications will be incorporated as '

part of the license.

Reference Section 3 of NUREG-1000.

e e

t 0

9 6

- -' , . - . .,- . . ,, ,_ _ _ _ , , _ ,_ _ , , ,_,a__ - _. ._ _ _ _ _ _ _ __ _

APPENDIX B Operating Instruction 01-22

CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLAST ,

UNIT 0 PLAhT INCIDENT AND POST-TP.IP INVESTIGATION .

OPERATING INSTRUCTION: 01-22 VOLUME VII i [..

" g 8 E !!i! 2 S i" Rev 005 Reviewed By: t0Im k. QA b Date: [f-l-83 Recommended By: Ono[d.h

~

nw Hanager~- Operations Date: 1/-J-/3 Approved By: ._e Date: si /r / P3 General Manager //

e 0

^ - - . _ _ - _ _ . . . . _ . _ m,

i LIST OF EFFECTIVE PAGES 0I-22 Pane (s) Revision 1-4 4 5-6 5 i

7 4 8 5 .

9 - 32 4 i

i 4

1 BSEP/Vol. VII/0I-22 i Rev. 5,

-e . _

-ey, ====v w e g , _ . _ _ . ___. *en... m . - w e = - . - ~ ~ * - --

• e*+

l 1.0 Purpose To establish a formal plant level instruction whereby plant incidents are properly investigated to ensure:

1.1 h e root cause of the incident is well understood and documented.

1.2 h e incident has not resulted in an unsafe or unacceptable condition for the operation of the power plant.

i 1.3 Appropriate corrective action is taken to prevent a recurrence of j the incident.

1.4 A contint.ing unanalyzed condition does not exist.

2.0 Definition Plant incident - a plant incident is a(an):

2.1 Unplanned release to the environs of radioactive materials, or radiation exposures, in excess of allowed limits.

l 2.2 Unplanned scram. .

l 2.3 Release of radioactive materials within the power plant due to incorrect operation of a system.

2.4 Unplanned actuation of a safety system.

2.5 Failure of a safety system to actuate or remain actuated.

2.6 Degradation of a system / component such that power plant operation requires use of the Emergency Instructions (EIs).

2.7 Fire within the protected area of the power plant which lasts i ten minutes or longer. ,

j 2.8 Discovery of a condition which would result in the failure of a j safety system to perform its intended function. This shall include deliberate and inadvertent acts (reference IE Information ,

I Notice 83-27).

2.9 Event that Plant Management determines warranting a formal investigation. .

3.0 Responsibilities 3.1 Shift Operating Supervisor Provides central direction of incident investigation until relieved by the Engineer - Operations.

3.2 Engineer - Operations BSEP/Vol. VII/0I-22 1 Rev. 4 a

l l *

. ~~ , - '

' ~ ~ ~ ~ ~

.: ~'_~~~~~Y - - '

L_. -_~~~~~

, 3.2.1 Assumes direct responsibility for investigating plant incidents, excepting radiological incidents:

3.2.2 Provides written report of incidents as provided herein.

3.3.3 Forwards report to Manager - Operations.

3.3 Shift Technical Advisor ,

Assists Shift Operating Supervisor in incident investigation. Aids Engineer - Operations as duties permit.

3.4 Manager - Operations 3.4.1 Determines when incident is terminated.

3.4.2 Recommends restart (if applicable) of the unit (s).

3.4.3 Forwards, with approval, incident investigation to Manager - Plant Operations.

3.5 Manager - Plant Operations 3.5.1 Gives final approval of incident report.

3.5.2 In absecce of plant General Manager, approves return of the unit (s) to service.

3.6 Fire Protection Specialist 3.6.1 Provides fire reports, as required, to Engineer - Operations, 3.6.2 Investigates fires; makes recommendations.

j I 3.7 Manager - Environmental & Radiation Control (E&RC) 3.7.1 Assumes responsibilities for radiological incidents.

3.7.2 Generates other written reports of incident as may be assigned by the plant General Manager.

3.8 Manager - Technical Support .

Providas engineering support, as requested', to aid in determining root causes of occurrence, and makes engineering raca==endations.

4.0 References 4.1 AI-43 .

4.2 EI-31 BSEP/Vol. VII/0I-22 2 Rev. 4 I

l

' 9 l

__;_; _-_ ~ __3

5.0 Discussions All plant incidents, as defined in this standard instruction, are of such a nature so as to warrant a formal, documented investigation to discover and remove the root cause of the incident. Additionally, this '

instruction may be put into effect for any incident as determined by the plant General Manager or Manager - Plant Operations. Each incident has two distinct phases in an investigative mode..  !

5.1 First, there is an immediate investigation to:

5.1.1 Obtain written or verbal first-hand reports of the event.

3.1.2 Retrieve and adequately la'oel all pertinent data regarding the event (i.e. , charts, computer printouts, log entries).

Take photographs, as applicable.

, 5.1.3 Determine the safety of the power plant and that all safety systems functioned as required.

5.1.4 Make an immediate recommendation regarding continued operation or restart of the power plant.

5.1.5 If a scram resulted, prepara a scram report (Attachment 3).

5.1.6 Assess immediate reportability (AI-43) and implementation of the Emergency Plan (PEP-02.1).

5.2 Second, there is a follow-up, in-depth investigation which:

5.2.1 Ensures initial determinations regarding causes of the incident and safety of the unit are adequate.

5.2.2 Ensures that an ATVS event did not occur. This review shall include verification that an incomplete automatic scram signal is not hidden by quick operator response such as a manual scram or mode switch positioning.

5.2.3 Determines the root cause of the event and makes appropriate corrective recommendations.

5.3.4 Reviews reportability.

For simple incidents, the immediate investigation nay also serve as the follow-up investigation. This determination will be made by the Manager - Operations.

Figure 1 indicates the incident investigation flow path.

~

BSEP/Vol. VII/0I-22 3 Rev. 4 4

~

\ ,

~ . ~ . - - - __ _ _ _ _ __

_ - ~ . . - -

6.0 Instruction 6.1 When a plant incident occurs or upon achieving a stable condition following a plant incident, the Shift Operating Supervisor shall contact the appropriate Engineer - Operations (or in the absence of the Engineer - Operations, the Principal Engineer - Operations) or other appropriate managers, and inform that person of the event. l i 6.2 'Iha Enginear - Operations or other designated individual will normally report to the site to direct the immediate investigation.

If conditions do not warrant this action, the Manager - Plant i Operations or Manager - Operations mey waiver this. This investigation shall address all the que.stions, as a minimum and as applicable, on Attachment 1. ,

NOTE: In the event of a fire, the Fire Protection Specialist shall normally perform this step. However, if the fire is other than minor in nature, the Engineer - Operations shall also report to the plant and assess nuclear safety.

This is defined as a fire of sufficient significance as to warrant a " notification of significant event" per 10CFR50.72. (See AI-43.)

6.3 Prior to the Engineer - Operations arriving, the Shift Operating Supervisor shall collect written statements from those involved regarding the event. Also, any other pertinent information (specified in Attachment 3) shall be gathered.

6.4 At all times, the function of the Shift Operating Supervisor and his staff shall be, foremost, the stable and safe configuration of the power plant (see EI-31 for more detail). Attachment 3 shall be completed.

_N_OTE_: SRV failure / challenge /actuations shall be documented on Attachment 5. Each actuation, or attempted actuation, of each SRV shall be documented, as well as duration of each actuation. Maximum torus temperature shall be recorded.

6.5 Upon reporting to the power plant, the Engineer - Operations shall review the collected information and, with the aid of the Shift Operating Supervisor and Shift Technical Advisor, develop initial conclusions and recommendations. Interviews, if deemed appropriate, shall be conducted. Engineering support will be requested if required. Within three working days, a formal written report in the i format of Attachment I will be presented for PNSC review and plant General Manager approval. Other time deadlines may be established by the plant General Manager. A brief corporate report (see Attachment 4) shall be prepared by the Engincor - Operations, and BSEP/Vol. VII/0I-22 4 -

Rev. 4 I

after review by the Manager - Operations, Manager - Plant Operations, and plant General Manager shall be transmitted to the Vice President - Brunswick Nuclear Project for further transmittal.

Submittal to the Manager - Operations shall be in three working days. An approved copy of the SRV failure / challenge /actuations report (Attachment 5) shall be forwarded to the Performance Engineering group following the day of the event. .

6.6 If completion of Attachment 1 indicates that the cause of the event is known and understood, immediate corrective action has reduced the probability of recurrence, there are no safety concerns, all safety systems functioned as required, and that an ATWS event was not hidden by prompt operator action, then continued unit operation or immediate restart may be conducted with the verbal permission of the Manager - Operations and General Manager.

6.7 If the cause of the event is not determined, if there are safety concerns, or the event has been repetitive, the Manager - Operations shall cause the Engineer - Operations to initiate a follow-up investigation. Follow-up investigations shall be similar in format to Attachment 2.

. 6.8 Follow-up investigations shall be directed by the Engineer - Operations. Technical support, as required, shall be supplied to the Engineer - Operations.

6.9 Follow-up investigations shall continue until such time as the PNSC and plant General Manager accept the follow-up report as being final. Until the final follow-up report is complete, an updated interim report in the format of Attachment 2 shall be supplied to the following personnel:

6.9.1 General Manager 6.9.2 Vice President - Brunswick Nuclear Project 6.9.3 Manager - Plant Operations 6.9.4 Manager - Operations 6.9.5 Vice President - Nuclear Operations Department The interim reports are due each month by the monthly date of the event. ,

6.10 In the event that cause of the unscheduled reactor shutdown cannot be determined, the General Manager may concur or approve a restart based on the following conditions.

6.10.1 Any further reasonable actions to determine cause is considered unproductive.

BSEP/Vol. VII/0I-22 5 Rev. 5 O

3-

6.10.2 No physical damage was done by the event and*a determination made that the plant had not operated beyond the boundaries established by approved plant safety and transient analysis.

6.10.3 Any reasonable action to gain additional information has been considered.

6.11 All reports shall contain sufficient detail (diagrams, simple flow diagrams or schematics, pictures, descriptions) to be readily l understood. '

6.12 The final investigative reports following final review by the PNSC and approval by the plant General Manager shall be distributed as follows:

6.12.1 Vice President - Brunswick Nuclear Project 6.12.2 Vice President - Corporate Nuclear Safety 6.12.3 Vice President - Nuclear Operations Department 6.13 Report numbers are maintained by the Cperations clerk.

6.14 Reports shall be considered a QA record and, when complete, shall be sent to Document Control.

7.0 Training and Qualifications 7.1 Responsible personnel, as delineated in Section 3.0 of this instruction, shall be trained in accordance with BSEP Training Instructions 200, 201, and 202.

7.2. Responsible personnel, as delineated in Section 3.0 of this instruction shall be qualified in accordance with the BSEP Administrative Procedures (Volume I, Book 1, Operating Manual).

l l

BSEP/Vol. VII/0I-22 6 Rev. S

ATTACHMENT 1 ,

Immediate Incident Investination Report No.

Unit No.

• Time Date

1. Status of the power plant immediately prior to the event (to include plant power levels, primary temperature, primary pressure, MWe (gross],

significant equipment / systems 00S). .

2. Evolutions in progress when event occurred.

3. Effect of the event on the power plant.

l

4. Attach completed copy of Attachment 3. ,

5. If incident involves failure of a component, describe the componemt (use illustrations, if useful). Include manufacturer, type, ratings, system identification, etc. Contact Maintenance and instruct them to retain and control the failed component for further assessment, if required.

I i

6. Desetibe any other circumstances which contributed to the event.

BSEP/Vol. VII/0I-22 7 Rev. 4 i

e

ATTACHMElff 1 (Cont'd) ,

Immediate Incident Investigation

7. Is the cause not understood? ( ) Yes ( ) No .

If the answer is no, describe. .

If the answer is yes, a follow-up investiga' tion is required (complete Attachment 2). .

8. Is the cause repetitive to require more extensive corrective action?

( ) Yes ( ) No NOTE: This is a judgement by the Engineer - Operations.

If yes, a follow-up investigation is required (complete Attachment 2).

9. a. Does a potential safety concern regarding operation or restart exist? (Complete Attachment 6.) ( ) Yes ( ) No Complete a follow-up investigation (Attachment 2), if required by Attachment 6. ,

b. Were there any safety systems that did not function as required?

(Complete Attachment 8) ( ) Yes ( ) No l

10. If any of the above questions is answered yes, then ONS must be notified to conduct an independent assessment of the event for PNSC review and General Manager approval prior to conducting restart or continuing operations (see Attachment 7).

11. If incident is a result of an automatic scram, was an ATVS event hidden by quick operator response such as a manual scram or mode switch positioning (review charts and computer printouts, reports, individual statements, etc.)? ( ) Yes ( ) No If yes, a safety evaluation must be written for PNSC review and General Manager approval prior to unit being returned to service (see Attachment 7). .

12. If all the above questions are answered No, operation of the power plant may continue with approval of the Manager - Operations and the General Manager.

13. Is the eveat reportable? ( ) Yes ( ) No .

If yes, what type of report?

BSEP/Vol. VII/0I-22 8 Rev. 5

~

'C . . . _ . . . _ ._ , _ . _ . _ . . _ _ . .

1 ATTACHMENT 1 (Cont'd)

Immediate Incident Investination f

14. Does the event wa' r rant a verification that a similar condition does not exist on the sister unit? ( ) Yes ( ) No If yes, a follow-up investigation is required (Attachment 2).

15. Follow-up, report required: ( ) Yes ( ) No Submitted: Date:

Engineer - Operations Concurrence: Date:

Principle Engineer - Operations

. Recommended: Date:

J Manager - Operations Approved: Date:

Manager - Plant Operations Reviewed: Date:

4 ONS Reviewed: Date:

PNSC F

Accepted: Date:

Genersl Manager i

I l BSEP/Vol. VII/OI-22 9 Rev. 4 I

l .

e i

,-,---< ,,- a n , -, - , . . . . -, , . , - . , - .--..,-a,,

ATTACHMENT 1 (Cont'd)

Immediate Incident Investigation NOTE: After any scram, the following charts will always be attached to Attachment 3.

- Recirculation Pump Flow A & B -

- Core Flow and Core Delta-P -

- APRM Flux - All Recorders.

- Feed Flow

- Reactor Water Level

- Reactor Pressure

- Computer Printouts

1. Sequence of events log from alarm typer -

2. NSS Post-trip los

3. BOP Post-trip los

4. CRD Position

- SRM Flux

- Main Condenser Vacuum

- SJAE Radiation Monitor

- MSL Radiation Monitor

- Reactor Building Ventilation Radiation Monitor

- Drywell Pressure N0rE: Other charts or computer printouts may be attached at the discretion of the Operations Engineer.

O i

BSEP/Vol. VII/0I-22 10 Rev. 4

I j e rx ~ _ _ . _ _

~_ - .- -- . - _ _ . . . _ . .-.

'l 4

ATTACIDENT 2 Follow-Up Incident Investigation 9

Report No.

' Unit No.

Time Date

( ) Interim Raport ( ) Final Report Cause of Follow-Up Incident Investigation:

( ) Repetitive Event .

( ) Safety Concern

( ) Clarity *

( ) Verification of sister unit

1. Briefly state initiating event (attach copy of Immediate Incident Investigation).

2. State result of the investigation to resolve item (s) above.

3. Pn,jmsed corrective action to resolve No. 2.

4. State conclusions regarding safe operation of the power plant.

5. Reportability evaluation.

a. Event is 10CFR21 reportable. ( ) Yes ( ) No l If Yes, notify Regulatory Compliance of evaluation.

( ) Notification made l

l BSEP/Vol. VII/0I-22 11 Rev. 4 I

e i

i

<- .~ - . .

ATTACHMENT 2 (Cont'd)

Follow-Up Incident-Investigation

b. " vent is reportable other than 10CFR21. ( ) Yes ( ) No If Yes, a copy of all regulatory reports are to be attached to this report.

List reports

6. Did inadequate procedures significantly contribute to the event? If so, specifically describe the inadequacies and procedures.

7. Is an operating experience report to be made? ( ) Yes ( ) No If Yes, follow format of Appendix A. Attach a copy of the OER to this report.

Is an entry into NOTEPAD desirable? Entries should be made if the 3.

incident provides industry useful information. ( ) Yes ( ) No l If Yes, notify the Manager - Technical Support who will coordinate NOTEPAD entries.

Date Notified:

l

9. If sister unit was checked to see if similar condition exists, state:

a. Who conducted check.

j b. When check was performed.

l

c. What results were of check.

l -

t l

BSEP/Vol. VII/0I-22 12 Rev. 4

, I i

e 1

ATTACHMENT 2 (Cont'd)

Follow-Up Incident Investigation Submitted: Date: _

Engineer - Operations Recommended:

Date:

Manager.- Operations Approved: Date:

Manager - Plant Operations Reviewed: Date:

ONS Reviewed: Date:

PNSC PNSC Action Item List ( ) Yes ( ) Not required Accepted: Date:

General Manager r .

1 BSEP/Vol. VII/0I-22 13 Rev. 4 o

6 y

- - -- _ , _ _ _ . . _ . . _ , . ._,__. .m_; . . . _ , . __ . _ _ . -.

ATTACHMEhT 3 Unit No.

BRUNSWICK STEAM ELECTRIC PLANT SCRAM No.

Date of SCRAM Time of SCRAM SCRAM Report

1. Conditions Prior to SCRAM: .

a. Mode Switch Position d. Rx Power  %

b. Total Core Flow lbs/hr e. Rx Press. osig

c. Unit Gen. Load (net) MWe f. Rx Vessel Level in.

2. Parameters which directly caused SCRAM:

Channel A Time /

min-sec cycle Channel B Time /

min-sec cycle

3. Describe plant operation in progress at the time of SCRAM, including events causing SCRAM:

4. Corrective Action / Remarks:

5. BOP post-trip log attached. (Initial)

6. NSS post-trip los attached (post-trip log from computer room).

(Initial)

7. SCRAM printout attached (alarm typer). (Initial)

8. CRD position after SCRAM; printout attached (computer).

(Initial) ,

9. Following charts attached. (Initial)

A. Recirculatfan Pump Flow A & B B. Cora Flow and iore Delta-P '

C. APRM Flux ,

D. Main Steam Flow E. Feed Flow F. Reactor Water Level G. Reactor Pressure H. SRM Flux

• I. Main Condenser Vacuum i

BSEP/Vol. VII/01 14 Rev. 4

'; I h

ATTACHMENT 3 (Cont'd)

J. SJAE Radiation Monitor K. MSL Radiation Monitor L. Reactor Building Ventilation Radiation Monitor M. Drywell Pressure

10. Cycle the SDV vent and drain valves after the SCRAM reset and leave open.

(Initial)

11. Verify that the North and South SDV Not Drained alarms reset following draining of SDV. (Initial)

~

12. SCRAM / Incident Critique sheets attached. (Initial)

13. SRV Failure / Challenge Report (if necessary). (Initial)

14. Recorders marked to indicate time of SCRAM. (Initial) 1

15. On-call personnel notified (Who)

16. The following personnel notified:

A. Manager - Operations B. General Manager C. NRC Resident Inspector SHIFT FOREMAN: / OPERATIONS ENGR.: /

Initials Date Initials Date SHIFT OPERATING SUPV.: /

Initials Date

• BSEP/Vol. VII/0I-22 15 Rev. 4 s

9 xmaan x = -

ATTACHMENT 4 Plant Incident Summary BACKGROUND DATA (Identify)

Incation: .

Time Frame:

System Primarily Involved:

• Report Number:

TRENDS (Fill in Blank)

Plant Incidents Year-to-Date- Total Lost MWH:

Plant Incidents Prior Year: Total Lost MWH Prior Year:

EVENT (Describe)

IMPACT ON SAFETY (Describe)

IMPACT ON OPERATIONS (Describe)

REASONS EVENT OCCURRED (List)

ROOT CAUSE ASSESSMENT (Check Appropriate Categories)

Personnel Error: Improper Training Failure to Follow Instructions or Procedures Other (Explain in Comments)

Design External Cause (Explain in Comments)

Program or Procedure Deficiency: Unclear Prc:edure Unavailable Procedure Not Covered by Procedure Not Covered by Program Component Failure' CORRECTIVE ACTIONS (List)

CORRECTIVE ACTION RESPONSIBILITY (Identify)

C010GNTS (List)

REPORTABILITY (Yes or No)

PREPARED BY APPROVED BY APPROVED BY -

APPROVED BY BSEP/Vol. VII/0I-22 16 Rev. 4 1

. \

_ s. .o. , _ _ _ _ _ _ . ...._ - . , . .. _ _ . _ _ . _ _ . . _ . . , _ . . . _ _ . _ _ _ _ . . __1 _. ... . _ .-. , _ _ . . , . __

Figure 1

,6 aa .

.End No pit. inciat.

occurred Immed. inves. .

b

- Ops.yEngr. = .

Immed. Inves.

- SOS NO b Scram - Ops.yEngr .-

- STA

- SOS .

- STA -

. =

o

• Cause Concur.

b YES-.-

Obvious r. ,

Cause Obvious '

. ~

^

9

.0 Safet,

. 60 g oncern or U epetitive No cause Immed. place plant into Safety Y. config. to .y Safety g Concern - remove safety Concern concern 1  %

l Return to Y' o service NO NO Investigation granted by 4 s. and Mgr.- PO$nt.

by Gen. Mgr.

Opa. Engr. Ops. Engr.

heads . Continues h investigative _Fo'llow-up team investigation

• by Operations

• Engineer A - ,

.f .

3 .

l

' ~ Resolved

[-

[ *

. Continue l investigation NO 0 g

I

-Resolved .

I \

until  :

resolved Concerns

- t Return to

- YES service d granted by Return Unit Mgr.-Ops. and go to no M O*"* N3#*

configuration per U Mgr.-Ops. Review report -

i by PNSC,0NS

- p " . 6 Approved by

' General Plant

,

• 8

- Copiesto[I VP-BNP

- C1:S p

- VP-NOD /

j BSEPVol. VII/OI-22 17 Rev. 4

\ . .

..E.'.... **' *

, '[7,*,** h l,===,4... . I. , , , ,

.4%

F I

ATTACHMENT 5 SRV FAILURE /CFAflS.NGES REPORT 10: PerformancedngineeringGroup FROM: Operations -

DISCUSSION: Failure of SRVs to close is to be reported immediately to NRC (within one hour), while a summary of the challengers (when SRVs open) is to be reported annually. Effective as of April 1, 1980.

Date:

Time of occurrence:

l Time NRC person notified if necessary:

Details of SRVs failure:

2 t

i Maximum torus temperature:

Copy to NRC coordinator:

Copy to Performance Engineering:

t l

l Shift Foruman Date

, Manager - Operctions cc: Scram Report

, BSEP/Vol. VII/0I-22 18 Rev. 4 i

e

+

E-_ - __

,

• ATTAClmENT 6 Screening Guidelines for Transients

. And Safety System Clia11enges EVENT TITLE: EVENT DATE:

~

A. Criteria for determining event significance YES NO

1. 'Deo or more failures occur in redundant systems during the same event.

2. 'hto or more failures due to a common cause occur during the same event.

3. Three or more failures occur that easily would have escaped detection by testing or examination.

4. Component failures occur that easily would have escaped detection by testing or examination.

5. An event proceeds in a way significantly different than would be expected.

6. An event or operating condition occurs that is not enveloped by the plant design bases.

7. An event occurs that could have been a greater threat to plant safety with different plant conditions, the advent of another credible occurrence, or a different progression of occurrences.

8. Administrative, procedural, or operational errors are committed that result from a fundamental misunder-standing of plant performance or safety requirements.

~

9. A sing 1e failure occurs in a nonredundant system.

10. 'neo apparently unrelated failures occur during the same event.

11. A problem results in an off-site radiation release or personnel exposure.

t

12. A design or manufacturing deficiency is identified as the cause of a failure or potential failure.

13. A problem results in a long outage or major equipment damage.

e BSEP/Vol. VII/0I-22 19 Rev. 4 I

e

- - - - - - - - -.-m-.-- ... .. - ,,;-- - . - . - _ .--- 71 _ _- ~-

-_i

ATTACHMENT 6 (Cont'd)

YES $

14. An ESF actuation and injection occurs.

15. A particular occurrence is recognized as having ,

a significant recurrence rate.

16. A particular occurrence is recognized as posing a safety concern not specifically delineated above.

17. If any of the above are answered yes, then a safety concern exists, and a follow-up investigation is required. (Attachment 2) .

I l

BSEP/Vol. VII/0I-22 20 Rev. 4 I

O me e ,.

oc- - A m . .e ==e me m -~ w ~ _ _ __

ATTACHMENi' 7 PNSC Restart / Continued Operation Criteria

1. The root cause of'the incident is understood.

2. Corrective action has been taken which reduces the probability of recurrence.

3. The incident has not resulted in an unsafe or unacceptable condition for the operation of the power plant.

4. A continuing unanalyzed condition does'not exist.

If an unanalyzed transient occurs PNSC should consider requiring a more detailed analysis including as appropriate:

A. Comparison to startup test data and past transients.

B. Retran analysis (nuclear fuels).

C. Sequence Risk Analysis (INPO)

If the cause of the incident was component failure, PNSC makes determination on final disposition of component.

a i

BSEP/Vol. VII/0I-22 21 Rev. 4 4 -

\ .

^^

- -- __ _ _m,

1 ATTACIDfENT 8 Transient Response Verification

1. Review the plant's transient response from process computer data and chart recorders and determine the following:

YES @ .

A. Did a vessel level transient occur?

(If yes, complete Attachment 85.)

B. Did a reactor pressure transient occur?

(If yes, complete Attachment 8b.)

C. Did a reactor power / flux transient occur?

(If yes, complete Attachment 8c.)

D. Did a drywell, pressure transient occur? _

(If yes, complete Attachment 8d.)

E. Did a condenser vacuum transient occur?

(If yes, complete Attachment 8e.)

F. Did an off-gas activity transient occur?

(If yes, complete Attachment 8f.)

G. Did a loss of electrical power occur 7 (If yes, complete Attachment 83 .)

^

l H. Was a scram setpoint reached?

(If yes, complete Attachment 8h.)

{

O BSEP/Vol. VII/0I-22 22 Rev. 4 I ,

o

\

L__ .. # _ . - - . - . -

ATTACIDENT 8a Vessel Level Transient

1. From computer and'RTUB recorders, obtain the lowest and highest levels reached during the transient.

2. Verify the appropriate automatic actions listed below occurred at or before technical specification limits.

1017,: Actual plant setpoints are conservative relative to technical specifications.

a. + 208 inches -- HPCI*. RCIC*. RFPT, Main Turbine Trips

b. + 192 inches -- High level alare

c. + 182 inches -- Low level alara recirculation runback permissive

d. + 162) inches -- Scram *,

, GRP 2: 6. & 8 isolation

• ADS permissive *

e. + 112 inches -- GRP 1 & 3 isolation

• HPCI* (1) & RCIC l

l f. + 2i inches --

CS* & kHR*. initiation p

g. - 53 inches -- Containment spray permission l NCrTE: Invest available limit is 140" unless both reactor recirculation

, pumps are tripped.

1

• Technical Specification required (1) Injection valve opening requires

? '-

the level signal to remain for 3 '6 seconds, t

( i i

l. ,

1 BSEP/Vol. VII/0I-22 23 Rev. 4 I

g g*

.. ,' j W -- -

ATrACIDiENT 8b -

Vessel Pressure Transient

1. From computer and'RTGB recorders, obtain the highest and lowest pressures reached during the transient.

2. Verify the appropriate automatic actions listed below occurred at or

• before technical specification limits.

E7FE: Recorder / instrument accuracy may be significant on pressure transients.)

a. 1325 psig -- Safety limit. *

b. 1125 psig --

3 SRVs (+/- 1%)*

c. 1120 psis -- ATWS Recirc Pump Trip

d. 1115 psig --

4 SRVs (+/- 1%)1

e. 1105 psig --

4 SRVs (+/- 1%)1

f. 1045 psig -- Scram 3 1020 psig -- Technical specification limit normal operation

h. 825 psig -- Group I in "run"

i. 410 +/-15 psig --

RHR/CS fajection valve permissive

j. 310 +/-15 psig -- Recirc Discharge valve isolation if initiation signal present

k. 140 psig --

SDS iso 12 tion NOTE: Highest available indicatic: 1: 1200 pri . If :::::d:: i:-upsca le high, then assume a safety limit has been reached or exceeded.

1 Consider recorder / instrument accuracy.

• Technical Specification required BSEP/Vol. VII/0I-22 24 Rev. 4 I

e O

• IY. M '- .=#_* _-__ __ _U _

"*M

}

h

, ATTACIDfENT 8e Power / Flux Transient

1. From computer and RTGB recorders, obtain the highest power / flux level reached during the transient.

2. Verify the appropriate automatic actions listed below occurred at or before the technical specification limits:

a. 120%' (fixed) APRM trip

b. Flow biased [(.66W+54)T]

c. 90% (Unit 2 if APRM se,tdown occurred) *

d. 13% (not in "run" mode) t l

BSEP/Vol. VII/0I-22 25 Rev. 4

• ^

, - - ... .~

_______~_- 9

ATTACHMENT 8d Drwell Pressure - Transient

1. From computer and RTGB recorders, obtain the lowest and highest drywell pressures reached during the transient. .

2. Verify the appropriate automatic actions listed below occurred at or ~

before the technical specification limits.

a. 2 psig --

HPCI initiation

. Grp 2, 6, 8 isolation

b. 5 psig -- Suppression pool to Rx. Bldg. vacuum breaker isolation valves open

c. 40 psig --

CAC/ CAD drywell inlet valves isolate l

i

. l l

O l

l i

l BSEP/Vol. VII/01-22 26 Rev. 4

1. l l

.x_. w: e- .._ . - - _ _ _ . _.m.,____ __ _

ATTACHMENT 8e Condenser Vacuum Transient

1. From computer and RTUB recorders, obtain the lowest and highest condenser vacuums reached during the transient (in inches of Hg..)

2. Verify the appropriate automatic actions listed below occurred at or

• before the technical specification limits.

a. 22 inches Hg - Turbine trip

b. 7" Hg - Grp I isolation -

Turbine bypass valves close P

• l l

l* .

l i

BSEP/Vol. VII/0I-22 27 Rev. 4 I ,

t l .. e t u . % _ _

w -t 4% ~

==, _wA =~e m = ===se~ ~ ; '*^'~~-~*=&-'""~ *'**** ***' ' " ' " ~ ~ ~ '

~

ATTACHMENT 8f Off-Gas Activity Transient

1. From computer printouts and RTGB recorders obtain the highest values of

a. MSL Rad Monitor (A - D)

b. SJAE Rad Monitor

c. RB roof vent rad monitor

2. Verify the appropriate automatic actions listed below occurrrA at or before the technical specification limit:

a. MSL Rad Mon (3+ normal) -- GRP I isolation MVP isolation

b. (ar/hr) -- Timer starts: 15 minutes later A0G - HCV-102 isolates.

. c. 11 (ar/hr) -- RB roof vent rad monitor --

Grp 6 isolation SBGTS initiation Rx. Bldg. ventilation isolates BSEP/Vol. VII/0I-22 28 Rev. 4 0

.--. .--2mg .w. - _ -m  %, _

.--,-------;. . - ~ ~ -

g

ATIACHMENT 8g Loss of Electrical Power Transient

1. From computer printouts and RTGB recorders determine which electrical busses (4 kv) lost power, and min / max voltage on 4 kV buses that did not lose power.

2. Verify the appropriate autoanatic actions listed below occur:

a. If either:

1. Lose of power to BOP bus

• E bus feeders trip and DG

2. Loss of power to E bus starts and energizes E bus

3. Degraded voltage on E bus t

e BSEP/Vol. VII/0I.-22 29 Rev. 4 0 t O

..,_...-- - m . _ _ . ~ _ . . _ . o .... . ~ ... .- - ._ _. - . -- - _ . . . . _ .

i 1

ATTACHMENT 8h Scram Setpoint Reached

1. From computer printouts and RTUB recorders determine if any of the following scram setpoints were reached: - I

a. IRM -- 120% of scale

b. APRM -- 120% (fixed)

(.66 W+54)T (flow biased) .

15% (not in "run")

c. Pressure High - 1045 psig

d. Vessel water level low -- +162.5

e. MSIV closure -- 10% closed

. f. MSL High Rad --

g. Drywell pressure high -- 2 psig  ;

h. TSV close -- 10% closed 8 5

1. TCV fast closure (850 psig EHC pressure)  !-

. I

j. Mode switch in shutdown

k. SDV level high -- 109 gals.

2. If any of the above setpoints were reached, verify automatic scram resulted.

. c

3. d If a manual scram occurred during a transient, verify no scram setpoints were exceeded prior to the manual scram. ,

• c b

BSEP/Vol. VII/0I-22 30 Rev. 4 I

i f

a A

. e -.

APPENDIX C Action Plans and Schedules

CAROLINA POWER & LIGHT COMPANY SALEM TASK FORCE REPORT ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY A. Item No(s): 1-NSS Post-Trip Log Improvements B. Est. Comp 1. Date: April, 1985 C. Unit: Technical Support D. Site: BSEP E. Overall Responsibility: E. A. Bishop F. Action Plan Responsibility: E. B. Wilson /E. O. Eagle II. RECOMMENDATION DESCRIPTION Investigate improvements to the NSS Post-Trip Log for accomplishing:

1. Expansion of point count from 10 to 15 points.

Transfer of data to bulk for temporary storage.

2.

, 3. Enable repeat of printout.

III. ACTION PLAN OVERVIEW Develop detailed project plan that identifies resources, priority, and operations impact. Obtain management approval and implement changes.

IV. COMMENTS Implementation of changes would provide additional data base for analyzing transient or trip conditions.

CAROLINA POWER & LIGHT COMPANY SALEM TASK FORCE REPORT ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY A. Item No(s): 2-BOP Post-Trip Log Improvements

~B. Est. Comp 1. Date: April, 1985 C. Unit: Technical Support D. Site: BSEP E. Overall Responsibility: E. A. Bishop F. Action Plan Responsibility: E. B. Wilson /E. O. Eagle II. RECOMMENDATION DESCRIPTION Investigate improvements to the B0P Post-Trip Log for accomplishing:

1. Check reducing scan rate to 5-second interval.

2. Reselection of a point set best suited to present needs.

3. Planning selected points in a faster scan class or creating special duplicate points for B0P Post-Trip Log use only; i.e., C160 is a special 1-second scan of reactor pressure, B016.

I III. ACTION PLAN OVERVIEW Develop detailed project plan that identifies resources, priority, and operational impact. Obtain management approval and implement changes.

IV. COMMENTS

CAROLINA POWER & LIGHT COMPANY SALEM TASK FORCE REPORT ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY A. Item No(s): 3-Enlargement of Sequence-Of-Events Buffer B. Est. Compl. Date: December, 1985 C. Unit: Technical Support D. Site: BSEP E. Overall Responsibility: E. A. Bishop F. Action Plan Responsibility: E. B. Wilson /E. O. Eagle II. RECOMMENDATION DESCRIPTION Enlarge sequence-of-events buffers in the core memory to retain additional points and storage of data on bulk memory as backup.

III. ACTION PLAN OVERVIEW Develop detailed project plant the identifies resources, priority, and operational impact. Obtain management approval and implement changes.

IV. COMMENTS Will allow retention of additional points and help alleviate potential printout backlog.

CAROLINA POWER & LIGHT COMPANY SALEM TASK FORCE REPORT ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY A. Item No(s): 4-Implementation of ERFIS/SPDS B. Est. Comp 1. Date: Refer to NRC Generic Letter 82-33 response C. Unit: Technical Support D. Site: BSEP E. Overall Responsibility: Ralph Saunders F. Action Plan Responsibility: Bill Hogan II. RECOMMENDATION DESCRIPTION Implementation of Safety Parameter Display System (SPDS) in response to requirements of NRC Generic Letter 82-33.

III. ACTION PLAN OVERVIEW Develop detailed project plan that identifies resources, pricrity, and

• operational impact. Obtain management approval and implement changes.

IV. COMMENTS Provide improvements in the following areas:

I. Faster scan rates.

2. Additional safety-related points.

3. Larger trending logs.

4. Larger historical logs.

5. Improsad display and replay of historical data.

6. Color graphic displays.

7. Improved point validatica techniques.

l CAROLINA POWER & LIGHT COMPANY ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY A. Item No(s): 5-Q-List Program Upgrade B. Est. Compl. Date: To be determined C. Unit: Technical Support D. Site: BSEP E. Overall Responsibility: E. A. Bishop F. Action Plan Responsibility: B. L. Parks II. RECOMMENDATION DESCRIPTION Upgrade current Q-list procedure to create a multi-level, more detailed component level quality classification system for plant equipment.

III. ACTION PLAN OVERVIEW -

Develop detailed project plan that identifies resources, priority, and work breakdown schedule. Obtain management approval, funding, and implement changes.

IV. COMMENTS Implementation completion date to be determined upon development of project plan.

CAROLINA PO'7ER & LIGHT COMPANY SALEM TASK FORCE REPORT

. ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY

$ A. Item No(s): 6-Implement Section 3.1.2 of NRC Generic Letter 83-28 B. Est. Comp 1. Date: September, 1984 (Submittal of Project Plan to NRC)

C. Unit: Technical Support D. Site: BSEP E. Overall Responsibility: E. A. Bishop F. Action Plan Responsibility: B. E. Hinkley II. ~ RECOMMENDATION DESCRIPTION 4

Submit to the NRC the results of a check of vendor and engineering recommendations applicable to Reactor Protection System in addition to SILs. This review is to ensure that appropriate test guidance is included in the test and maintenance procedures or the technical specifications where required.

t III. ACTION PLAN OVERVIEW Develop detailed project plan that identifies resources, priority, and work breakdown schedule. Obtain management approval and implement.

IV. COMMENTS Preliminary review in progress. Can be coordinated with Item No. 9 action plan.

Final implementation completion date to be determined.

l

~y,,9 ,,,w--- -'~

T 'w~~-'- *W-'*

CAROLINA POWER & LIGHT COMPANY SALEM TASK FORCE REPORT ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY A. Item No(s): 7-Implement Section 3.1.3 of NRC Generic Letter 83-28 B. Est. Comp 1. Date: June 1984 C. Unit: On-Site Nuclear Safety D. Site: BSEP E. Overall Responsibility: R. E. Helme F. Action Plan Responsibility: R. E. Helme .

II. RECOMMENDATION DESCRIPTION Research and identify any post-maintenance test requirements in existing technical specifications applicable to the Reactor Protection System which are perceived to degrade rather than enhance safety. Review to include implied post-maintenance tests indicated by the action statements and those referenced in Technical Specification 4.0.5. Submit to NRC any applicable changes to test requirements.

III. ACTION PLAN OVERVIEW Perform technical specification review and submit written report as supplement to NRC Generic Letter 83-28 response.

I IV. COMMENTS j Develop technical specification changes as applicable. (May require interface with Engineering and Regulatory Compliance.)

I I

l

. l l

I

)

CAROLINA POWER & LIGHT COMPANY SALEM TASK FORCE REPORT ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY A. Item No(s): 8-Implement Section 3.2.1 of NRC Generic Letter 83-28 B. Est. Comp 1. Date: August, 1985 C. Unit: Operations / Maintenance D. Site: BSEP E. -Overall Responsibility: J. W. Chare /J. P. Dimmette F. Action Plan Responsibility: J. W. Chase /J. P. Dimmette II. RECOMMENDATION DESCRIPTION Develop report documenting the review that verifies that post-maintenance testing is being performed after maintenance activities.

III. ACTION PLAN OVERVIEW Perform review and subunit written report as supplement to NRC Generic Letter 83-28 response.

IV. COMMENTS May require coordination with Engineering and On-Site Nuclear Safety (reference Item No. 10).

i CAROLINA POWER & LIGHT COMPANY

> SALEM TASK FORCE REPORT ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY A. Item No(s): 9-Implement Section 3.2.2 of NRC Generic Letter 83-28 B. Est. Comp 1. Date: December, 1985 C. Unit: Technical Support D. Site: BSEP E. Overall Responsibility: E. A. Bishop F. Action Plan Responsibility: E. B. Wilson II. RECOMMENDATION DESCRIPTION Submit to the NRC the results of a check of vendor and engineering recommendations for safety-related equipment to ensure that appropriate test guidance is included in the test and maintenance procedures or the technical specifications where required.

III. ACTION PLAN 6VERVIEW Develop detailed project plan that identifieu resources, priority, and work breakdown schedule. Obtain management approval and implement.

IV. COMMENTS

CAROLINA POER & LIGHT COMPANY SALEM TASK FORCE REPORT ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY A. Item No(s): 10-Implement Section 3.2.3 of NRC Generic Letter 83-28 B. Est. Comp 1. Date: December 1984 C. Unit: On-Site Nuclear Safety D. Site: BSEP E. Overall Responsibility: R. E. Helme F. Action Plan Responsibility: R. E. Helme II. RECOMMENDATION DESCRIPTION Research and identify any post-maintenance test requirements in existing technical specifications applicable to safety-related components which are perceived to degrade rather than enhance safety. Review to include implied post-maintenance tests indicated by the action statements and those referenced in Technical Specification 4.0.5. Sub'itm to the NRC any applicable changes to test requirements.

III. ACTION PLAN OVERVIEW Perform technical specifications review and submit written report to NRC Generic Letter 83-28 response.

l IV. CONNENTS Develop technical specification changes as applicable. (May require 1 interface with Engineering and Regulatory Compliance.) l l

i l

l CAROLINA POWER & LIGHT COMPANY SALEM TASK FORCE REPORT ACTION PLAN

SUMMARY

I. ITEM NO. & RESPONSIBILITY A. Ites No(s): 11-Implement Section 4.5.1 of NRC Generic Letter 83-28 B. Est. Compl. Date: November, 1984 C. Unit: Operations D. Site: BSEP E'.~ Overall Responsibility: J. W. Chase F. Action Plan Responsibility: J. W. Chase II. RECOMMENDATION DESCRIPTION Develop test procedure for off-line testing of back-up pilot solenoid values.

III. ACTION PLAN OVERVIEW Develop detailed project plan that identifies resources, priority, work breakdown schedule, and operational impact. Obtain management approval and implement changes.

IV. COMMENTS r

May require interface with I&C Maintenance. Implementation of test procedure will begin the next full cycle refueling outage after incorporation into the Plant Operating Manual. No technical specification change will be required.

E

-- ,.m ,- _

APPENDIX D UPS System Diagram

1 .

1 I

Q s in51[R .

p , PRil'ARY POWER CollVERTER ._. $yg g

--_________) DISPAIG ,

I I M l

• usEm ,

D IPMEING  ;';

l STATIC C 211/480 %

$0ktCE es 480 VAC 65 HZ o }-o^o-. INVERTEA gy ggg a 04 211/480VAC d.

33,3 WIRE g

8fCIlflER

-o o l 12a/208' d ja, g gjg s

WM l l

^ '

, 250VDC 0-t-0 C >!  !

SLOCKING l I O!00E j r/JiuAL

]

3 [_____________g  ;;

,TM,.*iSFEA i

i $TANDBY PLM R CONVERTER r- i

!  ?% - l l l 3 m n.0.

i ^ i l " 2. { 450 VAC, 60 HZ C 3 O- g fg  ;, IMRTER [c '

3. 3 me i i YB

" l l

1 l

250VDC 0-t-o^c >l BLOCKING l

! l DIOCE ,

1 l l l

0 SYSTEM OUT M 120/203VAC, 60 MZ

! 38, 4 VIRE 5

s u UPS SYSTEM i Figure 52-1

APPENDIX E Process Computer Parameters l

l

I APPENDIX E Figure 1 DIGITAL INPUTS AND SEQUENCE-0F-EVENT CONTACTS

\

l Q_

APPENDIX D FIGURE 1

. DIGITAL IMPUTS & SEQUENCE OF EVENT CONTACTS PSUn A500 RECIRC LOOP'A INACTIVE NORM PSun A501 RECIRC LOOP B INACTIVENORN PSUM A502 MAIM STM LINE A HI FLOWNORR

. PSUMA5T0 MAIN STM LINE B HI FLOW NORA )

PSUA A504 MAIN STM LINE C HI FLOW NORA FSUR A50L MAIN STM LINE D HI FLOW NORA PSun A504 MSL A LEAK DETECTION NORE 1 l

PSUA A507 MSL 8 LEAK DETECTION NORM PSUA A508 MSL C LEAK DETECTION NORN PSUR A509 MSL D LEAK DETECTION NORA '

ESun a:i10 Ituu n38.AM:IB N9RA.

PSUN A511 CHILLER 28-RM-TB NORA PSUR A512 CHILLER 28-RM-TB NORA ALM A513 NSS RECIRC LOOP EGUALZR OPEN PSUA A514 DISCN V0L HI UTR R00 SLK OFF PSUR A516 REFUEL INTLK R0D SLOCK NORA

- PSun A517 CRD R00 TIMER MALFUNC NORR PSun A516 RWM SLCD' ALARM OFF \

l PSUM A519 SIM DET NOT START-UP POS OK PSUA A520 SRM UPSCALE ALARM NORA

' PSUA A521 SRM INOPERATIVE ALARM NORA PSUA A522 SRM BYPASSED NORR FSUR A523 IRM DET NOT FULL-INNORN POS PSUR A524 IRM DOWNSCALE ALARMNORM PSUM A525 IRN IN0 PERATIVE ALARM NORR PSUA A526 IRM UPSCALE ALARM NORM PSUN A527 APRM 00WNSCALE ALARA NORN PSUM A528 APRM UPSCALE ALARM NORN '

PSUN A529 APRM INOPERATIVE ALARM NORN PSUA A531 R8M DOWNSCALE ALARMNORA PSUA A532 RBM TRIP ON LEVEL NORA PSUR A533 RBM INOPERATIVE ALAIM NORA

' PSUN A534 FLO UNIT UPSCLE TRP/INOP NORR PSUA A535 IRM SYPASSED OFF PSUR A534 APRM CH 1 BYPASSED OFF PSUM A337 APRM CH 2 BYPASSED OFF PSun A536 APRM CH 3 BYPASSED OFF

' PSUA A539 APRM CH 4 BYPAESED OFF PSUA A540 APRM CN 5 BYPASSED OFF l , -

PSUR AS41 APRM CN 4 SYPASSEDOFF PSUM A542 RBM 8YPASSED OFF

. PEUA AS43 ROD OUT CLOCK OFF PSUM A544 ALARM ON FLOW COMPARATOR NORM PSUM A544 CONTROL R00 WITHDRAW ON PSUA A550 RWM OPERABLE ALM OFF ALM A552 RWM ROD W/ DRAW PERM ECHO ON A553 RWM RCD INSERT PERM ECHO ON PSun A554 LOW POWER LEVEL ALARM 0FF PSun A555 LOW POWER LEVEL IN!!LOCU OFF A

I t

I

--S .- _--_._-._.n-- - . , , - , , , - . , - - - - - - , - - - ., m . : O -. . - - - - - - . - - - - - - - , . - - - - - - - - - - -

)

PSUN A556 RFIS MALFUNCTION OFF PSUM A559 RWM SYSTEM DIAGNOSTIC 0FF PSUR A560 TIP MACHINE A READY ON l PSUS A561 TTP MACHINE B READY ON PSpa A562 TIP MACHINE C READT ON PSUA. A563 TIP MACHINE D READY ON

, ALM A565 RPT SYS A QUT OF SEfVICE TRIP ALM A566 RPT SYS B 0UT OF SERVICE TRIP l PSUA A567 R0D DRIFT ALARM OFF PSUN AS48 R0D SELECTED AND DRIVING 0FF PSUS A569 HD PUMP C STATUS ON I PSUN A570 ALL RWCU PUMPS OFF NO ALM A571 CORE SPRAY PUNP A TRIP PSUR D500 DISCH VOL LVL CHANNEL A1 RSET PSUN D501 DISCH V0L LVL CHANNEL 81 RSET l PSUA 0502 DISCH V0L LVL CHANNEL A2 RSET l PSun D503 DISCH V0L LVL CHANNEL B2 RSET PSUN D504 LOAD REJECT SCRAM CN C RSET PSUR D5DS LOAD REJECT SCRAM CN D RSET

~

PSUN D506 230 KV PCB 303 NORN PSUN D507 MSIV < 905 OPEN CHNL A1 NORN

PSUA D500 MSIV ( 90 OPEN CHNL.B1 NORA RSUM D509 MSIV ( 90

OPEN CHNL A2 NORN PSUA D510 MSIV ( 90% OPEN CHNL 82 NORM PSUN D511 CONTMT HIGH PRESS CN At NORM PSUN D512 CONTMT HIGH PRESS CN 81 NORN PSUN D513 CONTNT HIGH PRESS CH A2 NORN PSUR D514 CONTMT HIGH PRESS CN 82 NORA PSUN 0515 REACTOR CHNL A1 HI PRESS HORN PSUM 0516 REACTOR CHNL 81 HI PRESS NORN '

PSUR D517 REACTOR CHNL A2 HI PRESS NORE PSUR D518 REACTOR CHNL 82 HI PRESS NORA PSUN D519 REACTOR LO WTR LVL CH A1 NORN PSun D520 REACTOR Lo WTR LVL CH B1 NORA PSUN D521 REACTOR LO WTR LVL CH A2 NORM PSUA D522 REACTOR LO WTR LVL CH B2 NORA PSUN D523 MSL A1 HIGH RADIATION RSET PSUA D524 MSL 81 HIGH RADIATION RSET .

PSUR D525 MSL A2 HIGH RADIATION RSET PSUE D526 MSL 82 NIGH RADIATION RSET PSun D527 NEUT MON SYSTEM CHNL A1 RSET PSun D520 NEUT MON SYSTEM CHNL B1 RSET PSun D529 NEUT MON SYSTEM CHNL AD RSET PSUN D530 NEUT MON SYSTEM CHNL D2 REET PSUA D531 LOAD REJECT SCRAM CH A RSET i -

PSUA D532 LOAD REJECT SCRAM CN B RSET PSUR D533 MANUAL SCRAM CHANNEL A RSET l

PSUN D534 MANUAL SCRAM CHANNEL U RSET PSUN D535 REACTOR SCRAM CHANNEL A RSET PSUM D536 REACTOR SCRAM CHANNEL E RSET PSUN D538 TSV FAST CLOSURE CHNL A1 RSET PSUW D539 TSV FAST CLOCURE CNNL 81 RSET _ .

( *

• \

. , , , , y% ,, , .,-- wws-er P e 4-' +-= '-'"""'P* * ' * * ' ~ ~ " - * - ^ * " " ' ~ " " " - ' ' ' ""

i PSUR D540 TSV FAST CLOSURE CNNL A2 RSET PSUM D541 TSV FAST CLOSURE CHNL 82 RSET ,

PSUA D540 TCV FAST CLOSURE CNNL A1 RSET '

PSUN D543 TCV FAST CLOSURE CHNL B1 RSET PSUA D544 TCV FAST CLOSURE CNNL A2 RSET PSUA D545 TCV FAST CLOSURE CNNL 82 RSET PSUM D546 APRM CHNL A UPSCALE LVL RSET PSUR D547 APRM CHNL 8 UPSCALE LVL RSET PSUN D540 APRM CHNL C UPSCALE LVL RSET PSUN D549 APRM CHNL D UPSCALE LVL RSFT PSUN D550 APRM CHNL E UPSCALE LVL RSET PSUA D551 APRM CHNL F UPSCALE LUL RSET PSUM D552 230 KV PCS 288 NORA PSUA 0553 230 XV PCS 30A NORM PSUR D554 IRM CHNL A UPSCALE LVL RSET PSUN D555 IRM CHNL B UPSCALE LVL RSET PSUA D556 IRM CHNL C UPSCALE LVL RSET PSUN D557 IRM CHNL D UPSCALE LVL RSET PSUN D558 IRM CHNL E UPSCALE LVL RSET PSUR D559 IRM CHNL F UPSCALE LVL RSET PStin D54D IRM CHNL G UPSCALE LUL RSET PSUR D561 IRM CHNL H UPECALE LVL RSET

'PSUR D564 APRM CHNL A SETDOWN RSET PSUR D565 APRM CHNL B SETDOWN RSET PSUA D546 APRM CHNL C SETDOWN RSET PSUR D567 APRM CHNL D SETDOWN RSET /

PSUA D569 230 XV PCS 31A NORA >

PSUN D570 230 KV PCS 318 NORN PSUN D571 RPT SYS A BKR3A/3B CLSD j PSUS_QJEJf7_JYE.J.BU_WM CLSp .

PSUA D573 AIR COMPR 20 MOTOR OVLD NRML PSUR D574 AIR COMPR CD GRND FAULT NRML PSUA D575 SRV F013A STATUS CLSD 1 PSUR D574 SRV F0138 STATUS CLSD PSUR D577 SRV F013C STATUS CLSD PSun D578 SRV F0130 STATUS CLSD PSUR D579 SRV F013E STATUS CLSD PSUMD585~'StVF013FSTATUS CLS6 PSUN D501 SRV F013G STATUS CLSD PSUN D582 SRV F013H STATUS CLSD PSUN D503 SRV F013J STATUS -CLSD PSUS D584 SRV F013K STATUS CLSD PSUN D585 SRU FDT3L STATUS CLSD PSUA D5b6 APRM CH A UPSC THERRAL.

REET PSUN D587 APRM CH B UPSC THERRAL. RSET PSUN D5BB APRM CH C UPSC THERRAL RSET PSUN D589 APRM CH D UPSC THERNAL 'RSET PSUN- DS90 APRM CH E UPSC THERAAL RSET PSUR D591 APRM CH F UPSC THERRAL RSET PSUM 0590 230 KV PCS 27B NORA l PSUR D595 230 KV PCB 28A NORA 2

/ .

s

. . 1

s .- .

PSUR D600 EXNAUST N000 A TEMP HIGH NRML PSUR D601 EXNAUST N00D B TEMP HIGH NRML

/ PSUA D602 TURB TNRUST BRG WEAR NRML PSUA,D603 TURB 0VERSPEED TRIP L/0 NRML

. PSUR D604 TURB MASTER TRIP SYS NRM'.

, PSUR D6DS OVERSPEED TRIP NRML PSUR D6D6 OVERSPEED TRIP RESETTING NRML PSUA D607 UAT WINDING X GROUND NRML PSUR D600 UAT WINDING Y GROUND NRML PSUA D409 230 KV PCB 27A NORA FSUA D610 MAIN XFMR FAULT PRESS NRML PSUN D611 GEN GROUND CURRENT RELAY NRML PSUA D612 TURBINE PROTECTIVE CKT NRML PSUR D613 UAT DIFF RELAY NRML PSUA D614 UAT OVERCURRENT RELAY NRML PSUR D615 UAT FAULT PRESS RELAY NRML PSUR D616 GEN PCB A (29A) OPEN PSUM D417 GEN PCB B (298) OPEN PSUR D618 GEN LOSS OF EXCIT RELAY NRML

/ PSUa D619 SINGLE ZONE FAULT RELAY NRML PSUA D620 REVERSE POWER RELAY NRML ,

~

PSUR D621 GEN XFMR DIFF RELAY NRML PSUR D622 GEN PCB PRI RELAYING NRML PSUR D62% GEN DIFFERENTIAL RELAY NRML

. PSUA D624 GEN OVERCURRENT RELAY' NRML PSUI D625 NEG PHASE SEGUENCE RELAY NRML PSUR D626 SAT DIFT RELAY NRML PSUA D627 TUWB SNAFT PUMP PRE 3S LO NRML PSUA D428 LOSS OF COOL TRIP NRML PSUM D620 CONDENSEE A VACUUM NRML PSUA D630 CONDENSER B VACUUM NRML PSUR D631 HYD FLUID SYSTEM PRESS TRIP PSUN D402 MOIST SEP LEVEL HI TRIT NRML PSUN D633 GEN PRIMARY L/0 RELAY RSET PSUR D634 GEN BACKUP L/0 RELAY RSET PSUM D435 CASWELL BEACH L/0 RELAY RSET PSUR D436 230RV BUS TA PRI L/0 RSET PSUR D637 230KV BUS 2A BU L/0 RSET .

PSUA D638 230KV BUE 2B PEI L/G RSET -

PSUM D639 230KV BUS 2B BU L/0 RSET PSUM D640 230KV TIE BUS DIFF 'L'/6~RSET PSUM D641 BUS E1 UNDERVOLTAGE RSET rSUN"D642 BUS E2 UNDERV0LTAGE RSET r

PSUM D643 BUS E3 UNDERVOLTAGE RSET PSUR D644 BUS E4 UNDERVOLTAGE RSE!

e

, PSUR E500 LTG SWGR 2L TRANS TEMP NRML PSUR E501 LTG SWGF 4L 1RANS TEM 6 NRML

' PSUA E502 SUBSTA ' 2C XFMR TEMP NRML PSUA E503 SUBSTA ( 2F XFMR TEMP NPML j PSUM E504 SUBSTA E7 rFMR TEMP NRML PSUA E505 SUBSTA ES XFMR TEMP NRML )

PSUR ELO.4 SUSSIA COMM D TRT IEMP NRML i e ,

l' & > j

!- (

1

.]?'/ *,

lj. c. i

, - I *

)

E

• , _,_ __~.._..,:_...- .-/---------- ---- - --- - ------"--~~~

-. .y . . - . . .. .. . .. _

. ,j PSUM E507 SUBSTA 25Y XFMt TEMP NAML PSUM E508 SUBSTA ES XFMR TEMP i NRML PSUR E509 SUBSTA E4 XFMR TEMP NRML PSUB E51D SUS E2 INC BER FR SBS 1E NRML PSUA E511 SUS E2 TIE BKR 70 SUS E1 NRML FSun E512 SUS E2 TIE SKR 70 BUS E4 NRML (FSUM E513 DIESEL GEN 2 70 BUS E2NRML

'PSUM E514 8US E3 INC BKR FR SUS 2D NRML 2PSun E515 BUS E3 TIE BKR 70 SUS E1 NRML

' 'PSUR E516 BUS E3 TIE BER 70 80S E4 NRML FSUR E517 DIESEL GEN 3 TO Bb5 E3NRML PSUN E518 BUS E4 INC SKR FR SUS 2C NRML PSUR E519 BUS E4 TIE SKR FR SUS E2 NRML PSUA E52D SUS E4 TIE SKR FR BUS E3 NRML s

PSUR E521 DIESEL GEN 4 70 BUS E4 NRML

'PSUM E522 DIESEL GEN 1 AUT0-START NRML PSUM E523 DIESEL GEN 2 AUT0-START NRML PSUN E524 DIESEL GEN 3 AUTO-START NRML PSun E525 DIESEL GEN 4 AUTO-START NRML

' PSUR E526 4KU BUS 20 70 SUBSTA 2E NRML PSUA E527 4KU DOS 2C TO SUSSTA 2F NRML PSUR E528 4KV COMM 8 70 SUBSTA 2L NRML PSun E529 4KV COMM 8 70 SUBSTA 2SY NRML Ptun E530 COMM 8 TO SUBSTA ConMNRML 0 PSUR ES31 BUS E1 70 SUBSTA EU NRML PSUN E532 BUS E2 TO SUBSTA E4, NRML PSUR E533 SUS E3 TO SUBSTA E7 NRML PSun E534 8US E4 TO SUBSTA E8 NRML PSun ES35 8US 28 INC SKR FROM UATNRML PSUN E534 BU3 28 INC SKR FROM SATNRML PSUN E537 BUS 2C INC SKR FROM UAT NRML .

PSUM E538 BUS 2C INC BKR FROM SAT NRML PSUR E539 BUS 2D INC BKR FROM UAT NRML PSun E540 SUS 2D INC BKR FROM SAT NRML PSUA E541 SAT INC LINE TO CORM 8NRML PSua E542 COM BUS 8 TIE BKR.COMM A NRML PSUA E543 SUS E1 INC SKR FR 9US 10 NRML PSUA E544 SUS E1 TIE BKR FR SUS E2 NRML PSUN E545.8US E1 TIE.8KR FR SUS E3 NRML PSUN E546 DIESEL GEN 1 TO SUS E1 NRML

, PSUN E547 BUS 2D FEED'70 SUS E3 NRML l PSUN E548 BUS 2C FEED 70 EUS E4 NRML l PSUN E549 SAT WINDING X GROURDNRML PSUR E55D SAT WINDING Y GROUND NRML ALM E559 C8 23KV PCB CS8 TRIP PSUN E540 N2 VENT LINE PRESS WPML PS!M E541 CW DISCN PUMP 2A NRML PSOH E562 CW DIEUI PUMP 2r NRML PSUN E563 CW DISCN PUMP 2C NRML PSus E564 CW DISCH PUMP 20 NRML PSpa E545 ALL STAT COOL PUMPS OFF NO PSUR E544 TURNING GEAR ENGAAED NO PSUR E567 SUS 28 UNDERVOLTAGE RSET J

PSUN E548 BUS 2C UNDERVOLTAGF ASET ,

I i; -

[ + + . . . . _ . . _ _ _ . . _ . _ . . .

RSET PSua E549 BUS 2D UNDERVOLTAGE RSET PSUA EO O COM B BUS UNDERVOLTAGE NRML PSUM E571 U-1/U-2 SAT TIE SKR TRIP ALM E572 CRD PUMP A NRML PSUR E573 CRD PUMP S PSUN E574 CRD PUMP A NRML PSUM E575 4RD PUMP B ggnt PSUM E576 CRD PUMP A ggyt PSUA E577 CRD PUMP s NRML ESus_C78_ IDEE StAALTE5P A MUtL, PSUA E579 CORE SPRAY PUMP S NRML PSUA E580 REACTDR IN RUN OR S-U YES j PSUR E581 SUB 2L FEEDER NRML PSUS E562 SUS 4L FEEDER NRML PSun E583 SUB 2E FEEDER NRML PSUN E534 SUS 2F FEEDER NRML PSUA E585 SUE 25Y FEEDER NRML PSUM ESB6 SUU COMM D FEEDER NRML PSUM E587 SUE ?L FDR RE LTG 28 NRML

~

PSUA ESES SUS 2L FDR TB LTG 2D NRML PSUR E589 SUS 2L FDR CB LTG 2A NRML PSUN E590 SUB 4L FDR MCC-SBA NRML PSUA E591 SUC 4L FDR PNL 2S1 2S2 NRML PSUA E592 add!N OFFICE SLDG LIGHTS NRML PSUR E593 ADMIN OFFICE BLDG POWER NRML-PSUR E594 SU8 2E FDR MCC-2TA NRML PSUN E595 SUB 2E FDR MCC-2TB NRML FEUM E596 SUG 2E FDR MCC-2TC NRML PSUA E597 SUE 2E FDR PNL 2E-TB NRML PSUR E598 SUB 2E FDR MCC-2TF NRML ,

PSUR E599 SUS 2E FDR MCC-2TE NRML PSUN E600 SUE 2E FDR MCC-2TL NRML PSUR E601 SUB 2E FDR MCC-2TJ NRML PSUN E602 SUB 2F FDR MCC-2TN NKML PSUA E603 SUS 2F FDR MCC-2TG NRML PSUN E604 SUS 2F FDR MCC-2TH NRML PSUR E605 SU8 2F FDR MCC-2TM NRML FSUA E606 SUB 2F FDR PNL 2F-TE NRML

, PSUE E607 SUB 2F FDR MCC-2TE NRML PSUE E608 SUR 2F FDR MCC-2TD NRML PSUN E609 COMM D FDR MCC-RWe ' NRML PSUR F610 COMM D FDR MCC-RWA NRML PSUS E611 COMM D FDR MCC-25A NRML -

PSUN E612 COMM D FDR TH CRANES NPML PSUn E613 BUS El FDR $URSTA EL NRML PSUR E614 BUS E2 FDR SUBSTA E4 NRML PSUN E615 BUS E3 FDR SUBSTA E7 NRML PSUF E616 SUS E4 FDR SUBST4 E8 NRML PSun E617 RHR PUMP A NRML FSUM E618 RHR PUMP E NRML PSUA E619 RNR PUMP C NRML PSUM E620 RNR PUMP D NRML o

b .

PSUM E421'RNR SW PUMP A NRML PSUM ELC2 RHR SW PUMP E NRML PSUR E623 RHR SW PUMP C NRML PSUR E624 RHR SW PUNP D NRML' ALM E605 CC 4RV BUS B INC Eli. TRIF PSUN E626 C5 4RV SUS A/S TIE IKR NRML

ALM E627 CB YFMR & FDR BRR TRIP MLM E626 CE 4COV BUS E INC BRP TRIT l ALM E629 CE 4BOV BUS A/F TIC BKR TRIF i PSua E630 CF BRG MATER PUMP 1 NRML ELM E631 CB SRG WATER PUMP 2 TRIP iPSUR E632 CS SUPERVISORY STS SCAN NRML ,

FSUR E633 C8 SUPERVISORT SYT. SROUf' NRML TSun E634 CB SUPV MASTER

' ~

TO REMOTE NRML PSUM E635 CB SUPV R5fiOTE TO MASTER NRML' ALM E636 RHR PUMP A TRIP ALM E637 RHR PUMP B TRIP ALM E638 RHR PUMF C TRI? -

ALM E63* RHF PUMP O TRIF ALM E640 CW PUMP A STATUS OFF F50e E641 CW PUMP B STATUS CH PSUA E642 CW PUMP C STATUS ON PSUR E643 CW PUMP D STATUS ON PSua F500 FW HTR 1A LEVEL NRML PSua F501 FW HTR 18 LEVEL NRML PSUR F502 FW HTR 2A LEVEL NRML '

PSUR F503 FW HTR 28 LEVEL NRML ALM F504 FW HTR 3A LEVEL HIGN l PSUN FSOS FW HTR 38 LEVEL ERML PSUS F506 FW HTR 4A LEVEL HRML PSUA F507 FW H1R 4C LEVEL NRM'$

PSUA F506 FW HTR SA LEVEL NRML PSUR F509 FW HTR 58 LEVEL NRML ALM F510 HD DEAERATOR LEVEL HIGN PSUR F511 HD DEAERATOR LEVEL NRML PSUR F512 HTR DRAIN PUMP A NRML

'PSUF, F513 CHILLER 2F-RM-T8 NRML 8PSUN F514 HTR DRAIN PUMP C NRML

'PSUR F515 FW HTR 1 A LEVEL HIGN RSET IPSUR F516 FW HTR 18 LEVEL HIGN RSET IPSUR F517 FW HTR 2A LEVEL HIGH RSET

• REET

'PSUR F51D FW HTR 28 LEVEL HI6H

'PCUM FS19 FW HTR 3A LEVEL HIGN R3ET

'PSun FU20 FW HTR 3R LEVEL HIGN RSET PSUR FL21 FW HTP 4A LEVEL HIGN RSET ,

PSUP F522 FW HTR 4F LEVEL HIGH RSET PSUN F522 FW HTR 5A LEVEL HIGH RSET PSUR F524 FW HTR SC LEVEL H16H RSET i

PSpa F525 HD DEAERA10R LEVEL HIbH NRhl

PSus F526 TURI: SYPASS VALVE STATUS NRML

'PSun F527 HD DEAERATOR LEVEL LOW NRM PSUR F528 CHILLER 2A-RM-TB NORA

, PSun FS29 CHILLER 24-RM-TB NOPR e

e s f .

I -

. .  :: - - _ . .= ..: . - _ - = _ = - - - .- --____ . =.

~~ ._ .- _ ~~ ~ ~ - - - - - - - - _.

~

PSun F530 CHILLER 2A-RM-TB NORA l PSUN F531 CW DISCH PUMP B MTR TEMP NDRA PSun F535 CIRC WATER INTAKE PUMP A NRML PSUR F536 CIRC WATER INTAKE PUMP U NRML l 2

PSUR F537 CIRC WATER INT ARE PUNP C NRML PSUA F536 CIRC WATER INTAKE PUMP D NRML j PSUE F539 RFP A BRG OIL PRESS LDW NRML  !

PSun F540 RFP A ACT THRST BR6 WEAR NRML PSun F541 RFP A INAC THRT BRG LEAR NRML

' PSus F542 RFP A MAN TRIP SWITCH RSET PSUR F543 RFP A TURS BRG OIL PRESS NRML PSUA F544 RFP B BRG OIL PRESS LDW NRML tPSUR F545 RFP B ACT THRST BRG WEAR NRML ,

PSUA F546 RFP B INAC THRT BRG WEAR NRML I

PSun F547 RFP B MAN TRIP SWITCH RSET l PSUN F548 RFP'B TURB BRG OIL PRESS NRML PSUA F552 TB CCW ND TANK LVL NI/LO NRML PSUN F5f3 TB CCW PMP DISCH PRESS NRML PSUR F554 78 CCU HXS OUT TEMP NRML PSUR F555 TB CCW HXS OUT TEMP NRML PSUA F556 0FF GAS DISCH HOR PRESS NRML

!GNR F5S7 STACK FILTER DIFF PRESS NRML l

IGNt F558 STAND-BY FILT DIFF PRESS NRML PSUM F559 COND FILT DEMIN DIFF NRML PSUB .F540 .52 ARE.E340 JE 12051 _ _ . NRML PSUM F541 SPARE F561 (C1206) NRML PSUM F562 CIRC WATER INTAKE PUMP A NRML PSUE F563 CIRC WATER INTAKE PUMP B NRML PSUN F564 CIRC WATER INTAKE PUMP C NRML .

PSun F545 CIRC WATER INTAKE PUMP D NRML PSUR F566 CIRC WATER INTAKE PUMP A NRML PSua F547 CIRC WATER INTARE PUM? 8 NRML PSUN F546 CIRC WATER IN1AKE PUMP C NRML

. PSUA F569 CIRC WATER INTAKE PUMP D NRML PSUR F570 CONDENSATE PUMP A NRML PSUM F571 CONDENSATE PUMP B NRML PSUR F572 CONDENSATE PUMP C NRML PSUN F573 CONDENSATE PUMP A MRML PSUN F574 CONDENSATE PUMP b NRML PSUN F575 CONDENSATE PUMP C NRML i

PSUN F576 COND BOOSTER PUMP A NRML PSUN F577 COND BOOSTER PUMP 8 NRML PSUP. F57C COND B0OSTER PUMP C NRML PSun FU7? COND B0OSTER PUMP A NRML PSUA F580 COND B00 STER PUMP C NRML PSUA F501 COND B0OSTER PUMP C NRML PSUn F582 HEATER DRAIN PUMP A NRML PSUR F583 HEATER DRAIN PUMP B NRML PSun F594 HEATER DRAIN PUMP C NRML PSUR F585 NEATER DRAIN PUMP A NRML PSuf F586 NEATER DRAIN PUMP B NRML l

, \

PSUE F587 HEATEFORAIN ' PUMP C NRML ~

PSUE F588 CW DISCH PUMP A NRML PSUR F589 CU DISCH PUMP B NR ML-PSU'E F590 CW DISCH PUMP C NRML

.PSUN F591 CW DISCH PUMP D NRML ePSup F592 CW DISCH PUMP A NRML IPSUR F593 CW DISCH PUMP B NRML IPSUN F584 CW DISCH PUMP C NRML iPSUR F595 CW DISCH PUMP D NRML

!PSUA F596 CW PUMP A LUBE WATER NRML IPSUR F597 CW PUMP B LUSE WATCt NRML

'PSUN F598 CW PUMP C LUBE WATEt NRML PSUR F599 CW PUMP D LUBE WATER NRML PSUN F600 CW DISCH P 2A LUBE WATER NRML PSUN F601 CW DISCH P 28 LUBE WATER NRML PSUR F6D2 CW DISCH P 2C LUBE WATER NRML

, PSUR F603 CW DISCH P 2D LU8E MATER NPML PSUR F604 CW DISCH PUMP D MTR TEMP NO2R PSUR F6D5 COND PUMP A STATV4 ON PSUR F606 COND PUMP B STATUS ON ALM F607 COND PUhr C STATUS OFF

' PSUR F608 ESOP RUNNING N0 4 ALM F609 COND B0OSTER PP A STATUS OFF PSUE F610 COND B0OSTER PP B STATUS ON PSOE F611 COND 800 STER PP C STATUS ON ALM F612 HD PUMP A STATUS OFF i PSUR F613 HD PUMP O STATUS ON ALN. G500 STAT C00L INLET FLOW LOW t

PSUA G501 STAT COOL TANK LEVEL NRML '

p PSUR G502 STAT COOL INLET PRESS NRML l nu nt PSUM G505 GEN LIGUID DETECT LEvLL l PSUA C504 7.XC LIGUID DETECT LEVEL NRML j NRML PSOE G505 IEN H2 SAS PRESS HIGH l

PSun G506 UEN K2 GAS PRESS LOM. . . PRNL -

[ PSUR G507 SEAL CIL VAC TANK LEVEL NRML

+

NRML PSUR G508 SEAL CIL VAC TK LEVEL PSUR C509 SEAL OIL LIG DETECT LVL NRML NRML PSUA G510 H2 SEAL OIL DIFF PRESS i N0 PSUE GS11 TU HTRS 1A-2A OUT SERU NO PSUR C512 FW HTRS 1F-2S OUT SERV i

PSUn G513 COND STORAGE TANK LEVEL NRML

" PSUR G514 COND STORACE TANE LEVEL NRML

! NRML PSUR G513 EXCTTER C00L FLOW NRML PSUN G516 STATOR COOL TANK LEVEL PSUN G517 GEN PCB SACKUP RELATING NRML RSET PSUA G518 LOSS OF COOL TRIP CKT TRIP ALM G519 CORE SPRAY PUMP B TRIr AL'M L500 RHR SERU WTR PUMP A TRIP ALM L501 RHR SERV WTR PUMP R TRIP I ALM L502 RHR SERV WTR PUMP C TRIP ALM L503 RHR SERV WTR TUMP 0

' I d ,

-;1: _. 2*, - - - . - - ~? L_ = ~ ~~ :_ , ::S_Ns, h 55,, ,

?,? -.

E- .

(!

. . 'l U-e.

hl 1:P l l

PSUA L504 FIRE ? UMP NRML FEED NRML PSUR L505 FIRE PUMP ALT FEED NRML h PSUA LSUo DIESEL GEN 1 GROUND PSUR L507 DIESEL GEN O GROUND PRML NRML f-l PSUN L508 DIESEL GEN 3 GROUND NRML II PSUA L509 DIESEL GEN 4 GROUND NRML $g PSUN L510 CONV HDR SERV WTR PUMP A.NRML PSLN L511 CONV HDR SERV WTR PUMP P NRML p PSUM L510 CONV HDR SERV WTR PUMP C NRML p ,

PSUA LS13 NUC HDR SERV WTR PUMP A NRML (; ,

ALM L514 NUC HDR SERV WTR PUMP B TRIP i PSUR L515 CONV HOR SERV WTR PUMP A NRML I PSUM L516 CONU HDR SERV WTR PUMP S NRML r i PSUR L517 CONU HDR SERV WTR PUMD C NRML h PSUR L51B CONV HDR SERV WTR PUMP A NRML  ;

~

PSUR L519 CONU HDF EERV WTR PUMP U NRML [

PSUR L5:3 CONV HDR SERV WTR PUMP C NRML E PSUR L521 NUC HDR SERV WTR PUMk A NRfil k PSUh L"J".2

. NUO HDR SERV WTR PURP E NRML ,

PSUN L5:3 NUC HDR SERV WTR PURP A NRML i PSUA L524 NUC HDR SERV UTR PUdP S NRML i PSUN L525 SERV SLDG SANITARY TK LV NRML g. ,

PSUR L526 SEWAGE SYSTEM NRML E PSUR L527 CW DISCH PUMP A MTt TEMP NORM ALM L52D RFP TURBINE A TRIP RESET NO l

{J PSUN L529 RFP TURBINE & TRIP RESET YES t PSUf! L520 DW C00L 6 BLOWER STATUf. ON -

7 PSU8 L531 DW COOL C BLOWEF STATU!i DN .

PSUR L532 DW COOL C ELOWEF STAlUS ON .

E-PSUN L532 DW COOL D BLOWER STATUS ON

• PSUA L600 BOTH RFP TURETHE RESET NO k'.

PSUR L401 ALL COND PUMPS OFF NO PSUR L600 ALL COND 800 STER PP OFF NO '

PSUR. L603 REACTOR SCRAPd CH A + B RSET __

~

PSUR L604 GENERATOR ON-LINE: NO PSUR L605 COMM A/COMM S CROSSTIED NO PSut T500 HYD FLUID TANK LEVEL NRML /

PSUN T501 H)D FLUID SUPPLY PRESS NRML I PSUN T502 ERG OIL SUPPLY HDR FRES5 NRML I PSUM T503 CW DISCH PUMP C ATF TEMP NORn j t

k i

3 1

3 4

l s r .

4 s - _- ___ _ _ _

APPENDIX E Figure 2 NSS DEMAND TRIP LOG t

l i

l t

i

?

f t

i l

i f

l

i

. APPENDIX E

. . . FIGURE 2 .

NSS DEMAND TRIP LOG *

.. -. . .~.... . . . . . . . . . .. ....a.

C .

_ . . . _ .. ,. .._____. __.._ ~ . . . .. ..,... _ .__

C l C 110400 NEs Co m 0 Terr L0s

- ~ " ' ~ ~ ~ ~ " ~ ~

TDE 8000 9059 C140 9017 8018 C158 C159 8033 50'41 7017 C 110259 0.2 0.2 -2.3 0.13 -4.30 0.18 -0.24 184.7 0.21 14.7 110300 0.2 0.2 -2.3 0.14 -4.34 0.18 -0.15 184.8 0.21 14.7 .

110301 0.2 0.2 -2.3 0.12 -4.13 0.18 -0.11 184.8 0.21 14.9

~ ~ ~ " ~ ~ ~

C 110302 0.2 0.2 -2.3 0.13 -4.27 0.10 -0.21 184.7 0.21 14.?

~

110303 0.2 0.2 -2.3 0.13 -4.33 0.18 -0.15 104.8 0.21 14.7 '~ ' ~ " ~ ~ ~ "

l 110304 0.2 ( O.2 -2.3 0.12 -4.41 0.18 -0.15 154.8 0.21 14.9 C 110305 0.2 0.2 -2.3 0.14 -4.50 0.10 -0.18 184.7 0.21 14.9 110304 0.2 0.2 -2.3 0.14 -4.47 0.18 -0.11 184.8 0.21 14.9 110307 0.2 0.2 -2.3 0.13 -4.47 0.10 -0.15 1 64.8 0.21 14.9

~ ~ ~ ~

~~'

C 11030s 0.2 0.2 -2.3 0.13 -4.25 0.1s -0.21 1s4.s 0.21 14.9 110309 0.2 0.2 -2.3 0.14 -4.30 0.18 -0.24 184.8 0.21 14.9

, 110315 0.2 0.2 -2.3 'O.14 -4.27 0.18 -0.18 184.8 0.21 14.7'~~~ ~ ~~ ~

l' C 110311 0.2 0.2 -2.3 0.14 -4.44 0.1s -0.24 1s4.s 0.a 14.?

110312 0.2 0.2 -2.3 0.14 -4.41 0.18 -0.21 154.8 0.21 14.9 ~ ' ~ ~ ~ ~ ~ ~

110313 u.2 0.2 -2.3 0.14 -4.30 0.18 -0.11 184.8 0.21 14.9

~

C 11o314 0.2 0.2 -2.3 0.14 -4.27 0.1s -0.11 184.s 0.21 14.7 (

~

110315 0.2 0.2 -2.3 0.14 -3.?? 0.18 -0.24 184.s 0.21 14.7 ~ ' ~ '

110314" 'O.2 0.2 -2.3 0.14 -4.19 0.18 -0.19( 184.8 0.21 '14.7 C 11 o317 - 0.2 0.2 -2.3 0.14 -4.44 0.1s -0.15 1s4.7 0.21 14.9 i

~~~

110318 0.2 0.2 -2.3 0.14 -4.34 0.18 -0.21 184.0 0.21 14.? *~

"'~

110319 0.2 0.2 -2.3 0.14 -4.30 0.18 -0.11 184.8 0.21 14.? l C 110320 0.2 0.2 -2.3 0.14 -4.44 0.1s -0.24 1s4.8 0.21 14.7 -

110321 0.2 0.2 -2.3 0.14 -4.34 0.18 -0.21 184.8 0.21 14.7 i

7 10322 * 'O.2 0.2 -2.3 0.14 -4.30 0.10 -il.24 194.5 0.21 14.7

" ~ ~

l C 110323 0.2 0; -2.3 0.14 -4.30 0.1s -0.15 1s4.s 0.21 14.7 , - .

l _,,,,11 0324 0.2 0.2 ,-2.3 0.14 -4.22 0.18 -0.15 184.8 0.21 14.7 . . _ ,

110325 0.2 0.2 -2.3 0.14 -4.39 0.18 -0.24 184.8 0.21 14.7 C 11 o324 0.2 0.2 -2.3 0.14 -4.47 0.18 -0.11 1s4.s 0.21 14.9 ..

_ _110327 .,, 0.2 0.2 -2.3 0.14 -4.36 0.18 -0.21 184.0 0.21 14.7 *

• 11032s 0.2 0.2 -2.3 0.14 -4.37 0.18 -0.11' 184.0 0.21 14.7

• C 110329 0.2( 0.2 -2.3 0.14 -4.34 0.is -0.te 1e4.s 0.21 .14.7

_,_110330 0.2 , 0.2 -2.3 0.14 -4.44 0.18 -Oi15 184.8 0.21 ,14.7 _ ___

110331 0.2 0.2 -2.3 0.14 -4.37 0.18 -0.15 184.8 0.21 14.9 C 110332 0.2 0.2 -2.3 0.14 -4.37 0.1s -o.24 1s4.s 0.21 14.9 s' 110333 0.2 0.2 -2.3 0.14 -4.44 0.18 -0.11 104.8 0.21 14.7 ~

110334'~~~ 0.2 ~ 0.2 -2.3 0.14 -4.30 0.18 -0.18 184.8 0.21 ' 14.7 .

Q 110335 0.2 0.2 -2.3 0.14 -4.33 0.18 -0.24 184.8 0.21 14.f -

i 110334 0.2 0.2 -2.3 0.14 -4.47 0.18 - 0.21 184.s 0.21 14.7 110337 ' ' O.2

• 0.2 -2.3' O.14 -4.44 0.18 -0.15 184.8 0.21 14.9

' ~ ~ ~ ~

O '

11033s O.2 c.2 -2.3. O.14 -4.44 0.1s -0.1s 184.s 0.21 14.7 .

110339~ ~

0.2 0.2 -2.3 0.14 -4.47 0.18 -0.21 ~184.8 0.21 14.? ~ ~ ' " ~

110340 0.2' ~ 0.2 -2.3 0.14 -4.34 0.18 -0.15 194.7 .0.21 '14.f O 11 o341 0.2 .O.2 -2.3 0.14. -4.34 0.1s -0.fo 184.s 0.21 14.9 1.10342 _,_O.2. , 0.2 -2.3 0.14 -4.34 0.10 -0.24 184.8 0.21 14.7 , . , , _ , , ,

110343 0.2 0.2 -2.3 0.14 -4.41 0.18 -0.11 184.8 0.21 14.9 C 110344- 0.2 0.2 -2.3 0.12 -4.33 0.1s -c.11 184.s 0.21 14.9

,_,_11034)., 0.2 .

0.2 -2.3 0.14 -4.25 0.18 -0.18 184.s 0.21.. 14.C 110344 ' O.2 0.2 -2.3 0.14 -4.30 0.18 -0.24 194.8 0.21 14.?

C 110347 0.2 0.2 -2.3'.0.14 -4.22 0.1e -0.1s 1e4.s 0.21 14.9 110349 ~~

0.2 ~

0.2 -2.3 0.14 -4.47 0.18 -0.21 184.8 0.21 -14.9 ~~ ~ ~ ' '

11 0349 0.2 0.2 -2.3 0.14 -4.53 0.18 -0.15 134.3 0.21 14.f Ce , 110351 0.2 0.2 -2.3 0.14 ' -4.44 0.13 -0.21 184.8 0.21 14.7

~

110331 0.2 0.2 -2.3 0.14 -4.39 0.13 -0.18 154.8 0.21 14.9 -

,110352 0.2~ 0.2 -2.3 0.14.-4.44 'O.18 - 0.21 184.8 0.21 14.7 * ~

.. 110353 0.2 0.2 -2.3 0.14 -4.44 0.18 -C.24 144.8 0.21 14.9 .

,f _110354, 0.2 0.2 -2.3 . ' t.14 -4.44 0.18 -0.15 _184_.s _0.2t_. 14.f ._ _ , , ,_

\ *

\

. . = . . -- -

e *

....._a.____....____,...__._......._.__

~

U T 115ZD3_SSUM 8000. APRM A. FLUX.LEts rpgg ,

- *0 11703 SSLM 8059 GR058 GENERATOR PWR MW C

11704 SSUM C160 RX PRESSURE 1 SEC SCAN 1 04_SSUM.B017_RX.C0RE PRESS..DIFf_ PSID 1 1705 SSUN B018 RX TOTAL CORE FL0 MLB/HR 1l11705 SSUM C158 RX FW FLOW A 1 SEC SCAN- .,

o itL1706_SSult C159..RX.FW. FLOW. 8 1 SEC_ SCAN 111706 SSUM 8033 REACTOR WATER LEVEL INCH 111707 SSLM 8041 TOTAL STEAM FLOW MLBhR 11120Z_SSUM.J01Z IURR.JHR0_T.TLE_P_RESSURE

,.7. ,:

h.. c. :..,;.

..,..-:a ,;, ., .. . . c. . . . - .

.c

. r . s_w, . -:.. .--

. _ . . 3

.- V. -s.. . -

..  ! ,' m. ,.>-- c.. . ,w ~ . . ..:

.,

• a- ,,$,.

, , , c. .

,. .c: 4- *

. ,. - .__,,,~ >

y ; .

. . I' .

, %' ~ ~'

• a- "s y . j . .:. . ... . .

j @*

.'* ' ?

• y,.. s .

J v 4,>,

• t 'p'$m

..y.e-;*.. .. .,

• a a

'. v. n f*. v + .

.. ; . 3 -';

.. ,c: s.,.: Q;.,y...:. s..<

- i:i.,'M '.:p I. u :, ,c, q . - h N..  ?.

• .s<

.s . . , :. . . , ,

. . . . , . . , r.s. y:.., ,

..s : ~~ ,

. i .

l l t

.s. . -- .>i..;....

. . *;, ~.4 c c, :  ?..'k '. 3

, 4[ . .,. - ..

[v . . ..-

. , .- ., a

. . . . .  ; .. .: . . . , c._ -

s .

. E. . . - .. - . - - - . _ . - _ , . _ . _ . . _ . - . -

/ .J -

. l

• 1

.. e lQ l -

~

1 .,

l l

I APPENDIX E Figure 3 B0P LOG y .-.-,. -. - - - .

1 APPENULX To -

io o o o

~ ~

e e.o .

o e o o e. e e a a * ' .' ' .'

BOP LOG 11llg i Bl5 *i l

.I e a a

, i, ,

i r c 11 1 1

. 1 I

i - -=

11 I '

l'E.ell l 1

. .o l

1 i  ! lit-l i ,

j g ill I !

! E l l11 j : j ill i !

~"

- g ei=il i .

. l!i!! i 1 I al lI lli!! !

I li bill i .

iii l i

~

!' 111 lI ill -I l i j il g

. . 111 -

a -

! inil :

l Iijer !

liiee i

! . ill t i -

! E- ll! i l l,ii s i

- o i  !;- 5 til I I iji s i

!! iii > I ilI !

d l

.! 1 in i1 si -

i i ce

i In a

3: Iils .s .n 1 1 r o -

s 0 ,il l i I, CL 5ll 1 1 s

=

E a ill 1 1 lIs i

@g 1lili i i1

<l l

ll! 11 .

1 ,

i

$.0 c. o o 8

o , , , . , ,

8 1

, ,- ,z

.:. = -- -_

I

.s a n .. .. .. .. .. .o <. .. .. .. . . . .. . ,

, ,~

l If , i g

,g It

• i N I!!lt i j

'*

• I

$}$!  !

l

• I I !!!!! $

l g i a >i  ! ,.hl.D 3

2

, - a j *i i

i= *

, 11-1 1!

I i.

~ '

~

i 11 jl 1 p

• i .. ..

~

illil ! .

[Il! > l Gil' 8 l11121 !l!l 1 l i4 I I .

i!*

i i 1.

Ill i I -

i! !'ir l .

< 11 j i 2 E

llh i .

!!! I i

~

,  ! l!* !

iii i ! .

8  !!!! * !

I!! > i '!:l! >!

l j!!l i  !:l!- !

l l

ljil 1 ini!- I I I. . I I o e e a . . . . . . . . . n,. . . . . s s <

\ s

1. y,- -

. . . . . . . . . . . . . . s ( t t t.

, 1i1111 ! .

~

g Einlii !

I is!"! " > .I E

l$!!! 5 E i'!! - I

, g !i! i !

!  ! :lj!!* !

! j [!Ia i i !ll!!* !

M E  ! Iu 'I! .

ill

• i g

!an  ! - I il'e i t

Isl s i l .sll

• I iHi mi!* !

! n -

mij ! ! ssi!* !

j l ~ '

1 liii i i  ; Ilii > !

g !!! e i slil

• i jj irl - i ,

• !il

• i

!! 11 1 1 sIl

• I i

e i!! - i mii> i b

l mi!* I ti

~

in 1 1 j ija!

• I la II sji! * !

t

,- y s i *[i! * !

l-to . . . . a. . . . m. e e e. _ e_ * * * . o , 0 . . o . ..c

o . . . . . o o . . . . .

o . . . , , e , ,

in *  ! Il j i a

! llll I ira .

are - ! isili I .

h ni ! -

tilli I.

y ses

• i i

1111 ] !

I

~

in *  ! .

! j!

s i t!= *. ! mijl

• i E

sus *  ! , ll .* I '

3a , e -

in .

~.

st i:

its *  ! .

l i

! s 3:e ,

5 g as2i}l3 i s et s.i,

=g-in.

I it.* .

14in!.

i> =

3 I=='ga?

= i r sus , a s E it hyt,l ip s' l

I sua > "=

a *

~

Ihj!.!i gp s

sin > I E i,!I!.I!.!

.,i .

sus ,  ;

n.

.!!!!:~

ya .

3= , !

~

sin i  ! i!= > !

pin i I i!=

• i

g. ) ,

g!

b . . . , s. . . -. . . . .

. 2

.,=.*_*.z_ __s._.

• * * *

• yos.=r. *. . . w. _ * **=;***. .

-_==-.=ha= . . . .

%._* .qg-=* _ ,,

l APPENDIX E Figure 4 COMPOSED POINTS (Non-Limit Checked Calculated Values)

APPENDIX E PIGURE 4

. CostPOSED POINTS FSfC250Tlat0TFLOCORFACTOR l

PStst C251 SPEC VOL THR0 FLO FT3/LB-1 l PSINt-C252-4GT-T4490TTt.E-PRES ---PSIAi:* l PSUB C253 SPARE

{

pguR-C254-9PMC - - - - -

PSUN C255 SPARE PSUll C256 SPARE De P9tNI C257-SPAftE - --

f5t!N C258 SPARE PSUN C259 SPARC PSUN C260-TIME-BPAN - - SWt IPSUN C261 GEN LOSS MIN H2 PRES MW iPSUE C262 DIF NYDR0 GEN PRES PSI lPSUN-C263-MIN-NYDROSEN PRES - PSI IPSUN C264 THROT FLO FR CURV MLB/HR IPSUE C265 SPARE PSUM-C266-SPARE ----- -

PSUE C267 SPARE PSUR C248 SPARE fSUN -C269-SPARE --

PSUE C270 SAT STM ENTNALPY BTWLB PSull C271 SAT WTR ENTHALPY BTWLB PSull-C272-MN-STN MOIST CONTENT -

PSUB C273 RX FW LP A AVG TEMP DEGF PSUM C274 RX FW LP 8 AV6 TEMP DEGF -

PSUE C275 SP ARE ---- -- - -- -

D PSUN C276 SPARE D PSUR C277 RX FW PRESSURE PSIA PSUI C278 RX FW A ENTHALPY BTWLS PSUN C27F RX FW 5 ENTHALPY BTWLB PSUR C280 NO OF GOOD YALUES IN SUN PSull-C281-SPARE -

PSUN C282 RWCU INLET TEMP DEGF

'PSUN C283 RWCU OUTLET TEMP DEGF PSUli-C284 RUCU IN ENTNLPY- BTU /LB PSUfi C285 RWCU OUT ENTHLPY gTU/LB

, PSUE C286 NEAT ADD COND PP 8TWHR PSull@7-NEAT-ADD-COND SP -3TWHR

f8UM-C288 ilEAT-ADD FU PUMPS STU/HR iPSUM C289 SPARE i

IPSUM C290 SPARE PSUN C2944 PARE - - - , - - - - - -

PSUR C292 SPARE PSUR C293 SPARE PSUR C294-SPARE- -

l 1

PSUR C295 SPARE PSUR C296 SPARE PSUN-C297-SPARC - --

PSUN C298 SPARE PSUR C299 SPARE PSulH!300 SPARC - - - - -

PSUN C301 SPARE PSUR C302 SPARE -*

PSUR-CSOC-SPARC -

PSUR C304 1/ARE PSUN C305 srARE -

PSUR-C306-SPARC - ---

PSUR C307 SPARE

PSUR C30S SPARE PSUR-C309-SPAiitE --- -

PSUN C310 PCNT CHNGE HT RATE (

PSUM C311 COND SACE PRESSURE IN.HG

'fSW-C3te-tH-9E9f9M-TEAM-9fFF-DESF -

iPSUN C313 SPARE

'PSUh C314 SPARE fSUR-C315-SPARC

-PSUN C316 SPARE PSUN C317 E RH ACT TERM DIFF DEGF

-PSUlF C318-U RH ACT TERM DIFF DEGF PSUR C319 SPARE

• l PSUR C320 SPARE PSUR- C321- SPARE - -

PSUR C322 SPARE

PSUM C323 SPARE .

LPSUR-C324 SPARE --- - -

PSUR C325 SPARE iPSUN C326 SPARE l PSUR- C327-E-RH-INLET-STM -TEMP- DEGF tPSUN C328 N RH INLET STM TEMP DEGF 8PSUR C329 SPARE

~

~~

-PSUR-C330 5fhRE --

~'

PSUR C331 SPARE PSUN C332 SPARE

- -PSUR C333 SPARE - - - - - - --

i PSUll C334 SPf.RE PSUR C335 SPARE PSUR C336 SPARE -3 PSUN C337 E RH CS0VR STM TEMP DEGF

'PSUR C338 U RH CS0VR STM TEMP DEGF i -PSUR- C339- SPARE- -- - -

i PSUlf C340 SPARE i

PSUR C341 SPARE

.PSUR C342 SPARE --- ---- --

PSull C343 SPARE PSUR C344 SPARE "

i

/ ' -PSUN C345 SPARE--- -- --- -

'PSUN C346 SPARE PSUR C347 SPARE

~

( g{ =, - - - - * + * -. . - - - -

f9UM-C948 CTC -

PSUN C349 SPARE PSUR C350 COND A-N CW T RISE DEGF

@SUR-C384-COND-44-CW-T -R ISE --4EGF.

IPSUR C352 COND 9-N CW T RISE DE8F l IPSUN -v COND B-S CW T RIEE DEGF j

1. SUN-C354-COND *-M -CW-0UT T- DEGF PSUR C355 COND A-5 CW OUT T DEGF PSUR C356 COND B-N CW OUT T DEGF PSU5-C357-COND-8-S-CW-00T--T-CEGF PSUE C358 COND A-N CW INLET T DEGF PSUR C359 COND A-S CW INLET T DEGF PSUE -C360 - COND-8-N -CW - INLET--T -DEGF.

PSUR C361 TOND B-S CW INLET T DEGF

!PSUE C342 COND A-N BACK PRESS PSIA JPSUR-C363 -C05-A-S-8 ACE-PRESS-PSIA PSUE C364 COND B-N SACK PRESS PSIA PSUE C345 COND 9-S BACK PRESS PSIA PSUE-C366-COND-A-N-TEMP- ----DEGF PSUR C367 COND A-S TEMP DEGF lPSUN C368 COND B-N TEMP DEGF lPSU5-C369-COND-84 3EMP DEGF lPSUN C37D COND A-N SRTST TDIF DEGF

~

PSUE C371 COND A-5 SRTET 7 TF'DEGF~

P9UR - ,a G Z ; % 47 7 TCIT M C~

PSUR C373 COND B-S GRTST TDIF DEGF PSUR C374 COND A-N LEAST TDIF DEGF j PStRH!975-COND-A-S-TEAS T--Y DIF-MSF-PSUE C374 COND I-N LEAST TDIF DEGF PSUR C377 COND 8-S LEAST TDIF DEGF PSUR-C978 SPECMUNE-CW FT3/LS PSUE C379 COND TU8E CW TEMP DEGF PSUE C380 COND CW OUTLET TEN? DEGF PSUN-C30t-COND CW-IHt.ET--TEMPP DEGF ,

PSUR C382 INTAKE CANAL AVG TERP PSUE C383 DISCNARGE CANAL AVG TE M

- PSUR-CB844ISC-INTAK-DEL-AYS TEM.

PSUE C385 SPARE

PSUN C386 SPARE PSUR-C387-SPARE --

PSUE C388 SPARE -

PSOE C389 SPARE l

PSUR-C390-SPARE - - - - -

PSUN C391 SPARE PSUE C392 FW NTR 3A STATUS DEGF ,

P6UE-C993-FW NTR -4A-STATUS -- DEGF ,

PSUR C394 SPARE PSUR C395 SPARE P2UR C396 SPALC - -

i PSUR C397 SPARE PSUR C398 FW NTR 38 STATUS DEGF l

' PSUR -C399- FW NTR -48 STATUS -- DEGF PSUR C400 SPARE PSUR C401 SPARE ,

PSUR - C402 SP ARE - - - -- - -

PSUR C403 SPARE PSUR C404 SPARE i

PSUR C405 SPARE --- --- ---

l PSUE C406 SPARE I PSUE C407 SPARE -

l \

i -

l PSUM-C408-SPATE --- -- ---

PSUE C409 SPARE PSUE C41D SPARE

-PSUN -C411-SPARE -- - - -

PSUE C412 SPARE PSUN C413 SPARE PSUN-C414 FW NTR-1A EXT STM T DEGF

,PSUM C415 FW NTR 2A EXT STM T DEGF PSUE C416 FW NTR 3A EXT STM T DEGF PSUR-G417-FW-NTR -44 EXT STM T DEGF PSUReC418 FW NTR 5A EXT STM T DEGF PSUM C419 SPARE D PSUN-C420 FW -NTR-4E EXY STN T DEGF PSUN C421 FW NTR 28 EXT STM T DEGF PSUN C422 FW NTR 38 EXT STM T DEGF PSUE C423-FW NTR -48 EXT-STM- T DEGF PSUR C424 FW NTR 58 EXT STM T DEGF

PSUN C425 PERCENT CORE AV6 XENON PSUN-C426-TINE LAST P1 RAN-- HHMM PSUM C427 TIME LAST P2 RAN F#iMM PSUR C428 DATE LAST P2 RAN MMDD f6UM C429 SPARE- -

PSUR C43D SPARE PSUE C431 E MOISTURE SEP DP PSID PSUR-C432-9-M6fST = 2 % 7-CT ^SIG -

IPSUN C433 GROSS GEN DURING DT MWH PSUE C434 GROSS GEN DURING Nt MWH PSOE-C435-SPARC - - - -

.PSUE C436 UAT ENER8Y CONSUN/DT MWH--

,PSUN C437 UAT ENER6Y CONSUN/Nt MWH PSUVt438 CBT-ENERBY CONSUN/DI MWH PSUN C439 CET ENERGY CONSUM/NR MWN PSUR C440 SAT ENERBY CONSUN/DI MWH PSUN-C441-SAT-ENER8Y-CONSUM/Nt MWH .

PSUN C442 SPARE PSUN C443 SPARE ,

PSUN-C444 -SPARE. - - - - - - - -

PSUN C445 SPARE PSUN C446 CPARE

.PSUE C447-SPARC - - - - - - - - - - -

PSUE C448 SPARE PSUE C449 SPARE fSUN-C450-COMP ON -LINE-DAILY -- HR PSUN C451 COMP ON LINE M mt,Y HR PSUN C452 DAILY LOAD FACTOR

-PSUE C453 GROSS-SENRTION DAILT MWH PSUN C454 UNIT TIME ON LINE/D HR PSUR C455 MAX NR GEN RATE / DAILY MW PSUN C456 MONTNLY LOAD FACTOR PSUN C457 GROSS GEN MONTHLY NWH PSUN C458 UNIT TIME ON LINE/M HR t PSUR C459 MAX NR SEN RATE /MTHLY MW PSUN C440 DAILY CAPCTT FACTOR ~

- PSUN C461 MTHLY CAPCTY FACTOR

-PSUM C462 DAILY USE-FACTOR PSUM C463 ELAPSED TIME DAILY HR FSUR C464 MTHLY USE FACTOR

-PSUN C465 ELAPSED TIME MTHLY NR s

PSUN C466 DAILY SERVICE FACTOR r PSUN C467 MONTHLY SERVICE FACTOR

'k g

i o=w w m z_ _ : ..m 4. m_ ,z = . - . - _ - . - ._.- . . . _. --- a _m=- -

4

+

APPENDIX E Figure 5 ANALOG POINTS AND LIMIT CHECKED CALCULATED VALUES (All points which have entries in Table I) l

l Appendix E Figure 5 Analog Points PSUN A000 LPRM 20-05 FLUX A 8/CM2 IPSUM A001 LPRM 20-05 FLUX 8 W/CM2 IPSUN A002 LPRM 20-05 FLUX C W/CM2 .

JPSUM A003 LPRM 20-05 FLUX D W/CM2 lPSUM A004 LPRM ES-05 FLUX A W/CN2

!PliUM A005 LPRM 28-05 F. LUX E_.W/CN2 fPSUN A004 LPRM 28-05 FLUX C W/CM2 1

'PSUM A007 LPRM 28-05 FLUX D W/CM2 PSUN A000 LPRM 34-05 FLUX A W/CM2 PSUN A009 LPRM 36-05 FLUX B N/CM2 PSUM A010 LPRM 36-05 FLUX C W/CM2 PSUM A011.LPRM 36-05 FLUX D.. W/CM2 PSUN A012 LPRM 12-13 FLUX A W/CM2 PSUM A013 LPRt[ 12-13 FLUX 5 W/CR2

.PSUM A014 LPRM 12d3. FLUX C W/CM2 PSUM A015 LPRM 12-13 FLUX D W/CM2 PSUM A014 LPRM 20-13 FLUX A W/CH2

.PSUM_AG1LLPRM 20_13.ELUX. B. . W/CM2 PSUM A018 LPRN 20-43 FLUX C W/CM2 PSUN A019 LPRM 20-13 FLUX D W/CM2

.PSUM. A020. LPRM 28-13. FLUX A W/CH2 PSUM A021 LPRM 28-13 FLUX S W/CM2 PSUM A022 LPRM 28-13 FLUX C W/CM2 PSUN A023.LPRM 28-13.. FLUX D W/CM2 .

- PSUM A024 LPRM 34-13 FLUX A W/CM2 PSUM A025 LPRM 36-13 FLUX 8 W/CM2 PSUN A026 LPRM 36-13. FLUX C W/CM2 PSUM A027 LPRM 34-13 FLUX D W/CM2 PSUM A028 LPRM 44-13 FLUX A W/CM2 PSUM A029 LPRM 44-13 FLUX M 7CM2 PSUM A030 LPRN 44-13 WLUX C W/CM2 PSUM A031.LPRM.44d3 FLUX. O._ W/CM2 PSUM A032 LPRM 04-21 FLUX A W/CM2

• PSUN A033 LPRM 04-21 FLUX 8 W/CM2 PSUM A034 LPRM 04-21 FLUX C W/CH2 PSUN A035 LPEN 04-21 FLUX 0 W/CM2

' PSUM 40?4 LPRM 12-21 FLUX A N/CM2 PSUN A037 LPRM 12-21 FLUX 8 W/CM2 PSUM A03S LPRM 12-21 FLUX C W/CH2 PSUN A039 LPRM 12-21 FLUX D W/CM2

' PSUN. A040 LPRN 20-21 FLUX A W/CM2 PSUN A041 LPRM 20-21 FLUX 8 W/CM2 PSUM A042 LPRM 20-21 FLUX C W/CM2 l

F L _.. _ . _

- . ~ _e - - -

--- ^ = -- '

-' = -

. ..___ _ . . . -- - . . _ . - . -_= . . .. - .._ . -- . -

1 1

l PENI A043 LPRfL20-R1.J. LUX..D.. W/CM2

' PSUM-2044'LPRM 2D-21 FLUX A W/CM2 fauM A045 LPRM 2D-21 FLUX B

• W/CM2 tsutLA044._LPRM' 2s-et FLUX .C. W/CM2_

PSUM A047 LPRM 29-21 FLUX D W/CM2

'PSUN A048 LPRM 34-21 FLUX A W/CM2 18U!L. 404' LP_R8L3':21_ FLUX _s W/CM2 IPSUM A050 LPRM 36-21 FLUX C W/CM2 IPSUM A051 LPRM 36-21 FLUX D W/CM2 lESUN, A052..LPRfL44: 21 FLUX, A_ W/CM2 l

IPSUM A053 LPRM 44-21 FLUX B W/CM2 IPSUM A054 LPRM 44-21 FLUX C W/CH2 l TSutL4055_LPRM M-2.1 FLUK. D... W/CM2

'PSUM A056 LPRM 04-29 FLUX A W/CM2

'P8UM A057 LPRM 04-29 FLUX B W/CH2 P.SutLA058_LPRN_DA-2f_ FLUX C. 8/CM2 PSUM A059 LPRM 04-29 FLUX D W/CH2.

PSUM A060 LPRM 12-29 FLUX A W/CM2

.ESufL9041 LPRMJ2_-29 FLUX _3__W/CH2_

i ~

PSUM A042 LPRM 12-29 FLUX C W/CM2 PSUM A043 LPRM 12-29 FLUX D W/CM2 -

PSUM.A044 LPRM 20-2? FLUX A W/CM2 PSUM A045 LPRM 20-29 FLUX B W/CM2 PSUM A064 LPEN 20-29 FLUX C W/CM2

.250fL6067_.LPRM_RD .29_ FLUX..D.._W/CR2

.FSUM A048 LPRM 20-29 FLUX A W/CM2 PSUM A049 LPRM 29-29 FLUX B W/CM2' fAutLA070._Lf'.R_tLaS:29_ILUX_ C._.. /CM2 PSUM A071 LPRM 28-29 FLUX D W/CM2 PSUN 4072 LPRM 34-29 FLUX A N/CM2 f_ SUM _ A073 LPRM_34.-29 FL_UX_.9__W/CM2, PSUN A074 LPRM 34-29 FLUX C W/CH2 PSUM A075 LPRM 34-29 FLUX D W/CM2 PSUff._A076 .LPR21._4&-29_ FLUX A .. W/CM2, PSUM A077 LPRM 44-29 FLUX B U/CH2 PSUM A078 LPRM 44-29 FLUX C W/CM2 fSUM. .A077. LPRM_.4_4-29.. FLUX _D_ W/CM2

'PSUM A080 LPRM 04-37 FLDX A . W/CM2

~

PSUM A081 LPRM 04-37 FLUX B W/CM2 *

.PSUM A082..LPRM,04-37. FLUX C. W/CM2

-. PSUM A083 LPRM 04-37 FLUX D W/CM2

- PSUM A084 LPRM 12-37 FLUX A N/CM2

.PSUE_ A085 LPRM_12-37._ FLUX _B_ 5/CM2_

PSUM A084 LPRM 12-37 FLUX C W/CM2 PSUM A087 LPRM 12-37 FLUX 0 W/CM2 PSUM ADS 8123)L2Q-JZJ1UUL.WCfgl PSUM A089 LPRM 20-37 FLUX 3 W/CM2

'PSUM 4090 LPRM 20-37 FLUX C W/CM2 PSUM_A091_LPRM 20-37. FLUX D W/CM2 ,

PSUE A092 LPRM 29-37 FLUX A N/CM2 '

PSUM A093 LPRM 20-37 FLUX 8 U/CM2 f(UM A0!i AP.RM 28-37 FLUX C _W /TM.'

o' .

e g .'-v- w w , - - w--=nw-~ w

-- + . . _

y,y, , , , ' . - -,

g y ---r--- --,y9y-_g.9 w

y g. y -- ,_,,_,,, - -

,-,-.,-..p -, ._- ,,,,- -,_.--,w-,,&.--,

, .- -we , ,. - --- -- ------i

. . l l

l PSun A075 LPRM 28-37 FLUX D W/ car" PSUM A096 LPfM t 36-37 FLUX A W/CM2 l 151N1.4097 LP.?Ma s:27_.ELUX 5__.WICH2._ '

'PSUN AOfB LPRM '36-37 FLUX C W/CM2

PSUM A0ff LPRM 34-37 FLUX D W/CM2 .

Mun Mful tPRn__44-3Z ELUX .A W/CM2_

'PSUM A101 LPRM 44-37 FLUX B W/CM2'

'PSUM A102 LPRM 44-37 FLUX C W/CM2 PSUM_A101.LEAM_.44-3Z FLUX..D W/CM2_.

PSUN A104 LPRM 12-45 FLUX A N/CM2 PSUM. A105 LPRM 12-45 FLUX B W/CM2 PSUM_A106.LPRM.12-45. FLUX.C _W/CR2 PSUM A107 LPRM 12-45 FLUX B W/CM2 PSUN A10B LPRM 20-45 FLUX A W/CM2 18UtLA1Df_.LP.RM_20-45_ FLUX .p_W/CM2._

PSUM A110 LPRM 20-45 FLUX C W/CM2 PSUM A111 LPRM 20-45 FLUX 0 W/CM2 ESUK_A112_LRRK_26:45. FLUX A W/CM2 PSUM A113 LPRM 23-45 FLUX B W/CM2 PSUM A114 LPRM 23-45 FLUX C' W/CM2 ,

PSUM.A115_LPRM.23:45. FLUX D W/CM2._

PSUM A116 LPRM 36-45 FLUX A W/CM2 PSUM A117 LPRM 36-45 FLUX B W/CM2 PSUM_A113.LPRN.34:45 FLUX C W/CH2..

PSUM A119 LPRM 36-45 FLUX 0 B/CH2 PSUM A120 LPRM 44-45 FLUX A W/CM2 PSUM_A121 LPRM 44 _45 FLUX B. . W/CH2_.

PSUM A122 LPRM 44-45 FLUX C W/CH2 PSUM A123 LPRM 44-45 FLUX D W/CM2 PSUN A124.BUARD BED D1 TEMP. _

PSUM A126 CHRC0AL ADSB BED D3 TEMP

• PSUM A127 CHRC0AL ADSB B C D4 TEMP PSUM.A_128.CHRC0Ak ADSW BED D5. TEMP _

PSUM A129 CHRC0AL ADSB BED D6 TEMP PSUM B000 APRM A FLUX LEVEL 2PWR

• PSUM.B001..APRM B FLUX LEVEL. ZPWR.

PSUM B002 APRM C FLUX LEVEL 2PUR PSUM B003 APRM D FLUX LEVEL ZPWR f.SIM_8004. At'?M. E_ FLUX LEVEL _. . %PWR .

PSUM S005 APRt3 F FLUX LEVEL ZFUR IMSR 8006 SPARE u DEL. 3007. SPARE' _. ._ . . .

n DEL B008 SPARE DEL B009 SPARE .

DEL 3010 SPARE. . ... ..

l PSUN B011 TIP A FLUX LEVEL ZPWR PSUM 3012 TIP B FLUX LEVEL %PWR PSUM 3013 TIP C FLUX LEVEL 2PWR PSUM B014 TIP D FLUX LEVEL IPWR

, DEL B015 SPARE l

.CCUT B016 REACTOR PRESSURE .. PSIG PSUM 3017 RX CORE PRESS DIFF PSID HIGH B013 RX TOTAL CORE FLO MLB/HR DEL __BQif SP.ARE - -- --

h

1 l

PSUN 9020 CRD SYSTEM FLOW MLB/HR DEL 8021 SPARE f.EWL3022_RK_EW_L90P_. A.ELOW. ML8 /HR _ s PSUR 3023 RX FW LOOP 3 FLOW MLB/Mt i PSUM 3024 RUCU SYS FLOW A MLB/HR ,

.PSutt.3025.RWCU STL FL48.5. _.MLB/HR l

DEL 8024 SPARE IDEL B027 SPARE .

IDEL__B028_SPARr .,

j IDEL 3029 SPARE

• lOEL 8030 SPARE (F.SutL5031_RECIRC_PF_ MTR. 4. PWR MW IPSUM 3032 RECIRC PP MTR B PWR MW IPSUM 3033 REACTOR WATER LEVEL INCH l DEL _.503k_ SPARE ,____

IDEL B035 SPARE IDEL B034 SPARE 1

!PSUM 3037 RECIR LP A1 DR FL MLB/HR

'PSUM 8038 RECIR LP A2 DR FL MLB/HR PSUM B039 RECIR LP B1 DR FL MLB/HR i

PSUM 8040 RECIR LP,82,DR,,FL ML8/NR PSUM B041 TOTAL STEAM FLOW ML8/NR DEL B042 SPARE del,,__5043 SPARE ___,..,_ ,

DEL 8044 SPARE DEL 8045 SPARE DEL __8044, SPARE , _ _ _ _ .

PSUN 8047 RUCU SYS INLT TEMP DEGF. , _ _

. PSUN B048 RWCU SYS OUTL TEMP DESF DEL _ 3049 SPARE _ . . _ . _

PSUM B050 RX FW INLET A1 TEMP DESF_ . .

PSUN B051 RX FW INLET A2 TEMP DEGF PSUN B052_.RX.FW INLET 81. TEMP DEGF__

PSUM 8053 RX FW INLET 82 TEMP DEGF DEL 8054 3054.SEE COMPUTER ENGINR ,

PSUN B055.RECIRC A1,INLT TEMP DEGF PSUM 3056 RECIRC A2 INLT TEMP DEGF PSUM 8057 RECIRC B1 INLT TEMP DESF FSUM.,8058_RECIRt; B2.INLT, TEMP _DEGr l

? SUN 5059 GROSS BENERATOR PWR MW ,

PSUM 3040 A06 CLR COND OUTLET TEMP )

DEL, 3061.A0G SYS DISCH RAD-LOG UC 1 DEL 2062 SPARE 0-160 M9 l DEL ED63 SPARE D-160 MV DEL _,8064 SPARE 0-160 MV PSUM C000 TOTAL RX FW FLOW MLB/HR PSUM C001 CRD SYSTEM FLOW ML8/HR PSUN C002 MAIN STEAM FLOW ML8/NR PSUN C003 INST REACTOR PWR LVL I PSUM C004 COND DUMP FLOW MLS/HR PSUM_CC05.RWCU_ TOTAL FLOW MLB/HR PSUR Cfl04 HOTWELL MAREUP FL MLB/HR PSUM C007 MAREUP FLOW RE0 ML8/HR .

PSUN C008 SPARE,. .,

1. , PSUM C009 TURB THROTTLE FLO MLB/HR PSUM C010 CORR THROTTLE _F,L,0,_MLB/_HR , ,

e r ______,,,,,,,,,,__,,,____,,,,,,,,,_,_,L ,, ,_ _ ____,. _ __ _ _,__ _ ,._,__, _ ,,____ _ __,,,_, . _ _ _ , , _ , , . , _ _ _ _ , , , , ,, _ _ _ .

. l e

(

PSU

~~ '_M__C011 TOTAL RECI.RC FL9W MLB/HR_ _.

PSUM CD12 RX RECIR LP A FLO MLS/NR PSUN CD13 RX RECIR LP E FLO MLS/HR

- pem rm a are A m etram rra m n/ g ,

~

IPSUM CD'15 RFP 5 SUCTION FLO MLBTHR

%SUNC016FWRECIRCTOCONDMLB/HR lEB1NLCo.1Z_D6LEL@R .DR TK. FL MLB/HR.,

IPSUM C018 09 E4UIP DR TK FL MLS/HR IPSUM C019 SPARE F. SUM _CO20_ UNIT _SROSS POWER.___ M.,

'PSUM CO21 UNIT AUX XFMR PUR AW

'PSUM CO22 START-UP XFMR PWR M ESUM_CO23.CASWELL BCH..Xf'P9t.PWR. NW_

PSUM CO24 DIESEL SEN POWER MW PSUM CO25 AVG AUX LOAD MW PSUM.CO26 AVG NET LOAD . MW PSUM CO27 GEN APPARENT POWER MVA PSUM CO2S P2 CORE AVE EXP MWD /T PSUM CO2?_ POWER. FACTOR _.___.. ..

PSUM C030 GEN DYNAMIC LOSSES MW PSUM C031 TOTAL GEN LOSSES MW PSUM CO32.RECIRC. PUMP POWER. MW.

CCUT C033 INST TOT U2 AUX LOAD MW PSUN C034 AUX ENERGT CONSUM/HR MWH PSUM:.CO35. NET _ ENERGY GEN /HR _ . MWH ,

PSUM C034 NET SEN TO SWYD/Hf MWH PSUM C037 SPARE PSUM C038 SPARE -- _ . _. . _ _ .

{ PSUN C039 SPARE

• l PSUM C040 MAIN STM ENTHALPY BTU /LB PSUM.C041_RX.FN. ENTHALPY _ BTU /LB

! PSUM C042 AVG RX FW TEMP DESF l PSUN C043 CRD ENTHALPY BTU /LO PSUM_C044.RWCU HEAT. LOSS M8TU/HR PSUM C045 DUMP WATER ENTLPY BTU /LB

' PSUM C046 HT ADD BY PUMPS M8TU/NR fSutLC047._HLLOSS TO.RBCCW MeTU/HE_

PSUN C048 MN STM HEAT FLOW BTU /HR PSUM C049 RX FU HEAT FLOW MBTU/HR PSUM C050 CR0 NEAT FLOW. M8TU/NR PSUM C051 R P 2A SEAL LEAKAGE GPM PSUM C052 2A SEAL STAGING FLOW GPM PSUM C053 R P 28 SEAL LEARAGE GPM l LOW C054 29 SEAL STAGING FLOW GPM PSUN C055 CW DIFFERENTIAL TEMP.

PSUM C056 SPARE _..__ .. .

PSUM C057 SPARE PSUM CD58 SPARE PSUM_. CD59. .SP ARE_ ,_ .

PSUM C060 REACTOR CAPACITY MLB/NR PSUM C061 HT ADD WORK FLUD MBTU/HR PSUM C042 NSS.SYS HT LOSS MBTU/HR l' .

s

n. _ _ _._w- - _n .--e . ...mg_.- -

- - - - -c- -

PSUM C063 NES SYSTM HT ADD MBTU/HR

'PSUM C064 REACTOR POWER LEVEL MW 2SMM C0&5. MSS..STS.. EFFICIENCY X.

PSUN C066 AVERAGE APRM Z'PWR .

PSUN C067 CALC REACTOR PUR LYL X

.PSUM._C0&f_AY TEMP., AT_90..ELEV. X.. 07.

PSUN C070 AV TEMP 70-80'ELEV X .03 PSUM C071 AV TEMP 28-45 ELEY X .47

,P_5UfLC072. AV_. TEMP 10__23. ELEV..X. 1f.

, PSUM C073 AV TEMP ( 5 ELEV X .24 l

PSUM C075 HT ADO TURO LOOP MSTU/NR PSUN .CD7A. BER_IHER._MI RATE _EIll/IMH IPSUM C077 COR TURO HT RATE STU/KWH

'PSUM C078 E REHEATER PERF DEGF

.PSUfL.C079.W.REHEATIR. PERI" .. DEGF.

PSUM C080 SPARE PSUM C081 SPARE PSUN CD82. SPARE . .. --.

'PSUM C083 SPARE

'PSUM C084 SPARE

.PSUM..C085_ SPARE _ _ . _ . ..

PSUM C084 SPARE PSUM C087 SPARE -

_FSUM_CO8S SPARE --- . . ... . . .

PSUM C089 SPARE PSUM C090 NEAT REJ 70 COND M87U/HR

.ESUN C091.CW TEMP RISE. _ __. DEGr_

- PSUM C092 COND SETST TEMP DIF DE8F PSUN C093 C0HO LEAST TEMP DIF DE8F l

.PSUM C094 LOG MEAN TEMP DIFF DE6F ,

PSUM C095 ACT HT XFER COEFFICIENT -

PSUM C096 COND CU VELOCITT FT/SEC

.PSUM C097 HEI HEAT XFER RATE, . _ , .

-PSUM C098 CLEANLINESS FACTOR PSUM C099 AVG HOTWELL TEMP DE8F

_PSuM.C100 SPARE. __. - _ ___. .

IPSUM C101 SPARE

..euw c ne esim_e

• -WW w Tww WT TT FT

' ESUM_C103. SP ARE

-PSUM C104 SPARE

.PSUM C105 FW HTR 1A TEMP RISE DE8F

' PSUM C106 FW HTR 2A TEMP RISE DEGF PSUN C107 FW HTR 3A TEMP RISE DE6F PSUM C108 FW HTR 4A TEMP RISE DEGF PSUM_C109 FW HTR.5A TEMP _ RISE.DEGF i

PSUM C110 SPARE PSUM C111 FW HTR 18 TEMP RISE DE8F

!PSUM C112 FW HTR 28 TEMP RISE DE6F

'PSUN C113 FW HTR 38 TEMP RISE DEGF PSUM C114 FW HTR 48 TEMP RISE DE6F

, _P._ SUM 1_C 15_FW NTR,58 TEMP _ RISE..DEGF.

PSUN C116 SPARE l

l l s

t IPSUM C117 DCut 14 TEMP RISE DEGF TSUN C118 DCLR 13 TERP_R.ISE__DE8F_,_ i

.PSUM C119 SPARE . .

PSUM C120 SPARE

.2 9M C121 _SP.ARE

'PSUM C122 SPARE.

'PSUM C123 SPARE .

PSUfLC124 SPARE ___

PSUM C125 9 PARE

!PSUM C124 SPARE =

lES.UM_C127_ SPARE IPSUN C128 SPARE IPSUM D129 FW NTR 1A TERM DIFF DEGF -

280tLG130fW_HTR._2A__ TERM. DIFF D.ESF__,

IPSUM C131 FW NTR 3A TERM DIFF DESF

!PSUM C132 FM NTR 4A TERM DIFF DE6F TSull.C.1.33 FW HTR

_ SA TER_M_DIFF DEG_F,,_

'PSUM C134 SPARE

'PSUM C135 FW NTR 18 TERM DIFF DE8F PEUM c12A FW MTR 73 TrtM .nIFF DFEF -

PSUN C137 FW NTR 38 TERM DIFF DE6F PSUM C138'FW NTR 48 TERM DIFF DFGF

_P_SUfLC.13'Id MTR,j5%_TERfl DIF.f_DE8F _

PSUM C140 SPARE' j PSUM C141 SPARE PSUM C142. SPARE _ _ _ _

PSUM C143 SPARE PSUM C144 SPARE PSUM C145 SPARE _.__ . . . _ . . ,

PSUM C144 SPARE PSUM C147 SPARE PSUM.C148 SPARE _.__._. .. . _

PSUM C149 SPARE PSUM C150 SPARE FSUM.C151. SPARE _ _ _ . _ _ . . _

PSUM C152 SPARE PSUN C153 SPARE -

rSuM Cis4 SPARE..._ __.. _.

PSUM C155 DRN COOL (.P DIF 3A DEGF

'PSUN C154 DRN COOL AP DIF 4A DEGF

.PSUM C157 DRN COOL AP.DIF.5A DE8F PSUM C158 RX FW FLOW A 1 SEC SCAN PSUM C159 RX FW FLOW 8 i SEC SCAN PSUM C1&D RX PRESSURE 1.SEC SCAN-PSUN C161 DRN COOL AP DIF 38 DE6F PSUM C162 DRN COOL AP DIF 48 DEGF

'PSUN C163 DRW COOL AP DIF 58 DEGF PSUM C164 SPARE .

i PSUN C165 SPARE i

l 'PSUM C146 SPARE _ . . . ..

PSUM C167 SPARE PSUN C148 SPARE

/ .

?

a . - .

= . _ .. _

t ..

1

~

.ESUM.f149 SEur .

PSUM C170 SPARE ,

.PSUN C171 SPARE LPSUILCJZ2 SPARr -

iPSUM C173 SPARE IPSUN C174 SPARE -

{P.SutLC1Z5_ SPARE lPSUM C174 MCIST SEP REF DP PSI PSUM C177 E MOIST SEP PERFORM PSI (PSUM.C178..W. MOIST.SEP. PERFORM PSI (INVO C179 SRV F013A OPENING COUNT .

!INSR C187 SRV F013J OPENING COUNT

',P. SUM._,C1.9p__ UNIT _ SRS. HT R ATE B TU/KWH

'PSUN C191 UNIT NET NT RATE BTU /NWN

'PSUM C192 PERCENT AUX LOAD 1

.ESUM_C193 tP_A..NEATUP RATE DE8F/NR P30M C194 RPV HEATUP RATE DED F/NR PSUM C195 RX TEMP HEATUP DEG F/NR ESUM_C196_ SPARE __

PSUM C197 SPARE PSUM C199 FEEDUATER WAV(1) MLBH PSUM.C199. FEEDWATER WAV(2). MLSH DEL E000 SPARE 10-50 MA .

DEL E001 SPARE 10-50 Md PSUM.EQO2. BUS.25_ VOLTAGE PSUN E003 BUS 23 CURRENT PsuM E004 BUS 2r LOAD 1 DEL._E005_SFARLD-JMLILV DEL E004 SPARE 0-160 MV PSUM E007 BUS 2C VOLT 48E PSUM E008 BUS.2C CURRENT..

PSUM ED09 BUS 2C t.043 PSUM E010 SPARE (0-80 MV)

PSUM.E011 SPARE.(0280 MV)_ ... ..

PSUN E012 BUS 20 VOLTAGE PSUM E013 $US 20 CURRENT ESUM E014_ BUS JD. LOAD _ . _ .__

PSUM E015 230FV FEEDER 27 LOA 0

' PSUM E016 230kV FEEDER 27 REACTIVE

. PSUM_E017 230KV FEEDER 28 LOAD

\

l PSUN E018 230KV FEEDER 28 REACTIVE l -

PSUN E019 230KV FEECER 30 LOAD PSUM E020 230KV FEEDER 30 REACTIVE l

j PSUM E021 230KV FEEDER 31 LOAD PSUM E022 230KV FEEDER 31 REACTIVE PSUM E023 MN XFMR PH A WINDING T PSUM E024 MN.XFMR PH B WINDING T

, PSUM E025 MN XFMR PH C WINDING T P. SUM.E024.UAT WINDING H TEMP.,

l - PSLH EC27 UAT WINDING X TEMP l - PSUM EC28 UAT WINCING T TEMP PSUM E029 SAT WINDING X TEMP.,,

p '

!  ! ~

d -

\ .s

~~~

r

'PSUM EU30 SAT WINDING T TEMP PSUM E031 CASWELL SEACH XFMR WND T LLR4. E032,_ DIE _SE_L ,6.ENER A708.,1_ LOAD -

'PSUM E033 DIESEL W NERATOR 2 LOAO PSUM E034 DIESEL SENERATOR 3 LOAD l_fSuff_E035_ DIESEL SENERATOR 4 LOAD _

lPSUM E034 COMMON SUS B VOLTAGE

]PSUN E037 COMMON BUS B CURRENT ifjlE_ EMS _G98M0#_ BUS )_. LOAD IPSUM E03P ENER8 BUS E1 VOLTAGE iPSUM E040 ENERG BUS E2 VOLTAGE

!PSuM.E041_ENER8. BUS._E3_ VOLTAGE

!PSUM E042 EMERS BUS E4 VOLTAGE

!PSUN E043 DIESEL SENERATOR 1 V0LTS

'f_MN._Xp44 D_LESKL_6ENERATOR_. 2_ VOLTS _,_

'PSUM E045 DIESEL SENERATOR 3 VOLTS

!PSUM E044 DIESEL 8ENERATOR 4 V0LTS LPSUM E047,,230KV_ FEEDER __27. V0LTAGE PSUN E048 230KV FEEDER 28 VOLTAGE PSUM E049 230KV FEEDER 30 VOLTAGE EIGH_E050__230KV, FEEDER 31 V0LTAGE____

PSUN E051 23OKV SUS 2A VOLTAGE PSUN E052 230KV BUS 28 VOLTAGE PSUM_E053_. SPARE ._ , .. _ . _

PSUM E054 EPARE DEL E055 LEAK RATE TEST DW PT # 1

.Q[k__E054 LEAK RATE TEST DW PT'N 2 DEL E057 LEAK RATE TEST DW PT N 3 DEL E058 LEAK RATE TEST DW PT # 4 .

JSUM_.E059. SPARE RTD JR4) ,, ...

PSUN E040 TEST PT JET PMP XHTRS IN_

DEL E041 LEAK RATE TEST DW PT # 5

,OEL_ E042_ LEAK _ RATE TEST DW PT W 6_

DEL E043 LEAK RATE TEST DW PT N 7 PSUN E044 SPARE MV SIGNAL 0-140 PMM FDa$.JigI)LIURRINE. SP.EEaJ>f_

PSUM ED66 SPARE LOW LEVEL MV CCUT F000 COND A-N H0TW BISCH TEMP

_CCUT F001__COND A-S HOTW DISCH TEMP CCUT F002 COND 8-N HOTW DISCH TEMP

, CCUT F003 COND B-S HOTW DISCH TEMP

'PSUM F004 COND PUMP DISCH HDR TEMP PSUN F005 COND TO DEMIN/FILT TEMP DEL F006 F006.SEE COMPUTER ENGINR PSUM F007 DRN CLR.1A COND IN TEMP.

CCUT F008 FW HTR 1A COND IN TEMP CCUT F009 FW HTR 1A COND 007 TEMP CCUT.F010.FW HTR 2A COND OUT TEMP..

PSUM F011 DEN CLR 18 COND IN TEMP CCUT F012 FW HTR il COND IN TEMP

.CCUT F013 FW HTR 18 COND OUT TEMP CCUT F014 Fl( HTR 28 COND OUT TEMP l

.c -

• - -o

~

t CCUT F015 FWI RTR .35'i 0ND TR T MP CCUT_F014_EW_HTR_J4_COND.DUT_ TEMP _

CCUT F017 FW NTR 36 CONO IN TEMP' .

CCUT F018 FW HTR 38 C080 007 TEMP CCUT M9 EM_HIL4A EW_IN_ TEMP CCUT F020 FW NTA 4A FW OUT TEMP Cuff F021 FW NTR SA FW OUT TEMP CCUT.FD22.FW_HTR.48.FW.IN TEMF...._.

CCUT F023 FW NTR 48 FW 0UTLET TEMP CCUT F024 FW NTR 58 FW OUTLET TEMP PSUN.ED21.RFP_A..SUCTIOK. FLOW _.

PSUM F024 RFP 9 SUCTION FLOW PSUN FOR7 FW NTR 1A SHELL PRESS ,

f812LE028 EU.. HTA._18_SHELL. PRESS PSUN F029 FW NTR 2A EHELL PRESS PSUN F030 FW NTR 28 SHELL PRESS ESUfLED31_FW_.HTR 3A_SHELL PRESS PSUN F032 FW HTR 38 SHELL PRESS '

PSUN F033 FW HTR 4A SHELL PRESS ESUN F034.FW HTR 48 SHELL PRESS PSUM F035 FW HTR 5A SHELL PRESS PSUN F036 FW HTR 58 SHELL PRESS SAD _ F037 FW.HTR_2A PRN.OUT. TEMP.._

SAD F038 FW HTR 1A DRN OUT TEMP PSUM F039 DRN CL.t '!A DRN OUT TEMP PSUN.F040.FW HTR.28 ORN OUT TEMP __

i PSUM F041 FW HTR 18 DRN CUT TEMP PSUN F042 DRN CLR 18 DRM OUT TEMP

.PSUN,F043.FW HTR 5A,DRN OUT. TEMP,,.

PSUN F044 FW HTR 4A DRN OUT TEMP

• PSUM F045 FW HTR 3A DRM OUT TEMP PSUM F046 FW HTR 58 DRN 007. TEMP PSUN F047 FW HTR 48 DRN OUT TEMP PSUN F048 FW HTR 38 DEN 007 TEMP.

I SAD F049 HOTWELL MAKEUP FL ML8/HR PSUN F050 COND A-N CIRC UTR INLET PSUN F051 COND A-N CIRC WTR OUTLET PSUN.F052 COND A-S CIRC WTR INLET

' PSUN F053 COND A-S CIRC WTR CUTLET PSUM F054 COND 8-N CIRC WTR INLET

!PSUN.F055 COND B-N CIRC.UTR OUTLET

'PSUM F056 COND 8- S CIRC HTR INLET

'PSUN F057 COND E-S CIRC WTR OUTLET

DEL._EQ58_FD58,SEE COMP #IER ENGINR DEL F059 LEAK RATE TEST (SPARE)

HIGN F060 CONU SW PUNP A STATOR T BAD F061.CONV SW PUMP 8 STATOR T PSUM F062 CONV SW PUMP C STATOR T 8AD F063 NUC SW PUMP A STATOR T .

PSUN F064 NUC SW PUMP S STATOR T PSUN F065 RNR SW PUMP A STATOR T PSUM.F046 RNR SW PUMP 8 STATOR T e .

_,w-w,m,-,,--,,-,,n-_-,_.-,m n m-e ,

- t ,

l

.ESUM N' m nu_PUNIL.E_AIAYod T

-PSUN F048 RNR SW PUNP'D STATOR T ML F049 CW PUNP A STATOR TEMP

.PSUM1070_CW..PunP'_8_ STATOR.. TEMP . __  !

'PSUN F071 CW PUNP C STATOR TEMP PSUN F072 CW PUNP D STAT 4R TEMP

!OEL. F073 SPARE _______._ _ .._ __

PSUN F074 SPARE RTD PSUN F075 SPARE RfD PSUN.F076.. SPARE RTD.__ . ..

PSUN F077 CWe PUNP A STATOR TEMP..

PSUN F078 COMO PUMP 8 STATOR TEMP fputLE079 C0!!D PU!IP_ C STATOR TEMP PSUN F080 COND BSTR PUNP A 5 TAT T iPSUN F091 COND 887R PUNP 8 STAT T f

f 8UN. FOS 2_COND_.85TR_PUNP C STAT T__

i IPSUN F083 NTR DRAIN PUMP A STAT T 1840 F084 NTR DRAIN PUMP 8 STAT T

-  ! PSUM _F085.HTR,. DRAIN _ PUMP _.C,, STAT.T .

'OEL F084 SPARE DEL F087 SPARE DEL _.F088. SPARE RTD.(R4) . . . _ _

CCUT F089 RFPT A OIL FR COOL T CCUT F090 RFFT A ACT TNST BRG T

.CCUT_F091.RFP_T_ A INAC. THST SRG T CCUT F092 RFPT A NP BR6 OIL T CCUT F093 RFPT A LP BRG OIL T

_C_ CUT.,E09.4_ EAST _ MOIST-SEP SHELL - T CCUT FD95 E 1ST STABE RNTE IN TENP

• CCUT F096 W 1ST STAGE RNTR IN TEMP CCUT_F097_ Wi;ST_ MOIST-SEP SHELL -

T..

CCUT F098 E 2ND STAGE RNTR IN TEMP PSUN F099 RFFT 8 OIL FR COOL T '

PSUM.F100 RFPT 8 ACT THST BRG T i

PSUN F101 RFFT 8 INAC TNST BRG T l PSUN F102 RFPT 8 HP BRG OIL T l

' PStfM F103 RFPT 8 LP BRG OIL T PSUM FiO4 M 2ND STAGE RNTR IN TEMP DEL F105 SPARE PSUMJ106_ SPARE __

PSUN F107 SPARE DEL F108 SPARE DEL _ F109 SPARE

DEL F110 SPARE DEL F111 SPARE DEL __F.112. SPARE. . _ , _ . . . _

PSUM F113 TCC NX OUT TEMP PSUM F114 RCC NX OUT TEMP

.PSUM_F115 RFP 8.,LP STM INLET TEMP PSUM F114 RFP 8 HP STM INLET TEMP PSUN F117 RFP A LP STM INLET TERP

.ESutil.D 6._REE .A.l!P. STA. INLEI..TE5P,. .

d *

._. . . , _ _ _ - . . . . . _ . _ . . _ . , . ~ . _ _ _ . _ _ . _ . _ . _ . _ _ _ _ _ _ . _ . . _ _ _ _ . . _ _ , . . . . . . _ - . _ _ . . _ _ . _ , . . . - _

~

IPSUM F119 8 PARE TC/CC

'PSUN F120 SPARE RTD (24) '

Pitt1H F121 MTR DEN Ka PRERS PSIG DEL F122 COND F/D OUTLET UMNOS DEL F123 RUCU DEMIbi A OUT COND

'1 f12.4.RWCU DEMIN 3.007 COND DEL F125 RWCU DEMIN CO*l INL COND PSUN F126 TEST PT JET PMP XHTRS IN m F12Z_ LEAK..AATE TEST _ TEMP _#3 DEL F128 LEAR RATE TEST TEMP # 5 DEL F129 LEAR RATE TEST TEMP N 4

. DEL._f_1'lle LEAK _ RATE TENT TEMF N22._

IDEL F131 LEAK RATE TEST TEMP #23 l

5 F132 LEAR RATE TEST TEMP 8,8 Ist F122 LE4E.RA1E.IEST_. TEMP.R_f_ _

l DEL F134 LEAK RATE TEST TEMP N10 lCCUT F135 DRYWELL CLR A-COIL A-T

!CC'4 T_E134. DRYWELL. CLR.. A-C0ZL. 5-T__ ..

!CCUT F137 DRYWELL CLR B-C0IL A-T

'CCUT F138 DRYWELL CLR B-C0IL 8-T CCUT._E13.iLDRYWELL, CLR C-COIL A -T PSUR F140 WEST RN SNELL PRESS l PSUM F141 COND BSTR 28 OIL RETURN PSUM F142 COND BSTE 28 RADIA 5 TC PSUM F943 COND BSTR 28 THRS B TC l PSUM F144 COND SSTR 2C OIL RETURN l ESUN_F_1.45. SPARE TC/CC PSUM F146 SPARE TC/CC PSUM F147 PRI CONTN DIV I EL-90 T RSUM.F148..PRI.CONTN DIV.I EL-75 T__. {

PSUN F149 PRI CONTN DIV I EL-45 T  !

PSUM F150 PRI CONTN DIV I EL-35 T i j RSUM_F_151.PRI CONTX..DIV_I EL-23.T..

PSUM F152 PRI CONTN DIV I EL-15 T PSUM F153 RX'RECIR PUMP A TH BIG T l

PSUM F154.RX RECIR PUMP 8 TH BRG T PSUN F155 COMPUTER ROOM TEMP PSUM F156 COMPUTER INTERNAL TEMP PSUM F157 COND 85TR.2A OIL RETURN __.

PSUN F158 COND ISTR 2A RADIAL 8 TC PSUM F159 COND SSTR 2A TNRS B TC nEL_ F160 LEAK RATE TEST TEMP R19 t

DEL F161 LEAK RATE TEST TEMP N20 DEL F162 LEAK RATE TEST TEMP N21 PSUM G000 GENERATOR VOLTAGE PSUN 6001 GENERATOR CURRENT PH A PSUM U002 SENERATOR CURRENT PH B PSUN 6003 GENERATOR CURRENT PH C DEL G004 SPARE 10-50 MA PSUM G005 GENERATOR MEGAVARS j DEL 6006 SPARE 10-50 MA PSUN G007 GEMi'RATOR FIELD VdLTAGE PSUN 6008 GENERATOR FIELD CURRENT l FSUM G009 STATOR COOLANT INLET T l PSUN 6010 STATOR COOLANT CUTLET T LOW G011 GEN NYDROGEN PRESS i PSUM G012.G H2 NOT GAS 70 CLR A T. I PSUM G013 G H2 HOT GAS TO CLR S T

..-.-a,.....-..-.-.-_--,-.__.-.-.-.-..-. . - . . + -.- -- .- . - - . .

~

l

, lPSUN 9014 8 H2 COLD SAS FR CLR A T g Anne mnmaeeneenav IPSUN 8016 SEN STATOR SLOT 1 TEMP j lPSUN 8017 SEN STATOR SLOT 4 TEMP ,

(PSINLS018. 8EN_ STATOR _ SLOT 7- .. TEMP _.

iPSUM 0019 BEN STATOR SLOT 10 TEMP

!PSDM 0020 SEN 5TATOR SLOT 13 TEMP ffSutL6021_SEN STAT.0R. SLOT.14 TEMP._  ;

'PSUM 8022 GEN COLD NYDRCSEN TEMP PSUN 0023 COLO AIR-DEN COLL TEMP

.PSUIL6024_H0.T_ AIR _-6EN_ COLL TEMP PSUN 6025 EXC ALTERNATOR SLOT 1 T

'PSUM Gota EXC ALTERNATOR SLOT 2 T ,

'PSUM_G027_.EXC. ALTERNATOR SLOT.3 T_

IPSUM GQ8 EXC ALTERNATOR SLOT 4 T 165tL 6029 EXC ALTERNATOR SLOT 5 T

!PSUN G030.EXC. ALTERNATOR SLOT _6.T_

'PSUN 6031 EXC COLD AIR TEMP PSUN 8032 GEN STATOR COOLANT 1 T PSUM GO33 GEN STATOR COOLANT 4 T PSUM 3034 GEN STATOR COOLANT 7 T PSUM GO35 GEN STATOR C0OLANT 10 T fSUM. G036. GEN. . STATOR _ COOLANT._13. T.

PSUM 6037 GEN STATOR COOLANT 16 T LOW S038 6EN FIELD TEMP LRL._6039. STATOR. COOL IN_,UMNOS.. .

PSUM 6040 STATOR COOL 007 UNHOS DEL 0041 LEAK RATE TEST DW PT N 8 DEL __60.42. LEAK, RATE TEST DW PT N.9 PSUM 6043 PUMP A SEAL NX INLET T -

PSUM G044 PUMP A SEAL CCW TEMP

.PSUM SO45. PUMP A. SEAL HX OUTLET. T.

DEL 6044 SPARE (FUTURE-CUTC)

. DEL G047 SPARE (FUTURE-CUTC) i_ DEL,__.G048_ SP AR E_ ( F,UTUR E-CUTC )._

IDEL G049 SPARE (FUTURE-CUTC) iDEL 6050 SPARE LOW LEVEL MV

!.1EI,__G051_ SPARE __(FUT. LOW LEV. MV)

DEL 6052 SPARE (FUT. LOW LEV. MV)

-DEL GC53 SPARE (FUT. LOW LEV. MV)

. del._ G054 SPARE (FUT. LOW LEY. MV)_ .

PSUM LOGO BAROMETRIC PRESS DEL E001 LEAK RATE TEST DW PT W10 DEL _ L003 i.EAK RATE TEST TEMP W13 DEL L304 LEAK RATE TEST TEMP N14 DEL LOO 5 LEAK RATE TEST TEMP #15

. DEL _ LOO 4_LEC' RA7E TEST. TEMP N16_,

DEL LD07 LEAK RATE TEST TEMP N17 DEL LOO 8 LEAK Raft' TEST TEMP #18'

DEL __ LOO 9. TEST _PT JET PMP XMTRS IN PSUM LO10 COND SSTR 2C RADIAL 8 TC

'PSUM LD11 COND ISTR 2C THRUST 8 TC e .

l t

~

PSMN LD_1.R _STEAtl_ CHEST PRESSURE LRL LD42 LEAK RATE TEST TEMP #11 DEL LO43 LEAK RATE TEST TEMP ,R12 DEL LO_4s_ SPARE _.

IDEL LO43 SPARE. .

IDEL LD44 SPARE JEL LD47 SPARE l DEL LO48 LEAK RATE TEST TEMP 824 DEL 1049 SPASE- . . . .

nri_ indn maasr_ -

~'

tiEL LD51 SPARE ~~

PSUM LD53 SPARE (FUTURE RTD-6RND)

_paa LD50.INIAELCANAL. WATEllIEMe__ _

IPsuM LD57 CIRC WTR DISCHARE TEMP

- IPSUM L102 E MSR 2ND STAGE STM PRES

'PStNLL103 W MSR. 2ND.STA6E.STM PRES PEUM L122 DW FLOOR DR TK FL MLI/Ht BAD L123 DU EeUIP DR TK FL MLS/HC.

l PSUfLL125. IHTAKE. CANAL. LEVEL . FT _.

DEL L126 L126 SEE ENSR NOTE S1-1 j PSUN L127 EAST RH SHELL PRESS PSUM_L128 TORUS PRESSURE . . PSIG PSUN L129 STACK EFFL MONTR LOG CPS PSUM S000 SHORT CIRCUIT CH 0 MV l ESUM_S001 10_MV_ REFERENCE CH_0 .MV_

PSUN S002 SHORT CIRCUIT CH 1 MV PSUN S003 10 MV REFERENCE CH 1 MV PSUM S004.T/C REFER JUNCTION DEGF. .

PSUM S005 SHORT CIRCUIT CH 2 MV PSUM S006 10 MV REFERENCE CH 2 MV .

DEL. S007. SPARE.. .. .

CCUT T000 COND A SHELL VACUUM CCUT T001 COND 8 SHELL VACUUM iPSUM.T002 W MOIST SEP TO CIV-1 T. l IPSUM T003 W MOIST SEP TO CIV-2 T PSUM 7004 E M0IST SEP TO CIV-3 T PSutt_T005_E M0IST SEP_T0_CIV-4.T IPSUM T006 1ST STAGE SHELL INNER T IPSUM T007 1ST STAGE SHELL OUTER T

!PSUM T008 HTD FLUID SUPPLT PRESS

'HRL 7D09 H2 PURITT .  %

DEL T010 SPARE (FUTURE-CUTC)

DEL. T012 SPARE.(FUTURE-CUTC). .

DEL T013 SPARE (FUTURE-CUTC)

DEL T014 SPARE (FUTIJRE-CUTC)

DEL T015 SPARE MV SIGNAL 0-160 BAO T016 MAIN STEAM TEMP OEGF CCUT TD17 TUR8 THROTTLE PRESSURE

'CCUT T018 FIRST. STAGE PRESS._ ..

'PSUM T019 E iST STAGE REHEAT PRESS

!PSUN T020 W 1ST STAGE REHEAT PRESS

'PSUM T021 E MCIST SEP OUTLET PRESS i

_ _ _ _ __ _ _. . . .. E

t PSUM T022 W MOIST SEP OUTLET PRESS PSUM WOOO SRG 1 OIL DRAIN TFMP -

ESHff.* WOQ1_BitG._R_0J k DRAIN __ TEMP PSUN N002 3RS 3 OIL DRAIN TEMP PSUM WOO 3 TMRUST SRS FRONT DRN T ESUM_8004_ THRUST 3Rs REAR. DEN T__ ..

IPSUM 9005 BR6 4 OIL DRAIN TEMP lPSUM N006 386 5 OIL ORAIN TEMP l

TSUM WOO 7.8R6_4.0IL DRAIN. TEMP _

'PSUM N008 SRG 7 OIL DRAIN TEMP tPSUM 9009 3R6 8 OIL DRAIN TEMP TSutl.WD10._8RG 9 OIL'. DRAIN TEMP. -

'PSUN WO11 BRG 10 OIL DRAIN TEMP PSUM WO12 TURS LUB OIL FROM COOL T

.tSUM_WO.13_IURq_ W8.OI_k 10..C00LER T PSUN WO14 BR6 1 METAL TEMP ..

PSUN WO15 BRG 2 METAL TEMP f.SINI WD16 Sts-2 MTM Tm - -

PSUM WOf7 BR6 4 METAL TEMP PSUM WO18 BRG 5 METAL TEMP l ?_ SUM.WO1?_BRG_6_ METAL., TEMP _ _ __

l PSUM 8020 BR8 7 METAL TEMP PSUM WC21 3RG 8 METAL TEMP PSUM WO22 BRS.9 METAL TEMP __

PSUM WO23 BR6 10 METAL TEMP PSUN WO24 THRUST BRG FRONT METAL T PSUM WO25.. THRUST BRG REAR METAL T CCUT WO24 HD PUMP A MTR UP SLV 8-T -

CCUT WO27 HD PUMP A MTR L0 SLV 8-T CCUT WO28 HD PUMP A MTR THRUST 8-T PSUM WO29 HD PUMP 8 MTR UP SLV 8-T SAD WO30 HD PUMP 8 MTR L0 SLV 8-T ISUM.WO31._HD. PUMP S NTR. THRUST 8-T.

~PSUM WO32 HD PUMP C MTR UP SLV 8-T PSUM WD33 HD PUMP C MTR L0 SLV 8-T --

PSUM WO34.HD PUMP. C MTR THRUST 8-T PSUM WO35 COND PP A MTR UP SLV 8-T

• PSUM WO34 COND PP A MTR L0 SLV 8-T PSUM WO37.COND.PP A. MTR THRUST 8-T

, PSUN 6038 COND PP 3 MTR UP SLV 8-T PSUM WO39 COND PP S MTR L0 SLV 8-7 PSUM WO40. COND PP 8 MTR THRUST B-T CCUT WO41 COND PP C MTR UP SLV 8-T CCUT WO42 COND PP C MTR L0 SLV 8-T CCUT.WO43.COND ff C MTR THRUST 8-T l CCUT WO44 COND SSTR A MTR IN80 8-T CCUT WO45 COND BSTR A MTR OUT 8- T '

PSUN WO44..COND BSTR S NTR IRBD B-T PSUM WO47 COND BSTR 8 MIR OUT 8-T PSUM WO48 COND BSTR C MTR IN80 3-T PSUM WO49 COND SSTR.C.MTR.0UT._.8-T A

, PSUM WO50 RHR SW PP A MTR IN8D 4-7

. .. . _. .. m t

PSW M 51 RHE SW PP A NTR OUT B-T tatt W0s__g._R_HR SW PP 8_MTR_.IN80_8-T_

PSUM WO53 RM SW PP S NTR OUT 8-T PSUM WO54 RNR SW PP C MTR INSD 8-T ES.UJ_WO55_RNR_SW PP C MTR OUT 8-T.

PSUM WO54 RM SW PP D MTR INSD O-T PSUM WO57 RNR SW PP O MTR OUT 8-T PAD _._WO58_CONV SW PP 6 MTR UP 8-T .

4 5A0 WO59 CONV SW PP A MTR TH 8-T PAD WO60 CONU SW PP A MTR LO 8-T gSUM WO61 C0hV_SW PP_8 MM _UP_8-T_, _

PSUN WO42 CONV SW PP S MTR TM O-T pf!Oh WO43 CONY SW PP 8 MTR LO 8-T ISUMWO44__ CONY __SWPP_C.MTRUP_8-T_ _,

!PSUN N045 COMU SW PP C MTR TH 8-T

'PEUM WD64 CONV SW PP C MTR LO 8-T PSUM WO67 NUC SU PMP A MTR UP 8-T

- ~

l I

PSUM WO48 NUC SW PMP A MTR TES TI-PSUM WO49 NUC SW'PMP A MTR LO 8-T

.P.SW WO70 NUC SW PMP S MTR UP 8-T

. PSUM WO71 NUC SW PMP 3 MTR TH 8-T PSUM WO72 NUC SW PMP 8 MTR LOW 8-T CCir WO73_CTRC WTR_P, A MTR UP_8-T CCifT WO74 CIRC WTR P A MTR TH 8-T i CCUT WO75 CIRC UTR P A MTR LOW 8-T PEuM. un7A IIRc MIL P. 2_ MT.R. Ot-1 ~

PSUM ko77 CIRC UTR P S NTR TH B-T PSUN WO78 CIRC WTR P 8 MTR LOW 8-T t

.fSUN.WO79.. CIRC WTR.P C MTR UP 8-T PSUM 9000 CIRC WTR P C NTR TN 8- T PSUM WO81 CIRC WTR P C MTR LOW B-T

, .PSUN.WOS2. CIRC WTR P D.MTR UP B-T

• PSUN WOS3 CIRC WTR P D MTR TH B-T PSUM WOS4 CIRC WTR P D MTR LOW 8-T HIGH WOS5 PRI.CONTN DIV.II EL-40.T.

PSUM.WOS4 PRI CONTN DIV II EL-2G T

• HIGH WOS7 PRI CONTN DIV II EL-18 7 PSUM WO88 PRI CONTN DIV II EL-10 T I PSUM WO89 BEARING 1 VIBRATION PSUM WO90 SEARING 2 VIBRATION

' PSUM.WO91 GEARING 3_ VI8 RATION PSUN WO92 BEARING 4 VIBRATION PSUM WO93 BEARING 5 VIBRATION -

PSUM WO94 BEARING 6 VISRATION PSUM WO95 SEARING 7 VIBRATION PSUN WO96 BEARING 8 VIBRATION

PSUM.WO97_ BEARING 9 VIBRATION _

PSUM WO98 BEARING 10 VIBRATION PSUM WO99 TUR8 BRG OIL HOR PRESS CCUT W100 DRTWELL CLR C-C0IL 8-T CCUT W101 DRYWELL CLR D-COIL A-T RAD W102 DRYWELL CLR D-C0IL R-T I

S.

_y., m. _ - _ _ . _ _ _ _ . . _ _ _ _ _ . - _ _ _ _ _ - _ . _ _ _ _ _ , _m, . .,_, .,..._..,_,_m..r__mm, _-,.-,_me

t

• l 4

' ESlat_W101.QW_ E4MI?_.OR_ILRCC_.0.UT-T PSUN W104 ANALOG TESTING POINT PSUM W105 PRI CONTN DIV I EL-13 T

.ESUPLW104._SURt, P00L_DIV I .e _1.T j - -- PSUN W107 SUPP P0OL CIV I 4-2.T.. . 7 ,

PSUN Br108 SUPP* FOOL H2O DIV I T ESUM.W.109.PRI_CONTN.DIV.II EL-80 T PSUN W110 PRI CONTN DIV II EL-70 DEL W111 SPARE (FUT. LOW LEV. MV)

DEL..W112 SPARE (FUT. LOW LEV. MV)

DEL W113 SPARE (FUT. LOW LEV. MV)

DEL W114 SPARE (FUT. LOW LEV. MV)

.PSUN W115. SUP.P_ POOL DIV II 4-3 L_,_ ;.

PSUM W114 SUPP POOL DIV II e-4 T PSUM W117 SUPP POOL N20 DIV II'T' HRL. W118 PRI CONT EL.90 FT TEMP... .

DEL W119 SPARE CCTC DEL W120 SPARE LOW LEVEL MV

_DE!,_ W121 SPARE LOW LEVEL MV. .... . ..

DEL W122 SPARE LOW LEVEL MY DEL W123 SPARE LOW LEVEL MV DEL W124 SPARE (FUT. LOW LEV. MV)

DEL W125 SPARE (FUT. LOW LEV. MV) w -- ,.= ww.* - ,-.

,___.__,.pm .,.,,.7-_,.rp, n , , ,. y,,, ,_. p..m,,--m,,~, , _ , , . ,,,,. ,. ---p,

APPENDIX F Control Roo:3 Strip Charts

\

l

The following is listing of many of the Control Room strip charts:

1. Recirculation Pump Suction Temperature - O' to 600*F

2. Recirculation Pump Flow A and B - O to 55,000 gpm

3. Total Core Flow Jet Pump - O to 90 million Ib/hr

4. Core Pressure Drop - O to 100% (100% = 30 psid)

5. IRM/APRM power - O to 125%

6. Steam Flow - O to 12 million Ib/hr

7. Feedwater Flow - O to 12 million Ib/hr

8. Reactor Water Level - 150 to 210 inches

9. Reactor Dome Pressure - O to 1200 psi and 800 to 1100 psi

10. RHR Flow - O to 30,000 gpm

11. Post-Accident Reactor Vessel Level - O to 200 inches

12. Drywell Equipment and Floor Drain Sump Flows - O to 125 gpm

13. Main Turbine Eccentricity on Turning Gear - O to 50 divisions (2 mils per division)

14. Cond2nser Condensate Conductivity - O to 10 micro mhos

15. Intake Canal Level - -3 to +19 ft*(Reference Sea Level)

16. Post-Accident Primary Containment Pressure - 5 to 245 psig

17. Discharge Canal Level - +2 to +6 ft (Reference Sea Level)

18. Off-Gas Vent Pipe Radiation Monitor - 101 to 10 13 micro curries per sec and 0 to 100% (linear with range switch)

19. RBCCW Radiation Monitor - 10 1 to 10 ' counts /sec

20. Radwaste Effluent Monitor - 0.1 to 10' counts /sec

21. Reactor Building Vent Monitor - 10 2 to 108mR/hr

22. Drywell Temperatura Recorder - 0* to 400'F (24 points)

23. Torus Level - -10 to +6

-n n, -. . , , - - . . . .-, - - - + - - - , , ,. ..-, -r w

24. Turbine Building and Reactor Building Stack Flow Rate - O to 100 scfm

25. Discharge Canal Temperature - 0' to 130'F

26. Condensate Pump Suction / Discharge Conductivity - O to 100 micro-mhos

27. CP&L System Voltage - O to 300 kV

28. Area Radiation Monitors - 0.wl to 100 mR/hr (multi-point)

29. Continuous Air Monitor - 101 to 10' counts / min

30. Drywell Radiation Monitor - 10 1to 10' counts / min

31. Recirculation Pump Drive Motor Temperature - 0' to 300*F

32. Recirculation Pump Temperature - O' to 300*F

33. RHR Water Temperature - 0* to 600*F and HPCI Turbine Pressure O to 600 psi

34. Main Stack Radiation Monitor - 10' to 107 R/hr

35. Turbine Building Exhaust Vent Radiation Monitors - 10' to 10 7R/hr

36. Drywell/ Torus Hydrogen and Oxygen Concentration

37. Drywell Area High Radiation Monitors

38. Unit Net Megawatts

39. Main Turbine Vibration

40. Reactor Feed Pump Turbine Vibration

41. SRV Tailpipe Temperatures

42. MSIV Radiation Monitors

43. SRM Count Rates

44. Main Turbine and Valve Chest Temperatures

45. Reactor Feed Pump Turbine Temperature

46. Main Turbine Shaft Expansion l

l p - , y - - - . . - . a , - . , , - - - . - , , . . - - . , - -,g-, , - - , ,-v. ,n - - ,, , . ,,,,-, ,-

l APPENDIX G Post-Maintenance Testing Requirement Routing Process J

APPENDIK G (CONT'D) .

to N

R

• No Shift Foreman ISI Performs (

g Review Required I i Prenaintenance

.e frestina YtS M '

If U Shift Forgman Assigne Planner /Analys Attach PHTR, Planner adde '

' &A rz ion

• ISI &, Post i

Written 1 App 11 a le outes FP To FPSG

)*nNa a e et

c- .

, *g Requirement Maint. Test Re% Maintenance j -

• I .g Fogn if i I I Performed FPSG Reviews 8 , ggy WR&A. Adds PMTP I 1 Forwarda To ] q l' Planners (If Maintenance I Appijcable) ~

Foreman Xeron't . $

-4 i Completed WR&A e YES FP 3

& Attaches To $

, 4 a' f

PHTR k.

No m l

! I y- y

SOS VerIjes PMTR >

I w *

. NO Satisfactorily 1I E i 0 FP Completed . PMTR PitTR SOS /SF or Completed, inform i __

j 0-List PHTR C g,. Ir --

designee NO Tech Spec ISI SF Syetem ready '

JL -

Routed Performed Applicable Review for Operation 1 .

i ,g YES FPSC reviews I

j YES. ~

xeroxed WR&A -

! and performs PMTR 4

- ~

1 .

1 e ~

l .*

Tr U 1r

] if Non-Q, requiring I Planner QA NPRD ISI Haintenance I '

- SFReview$I, Q-List, I s Foreman g Review Review Review '

Tech Spec., Review Review Fire Protection Document - --

Non-Q, not requiring SF Review 1

control I

• f . .

APPENDIX G POSTMAINTENANCE TESTING REQUIREMENTS Yes. No Yes Ne WR&A #

ISI- [ [ Tech Spec l[ l[

Q-List _ _ Fire Protection l_ l_

Maintenance (Note 1 and 2)

Completed By .

A. ISI Posttest Requirements (Siraature) SAT UNSAT Date Completed By B. Postmaintenance Test Requirements (Signature) SAT UNSAT Date Planner / Analyst Date Operations

~

Technical Completed By

-C. Specification Required Testing (S*tnature) SAT UNSAT Date I

~

Operations Ctaff Date NOTES: 1. In urgent situations, this will be completed by the STA, SF, and/or SOS, when the Planner / Analyst is not available.

2. The ISI Coordinator is to be contacted if clarity is required.

Testing completed satisfactorily / unsatisfactorily (circle one), and Shift Foreman notified. If unsatisfactorily completed, generate Work Request &

Authorization and record iden:ification number below: -

WR&A #

SOS Date BSEP/Vol. XII/MP-14 29 Rev. 19 f

1

APPENDIX H Vendor Recommendation Processing Routing Diagram O

t 9

! VENDOR RECOMMENDATIONS

5 y /V.R.\

.J Loc \

~ gf

] Performance / File [

Iby

. gtB Reliability Group L p'N lg gf(" l Not #4; EU

- Og Applicable-l3 File j .) ENGINEERING / ONS

( V.R. MEMO l,

/s Not W

N A I

EW / OPER./MAINT.

'd Per f . / Rel.-

3 Groupw OEF I Implement Deviate j l $/

Deviate g p , y ,,

irom V.R. \TNp-?O N omplet Mgr.-Plant N EWR Operations Engineering Operations Maintenance Implement V.R. ,, _

o \f si s sf h

Engr. Supv.

Gen. Mgr.

Perf./Rel.

Croun 1 Perf./Rel. ,, $\ -

ONS U

Perf./Rel. File [

I a: Group 3r Deviation Implementation [

5 g  %/ d Engr. Supv. @

Z -

• d Gen. Mgr. y j

-4 V.P.-Nuclear Onerations M

[V.R' U

, f

'omple t e M S/ Perf./Rel.

\ File / T.ng . EWR Approved A \ \File/ / - L. V.P.-Nuclea, Onerations Group sf Complete l EWR s Perf./Rel. Not Approved -

l Group sr

.R.\

^ s/

Oper./Maint. b Perf./Rel.

Group

ONS 5

1s jo VENLOR RECOMFENDATION ROUTING DIAGRAM

~

b

7 ..

s

)

l 1

I t

1

(

l APPENDIX I Volume XI, Book 2: Q-List r.

" - - - - - - -. - - , _ _ , _ . . _ , _ , _ _ _ -**-'-Www --w+ - -w, - , ,. . . , ,,, _ _

APPENDIX J General Electric Service Information Letters (Review in Accordance with Section 3.1.2)

. w , s. -w - , - - - _ - -- - .- - - -

The following SILs were reviewed for pertinence to the Reactor Protection System;

1. SIL No. 39: General Electric Magne-Blast Air Circuit Breakers

2. SIL No. 44: HFA Relay Coil Life

3. SIL No. 44: Recommended HFA Relay Inspections Supplement No. 1

4. SIL No. 44: Possible Coil Spool (Bobbin) Failures on HEA Relays Supplement No. 2

5. SIL No. 44: Possible HFA Relay Failure Propagation Supplement No. 3

'6. SIL No. 44: HFA Relay Magnetic Coil Assembly Replacement and

{ Supplement No. 4 Relay Adjustments

7. SIL No. 77: Binding of HGA Relay Armature

8. SIL No. 90: Scram Pilot Valves on CRD Hydraulic Control Module

9. SIL No. 128: Maintenance of CRD Scram Filot Valves

10. SIL No. 128: Maintenance of CRD Scram Pilot Valves Revision 1

11. SIL .k 128: Preventative Maintenance for CRD Scram Pilot Valves Revisita '

Supplement No. I

12. SIL No. 128: Preventative Maintenance for CRD Scram Pilot Valves Revision 1

Supplement No. I t Revision 1

13. SIL No. 153: Electrolytic Corrosion of Coils on Pre-1969

- Manufactured HEA, HGA, HKA, and HMA Relays

14. SIL No.-155: Possible Failure of Type SBM Control Switches

15. SIL No. 155: Inspection and Cleaning of General Electric Type SBN Supplement No. 1 Control Switches

16. SIL No. 155: Inspection of General Electric Type SBM Control Supplement No. 2 Switches 4 -

17. SIL No. 217: " Positive Off" Type CR2940 Control Switches

18. SIL No. 229: Improved Contact Arm Retainers for Type CR120A Relays

19. SIL No. 230: Improved Time Delay Relay for ADS

20. SIL No. 230: Improved Time Delay Relay for Core Spray and RHR Supplement No. 1 Systems

21. SIL No. 230: Improved Time Delay Relays for Core Spray, Residual Revision 1 Heat Removal, and Automatic Depressurization Systems

22. SIL No. 230: Improved Time Delay Relays for Core Spray, Residual Revision 2 Heat Removal, and Automatic Depressurization Systems

, 23. SIL No. 308: Inspection of CR105/205D Contactors, CR106/206D Starters, and CR109/209D Reversing Starters

24. SIL No. 332: Relay and Switch Contact Cleaning

25. SIL No. 344: Mode Switch Shutdown Scram Reset Permissive

26. SIL No. 344: Mode Switch Shutdown Scram Reset Permissive Revision 1

27. SIL No. 360: CR2940 Tandem Block Switches

28. SIL No. 384: Connection Failures in Agastat Relay Type CR0095 Bases n

L 0

. .~ . . - - --

l CAKOLINA POWER & LIGHT COMPANY -

BRUNSWICK STEAM ELECTRIC PLANT UNIT 0 Q-LIST VOLUME XI Rev 024 1

Recommended By: -

d 84, i. Date:

4 V--93 Engineering Supprvisor Reviewed By: ' Om Date: GI Quality' Assurance /

Approved By: /h(k]AN@3 Date: $'3C 9 feneraI' Manager

/ T lul,Bj f f.,M;s 78.m u . 0 l !Lu #N _[ 9i

. -c n3, . "[ma i ' ti 'ei J baUNai UII .I t

- - - - , , ,, . .,, .,.,- ,.,,,,,-. . --- en, ,,, , -,n,.. ,,,,.,,,,,.,-,,.----------,--,,,.w- -

Volume XI - Book 2 9 h THIS PROCEDURE HAS NOT BEEN REVISED TO INCORPORATE THE PLANF MODIFICA-TIONS LISTED BELOW. REFER TO SECTION 2 0F THIS PROCEDURE FOR FURTHER INSTRUCTIONS. THIS PAGE IS TO BE INSERTED IN YOUR COPY OF VOLUME XI, BOOK 2 BEHIND THE COVER PAGE AND PREVIOUS LISTINGS REMOVED AND DESTROYED.

THIS LISTING IS UP TO DATE AS OF 6/15/83 .

PLANT PLANT MOD. NO. AFFECTED DRAVINCS MOD. NO. AFFECTED DRAWINGS78-085 D-2020 81-029 D-25021 78-110 D-20020 81-086 D-2040 D-25029 79-231E D-25037 81-099 F.P.-55046 79-231F D-25037 81-213 D-25025 79-231M Dl25037 D-25026 D-70007 79-232S D-2537 D-70029 79-232T D-2537 81-255 D-2268sh.1 D-2269sh.2 79-264 D-72006 82-010 D-2531 79-301 D-25045 D-2569 80-016 .

D-25015 82-224 D-20025 80-030 D-72018 83-024 D-25018 80 036 F-9503 80-078- '

PT01 D-2515 D-7029 80-079-PT01 D-25015 D-70029 i

I i Volume XI Rev. 2 3 s . -, - -

VOLUME XI - BC0K 2 LIST OF EFFECTIVE PAGES Page(s) Revision i 23 11 - v 24 1 22 2 23 3-9 22 10 23 11 - 19 22 20 23 21 - 35 22 36 - 178 24 i

4 I

d t

4 4

11 Volume XI Rev. 24

1 VOLUME XI - BOOK 2 TABLE OF CONTENTS Section Title Page

~

Caution Page i List of Effective Revision by Page 11 Table of Contents lii Procedure .

1 Introduction 1 2 Q-List Proceduro Update 1 3 Q-List Determination Criteria 2 4 Definitions. 6 Table I i 1-B21 Nuclear Boiler System 10 2 2-B21 Nuclear Boiler System 20 3 1-B32 Reactor Coolant Recirculation 30 4 2-B32 Reactor Coolant Racirculation 33 5 1-CAC Containment Atmospheric Control 36 6 2-CAC Containment Atmospheric Control 40 7 1-C0 Condensate System 45 8 2-CO Condensate System 46 9 1-C11 Control Rod Drive System 47 10 2-C12 Control Rod Drive System 49 .

11 1-C32 Feedwater Control System 51 12 2-C32 Feedwater Control System 52 13 1-C41 Standby Liquid Control Sys';em 53 14 2-C41 Standby Liquid Control Syrtem 55 15 1-C51 Neutron Monitoring 57 16 2-C51 Neutron Monitoring 59 17 1-C71 Reactor Protection System 61 18 2-C72 Reactor Protection System 62 19 2-DG Diesel Generator System 63 20 1-D12 Process Radiation Monitoring System 67 ,

l 21 2-D12 Process Radiation Monitoring System 69 22 1-D22 Area Radiation Monitoring 71 23 2-D22 Area Radiation Monitoring 72 24 Electrical Systems (Plant) 73 25- 1-E11 Residual Heat Removal System 75 26 2-E11 Residual Heat Removal System 81 27 ~ 1-E21 Core Spray System 87 28, 2-E21 Core Spray System 89 29 1-E41 High Pressure Coolant Injection System 91 30 2-E41 High Pressure Coolant Injection System 95 31 1-E51 Reactor Core Isolation Cooling System 98 lii Volume XI .

Rev. 2 4 a

. . ~~,

n .,.-_.p..._. .-.a..r ,.nn. , _ . , ,.m_.,,.4v-,,,,e,7,. ._,..,_g.,g., , _ . _ , ~ _ _ . .m-,,,, ,.n.- . , - . , , , , , , , , , , .

l VOLUME XI - BOOK 2 Table I (cont'd)

Section Title Page 32 2-E51 Reactor Core Isolation Cooling System 102 33 2-F0D Fuel Oil Diesel System 105 34 1-G16 Radwaste System Profilter Deep Bed 109 35 G16 Radwaste System Profilter Deep Bed- 110 36 1-G31 Reactor Water Cleanup - Filter Domineralizer 112 i 37 . 2-G31- Reactor Water Cleanup - Filter Domineralizer 114 38 1-G41 Fuel Pool Cooling and Filtering System 116

'39 2-G41 Fuel Pool Cooling and Filtering System 118 40 1-IA Instrument Air System 120 41 2-IA- Instrument Air System 123 42 LO Lube Oil System 126 43 1-MS Main Steam 130

. 44 2-MS Main Steam 131 45 .2-MUD Makeup Domineralizer System 132-

'46 1-0G Off-Gas System 135 47 2-03 Off-Gas System 137 48 1&2 Primary Containment Penetrations 139 49 1 # ';C Reactor Building. Closed Cooling Water 140 50 2 <CC Reactor Building Closed Cooling Water 142

.51 .1-iGT Standby Gas Treatment System 144 52 2 SGT Standby Gas Treatment System 146 53 1*SW Service Water System 148

~54 Service Water System 2-SW 152 55 1-TD Torus Drain and Keep Fill System 156 56 2-TD Torus Drain and Keep Fill System '

157 57 1-VA Ventilation Air System 158 l 58 2-VA Ventilation Air System 160 59 1-X Miscellaneous Instruments 163 60 2-X Miscellaneous Instruments 164 i-Table II Plant Structures 1 Pressure Suppression System 164 2 Reactor Building 164

'. 3' Diesel Generator Building 164 j' 4 Service Water Intake Structure 164 5' . Control Building 165 6 Primary Containment 165

.7 Fuel Pool Refueling System 165 8 Nitrogen and Off-Gas Services Building 166 9 Reactor Vessel Support Pedestals 166

~

iv Volume XI Rev. 24' I

- -,,n ., , , . ,. c,,, ,.,mm-. , , . - -.r,.w.,,,-n-,-,,,,n,r-, -r - p , , , . , - . - - , , , , , - - - , - , . ,

VOLUME XI - BOOK 2 Section Title Page Table III Consumable / Expendable Items 168 l

Appendix A Q-List Drawings 169 l

i

[

y Volume XI l Rev. 24

F I

l i

, VOLUME XI - BOOK 2 '

l

1. Introduction 1.1 This book provides: (a) the general criteria for determining which plant' items are Q-list items, and (b) a detailed listing of the Q-list system boundaries and items (Tables I, II, and III). Within Table I, items common to both units will be listed under Unit No. 2.

1.2 The contents of this book have been developed based on the information contained in the FSAR and the guidance provided by ANS-2.2.

2. Q-List Procedure Update 2.1_ This procedure has been updated to the latest drawing revision levels as listed in Appendix A. However, due to plant modification being declared operable prior to issuance of revised drawings,. there t

will be cases where this procedure does not reflect the current I plant as-built conditions. To assure that users of this procedure ,

I are aware of these cases, a caution page listing the plant modifications and the Appendix A drawings they affect is located f behind the procedure cover sheet. The caution page will be updated and distributed as modifications are declared operable or included in this procedure. Users shall review the caution page in  ;

conjunction with the tables contained in this procedure. If no plant modifications are listed as affecting the drawing referenced ,

in the table, this procedure contains the latest information. If 1 Volume XI Rev. 22

I VOLUME XI - BOOK 2 must be reviewed in conjunction with the table to determine the latest information.

2.2 The Technical Support Unit is responsible for maintenance of this procedure. The Document Control Subunit is responsible for distribution and accountability. These activities will be performed in accordance with the applicable procedures contained in Volume I of the plant Operating Manual.

NOTE: The revision level of the " Caution Page" will change only when the format is revised; it will not change each time a ,

plant modification is added or deleted. This page is included as a " notepad" to provide a standard place to record plant modifications which affect the contents of this procedure.

3. Q-List Plant Item Determination Criteria 3.1 The Q-list plant items for a nuclear power station are those structures, systems and components (of both safety and non-safety systems) whose integrity or reliability is essential in preventing or mitigating the consequences of postulated accidents (i.e.,

limiting plant process conditions) that have the potential of causing injury to the public from substantial levels of radiation or release of substantial quantities of radioactive material from their intended place of confinement within the plant. To qualify as a Q-list plant item, the plant item in question must be necessary to:

.i 2 Volume XI Rev. 23

VOLUME XI - BOOK 2 l l

a. Provide for structural integrity (or be a part) of the reactor coolant pressure boundary, or  !

I

b. Provide overpressure protection of the RCPB, or l

c. Make and hold the reactor subcritical during the occurrence of i i

frequent, infrequent, and limiting p1' ant process conditions, or l

d. Cool the core following normal reactor shutdown and during the occurrence of frequent, infrequent, and limiting plant process conditions, or

e. Cool another safety system component during the occurrence of frequent, infrequent, and limiting plant process conditions, or i

f. Provide essential services to the reactor containment during {

the occurrence of infrequent and limiting plant process condi-i tions, or l

g. Contain, control, or reduce the radioactivity release to the -

environment during the occurrence of frequent, infrequent, and limiting plant process conditions.

3.2 The Q-list contained in Tables I, II, and III clearly defines the structures, consumables/expendables, and the major components (i.e.,

piping, valves, pumps, tanks, vessels, heat exchangers, instruments, motors, etc.) that must be controlled in accordance with the requirements of the Corporate Quality Assurance Program. In case a conflict arises regarding the actual physical boundary of a Q-list component, the information that follows may be used for resolution.

3 Volume XI Rev. 22

VOLUME XI - BOOK 2 ,

3.2.1 Mechanical Components

a. Q-list " fittings" includes all items which form part '

of or are installed in the pressure boundary such as i branch outlet nozzles or nipples; instrument wells; i

. reservoirs; blind flanges, studs and fasteners in flanged joints between pressure parts; traps, strainers , orifices , etc.

b. When a valve, which serves as an interconnection i

between Q-list and non-Q-list components, is welded I on both sides, the weld on each side shall be treated as Q-list.  ; ,

c. All instrument lines and fittings that are tapped off Q-list components are themselves Q-list items:

(1) If they lead to Q-list instruments.

(2,) Up to and including the primary containment outer isolation valve if they lead to non-Q-list

, instruments and are tapped off RCPB components.

I (3) Up to and including the first root valve (from I

the process side) if they lead to non-Q-list ,

i e

instruments.

d. All instrument lines and fittings that are tapped off non-Q-list components and lead to Q-list instruments are themselves Q-list items up to and including the f

first root valve (from the instrument side).

4 Volume XI Rev. 22

VOLUME XI - BOOK 2 3.2.2 Instrumentation and Control Components

a. Instruments, controls, and their interconnecting wiring circuits that provide readouts and alarm functions which are the sole basis for correct manual initiation of nonautomatic safety system functions are Q-list items.

b. Instruments, controls, and circuitry between the process variable (s) sensors and the input terminals of the actuator systems involved in generating ,

signals that initiate automatic safety action are l Q-list items.

NOTE: The actuator system is that equipment which accepts safety system output signals and performs a safety action.

3.2.3 Electrical Components

a. Those circuit elements (such as annunciators, relays, j motors, indicating lights, ammaters, voltmeters, frequency meters, etc.) for safety system components, the failure of which could disable the accomplishment of a safety function, are Q-list items.

b. Circuit elements that are used either for information or analysis only (such as inputs to computer, rod position information circuit elements, etc.) are non-Q-list items.

5 Volume XI Rev. 22

l VOLUME XI - BOOK 2

/

l

c. Power supply and control supply circuit elements whose failure actuates the affected safety system (or its portions) in such a way as to put the reactor in a safe shutdown condition are non-Q-list items.

i

4. Definitions 1

4.1 Safety System ,

A safety system is any system that is primarily designed to accomplish, or the failure of which could prevent accomplishing, one ,

or more of the following functions:

a. Shut down the reactor.

b. Cool the core.

I

c. Cool another safety system. i

d. Cool the reactor containment after an accident, t

e. Contain, control, or reduce radioactivity released in an i

eccident.

f. Provide primary containment combustible gas centrol. '

Maintain the integrity of the reactor coolant pressure 8

g.

boundary.

4.2 Reactor Coolant Pressure Boundary (RCPB) ,

Reactor coolant pressure boundary (RCPB) for a boiling water-cooled i nuclear power reactor means all those pressure containing .

I components, such as pressure vessels, piping, pumps, and valves which are:

6 Volume XI Rev. 22  !

l

VOLUME XI - BOOK 2

a. Part of the Reactor Coolant System (the Reactor Coolant System for a direct cycle boiling water-type reactor extends to and includes the outermost containment isolation valve in the main steam and feedwater piping), or

b. Connected to the Reactor Coolant System, up to and including any and all of the following:

(1) The outermost containment isolation valve in system piping I which penetrates primary reactor containment.

I (2) The second of two valves normally closed during normal  !

I reactor operation in system piping which does not j i

penetrate primary containment.  !

(3) The Reactor Coolant System safety / relief valves.

4.3 Plant Process Conditions (PPC)  !

The full spectrum of plant process conditions that might occur at the Brunswick plant during its lifetime have been divided into four categories in accordance with their anticipated frequency of occurrence and risk to the public. They are:

a. Normal PPC include process conditions which are expected to occur normally or regularly in the course of planned plant operation.

Examples: Refueling, startup, power operation, hot standby, shutdown, routine testing and maintenance of i

components and systems during any of the above, etc.

i i

7 Volume XI j Rev. 22 j

i l

VOLUME XI - BOOK 2 l

l

b. Frequent PPC are those incidents which are anticipated to occur occasionally during plant life.

Examples: Generator / turbine trip, loss of " condenser cooling"/"feedwater heating," isolation of any or all main steam lines, inadvertent moderator cooldown, control rod withdrawal error, loss of feedwater flow, total loss of off-site ac power, trip of one or both recirculation pumps, turbine pressure regulator failure, recirculation flow control failure, single i failure in electrical system, inadvertent opening of a safety / relief valve, inadvertent pump start in a hot recirculation loop, minor Reactor Coolant System leak requiring unit shutdown, etc.

. c. Infrequent PPC are those incidents which might occur a few times during the plant life.

Examples: Blowdown of reactor coolant through multiple safety or relief valves, loss of reactor coolant from a break or crack which does not depressurize the reactor system but which requires the safety functions of isolation of containment, emergency core cooling and reactor shutdown, improper assembly of core during refueling, seizure of one recirculation 8 Volume XI Rev. 22

e VOLUME XI - BOOK 2 .

i pump, startup of an idle recirculation pump in a cold ,

i loop (the other loop being hot), reactor overpressure i with delayed scram, release of radioactive material i resulting from radwaste equipment failure, etc.

d. Limiting PPC are those faults that are not expected to occur but are postulated because their consequences would include the !

potential for the release of significant amounts of radioactive material.

i Examples: Control rod drop accident, fuel handling accident i

resulting in major clad damage of irradiated fuel, major rupture of that portion of the steam line which is not a part of the RCPB up to and including a double ended rupture of the largest pipe, major rupture of any pipe in the RCPB larger than that defined as an infrequent PPC and including a double ended rupture of the largest pipe.

9 Volume XI Rev. 22 1

Volume XI - Table I

1. 1-B21 - Nuclear Boiler System A. Mechanical Components:

1. All piping, fittings, and their supports, valves and their operators [ pneumatic including their controlling solenoid valve (s), manual and electric] that are designated B21 on drawings D-25020 (Rev. 7), D-25021 (Rev. 13), and D-25022 (Rev. 11) are Q-list items except for the portions that are listed below:

a. Test lines beyond valves B21-F018, B21-F026A through D, and B21-F031A and B (D-25021).

b. Reactor feedwater drains downstream of valves B21-V19, B21-V21, B21-V24, and B21-V26 (D-25021).

l

2. All of the following components are Q-list:

a. Reactor pressure vessel (B11-A001).

b. Reactor vessel support assembly.

c. Reactor vessel stabilizers (B11-U002).

d. Core shroud (B11-D001).

e. Control rod drive (CRD) housings.

f. Incore housings.

g. Reactor Laternals.

(1) Jet pump assemblies (B11-D233, D234).

(2) Top guide (for fuel assemblies) (B11-D004).

(3) Holdowns (for top guide) (B11-D008).

(4) Core support assembly (B11-D003).

(5) Fuel supports (B11-D159 through 162).

(6) Control rods (B11-D147).

(7) Control rod guide tubes (B11-D145).

10 Volume XI Rev. 23

Volume XI - Table I

1. 1-B21 - Nuclear Bollar System (cont'd)

h. Reactor components.

(1) Control rod drives (B11-D146).

(2) Control rod drive housing supports and restraints (B11-D141, D142, D143, D144, D146, and U004).  !

i. Fuel assemblies.

j. Feedwater spargers (B11-D081).

k. Core spray lines (B11-D076). '

l. Differential pressure and liquid control line (B11-D073).

m. Reactor vessel head cooling spray noznle (B11-D072).

n. The following condensing chambers and temperature equalizing columns:

(1) B21-D002.

(2) B21-D003A and B.  !

(3) B21-D004A, B, and C. '

(4) B21-D006A through H.

l (5) B21-D006J 'hrough t N. t l .

(6) B21-D006P, R, and S.

f

o. The following air accumulators for main steam isolation '

valves and safety / relief valves:

(1) A001A through A001D.

(2) A002A through A002D.

(3) A003A through A003H, J, K, L.

l i

l I,

11 Volume XI Rev. 22

- - . . . . . = . _ - _ _ . _ - . _ _ - _ , _ _. _. . _ - . - . . - _ . . , . _ . - _-

Volume XI - Table I

1. 1-B21 - Nuclear Boiler System (cont'd)

B. ' Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power suppli% mountings [except for B21-PT-N015A, B, C, and D mountings], and interconnecting wiring) shown on drawings D-20025 (Rev. 18), D-25020 (Rev. 7), D-25021 (Rev. 13),

D-25022 (Rev. 11), and D-72078 are Q-list:

Instrument No. Drawing No.

B21-FAT-4157 D-25021 B21-FAT-4158 D-25021 B21-FAT-4159 D-25021 B21-FAT-4160 D-25021 B21-FAT-4161 D-25021 B21-FAT-4162 D-25021 B21-FAT-4163 D-25021 B21-FAT-4164 D-25021 B21-FAT-4165 D-25021 B21-FAT-4166 D-25021 B21-FAT-4167 D-25021 B21-FE-N005A D-25021 B21-FE-N005B D-25021 B21-FE-N005C D-25021 B21-FE-N005D D-25021 B21-FS-F009 D-25021 B21-FS-F015A D-25021 B21-FS-F015B D-25021 B21-FS-F015C D-25021 B21-FS-F015D D-25021 B21-FS-F015E D-25021 B21-FS-F015F D-25021 B21-FS-F015G D-25021 B21-FS-F015H D-25021 B21-FS-F015J D-25021  ;

B21-FS-F015K D-25021 i B21-FS-F015L D-25021 B21 _'S-F015M D-25021 B21-FS-F015N D-25021 B21-FS-F015P D-25021 ,

B21-FS-F015R D-25021

• B21-FS-F015S D-25021 B21-FS-F041 D-25022 -

B21-FS-F043A D-25022 i B21-FS-F043B D-25020 ,

B21-FS-F045A D-25022 ,

B21-FS-F045B D-25020 B21-FS-F047A D-25022 ,

12 Volume XI Rev. 22 ,

Volume XI - Table I l

1. 1-B21 - Nuclear Boiler System (cont'd) '

Instrument No. Drawing No.

f B21-FS-F047B D-25020 B21-FS-F049A D-25022 B21-FS-F049B D-25020

~ B21-FS-F051A D-25022 i B21-FS-F051B D-25020 B21-FS-F051C D-25022 B21-FS-F051D D-25020 B21-FS-F053A D-25022 B21-FS-F053B D-25020 li B21-FS-F053C D-25022

, B21-FS-F053D D-25020 B21-FS-F055 D-25022 B21-FS-F057 D-25022 B21-FS-F059A D-25022 B21-FS-F059B D-25020 t B21-FS-F059C D-25022 B21-FS-F059D D-25020 B21-FS-F059E D-25022 B21-FS-F059F D-25020 B21-FS-F059G D-25022 B21-FS-F059H D-25020 B21-FS-F059L D-25022 B21-FS-F059M D,-25020 '

B21-FS-F059N D-25022  !

B21-FS-F059P D-25020  !

B21-FS-F059R D-25022 l B21-FS-F059S D-25020 i B21-FS-F059T D-25022 .

B21-FS-F059U D-25020  !

B21-FS-F061 D-25020  !

B21-FS-1205F D-25021 i B21-FS-1209C D-25021 i B21-FS-1209F D-25021 B21-FS-1210F D-25021 i B21-FS-1226C D-25021 B21-FS-1227F D-25022 B21-FS-1228E D-25021  !

l B21-FS-1228F D-25021 B21-FS-1229E D-25021 i B21-FS-1229F D-25021 i B21-FT-NO33A D-25022 ,

B21-FT-NO33B D-25020 B21-FT-NO33C D-25022 B21-FT-NO33D D-25020 l

13 Volume XI I

Rev. 22 f

w- n--n --- ~ , - - , ,er . ,w-,- - - - - , , - - - --~-------.~,----,n, ~ - - - - - - - -

Volume XI - Table I '

1. 1-B21 - Nuclear Boiler System (cont'd) i Instrument No. Drawing No.  !

B21-FT-N034A D-25022 l B21-FT-NO34B D-25020 i B21-FT-N034C D-25022 i B21-FT-NO34D D-25020 B21-FT-NO34E D-25022 -

B21-FT-NO34F D-25020 B21-FT-N034G D-25022 B21-FT-NO34H D-25020 ,

B21-FT-NO34J D-25022 ,

B21-FT-NO34K D-25020 l B21-FT-NO34L D-25022 l B21-FT-NO34M D-25020 B21-FT-NO34N D-25022 B21-FT-NO34P D-25020 B21-FT-NO34R D-25022 B21-FT-NO34S D-25020 B21-FT-N034T D-25022 B21-FT-NO34U D-25020 B21-FT-NO34V D-25022 B21-FT-N034V D-25020 B21-FT-4157 D-25021 B21-FT-4158 D-25021 i B21-FT-4159 D-25021 l B21-FT-4160 D-25021  !

B21-FT-4161 D-25021 l B21-FT-4162 D-25021 -

B21-FT-4163 D-25021 B21-FT-4164 D-25021 B21-FT-4165 D-25021 i B21-FT-4166 D-25021 B21-FT-4167 D-25021 B21-FY-4157 D-25021 ~~

B21-FY-4158 D-25021 B21-FY-4159 D-25021 B21-FY-4160 D-25021 B21-FY-4161 D-25021 B21-FY-4162 D-25021 B21-FY-4163 D-25021 B21-FY-4164 D-25021 B21-FY-4165 D-25021 B21-FY-4166 D-25021 B21-FY-4167 D-25021 B21-LI-R604A D-25022 B21-LI-R6043 D-25020 4 i 14 Volume XI l Rev. 22 ,

..y -- --

- s.- _ - , , -, _,-,---4-. - , ...

)

Volume XI - Table I ,

1. 1-B21 - Nuclear Boiler System (cont'd)

Instrument No. Drawing No.

• B21-LI-R604AX D-25022 i B21-LI-R605 D-25022  ;

B21-LI-3331 D-25022 i B21-LR-R615 D-25020 B21-LSH-N017D-3 l B21-LT-N017A-1 D-25022 B21-LT-N017B-1 D-25022 B21-LT-N017C-1 821-LT-N017D-1 B21-LT-N017A-2 D-25022 B21-LT-N017B-2 D-25022 B21-LT-N017C-2 B21-LT-N017D-2 B21-LT-N017D-3 B21-LT-N024A-1 D-25022 B21-LT-N024A-2 D-25022 B21-LT-N024B-1 D-25022 B21-LT-N024B-2 D-25022 B21-LT-N025A-1 B21-LT-N025A-2 B21-LT-N025B-1 B21-LT-N025B-2 B21-LT-N026A D-25022 B21-LT-N026B D-25020 B21-LT-N027 D-25022 B21-LT-NO31A D-25022 B21-LT-NO31B B21-LT-NO31C D-25022 B21-LT-NO31D B21-LT-NO36 D-25022 B21-LT-NO37 D-25020 B21-LT-N042A D-25022 B21-LT-N042B B21*-LT-3331 D-25022 B21-LIM-N017A-1 D-25022 B21-LTM-N017B-1 D-25022 B21-LTM-N017C-1 B21-LTM-N017D-1

B21-LTM-N017A-2 D-25022 B21-LTM-N017B-2 D-25022 B21-LTM-N017C-2 B21-LTM-N017D-2 ,

B21-LTM-N024A-1 D-25022 B21-LTM-N024A-2 }

D-25022 i B21-LTM-N024B-1 D-25022  :

B21-LTM-N024B-2 D-25022 B21-LTM-N025A-1 i 15 Volume XI Rev. 22 ,

1 1

1

. - - . - _ - ~ . . , . . . . . . _ , . , , . _ . _ . _ _ . . , . , _ . _ , _ _ . _ _ _ _ _ _

._,m

Volume XI - Table I

1. 1-B21 - Nuclear Boiler System (cont'd)

Instrument No. Drawing No.

B21-LTM-N025A-2 B21-LTM-N0253-1 B21-LTM-N025B-2 -

B21-LTM-NO31A-1 D-25022 B21-LTM-NO31B-1 B21-LTM-NO31C-1 D-25022 B21-LTM-NO31D-1 B21-LTM-NO36-1 D-25022 i B21-LTM-NO37-1 j B21-LTM-N042A-1 D-25022 B21-LTM-N042B-1 B21-LTS-NO31A-2 D-25022 B21-LTS-NO31B-2 B21-LTS-NO31C-2 D-25022 B21-LTS-NO31D-2 B21-LTS-NO31A-3 D-25022  !

B21-LTS-NO31B-3 B21-LTS-NO31C-3 D-25022 -

B21-LTS-NO31D-3 4 B21-LT3-NO31A-4 D-25022 l B21-LTS-NO31B-4 i B21-LTS-NO31C-4 D-25022 i B21-LTS-NO31D-4 ,

B21-PDT-N006A j B21-PDT-N006B B21-PDT-N006C B21-PDT-N006D j B21-PDT-N007A  :

B21-PDT-N007B l

B21-PDT-N007C B21-PDT-N007D  ;

B21-PDT-N008A B21-PDT-N008B B21-PDT-N008C B21-PDT-N008D B21-PDT-N009A  ;

B21-PDT-N009B B21-PDT-N009C B21-PDT-N009D B21-PDT-NO32 D-25022 B21-PDT-NO35 D-25022 B21-PDTM-N006A-1 B21-PDTM-N006B-1 B21-PDTM-N006C-1 B21-PDTM-N006D-1 B21-PDTM-N007A-1 B21-IDTM-50073-1 .

16 Volume XI Rev. 22

Volume XI - Table I l I

1. 1-B21 - Nuclear Boiler System (cont'd) '

Instrument No. Drawing No. -

B21-FDTM-N007C-1  !

B21-PDIM-N007D-1 B21-PDTM-N008A-1 1 B21-PDTM-N008B-1 B21-PDTM-N008C-1 B21-PDTM-N008D-1 B21-PDTM-N009A-1 B21-PDTM-N009B-1 .

B21-PDTM-N009C-1 l B21-PDTM-N009D-1 '

B21-PI-R004A D-25022 B21-PI-R004B D-25020 B21-PS-N045A D-25022 B21-PS-N045B D-25022 B21-PS-N045C D-25020 B21-PS-N045D D-25020 B21-PS-N056A D-20025 B21-PS-N056B D-20025 B21-PS-N056C D-20025 B21-PS-N056D D-20025 l B21-PT-N015 A B21-PT-N015B 4 B21-PT-N015C B21-PT-N015D B21-PT-N021A D-25022 B21-PT-N021B B21-PT-N021C D-25022 B21-PT-N021D B21-PT-N023A D-25022 B21-PT-N023B D-25022 B21-PT-N023C .

B21-PT-N023D B21-PTM5N015A-i

- ~'-

B21-PTM-N015B-1 B21-PTM-N015C-1 B21-PTM-N015D-1 B21-PTM-N021A-1 D-25022 B21-PTM-N021B-1 -

B21-PTM-N021C-1 D-25022 B21-PTM-N021D-1 B21-PIM-N023A-1 D-25022 B21-PTM-N023B-1 D-25022 B21-PTM-N023C-1 B21-PTM-N023D-1 ,

I t

17 Volume XI i Rev. 22 j

Volume XI - Table I j i

1. 1-B21 - Nuclear Boiler System (cont'd) i Instrument No. Drawing No.

l B21-PTS-N021A-2 D-25022 j B21-PTS-N021B-2 -

B21-PTS-N021C-2 D-25022 l B21-PTS-N021D-2 B21-PTS-N023A-2 B21-PTS-N023B-2 B21-PTS-N023C-2 B21-PTS-N023D-2 ,

B21-TS-N010A D-72078  !

B21-TS-N010B D-72078 B21-TS-N010C D-72078 l B21-TS-N010D D-72078 i B21-TS-N011A D-72078 B21-TS-N011B D-72078 B21-TS-N011C D-72078 321-TS-N011D D-72078 B21-TS-N012A D-72078 B21-TS-N012B D-72078 B21-TS-N012C D-72078 B21-TS-N012D D-72078 B21-TS-N013A D-72078 B21-TS-N013B D-72078 B21-TS-N013C D-72078 B21-TS-N013D D-72078 B21-TS-3225A D-72078 B21-TS-3225B D-72078  !

B21-TS-3225C D-72078  !

B21-TS-3225D D-72078 B21-TS-3226A D-72078 B21-TS-3226B D-72078 B21-TS-3226C D-72078 B21-TS-3226D D-72078 r B21-TS-3227A D-72078 ,

B21-TS-3227B D-72078  :'

B21-TS-3227C D-72078 B21-TS-3227D D-72078 B21-TS-3228A D-72078 B21-TS-3228B D-72078 B21-TS-3228C D-72078 B21-TS-3228D D-72078 B21-TS-3229A D-72078 B21-TS-3229B D-72078 B21-TS-3229C D-72078 B21-TS-3229D D-72078 18 Volume XI Rev. 22 i

+

r-Volume XI - Table I I

1. 1-B21 - Nuclear Boiler System (cont'd) i Instrument No. Drawing No.  ;

B21-TS-3230A D-72078 l

B21-TS-3230B D-72078 B21-TS-3230C D-72078 B21-TS-3230D D-72078 B21-TS-3231A D-72078 B21-TS-3231B D-72078 B21-TS-3231C D-72078 B21-TS-3231D D-72078 B21-TS-3232A D-72078 B21-TS-3232B D-72078 B21-TS-3232C D-72078

.B21-TS-3232D D-72078

2. Motors for all motor driven Q-listed equipment are Q-list.

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and '

panels, etc.) that provide a safety function are Q-list.

I l

19 Volume XI Rev. 22

Volume XI - Table I

2. 2-B21 - Nuclear Boilar System A. Mechanical Components:

1. All piping, fittings, and their supports, valves, and their operators [ pneumatic including their controlling solenoid valve (s), manual and electric) that are designated B21 on drawings D-2520 (Rev.12), D-2521 (Rev.15), and D-2522 (Rev. 15) are Q-list items except for the portions that are listed below:

a. Test lines beyond valves B21-F018, B21-F026A through D, and B21-F031A and B (D-2521).

l

b. Reactor feedwater drains downstream of valves E21-V19, B21-V21, B21-V24, and B21-V26 (D-2521).

l

2. All of the following components are Q-list:

a. Reactor pressure vessel (B11-A001).

b. Reactor vessel support assembly.

c. Reactor vessel stabilizers (B11-U002).

d. Core shroud (B11-D001).

e. Control rod drive (CRD) housings.

f. Incore housings.

g. Reactor internals.

(1) Jet pump assemblies (B11-D233, D234).

(2) Top guide (for fuel assemblies) (B11-D004).

(3) Holdowns (for top guide) (B11-D008).

(4) . Core support assembly (B11-D003).

(5) Fuel supports (B11-D159 through 162).

(6) Control rods (B11-D147).

(7) Control rod guide tubes (B11-D145).

20 Volume XI Rev. 23

Volume XI - Table I  !

2. 2-B21 - Nuclear Boiler System (cont'd)

h. Reactor components.

l (1) Control rod drives (B11-D146). l (2) Control rod drive housing supports and restraints (B11-D141, D142, D143, D144, D146, and UOO4).

i. Fuel assemblies.

j. Feedwater spargers (B11-D081).

k. Core spray lines (B11-D076).

1. Differential pressure and liquid control line (B11-D073).

n. Reactor vessel head cooling spray nozzle (B11-D072).

n. The following condensing chambers and temperature equalizing columns:

(1) B21-D002.

(2) B21-D003A and B.

(3) B21-D004A, B, C, and D.

(4) B21-D006A through H.

l l

(5)- B21-D006J through N.

(6) B21-D006P, R, and S.

o. The following air accumulators for main steam isolation valves and safety / relief valves are Q-list:

(1) A001A through A001D.

(2) A002A through A002D.

(3) A003A, C, D, H, J, K, L.

21 Volume XI Rev. 22  ;

l Volume XI - Table I

2. 2-B21 - Nuclear Boiler System (cont'd)

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, [

power supplies, mountings (except for B21-PT-N015A, B, C, and D mountings], and interconnecting wiring) shown on drawings D-2025 (Rev.18), D-2520 (Rev.12), D-2521 (Rev.15),

D-2522 (Rev. 15), and D-7278 are Q-list:

Instrument No. Drawing No.

B21-FAT-4157 D-2521 B21-FAT-4158 D-2521 B21-FAT-4159 D-2521 B21-FAT-4160 D-2521 B21-FAT-4161 D-2521 B21-FAT-4162 D-2521 B21-FAT-4163 D-2521 B21-FAT-4164 D-2521 B21-FAT-4165 D-2521 B21-FAT-4166 D-2521 B21-FAT-4167 D-2521 B21-FE-N005A D-2521 B21-FE-N005B D-2521 B21-FE-N005C D-2521 B21-FE-N005D D-2521 B21-FS-F009 D-2521 B21-FS-F015A D-2521 B21-FS-F015B D-2521 B21-FS-F015C D-2521 B21-FS-F015D D-2521 B21-FS-F015E D-2521 B21-FS-F015F D-2521 B21-FS-F015G D-2521 B21-FS-F015H D-2521 B21-FS-F015J D-2521 B21-FS-F015K D-2521 B21-FS-F015L .D-2521 B21-FS-F015M D-2521 B21-FS-F015N D-2521 B21-FS-F015P D-2521 B21-FS-F015R D-2521 B21-FS-F015S D-2521 B21-FS F041 D-2522 B21-FS-7043A D-2522 B21-FS-F043B D-2520 B21-FS-F045A D-2522 B21-FS-F045B D-2520 22 Volume X1 Rev. 22

Volume XI - Table I

2. 2-B21 - Nuclear Boiler System (cont'd)

?

Instrument No. Drawing No.

B21-FS-F047A D-2522  !

B21-FS-F047B D-2520 B21-FS-F049A D-2522 B21-FS-F049B D-2520 B21-FS-F051A D-2522 B21-FS-F051B D-2520 B21-FS-F051C D-2522 B21-FS-F051D D-2520 B21-FS-F053A D-2522 B21-FS-F053B D-2520 B21-FS-F053C D-2522 B21-FS-F053D D-2520 B21-FS-F055 D-2522 B21-FS-F057 D-2522 B21-FS-F059A D-2522 B21-FS-F059B D-2520 B21-FS-F059C D-2522 B21-FS-F059D D-2520 B21-FS-F059E D-2522 B21-FS-F059F D-2520 B21-FS-F059G D-2522 B21-FS-F059H D-2520 B21-FS-F059L D-2522 B21-FS-F059M D-2520 B21-FS-F059N D-2522 B21-FS-F059P D-2520 B21-FS-F059R D-2522-B21-FS-F059S D-2520 B21-FS-F059T D-2522 B21-FS-F059U D-2520 B21-FS-F061 D-2520 B21-FS-1205F D-2521-B21-FS-1209C D-2521 B21-FS-1209F D-2521 B21-FS-1210F D-2521 B21-FS-1226C D-2521

B21-FS-1227F D-2522 B21-FS-1228E D-2521 B21-FS-1228F D-2521 B21-FS-1229E D-2521 B21-FS-1229F D-2521 B21-FT-N033A D-2522 B21-FT-NO33B D-2520 I

221-FT-NO33C D-2522 B21-FT-NO33D D-2520 i 23 Volume XI Rev. 22

I I

Volume XI - Table I

2. 2-B21 - Nuclear Boiler System (cont'd)

Instrument No. Drawing No.

B21-FT-N034A D-2522 B21-FT-N034B D-2520 321-FT-NO34C D-2522 .

B21-FT-NO34D D-2520 B21-FT-NO34E D-2522 ,

B21-FT-NO34F D-2520 B21-FT-NO34G D-2522 B21-FT-NO34H D-2520 B21-FT-NO34J D-2522 B21-FT-NO34K D-2520 B21-FT-NO34L D-2522 B21-FT-NO34M D-2520 B21-FT-NO34N D-2522 B21-FT-NO34P D-2520 B21-FT-NO34R D-2522 B21-FT-NO34S D-2520 B21-FT-NO34T D-2522 B21-FT-NO34U D-2520 B21-FT-NO34V D-2522 B21-FT-N034W D-2520 B21-FT-4157 D-2521 B21-FT-4158 D-2521 l

B21-FT-4159 D-2521 B21-FT-4160 D-2521 B21-FT-4161 D-2521 B21-FT-4162 D-2521 B21-FT-4163 D-2521 B21-FT-4164 D-2521

! B21-FT-4165 D-2521 B21-FT-4166 D-2521 B21-FT-4167 D-2521 B21-FY-4157 D-2521 B21-FY-4158 D-2521 B21-FY-4159 D-2521 B21-FY-4160 D-2521 B21-FY-4161 D-2521 B21-FY-4162 D-2521 B21-FY-4163 D-2521 B21-FY-4164 D-2521 B21-FY-4165 D-2521 i B21-FY-4166 D-2521 l' B21-FY-4167 D-2521 ,

B21-LI-R604A D-2522 ,

B21-LI-R604B D-2520 B21-LI-R604AX D-2522 24 Volume XI i Rev. 22 a

i Volume XI - Table I i

2. 2-B21 - Nuclear Boiler System (cont'd)

Instrument No. Drawing No. ,

B21-LI-R605 D-2522 i B21-LI-3331 D-2522 i B21-LR-R615 D-2520

+

B21-LSH-N017D-3 D-2520 B21-LT-N017A-1 D-2522 B21-LT-N017B-1 D-2522 B21-LT-N017C-1 D-2520

. B21-LT-N017D-1 D-2520 B21-LT-N017A-2 D-2522 B21-LT-N017B-2 D-2522 B21-LT-N017C-2 D-2520 B21-LT-N017D-2 D-2520 B21-LT-N017D-3 D-2520 B21-LT-N024A-1 D-2522 B21-LT-N024A-2 D-2522 B21-LT-N024B-1 D-2522 B21-LT-N024B-2 D-2522 B21-LT-N025A-1 D-2520 B21-LT-N025A-2 D-2520 B21-LT-N025B-1 D-2520 B21-LT-N025B-2 D-2520 B21-LT-N026A D-2522 i B21-LT-N026B D-2520 i B21-LT-N027 D-2522 B21-LT-NO31A D-2522 B21-LT-NO31B D-2520 B21-LT-NO31C D-2522 B21-LT-NO31D D-2520 B21-LT-N036 D-2522 B21-LT-NO37 D-2520

B21-LT-N042A D-2522 l B21-LT-N042B D-2520 B21-LT-3331 D-2522 B21-LTM-N017A-1 D-2522 B21-LTM-N017B-1 D-2522 B21-LTM-N017C-1 D-2520 i B21-LTM-N017D-1 D-2520  !

I B21-LTM-N017A-2 D-2522 B21-LTM-N017B-2 D-2522  !

B21-LTM-N017C-2 D-2520 l B21-LTM-N017D-2 D-2520 l B21-LTM-N024A-1 D-2522

• B21-LTM-N024A-2 D-2522 l B21-LTM-N024B-1 D-2522 321-LTM-N024B-2 D-2522 l l

i 25 Volume XI Rev. 22 4, ,_ . - _ . , ._ ,- w - ----

Vclume XI - Table I ,

2. 2-B21 - Nuclear Boiler System (cont'd)  !

Instrument No. Drawing No.

B21-LTM-N025A-1 D-2520  ;

B21-LTM-N025A-2 D-2520 B21-LTM-N02SB-1 D-2520 B21-L'Df-N025B-2 D-2520 B21-LTM-NO31A-1 D-2522 B21-LTM-NO31B-1 D-2520 B21-LTM-N031C-1 D-2522 B21-LTM-NO31D-1 D-2520 B21-LTM-NO36-1 D-2522 B21-LTM-N037-1 D-2520 B21-LTM-N042A-1 D-2522 B21-LTM-N042B-1 D-2520 B21-LTS-NO31A-2 D-2522 B21-LTS-NO31B-2 D-2520 B21-LTS-NO31C-2 D-2522 B21-LTS-NO31D-2 D-2520 B21-LTS-NO31A-3 D-2522 B21-LTS-NO31B-3 D-2520 B21-LTS-N031C-3 D-2522 B21-LTS-NO31D-3 D-2520 B21-LTS-NO31A-4 D-2522 B21-LTS-N031B-4 D-2520 B21-LTS-NO31C-4 D-2522 B21-LTS-N031D-4 D-2520 B21-PDT-N006A B21-PDT-N006B l B21-PDT-N006C B21-PDT-N006D B21-FDT-N007A i B21-PDT-N007B B21-PDT-N007C B21-PDT-N007D B21-PDT-N008A B21-PDT-N008B B21-PDT-N008C B21-PDT-N008D l

B21-PDT-N009A B21-PDT-N009B ,

B21-PDT-N009C l

! B21-PDT-N009D i i

B21-PDT-NO32 D-2522 B21-PDT-NO35 D-2522 B21-PDTM-N006A-1 B21-PDTM-N006B-1 B21-PDTM-N006C-1 l B21-PDTM-N006D-1 26 Volume XI l Rev. 2.

Volume XI - Table I

2. 2-B21 - Nuclear Boiler System (cont'd)  !

Instrument No. Drawing No. i B21-PDTM-N007A-1  !

B21-PDTM-N007B-1  !

B21-PDTM-N007C-1 B21-PDTM-N007D-1 B21-PDTM-N008A-1 B21-PDTM-N008B-1 B21-PDTM-N008C-1 B21-PD".M-N008D-1 B21-IDTM-N009A-1 B21-PDTM-N009B-1 B21-PDTM-N009C-1 B21-PDTM-N009D-1 B21-PDTS-N006A-2 B21-PDTS-N007B-2 B21-PDTS-N008C-2 B21-PDTS-N009D-2 B21-PI-R004A D-2522 B21-PI-R004B D-2520 B21-PS-N045A D-2522 B21-PS N045B D-2522 B21-PS-N045C D-2520 B21-PS-N045D, D-2520 B21-PS-N056A D-2025 '

B21-PS-N056B D-2025 B21-PS-N056C D-2025 B21-PS-N056D D-2025 B21-PT-N015A B21-PT-N015B

B21-PT-N015C B21-PT-N015D B21-PT-N021A D-2522 B21-PT-N021B D-2520 B21-PT-N021C D-2522 B21-PT-N021D D-2520 B21-PT-N023A D-2522 ,

B21-PT-N023B '

D-2522 .

B21-FT-N023C D-2520 B21-PT-N023D D-2520 B21-PTM-N015A-1 B21-PTM-N015B-1 B21-PTM-N015C-1 .

B21-PTM-N015D-1

{

B21-PTM-N021A-1 D-2522 i B21-PTM-N021B-1 D-2520 B21-PTM-N021C-1 D-2522 B21-PTM-N021D-1 D-2520 27 Volume XI Rev. 22 l

Volume XI - Table I 2, 2-B21 - Nuclear Boiler System (cont'd)

Instrument No. Drawing No.

B21-PTM-N023A-1 D-2522 B21-PTM-N023B-1 D-2522 B21-PTM-N023C-1 D-2520 B21-PTM-N023D-1 D-2520 B21-PTS-N021A-2 D-2522 '

B21-PTS-NC 21B-2 D-2520 B21-PTS-Nu '1C-2 D-2522 i B21-PTS-N021D-2 D-2520 i B21-PTS-N023A-2 D-2522 i B21-PTS-N023B-2 D-2522 ,!

B21-PTS-N023C-2 D-2520 f B21-PTS-N023D-2. D-2520 i B21-TS-N010A D-7278 i B21-T3-N010B D-7278 B21-TS-N010C D-7278 l' B21-TS-N010D D-7278 f B21-TS-N011A D-7278  !

B21-TS-N011B D-7278  !

B21-TS-N011C D-7278 i B21-TS-N011D D-7278 l B21-TS-N012A D-7278 i B21-TS-N012B D-7278  !

B21-TS-N012C D-7278

. B21-TS-N012D D-7278 B21-TS-N013A D-7278 B21-TS-N013B D-7278 B21-TS-N013C D-7278 B21-TS-N013D D-7278 B21-TS-3225A D-7278 B21-TS-3225B D-7278 B21-TS-3225C D-7278 B21-TS-3225D D-7278 B21-TS-3226A D-7278 B21-TS-3226B D-7278 B21-TS-3226C D-7278 B21-TS-3226D D-7278 B21-TS-3227A D-7278 l B21-TS-3227B D-7278 .

B21-TS-3227C D-7278 i B21-TS-3227D D-7278 i B21-TS-3228A D-7278  !

B21-TS-3228B D-7278 l B21-TS-3228C D-7278 B21-TS-3228D D-7278 l

\

t 28 Volume XI  !

Rev. 22

I Volume XI - Table I

2. 2-B21 - Nuclear Boiler System (cont'd)

Instrument No. Drawing No. j B21-TS-3229A D-7278 '

B21-TS-3229B D-7278 B21-TS-3229C D-7278 B21-TS-3229D D-7278 B21-TS-3230A D-7278 B21-TS-3230B D-7278 B21-TS-3230C D-7278 B21-TS-3230D D-7278 B21-TS-3231A D-7278 B21-TS-3231B D-7278 B21-TS-3231C D-7278 B21-TS-3231D D-7278 B21-TS-3232A D-7278 B21-TS-3232B D-7278 B21-TS-3232C D-7278 B21-TS-3232D D-7278

2. Motors for all motor driven Q-listed equipment are Q-list.

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.)

that provide a safety function are Q-list.

o

! l l 1 l

I I

f l

29 Volume XI Rev. 22

t 1

Volume XI - Table I

3. 1-B32 - Reactor Coolant Recirculation System s

A. ' Mechanical Components: -

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid 3 valve (s), manual and electric) that are designated B31 on l drawings D-25018 (Rev. 11) and D-25048 (Rev. 13) are Q-list -

items except for the portions that are listed below:

a. All components downstream of the following flow switches:

B32-FS-F055A, B, C, D (D-25018)

B32-FS-F055E, F, G, H (D-25048) 4 B32-FS-F003A (D-25018)

B32-FS-F003B (D-25048)

B32-FS-F004A (D-25018)

B32-FS-F004B (D-25048)

B32-FS-F040A, C (D-25018)

B32-FS-F040B, D (D-25048)

b. Outer seal leakage discharge lines downstream of piping supplied by the pump vendor.

c. Seal staging flow and inner seal leakage discharge lines downstream of piping supplied by the pump vendor.

2. The sample line RXS upstream of valve F020 is Q-list (D-2518).

3. Solenoid valves for non-Q-list air operated valves V14 (D-25018) and V17 (D-25048) are Q-list items.

4. All of the following components shown on drawing D-25018 and D-25048 are Q-list:

i

a. Reactor recirculation pumps

! b. Heat exchangers  !

c. Pressure breakdown coils B. Ir.strumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on  !

drawings D-25018 (Rev. 11) and D-25048 (Rev. 13) are Q-list:

Instrument No. Drawing No.  !

B32-FC-3626 D-25018 B32-FC-3627 D-23048 l

B32-FE-N013A D-25318 .

B32-FE-N013B D-25048 l 30 Volume XI Rev. 22 j

Volume XI - Table I  ;

3. 1-B32 - Reactor Coolant Recirculation System (cont'd)

Instrument No. Drawing No.

B32-FI-1839 D-25018 i B32-FI-1842 D-25048

B32-FS-F003A D-25018 B32-FS-F003B D-25048 B32-FS-F004A D-25018 B32-FS-F004B D-25048 B32-FS-F009A D-25048 B32-FS-F0090 D-25018 B32-FS-F010A D-25048 B32-FS-F010C D-25018 B32-FS-F011B D-25048 332-FS-F011D D-25018 B32-FS-F012B D-25048 B32-FS-F012D D-25018 B32-FS-F040A D-25018 B32-FS-F040B D-25048 B32-FS-F040C D-25018 B32-FS-F040D D-25048 B32-FS-F055A D-25018 B32-FS-F055B D-25018 B32-FS-F055C D-25018 B32-FS-F055D D-25018

'B32-FS-F055E D-25048 B32-FS-F055F D-25048 B32-FS-F055G D-25048 B32-FS-F055H D-25048 B32-FS-F057A D-25018 B32-FS-F057B D-25048 B32-FT-N014A D-25048

B32-FT-N014B D-25048 l B32-FT-N014C D-25018 B32-FT-N014D D-25018 B32-FT-N024A D-25048 B32-FT-N024B D-25048

, B32-FT-N024C D-25018 B32-FT-N024D D-25018 B32-FY-K606A D-25048  !

B32-FY-K606B D-25048 i B32-FY-K606C D-25018 j B32-FY-K606D D-25018 B32-FY-K607A D-25048 B32-FY-K607B D-25048 B32-FY-K607C D-25018 l B32-FY-K607D D-25018 t 31 Volume XI Rev. 22 I

)

l Volume XI - Table I

3. 1-B32 - Reactor Coolant Recirculation System (cont'd)

Instrument No. Drawing No.

B32-FY-K608A D-25048 B32-FY-K608B D-25048 B32-FY-K608C D-25018 B32-FY-K608D D-25018 B32-PS-N018A D-25018 B32-PS-N018B D-25048 B32-PS-N018A-1 D-25018

\

2. Motors for all motor driven Q-listed equipment unless I specifically identified below as non-Q-list.

a. Motors for Q-list valves B32-F023A & B are non-Q-list.

b. Subcomponents of the reactor recirculation pump motors whose failure could not result in a pump seizure are non-Q-list.

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list items.

This includes but is not limited to M-G set drive motor breakers AA9 and AB3 and their control circuit elements that provide a safety function.

l i

l t

l l

32 Volume XI Rev. 22 i

l

Volume XI - Table I ,

2-B32 - Reactor Coolant Recirculation System A. Mechanical Components:

1

1. All piping, fittings and their supports, valves and their ,

operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated B32 on drawings D-2518 (Rev.14) and D-2548 (Rev.16) are Q-list items except for the portions that are listed below:

a. All components downstream of the following flow switches:

B32-FS-F055A, B, C, D (D-2518)

B32-FS-F055E, F, G, H (D-2548)

B32-FS-F003A (D-2518)

B32-FS-F003B (D-2548)

B32-FS-F004A (D-2518)

B32-FS-F004B (D-2548)

B32-FS-F040.A, C (D-2518)

B32-FS-F040B, D (D-2548)

b. Outer seal leakage discharge lines downstream of piping supplied by the pump vendor.

l

c. Seal staging flow and inner seal leakage discharge lines downstream of piping supplied by the pump vendor. l l

2. The sample line RXS upstream of valve F020 is Q-list (D-2518).  !

3. Solenoid valves for non-Q-list air operated valves V14 (D-2518) l and V17 (D-2548) are Q-list items. j i

4. All of the following components shown on drawing D-2518 and '

D-2548 are Q-list: ,

a. Reactor recirculation pumps i

b. Heat exchangers l B. Instrumentation and Electrical Components:

l '

1. All of the following instruments (including their controls, l

t power supplies, mountings, and interconnecting wiring) shown on +

! drawings D-2?l8 (Rev.14) and D-2548 (Rev.16) are Q-list: 1, I I Instrument No. Drawing No. ,

l B32-FC-3626 D-2518 l

B32-FC-3627 D-2548

! B32-FE-N013A D-2518 B32-FE-N013B D-2548 33 Volume XI Rev. 22 i

l

Volume XI - Table I l

4. 2-B32 - Reactor Coolant Recirculation System (cont'd) i Instrument No. Drawing No.

B32-FI-1839 f

D-2518 i B32-FI-1842 D-2548 B32-FS-F003A- D-2518 B32-FS-F003B D-2548 B32-FS-F004A D-2518 l B32-FS-F004B D-2548 B32-FS-F009A D-2548 B32-FS-F009C D-2518 -

B32-FS-F010A D-2548 B32-FS-F010C D-2518 B32-FS-F011B D-2548 B32-FS-F011D D-2518 B32-FS-F012B D-2548 B32-FS-F012D D-2518 B32-FS-F040A D-2518 B32-FS-F0405 D-2548 B32-FS-F040C D-2518

• B32-FS-F040D D-2548 B32-FS-F055A D-2518 i B32-FS-F055B D-2518  !

B32-FS-F055C D-2518 B32-FS-F055D D-2518 B32-FS-F055E D-2548 l B32-FS-F055F D-2548 B32-FS-F055G D-2548

B32-FS-F055H D-2548 .

l B32-FS-F057A D-2518  !

! B32-FS-F057B D-2548 f B32-FT-N014A D-2548 B32-FT-N014B D-2548 l- B32-FT-N014C D-2518 B32-FT-N014D D-2518 B32-FT-N024A D-2548 '

B32-FT-N024B D-2548 B32-FT-N024C D-2518 i B32-FT-N024D D-2518 i B32-FY-K606A D-2548  ;

l~

B32-FY-K606B D-2548 1 B32-FY-K606C D-2518 B32-FY-K606D D-2518 I B32-FY-K607A D-2548 l t B32-FY-K607B D-2548 4

l B32-FY-K607C D-2518  !

B32-FY-K607D D-2518 i B32-FY-K608A D-2548 B32-FY-K608B D-2548 l g 34 Volume XI g Rev. 22 ,

e

Volume XI - Table I

4. 2-B32 - Reactor Coolant R'acirculation System (cont'd) {

i Instrument No. Drawing No.

• B32-FY-K608C D-2518 B32-FY-K608D D-2518 B32-PS-N018A D-2518 B32-PS-N018B D-2548 B32-PS-N018A-1 D-2518

2. Motors for all motor driven Q-listed equipment unless specifically identified below as non-Q-list.

a. Motors for Q-list valves B32-F023A & B are non-Q-list.

b. Subcomponents of the reactor recirculation pump motors whose failure could not result in a pump seizure are non-Q-list.

3. All power and control circuit elements (such as circuit l

breakers, switches, relays, timers, fuses, cables, wiring, and ;

panels, etc.) that provide a safety function are Q-list items.

This includes but is not limited to M-G set drive motor breakers AA9 and AB3 and their control circuit elements that provide a safety function.

• t i

k i i

i i

35 Volume XI Rev. 22  !

I i

Volume XI - Table I

5. 1-CAC - Containment Atmospheric Control System A. Mechanical Components:

1. A1.1 piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric] that are designated CAC and NP on drawings D-25015 (Rev. 25) and D-72018 (Rev. 10) are Q-list items except for the portions that are listed below:

a. All components downstream of the following valves:

Component No. Drawing No.

CAC-IV998 D-25015 CAC-IV999 D-25015 CAC-V2 D-25015 CAC-V12 D-25015 CAC-V14 D-25015 CAC-V19 D-25015 CAC-V25 D-25015 CAC-V27 D-25015 CAC-V29 D-25015 CAC-V31 D-25015 CAC-V33 D-23015 CAC-V35 D-25015 CAC-V37 D-25015 CAC-V40 D 25015 CAC-V42 P-25015 CAC-V43 D-25015 i CAC-V45 D-25015 CAC-V46 D-25015 CAC-V52 D-25015 CAC-V54 D-25015 CAC-V59 D-25015 CAC-Y80 D-25015 CAC-V82 D-25015

b. Piping, relief lines, and fill lines for primary containment inerting and make-up upstream of valve CAC-V4 2

(D-25015).

c. Drain lines from drain pots associated with monitors CAC-ATH-1259 and CAC-ATH-1263 (D-72018).

2. Actuator and solenoid for the air operated non-Q-list valve CAC-V58 is Q-list.

36 Volume XI Rev. 24 L _

Volt.; XI - Table I

5. 1-CAC - Containment Atmospheric Control System (cont'd)

3. All of the folleving components shown on drawing D-25015 are Q-list items: .

Flexible connection FJ-1.

B. Instrumentation and Electrical Components:

-1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings D-2560 (Rev. 13), D-25015 (Rev. 25), D-25025 (Rev. 15), F-70083 (Rev. 10), and D-72018 (Rev. 10) are Q-list:

Instrument No. Drawing No.

CAC-AQH-1260-1 D-72018 CAC-AQH-1260-2 D-72018 CAC-AQH-1260-3 D-72018 CAC-AQH-1261-1 D-72018 CAC-AQH-1261-2 D-72018 CAC-AQH-1261-3 D-72018 CAC-AQH-1262-1 D-72018 CAC-AQH-1262-2 D-72018 CAC-AQH-1262-3 D-72018 CAC-AR-1259-1 D-72018 .

CAC-AR-1259-2 D-72018 CAC-AR-1260-1 D-72018 CAC-AR-1260-2 D-72018 CAC-AR-1260-3 D-72018

, CAC-AR-1261-1 D-72018 i CAC-AR-1261-2 D-72018 l

CAC-AR-1261-3 D-72018 CAC-AR-1262-1 D-72018 CAC-AR-1262-2 D-72018 CAC-AR-1262-3 D-72018 CAC-AR-1263-1 D-72018 CAC-AR-1263-2 D-72018 CAC-AT-1260-1 D-72018 CAC-AT-1260-2 D-72018 CAC-AT-1260-3 D-72018 CAC-AT-1261-1 D-72018 CAC-AT-1261-2 D-72018 CAC-AT-1261-3 D-72018 CAC-AT-1262-1 D-72018 CAC-AT-1262-2 D-72018 CAC-AT-1262-3 D-72018 i

l 37 Volume XI Rev. 24

Volume XI - Table I

5. 1-CAC - Containment Atmospheric Control System (cont'd)

Instrument No. Drawing No.

CAC-ATH-1259-1 D-72018 CAC-ATH-1259-2 D-72018 CAC-ATH-1263-1 D-72018 CAC-ATH-1263-2 D-72018 CAC-FIC-2717-1 D-2560 CAC-FIC-2720-1 D-2560 CAC-LI-2601-1 D-25015-CAC-LI-2601-3 D-25015 CAC-LI-2699-1 D-2560 CAC-LI-2700-1 D-2560 CAC-LI-3342 D-25015 CAC-LR-2602 D-25015 CAC-LSHL-2601 D-25015 CAC-LT-2601 D-25015 CAC-LT-2602 D-25015 CAC-LT-3342 D-25015 CAC-LY-2601 D-25015 CAC-LY-2601-1 D-25015 CAC-PDS-4222 D-25025 CAC-PI-1257-3 D-25015 CAC-PI-2703-1 D-2560 CAC-PI-2704-1 D-2560 CAC-PI-3341 D-25015 CAC-PI-4176 D-25015 CAC-PR-1257-1 D-25015 CAC-PSH-1257-2 D-25015 CAC-PSH-2684 D-25015 CAC-PSH-4175 D-25015 CAC-PT-1257-2 D-25015 CAC-PT-2685 D-25015 CAC-PT-3341 D-25015 CAC-PT-4175 D-25015 CAC-PT-4176 D-25015 CAC-PY-1257-2 D-25015 CAC-TE-778-1 F-70083 CAC-TE-778-2 F-70083 CAC-TE-778-3 F-70083 CAC-TE-778-4 F-70083 CAC-TE-778 F-70083 CAC-TE-778-6 F-70083 CAC-TE-778-7 D-25015 CAC-TE-1258-1 D-25015 CAC-TE-1258-2 D-25015 CAC-TE-1258-3 D-25015 CAC-TE-1258-4 D-25015 38 Volume XI Rev. 24

_ ~ ;

Volume XI - Table I

5. 1-CAC - Containment Atmospheric Control System (cont'd)

Instrument No. Drawing No.

CAC-TE-1258-5 D-25015

• CAC-TE-1258-6 D-25015 CAC-TE-1258-7 D-25015 i

CAC-TE-1258-8 D-25015 CAC-TE-1258-9 D-25015 CAC-TE-1258-10 D-25015 CAC-TE-1258-11 D-25015 CAC-TE-1258-12 -

D-25015 CAC-TE-1258-13 0-25015 CAC-TE-1258-14 D-25015 CAC-TE-1258-17 D-25015 CAC-TE-1258-18 D-25015 CAC-TE-1258-19 D-25015 CAC-TE-1258-20 D-25015 CAC-TE-1258-21 D-25015 CAC-TE-1258-22 D-25015 CAC-TE-1258-23 D-25015 CAC-TE-1258-24 D-25015 CAC-TR-778 F-70083 CAC-TR-1258 D-25015

2. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list items.

t 39 Volume XI Rev. 24

. .w, , --- . ,-y., ,-,--y --,-n-.--ww,_,c,,--7 ,- ww3 g - e,, --. , - -, -%- - , - - , . - - , - - - ,

Volume XI - Table I

6. 2-CAC - Containment Atmospheric Control System A. Mechanical Couponents_:

1. All piping, fittings and their supports, valves and their operators [ pneumatic including their controlling solenoid valve (s), manual and electric] that are designated as CAC and NP on Drawings D-2515 (Rev. 19), D-2560 (Rev. 13), and D-7218 (Rev. 13) are Q-list items except for the portions that are listed below:

a. All components downstream of the following valves:

Component No. Drawing No.

CAC-HV9 D-2560 CAC-HV10 D-2560 ,

CAC-HV13 D-2560 CAC-HV14 D-2560 CAC-HV18 D-2560 CAC-IV998 D-2515 CAC-IV999 D-2515 CAC-PCV-2705 D-2560 CAC-PSV1 D-2560 CAC-PSV2 D-2560 CAC-PSV3 D-2560 CAC-PSV4 D-2560 CAC-PSV5 D-2560 CAC-PSV7 D-2560 CAC-V2 D-2515 CAC-V12 D-2515 CAC-V14 D-2515 CAC-V19 D-2515 CAC-V25 D-2515 CAC-V27 D-2515 CAC-V29 D-2515 ~ ~

CAC-V31 D 2' lilt-~

CAC-V33 D-2515

CAC-V35 D-2515 l CAC-V37 D-2515 l CAC-V40 D-2515 l CAC-V42 D-2515 CAC-V43 D-2515 CAC-V45 D-2515 CAC-V46 D-2515 CAC-V52 D-2515 CAC-V54 D-2515 CAC-V59 D-2515 CAC-V80 D-2515 CAC-V82 D-2515 l

l l

l 40 Volume XI l Rev. 24 l l

Volume XI - Table I

6. 2-CAC - Containment Atmospheric Control System (cont'd) l Component No. Drawing No.

CAC-V84 D-2560 CAC-V85 D-2560 CAC-V86 D-2560 CAC-V91 D-2515

b. The CAC inerting storage vessel and its associated heat exchangers, heater vaporizer, and associated piping for A0G uses, pressure buildup coil, atmospheric vents, vessel fill, and piping for primary containment inerting and make-up upstream of valve CAC-V4 (D-2515, D-2560).

c. CAD vessel fill line upstream of valves CAC-HV15 and CAC-HV17 (D-2560).

d. Drain lines from drain pots associated with monitors CAC-ATH-1259 and CAC-ATH-1263 (D-7218).

2. Actuators and solenoids for the following air or nitrogen operated non-Q-list valves are Q-list:

CAC-CV-2683 (D-2560) '

CAC-CV-2698 (D-2560)

CAC-CV-2981 (D-2560)

CAC-TCV-2695 (D-2560)

CAC-V58 (D-2515)

HS-V503 (D-2560)

3. All of the following components shown on drawings D-2515 and D-2560 are Q-list items:

a. The CAD liquid nitrogen storage vessel (D-2560).

b. Pressure build-up coils associated with the CAD vessel (D-2560).

c. Ambient heat coil supplying back-up nitrogen to the instrument air header (D-2560).

d. Flexible connection FJ-1 (D-2515).

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on Drawings D-2515 (Rev. 19), D-2525 (Rev. 16), D-2560 (Rev. 13),

F-7083 (Rev. 13), and D-7218 (Rev. 13) are Q-list:

al Volume XI

< Rev. 24

Volume XI - Table I

6. 2-CAC - Containment Atmospheric Control System (cont'd)

Instrument No. Drawing No.

CAC-AQH-1260-1 D-7218 CAC-AQH-1260-2 D-7218 CAC-AQH-1260-3 D-7218 CAC-AQH-1261-1 D-7218 CAC-AQH-1261-2 D-7218 CAC-AQH-1261-3 D-7218 CAC-AQH-1262-1 D-7218 CAC-AQH-1262-2 D-7218 CAC-AQH-1262-3 D-7218 CAC-AR-1259-1 D-7218 CAC-AR-1259-2 D-7218 CAC-AR-1260-1 D-7218 CAC-AR-1260-2 D-7218 CAC-AR-1260-3 D-7218 CAC-AR-1261-1 D-7218 CAC-AR-1261-2 D-7218 CAC-AR-1261-3 D-7218 CAC-AR-1262-1 D-7218 CAC-AR-1262-2 D-7218 CAC-AR-1262-3 D-7218 CAC-AR-1263-1 D-7218 CAC-AR-1263-2 D-7218 CAC-AT-1260-1 D-7218 CAC-AT-1260-2 D-7218 CAC-AT-1260-3 D-7218 CAC-AT-1261-1 D-7218 CAC-AT-1261-2 D-7218 CAC-AT-1261-3 D-7218 CAC-AT-1262-1 D-7218 CAC-AT-1262-2 D-7218 CAC-AT-1262-3 D-7218 CAC-ATH-1259-1 D-7218 CAC-ATH-1259-2 D-7218 CAC-ATH-1263-1 D-7218 CAC-ATH-1263-2 D-7218 l

CAC-FE-2717 D-2560

-CAC-FE-2720 D-2560 CAC-FIC-2717-2 D-2560 CAC-FIC-2720-2 D-2560 CAC-FT-2717 D-2560 CAC-FT-2720 D-2560 CAC-FY-2717-4 D-2560 CAC-FY-2720-4 D-2560 CAC-LI-2601-1 D-2515 CAC-LI-2601-3 D-2515 1

42 Volume XI i Rev. 24 l

i l

Volume XI - Table I l

6. 2-CAC/NP - Containment Atmospheric Control System Instrument No. Drawing No.

CAC-LI-2699-2 D-2560 CAC-LI-2700-2 D-2560 CAC-LI-3342 D-2515 CAC-LITS-2699 D-2560 CAC-LITS-2700 D-2560 CAC-LR-2602 D-2515 CAC-LSHL-2601 D-2515 CAC-LT-2601 D-2515 CAC-LT-2602 D-2515 CAC-LT-3342 D-2515 CAC-LY-2601 "

D-2515 CAC-LY-2601-1 D-2515 CAC-PDS-4222 D-2525 CAC-PI-1257-3 D-2515 CAC-PI-2703-2 D-2560 CAC-PI-2704-2 D-2560 CAC-PI-2717 CAC-PI-2720 CAC-PI-3341 D-2515 CAC-PI-4176 D-2515 CAC-PISH-2703 D-2560 CAC-PISH-2704 D-2560 CAC-PR-1257-1 D-2515 CAC-PSH-1257-2 D-2515 CAC-PSH-2684 D-2515 CAC-PSH-4175 D-2515 CAC-PT-1257-2 D-2515 CAC-PT-2685 D-2515 CAC-PT-2703 D-2560 CAC-PT-2704 D-2560 CAC-PT-3341 D-2515 CAC-PT-4175 D-2515 CAC-PT-4176

- ~~ ~-

D-2515 CAC-PY-1257-2 D-2515 CAC-TC-2695 D-2560 CAC-TE-778-1 F-7083 CAC-TE-778-2 F-7083 CAC-TE-778-3 F-7083 CAC-TE-778-4 F-7083 CAC-TE-778-5 F-7083 CAC-TE-778-6 F-7083 CAC-TE-778-7 D-2515 CAC-TE-1258-1 D-2515 CAC-TE-1258-2 D-2515 CAC-TE-1258-3 D-2515 CAC-TE-1258-4 D-2515 43 Volume XI i Rev. 24  ;

Volume XI - Table I

6. 2-CAC - Containment Atmospheric Control System (cont'd)

Instrument No. Drawing No.

CAC-TE-1258-5 D-2515 CAC-TE-1258-6 D-2515 CAC-TE-1258-7 D-2515 CAC-TE-1258-8 D-2515 CAC-TE-1258-9 D-2515 CAC-TE-1258-10 D-2515 CAC-TE-1258-11 D-2515

. CAC-TE-1258-12 D-2515 CAC-TE-1258-13 D-2515 CAC-TE-1258-14 D-2515 CAC-TE-1258-17 D-2515 CAC-TE-1258-18 D-2515 CAC-TE-1258-19 D-2515 CAC-TE-1258-20 D-2515 CAC-TE-1258-21 D-2515 CAC-TE-1258-22 D-2515 CAC-TE-1258-23 D-2515 CAC-TE-1258-24 D-2515 CAC-TE-2718 D-2560 CAC-TE-2719 D-2560 CAC-TIC-2718 . D-2560 CAC-TIC-2719 D-2560 CAC-TR-778 F-7083 '

CAC-TR-1258 D-2515 CAC-TSL-2718 D-2560 CAC-TSL-2719 D-2560 CAC-TT-2718 D-2560 CAC-TT-2719 D-2560

2. Electric vaporizers are Q-list items (D-2560).

3. All power ord control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list items.

1

[

44 Volume XI Rev. 24 ,

1 l

Volume XI - Table I  ;

7. 1-C0 - Condensate System A. Mechanical Components:

1. All piping, fittings, and their supports, valves and their' operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated CO on drawings D-2040 (Rev.13), D-25016 (Rev. 8), D-25023 (Rev.15),

D-25029 (Rev. 18), and D-25024 (Rev. 14) within the boundaries listed below are Q-list items:

a. Gravity supply lines 1-CO-38-16-C-7, 1-CO-37-16-C-7, 1-CO-202-6-C-7, 1-CO-53-4-C-7, 1-CO-52-12-C-7, and 1-CO-37-12-C-7 from the condensate storage tank to:

(1) The Reactor Building (D-2040).

(2) Valves C11-F013A & B (D-25016).

(3) Valve E41-F004 (D-25023).

(4) Valve E51-F010 (D-25023, D-25029).

(5) Valves E21-F002A & B (D-25024).

b. Gravity supply lines to and including the following valves:

(1) CO-F021A & B and V303 on drawing D-25024.

(2) CO-V301 shown on drawing D-25023.

(3) CO-V310, V311, V312, V313, V314, V315, V316, V317, and V318 shown on drawing D-25016.

2. The condensate storage tank is a Q-liet item.

45 Volume XI Rev. 24

Volume XI - Table I

8. 2-C0 - Condensate System A. Mechanical Comoonents:

1. All piping, fittings, and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated CO on drawings D-2040 (Rev. 13), D-2516 (Rev. 14), D-2523 (Rev. 14),

D-2529 (Rev. 20), and D-2524 (Rev. 16) within the boundaries listed below are Q-list items:

a. Gravity supply lines 2-CO-42-4-C-7, 2-CO-38-12-C-7, 2-CO-202-6-C-7, 2-CO-41-12-C-7, 2-CO-37-16-C-7, and 2-CO-38-16-C-7 from the condensate storage tank to:

(1) The Reactor Building (D-2040).

(2) Valves C12-F013A & B (D-2516).

(3) Valve E41-F004 (D-2523).

-(4) Valve E51-F010 (D-2523, D-2529).

(5) Valves E21-F002A & B (D-2524).

b. Gravity supply lines to and including the following valves:

(1) CO-F021A & B and V303 on drawing D-2524.

(2) CO-V301 shown on drawing D-2523.

(3) CO-V310, V311, V312, V313, V314, V315, V316, V317, and V318 shown on drawing D-2516.

2. The condensate atorage tank is a Q-list item.

l l

l l

I 1

i l

l-l l

46 Volume XI Rev. 24

Volume XI - Table I

9. 1-C11 - Control Rod Drive System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their

• l operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated C11 on drawing D-25017 (Rev. 7) are Q-list items except for the portions that are listed below:

a. Piping downstream of V105 and V107.

b. Piping upstream of V115, V137, and V138.

c. Portable accumulator nitrogen charging system up to but excluding the HCU nitrogen charging fittings.

2. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated C11 on drawing D-25016 (Rev. 8) within the boundaries listed below are Q-list items:

a. CRD pumps suction piping from and including valves C11-F001A and B and F013A and B to the CRD pumps.

3. All of the following components are Q-list items:

a. Hydraulic control units (C11-D001)(D-25017).

b. CRD pumps (C11-C001A and B)(D-25016).

c. CRD pump inlet filters (C11-S001A and B)(D-25016).

d. All of the following CRD parts:

(1) Magnet housing (2) Piston head (3) Piston coupling (4) Socket head capscrew (P/N 117C4516P2)

(5) Collet and piston (6) Index tube (7) Spud (8) Nut (P/N 114B5460P1)

(9) Stop piston (10) Ring flange (11) Piston tube (12) Cylinder flange and tube 47 Volume XI Rev. 24 1

Volume XI - Table I

9. 1-C11 - Control Rod Drive System (cont'd)

B. Instrumentation and Electrical Comeonents:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawing D-25017 (nav. 7) are Q-list:

Instrument No. Drawing No.

C11-LDSH-129 D-23017 C11-LSH-N013A D-25017 C11-LSH-N013B D-25017 C11-LSH-N013C D-25017 C11-LSH-N013D D-25017 C11-LSH-N013E D-25017 C11-LSH-N013F D-25017 C11-PI-131 D-25017 C11-PI-R013 D-25017 C11-PSL-130 D-25017 C11-PSL-3363 D-25017 C11-PSL-3364 D-25017 C11-PSL-N012 D-25017 C11-TJ-K003 D-25017 C11-TR-R018 D-25017

2. Motors for all motor driven Q-listed equipment are Q-list unless specifically identified below as non-Q-list:

a. CRD pump motors are non-Q-list:

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

48 Volume XI Rev. 24

l l

l l

Volume XI - Table I

10. 2-C12 - Control Rod Drive System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated C12 on drawing D-2517 (Rev. 12) are Q-list items except for the portions that are listed below:

a. Piping downstream of V105 and V107.

b. Piping upstream of V115, V137, and V138.

c. Portable accumulator nitrogen charging system up to but excluding the HCU nitrogen charging fitting.

2. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated C12 on drawing D-2516 (Rev.14) within the boundaries listed below are Q-list items:

a. CRD pumps suction piping from and including valves C12-F001A and B and F013A and B to the CRD pumps.

3. All of the following com'ponents are Q-lis items:

a. Hydraulic control units (C12-D001)(D-2517).

b. CRD pumps (C12-C001A and B)(D-2516).

1

c. CRD pump inlet filters (C12-S001A and B)(D-2516).

d. All of the following CRD parts:

(1) Magnet housing (2) Piston head (3) Piston coupling (4) Socket head capscrew (P/N 117C4516P2)

(5) Collet and piston (6) Index tube (7) Spud (8) Nut (P/N 114B5460P1)

(9) Stop piston (10) Ring flange (11) Piston tube (12) Cylinder flange and tube 49 Volume XI Rev. 24

Volume XI - Table I

10. 2-C12 - Control Rod Drive System (cont'd)

B. Instrumentation and Electrical Comocnents:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawing D-2517 (Rev. 12) are Q-list:

Instrument No. Drawing No.

C12-LDSH-129 D-2517 C12-LSH-N013A D-2517 C12-LSH-N013B D-2517 C12-LSH-N013C D-2517 C12-LSH-N013D D-2517 C12-LSH-N013E D-2517 C12-LSH-N013F D-2517 C12-PI-131 D-2517 C12-PI-R013 D-2517 C12-PSL-130 D-2517 C12-PSL-3363 D-2517 C12-PSL-3364 D-2517 C12-PSL-N012 D-2517 C12-TJ-K003 D-2517 C12-TR-R018 D-2517

2. Motors for all motor driven Q-listed equipment are Q-list unless specifically identified below as non-Q-list:

a. CRD pump motors are non-Q-list:

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels,,etc.) that provide a safety function ara Q-list.

30 Volume XI Rev. 24

\

Volume XI - Tabic I

11. 1-C32 - Feedwater Control System A. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls,'

power supplies, mountings, and interconnecting wiring) shown on drawings D-25020 (Rev. 7), D-25021 (Rev. 13), D-25022 (Rev. 11), and FP-50014-1 sh. 4 (Rev. 12) are Q-list:

Instrument No. Drawing No.

C32-DPT-N003A D-25021 C32-DPT-N003B D-25021 C32-DPT-N003C D-25021 C32-DPT-N003D D-25021 C32-K600A FP-50014-1 sh.4 C32-K600B FP-50014-1 sh.4 C32-K600C FP-50014-1 sh.4 C32-LPR-R608 FP-50014-1 sh.4 C32-LT-N004A D-25022 C32-LT-N004B D-25020 C32-LT-N004C D-25022 C32-PI-3332 D-25022 C32-PT-N005A D-25022 ,

C32-PT-N005B D-25020 C32-PT-N005C D-25022 C32-PT-N008 D-25020 C32-PT-N009A D-25021 C32-PT-N009B D-25021 C32-PT-N009C D-25021 C32-PT-N009D D-25021 C32-PT-3332 D-25022

2. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

51 Volume XI Rev. 24

Volume XI - Table I

12. 2-C32 - Feedwater Control System A. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings D-2520 (Rev. 12), D-2521 (Rev. 15), D-2522 (Rev. 15),

and FP-50014-2 sh. 4 (Rev.11) are Q-list:

Instrument No. Drawing No.

C32-DPT-N003A D-2521 C32-DPT-N003B D-2521 C32-DPT-N003C D-2521 C32-DPT-N003D D-2521 C32-K600A FP-50014-2 sh.4 C32-K600B FP-50014-2 sh.4 C32-K600C FP-50014-2 sh.4 C32-LPR-R608 FP-50014-2 sh.4 C32-LT-N004A D-2522 C32-LT-N004B D-2520 C32-LT-N004C D-2522 C32-PI-3332 D-2522 C32-PT-N005A D-2522 C32-PT-N005B D-2520 C32-PT-N005C D-2522 C32-PT-N008 D-2520 C32-PT-N009A D-2521 C32-PT-N009B D-2521 C32-PT-N009C D-2521 C32-PT-N009D D-2521 C32-PT-3332 D-2522

2. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

52 Volume XI Rev. 24

Volume XI - Table I

13. 1-C41 - Standby Liquid Control System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated C41 on drawing D-25047 (Rev. 13) are Q-list items except for the portions listed below:

All components downstream of the following valves:

a.

C41-F015 C41-F025 C41-F017 C41-F027 C41-F021 C41-V4

b. Components upstream of valves C41-F031, F012, F010, and F014.

c. Overflow line 35-3-153 from tank A001 to the 55 gallon drum.

d. Drain lines from the SBLC pump's drip plate drains to the 55-gallon drum.

e. Demineralized water fill line to test tank (line No. 14-1-155).

2. All of the following components shown on drawing D-25047 are -

Q-list:

a. Standby liquid control pumps (C41-C001A and B).

b. Standby liquid control tank (C41-A001).

~

c. ~-AccunTillattirs~(C41;A003r and ~B) .

d. Explosive charges for squib valves.

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawing D-25047 (Rev. 13) are Q-list:

Instrument No. Drawing No.

C41-PI-R600 D-25047 C41-PT-N004 D-25047 C41-TE-N006 D-25047 C41-TIC-R002 D-25047 53 Volume XI Rev. 24

. _ _ _ _ . ~

l i

)

i Volume XI - Table I l

13. 1-C41 - Standby Liquid Control System (cont'd)

2. Motors for all motor driven Q-listed equipment are Q-list.

3. Tank heater A is Q-list.

4. Electric heat tracing on Q-list components is Q-list.

5. All power and control circuit elements (such as circuit breaJcers, witches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

.r . -

?

^

~

r f

./ , ,

~f

.S V

54 Volume XI -

, Rev. 24 ~

.-.,,-,..._4, . ___,_.,.g.m.._g. y _ . . _ . . - , _ , , . _ ._w --y r.

Volume XI - Table I 14 2-C41 - Standby Liould Control System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated C41 on drawing D-2547 (Rev. 10) are Q-list items except for the

, portions listed below:

a. All components downstream of the following valves:

C41-F015 C41-F025 C41-F017 C41-F027 C41-F021 C41-V4

b. Components upstream of valves C41-F031, F012, F010, and F014,

c. Overflow line 35-3-153 from tank A001 to the 55 gallon drum.

d. Drain lines from the SBLC pump's drip plate drains to the 55-gallon drum.

x.' e. Demineralized water fill line to test tank (line

x No. 14-1-155).

+ e .~

2 <- All of the following components shown on drawing D-2547 are

, - r/ Q-list:1 .

~

a. Scandby liquid control pumps (C41-C001A and B).

lr - , . ,

I b. ,

Standby liquid control tank (C41-A001).

s_

.g r ,- c: Accumulators (C41-A003A and-B).

d. Explosive charges for squib v11 pes.

( Instrumentation,and(EJsetri_calComoonents:

B. _

e ,

l < j- _

1. All of the following instruments (including their controls, power supplies,' mountings , and ' interconnecting wiring) shown on drawing D-2517 (Rev."10) are Q-list:

, Instrument No. - Drawing No.

C41-PI-R600 D-2547

' o -

C41-PT-N004 D-2547

'/ , i C41-TE-N006 .

D-2547 C41-TIC-R002 s D-2547

$r '

f _'

r, ,

55 Volume XI

. '/-

Rev: 24

(. ~s .- ,.

Volume XI - Table I

14. 2-C41 - Standby Liquid Control System

2. Motors for all motor driven Q-listed equipment are Q-14 .

3. Tank heater A is Q-list.

4. Electric heat tracing on Q-list components is Q-list.

.5. All power and control circuit elements (such as circuit breakers, witches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

J J

56 Volume XI Rev. 24

Volume XI - Table I J l

15. 1-C51 - Neutron Monitoring System A. Mechanical Components

1. All of the following neutron monitoring mechanical componen'ts shown on drawings FP-5224 sh.1 (Rev. 7), FP-5224 sh.2 (Rev. 7),

and FP-50462 (Rev. 1) are Q-list:

a. SRM/IRM dry tube MPL #B11-D191A through H, and J through M (FP-5224 sh.1).

b. SRM/IRM drive unit MPL #B11-D192A through H, and J through M (FP-5224 sh.1).

c. Drive unit flexible shaft (FP-5224 sh.1).

d. TIP tubing penetration flange MPL #C51-J003A through E (FP-5224 sh.2),

e. TIP guide tubing ball valve MPL #C51-J004A through D (FP-5224 sh.2).

f. Power range detector assembly MPL #B11-D193 (FP-50462).

B. Instrumentation and Electrical Comoonents

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings FP-5224 sh.1 (Rev. 7) and FP-5224 sh.2 (Rev. 7) are Q-list:

Instrument No. Drawing No.

C51-APRM-K605A and assoc. channel equipment FP-5224, sh 2 C51-APRM-K605B and assoc. channel equipment FP-5224, sh.2 C51-APRM-K605C and assoc. channel equipment FP-5224, sh.2 C51-APRM-K605D and assoc. channel equipment FP-5224, sh.2 C51-APRM-K605E and assoc. channel equipment FP-5224, sh.2 C51-APRM-K605F and assoc. channel equipment FP-3224, sh.2 C51-IRM-K601A FP-5224, sh.1 C51-IRM-K601B FP-5224, sh.1 C51-IRM-K601C FP-5224, sh.1 C51-IRM-K601D FP-5224, sh.1 C51-IRM-K601E FP-5224, sh.1 C51-IRM-K601F FP-5224, sh.1 C51-IRM-K601G FP-5224, sh.1 C51-IRM-K601H FP-5224, sh.1 C51-IRM-K602A FP-5224, sh.1 C51-IRM -K602B FP-5224, sh.1 C51-IRM-K602C FP-5224, sh.1 57 Volume XI Rev. 24

Volume XI - Table I

15. 1-C51 - Neutron Monitoring System C51-IRM-K602D FP-5224, sh.1 C51-IRM-K602E FP-5224, sh.1 C51-IRM-K602F FP-5224, sh.1 C51-IRM-K602G FP-5224, sh.1 C51-IRM-K602H FP-5224, sh.1 C51-1RM-K002A FP-5224, sh.1 C51-IRM-K002B FP-5224, sh.1 C51-IRM-K002C FP-5224, sh.1 C51-IRM-K002D -

FP-5224, sh.1 C51-IRM-K002E FP-5224, sh.1 C51-IRM-K002F FP-5224, sh.1 C51-IRM-K002G FP-5224, sh.1 C51-IRM-K002H FP-5224, sh.1 C51-IRM-N002A FP-5224, sh.1 C51-IRM-N002B FP-5224, sh.1 C51-IRM-N002C FP-5224, sh.1 C51-IRM-N002D FP-5224, sh.1 C51-IRM-N002E FP-5224, sh.1 C51-IRM-N002F FP-5224, sh.1 C51-IRM-N002G FP-5224, sh.1 C51-IRM-N002H FP-5224, sh.1 C51-IRM-R603A FP-5224, sh.1 C51-IRM-R603B FP-5224, sh.1 C51-IRM-R603C FP-5224, sh.1 C51-IRM-R603D FP-5224, sh.1 C51-SRM-K600A FP-5224, sh.1 C51-SRM-K600B . FP-5224, sh.1 C51-SRM-K600C FP-3224, sh.1 C51-SRM-K600D FP-5224, sh.1 C51-SRM-K001A FP-5224, sh.1 C51-SRM-K001B FP-5224, sh.1 C51-SRM-K001C FP-5224, sh.1 C51-SRM-K001D FP-5224, sh.1 C51-SRM-5001A FP-3224, sh.1 C51-SRM-N001B FP-3224, sh.1

! C51-SRM-N001C FP-5224, sh.1 C51-SRM-N001D FP-5224, sh.1 C51-SRM-R602 FP-5224, sh.1 l

2. Motor modules for SRM/IRMs S001A through H, and J through M are Q-list.

L 3. All power and control circuit elements (such as circuit

! breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

38 Volume XI Rev. 24

3 a

Volume XI - Table I

16. 2-C51 - Neutron Monitoring System A. Mechanical Components:

1. All of the following neutron monitoring mechanical componen'es shown on drawings FP-5224 sh.1 (Rev. 7), FP-5224 sh.2 (Rev. 7),

and FP-50462 (Rev. 1) are Q-list:

a. SRM/IRM dry tube MPL #B11-D191A through H, and J through M (FP-5224 sh.1).

b. SRM/IRM drive unit MPL #B11-D192A through H, and J through M (FP-5224 sh.1).

c. Drive unit flexible shaft (FP-5224 sh.1).

d. TIP tubing penetration flange MPL #C51-J003A through E (FP-5224 sh.2).

e. TIP guide tubing ball valve MPL #C51-J004A through D (FP-5224 sh.2).

f. Power range detector assembly MPL #B11-D193 (FP-50462).

B. Instrumentation and Electrical Components

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings FP-5224 sh.1 (Rev. 7) and FP-5224 sh.2 (Rev. 7) are Q-list:

Instrument No. Drawing No.

C51-APRM-K605A and assoc. channel equipment FP-3224, sh.2 C51-APRM-K605 Bland assoc. channel equipment FP-5224, sh.2 C51-APRM-K605C and assoc. channel equipment FP-5224, sh.2 C51-APRM-K605D and assoc. channel equipment FP-5224, sh.2 C51-APRM-K605E and assoc. channel equipment FP-5224, sh.2 C51-APRM-K605F and assoc. channel equipment FP-5224, sh.2 C51-IRM-K601A FP-5224, sh.1 l

C51-IRM-K601B FP-5224, sh.1 l C51-IRM-K601C FP-5224, sh.1 C51-IRM-K601D FP-5224, sh.1 C51-IRM-K601E FP-5224, sh.1 C51-IRM-K601F FP-5224, sh.1 C51-IRM-K601G. FP-5224, sh.1 C51-IRM-K601H FP-5224, sh.1 ,

C51-IRM-K602A FP-5224, sh.1 C51-IRM-K602B FP-5224, sh.1 C51-IRM-K602C FP-5224, sh.1 59 Volume XI Rev. 24

Volume XI - Table I

16. 2-C51 - Neutron Monitoring System C51-IRM-K602D FP-5224, sh.1 C51-IRM-K602E FP-5224, sh.1 C51-IRM-K602F FP-5224, sh.1 C51-IRM-K602G FP-5224, sh.1 C51-IRM-K602H FP-5224, sh.1 C51-IRM-K002A FP-5224, sh.1 C51-IRM-K002B FP-5224, sh.1 C51-IRM-K002C FP-5224, sh.1 C51-IRM-K002D FP-5224, sh.1 C51-IRM-K002E FP-5224, sh.1 C51-IRM-K002F FP-5224, sh.1 C51-IRM-K002G FP-5224, sh.1 C51-IRM-K002H FP-5224, sh.1 C51-IRM-N002A FP-5224, sh.1 C51-IRM-N002B FP-5224, sh.1 C51-IRM-N002C FP-5224, sh.1 C51-IRM-N002D FP-5224, sh.1 C51-IRM-N002E FP-5224, sh.1 C51-IRM-N002F FP-5224, sh.1 C51-IRM-N002G FP-5224, sh.1 C51-IRM-N002H FP-5224, sh.1 C51-IRM-R603A FP-5224, sh.1 C51-IRM-R603B FP-5224, sh.1 C51-IRM-R603C FP-5224, sh.1 C51-IRM-R603D FP-5224, sh.1 C51-SRM-K600A FP-5224, sh.1 C51-SRM-K600B FP-5224, sh.1 C51-SRM-K600C FP-5224, sh.1 C51-SRM-K600D FP-5224, sh.1 C51-SRM-K001A FP-5224, sh.1 C51-SRM-K001B FP-5224, sh.1 C51-SRM-K001C FP-5224, sh.1 C51-SRM-K001D FP-5224, sh.1 C51-SRM-N001A FP-5224, sh.1 C51-SRM-N001B FP-5224, sh.1 C51-SRM-N001C FP-5224, sh.1 C51-SRM-N001D FP-5224, sh.1 C51-SRM-R602 FP-5224, sh.1

2. Motor modules for SRM/IRMs S001A through H, and J through M are Q-list.

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

60 Volume XI Rev. 24

Volume XI - Table I

17. 1-C71 - Reactor Protection System A. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls,'

power supplies, mountings, and interconnecting wiring) shown on drawings D-25025 (Rev. 15), D-25026 (Rev. 15), and D-20020 (Rev. 17) are Q-list:

Instrument No. Drawing No.

C71-PS-N002A D-25025 C71-PS-N002B D-25025 C71-PS-N002C D-25026 C71-PS-N002D D-25026 C71-PSH-N003A D-20020 C71-PSH-N003B D-20020 C71-PSH-N003C D-20020 C71-PSH-N003D D-20020

2. All power and control circuit elements (such as circuit break-ers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) are Q-list items except for those listed below.

(Refer to GE elementary diagram FP-9527-55046.)

a. Reactor Protection System M/G sets C71-S001A and C71-S001B.

b. Reactor Protection System power distribution panel C71-P001.

c. Circuit breakers CB1A and CB1B in panels H12-P609 and H12-P611.

d. All indicating lamps and all annunciators.

e. All fuses in series with fail-safe circuit elements.

f. All control rod test jacks on panel H12-P610.

g. Accumulator test panels H21-P003 and H21-P012 and the accumulator test elements mounted on them.

h. Resistors C71-RIA, RIC, R1E, and R1G on panel H12-P609, and C71-RIB, RID, R1F, and R1H cn panel H12-P611.

1. Resistors C71-R3A through D and C71-R4A through D in panel H12-P624.

J. Scram logic test switches C71-S2A and S2C on panel H12-P609, and C71-S2B and S2D on panel H12-P611.

61 Volume XI Rev. 24

Volume XI - Table I 18.,2-C72 --Reactor Protection System A. Instumentation and Electrical Components: .

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on

. drawings D-2525 (Rev. 16), D-2526 (Rev. 17), and D-2020 I

(Rev. 17) are Q-list:

Instrument No. Drawing No.

C72-PS-N002A D-2525 C72-PS-N002B D-2525 C72-PS-N002C D-2526 C72-PS-N002D D-2526 C72-PSH-N003A D-2020 C72-PSH-N003B D-2020 C72-PSH-N003C D-2020 C72-PSH-N003D D-2020

2. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) are Q-list items except for those listed below.

(Refer to GE elementary diagram FP-9527-50015.)

a. Reactor Protection System M/G sets C72-5001A and C72-S001B.

b. Reactor Protection System power distribution panel C72-P001.

c. ' Circuit breakers CB1A and CB1B in panels H12-P609 and H12-P611.

d. All indicating lamps and all annunciators.

e. All fuses in series with fail-safe circuit elements.

f. All control rod test jacks on panel H12-P610.

g. Accumulator test panels H21-P003 and H21-P012 and the accumulator test elements mounted on them.

h. Resistors C72-RIA, RIC, R1E, and R1G on panel H12-P609, and C72-RIB, RID, R1F, end R1H on panel H12-P611.

i. Resistors C72-R3A through D and C72-R4A through D in panel H12-P624.

j. Scram logic test switches C72-S2A and S2C on panel H12-P609, and C72-S22 and S2D on panel H12-P611.

62 Volume XI Rev. 24

Volume XI - Table I Common - All Units Prefixed as Unit No. 2

19. 2-DG - Diesel Generator System A. Mechanical Components:

1. All piping, fittings, and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated DG/D1E/DSA on drawings D-2265 (Rev. 8), D-2266 (Rev. 7), and D-2267 (Rev. 4) are Q-list items except for the portions listed below:

a. All components downstream of starting air tank automatic drainers, air filter automatic drainers, and valves 2-DSA-V23, V35, V53, and V65 (D-2265); and valves V83, V95, V113, and V125 (D-2266).

b. All components downstream of air exhaust silencer drain connections (D-2267).

c. All crankcase vacuum blower discharge components external to the Diesel Generator-Building (D-2267).

d. All combustion gas exhaust components external to the Diesel Generator Building.

e. Instrument lines and valves which are connected to ~

instruments 2-DG-PDS-5PS and 2-DG-PI-71 (D-2267).

, f. All components downstream of instrument valve numbers:

Component No. Drawing No.

IV-1157 D-2265 IV-1159 D-2265 IV-1167 D-2265 IV-1169 D-2265 IV-1177

~ - -

D-2266

IV-1179 D-2266 IV-1187 D-2266 IV-1189 D-2266

2. All of the following components shown on drawings D-2265 (Rev. 8), D-2266 (Rev. 7), D-2267 (Rev. 4), D-2272 (Rev. 3),

and D-2273 (Rev. 3) are Q-list:

a. Valves VS, V6, V7, V8, V21, V22, V23, and V24 (D-2267)

b. Diesel generators (D-2265, D-2266).

c. All air compressors (D-2265, D-2266).

l l

63 Volume XI Rev. 24

Volume XI - Table I Common - All Units Prefixed as Unit No. 2

19. 2-DG - Diesel Generator System (cont'd)

d. The following tanks:

(1) Starting air (D-2265, D-2266)

(2) Control air volume (D-2265, D-2266)

e. The following filters:

(1) Control air (D-2265, D-2266)

(2) Diesel starting air (D-2265, D-2266)

(3) Compressor air intake (D-2265, D-2266)

(4) Combustion air intake (D-2267)

f. Control air moisture traps '(D-2265, D-2266).

g. Control air filter-dryers (D-2265, D-2266).

h. Diesel starting air automatic drainers (D-2265, D-2266).

i. Combustion air intake and exhaust silencers (D-2267).

J. Crankcase vacuum blowers (D-2267).

k. Crankcase vacuum oil separators (D-2267).

1. Combustion air intercooler (D-2272, D-2273).

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on l drawings D-2265 (Rev. 8), D-2266 (Rev. 7), and D-2267 (Rev. 4) are Q-list:

Instrument No. Drawing No.

DG-PI-7(1) D-2267 DG-PI-7(2) D-2267

DG-PI-7(3) D-2267 i DG-PI-7(4) D-2267 DG-PI-20A-20B(1) D-2265 DG-PI-20A-20B(2) D-2265 DG-PI-20A-20B(3) D-2266 DG-PI-20A-20B(4) D-2266 DG-PI-32(1) D-2267 DG-PI-32(2) D-2267 DG-PI-32(3) D-2267 l DG-PI-32(4) D-2267 64 Volume XI Rev. 24 i

Volume XI - Table I Common - All Units Prefi.~ed as Unit No. 2

19. 2-DG - Diesel Generator System (cont'd)

Instrument No. Drawing No.

DG-PI-787 D-2266 DG-PI-788 D-2266 DG-PI-1252 D-2266 DG-PI-1660 D-2266 DG-PI-1663 D-2266 DG-PI-1666 D-2266 DG-PI-1674 D-2265 DG-PI-1677 D-2265 DG-PI-1680 D-2265 DG-PI-1686 D-2265 DG-PI-1690 D-2265 DG-PI-1692 D-2265 DG-PS-202PS(1) D-2265 DG-PS-202PS(2) D-2265 DG-PS-202PS(3) D-2266 DG-PS-202PS(4) D-2266 DG-PS-204PS(1) D-2265 DG-PS-204PS(2) D-2265 DG-PS-204PS(3) D-2266 DG-PS-204PS(4) D-2266 DG-PSH-3PS(1) D-2265 DG-PSH-3PS(2) D-2265 DG-PSH-3PS(3) D-2266 DG-PSH-3PS(4) D-2266 DG-PSH-4PS(1) D-2265 DG-PSH-4PS(2) D-2265 DG-PSH-4PS(3) D-2266 DG-PSH-4PS(4) D-2266 DG-PSL-6PS(1) D-2265 DG-PSL-6PS(2) D-2265 DG-PSL-6PS(3) D-2266 DG-PSL-6PS(4) D-2266 DG-PSL-7PS(1) D-2265 DG-PSL-7PS(2) D-2265 DG-PSL-7PS(3) D-2266 DG-PSL-7PS(4) D-2266

2. Panels at nodes 2-HA9, 2-HBO, 2-HB1, and 2-HB2, and all items mounted in/on them are Q-list items except for nameplates, indicating lamps, internal panel lighting, panel heaters, running time meters, annunciators, and items in the exhaust unbalance circuits.

65 Volume XI Rev. 24

l Volume XI - Table I Common - All Units Prefixed as Unit No. 2

19. 2-DG - Diesel Generator System (cont'd)

3. Panels at nodes 2-H46, 2-H47, 2-H48, 2-H49, 2-H54, 2-H55, 2-H56, and 2-H57, and all items mounted in/on them are Q-list items except for nameplates, indicating lamps, internal panel lighting, panel heaters, annunciators, and resistance transmitters used for relaying stator and bearing temperature information.

4. Transformer and resistor compartments at nodes 2-F13, 2-F14, 2-F15, 2-F16, 2-F22, 2-F23, 2-F24, 2-F25, 2-F26, 2-F27, 2-F28, and 2-F29, and all items mounted in/on them are Q-list items except for nameplates, indicating lamps, and panel heaters.

5. Panels at nodes 1-H58, 1-H59, 2-H60, and 2-H61, and all items mounted in/on them are Q-list items except for nameplates, indicating lamps, and internal panel lighting.

6. Motors for all motor driven Q-listed equipment are Q-list.

7. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

66 Volume XI Rev. 24

Volume XI - Table I

20. 1-D12 - Process Radiation Monitoring System A. Mechanical Components:

1.

All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated D12 on drawings FP-5159 (Rev. 4) and D-20025 (Rev.18) within the boundaries listed below are Q-list items:

a. Sample chamber inlet line from and including valve D12-F011 to the sample chamber.

b. Sample chamber discharge line from the sarsie chamber to and including valve D12-F010.

c. Off-gas vial sampler inlet line from and including valve D12-F012 to and including the inlet solenoid valve.

d. Off-gas vial sampler discharge line from and including the discharge solenoid valve through valve F004 to the sample rack discharge line.

e. Sample pump inlet line to and including valve D12-F005.

2. Sample chamber D12-J005 is Q-list.

B. Instrumentation and Electrical Components:

i

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawing FP-5159 (Rev. 4) are Q-list:

Instrument No. Drawing No.

D12-K607 FP-5159 D12-RE-N004A FP-5159 l D12-RE-N004B FP-5159 l D12-RE-N006A FP-5159 D12-RE-N006B '

FP-5159 D12-RE-N006C FP-5159 i D12-RE-N006D FP-5159 I

D12-RE-N010A FP-5159 D12-RE-N010B FP-5159

D12-RM-K601A FP-5159 D12-RM-K601B FP-5159 D12-RM-K603A FP-5159

D12-RM-K603B FP-5159 D12-RM-K603C FP-5159 D12-RM-K603D FP-5159 l

l 67 Volume XI l Rev. 24 l

l

Volume XI - Table I

20. 1-D12 - Process Radiation Monitoring System (cent'd)

Instrument No. Drawing No.

D12-RM-K609A FP-5159 D12-RM-K609B FP-5159

2. Panel H12-P604 and all items mounted in/on it are Q-list items except for nameplates, indicating lamps, internal lighting, utility outlets, panel ventilation systems, and non-Q-list instrumentation (F-95003, Rev. 8).

3. All items mounted in case D12A-Z1A and case D12A-Z1B at node JH9 for H12-P606 are Q-list (FP-50054-1, Rev. B).

4. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

68 Volume XI Rev. 24 i

_ J

Volume XI - Table I

21. 2-D12 - Process Radiation Monitoring System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their

• operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated D12 on drawings FP-5159 (Rev. 4) and D-2025 (Rev. 18) within the boundaries listed below are Q-list items:

a. Sample chamber inlet line from and including valve D12-F011 to the sample chamber.

b. Sample chamber discharge line from the sample chamber to and including valve D12-F010.

c. Off gas vial sampler inlet line from and including valve D12-F012 to and including the inlet solenoid valve.

d., Off gas vial sampler. discharge line from and including the discharge solenoid valve through valve F004 to the sample rack discharge line.

e. Sample pump inlet line to and including valve D12-F005.

2. Sample chamber D12-J005 is Q-list.

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawing FP-5159 (Rev. 4) are Q-list:

Instrument No. Drawing No.

D12-K607 FP-5159 D12-RE-N004A FP-5159 D12-RE-N004B FP-5159 D12-RE-N006A FP-5159 D12-RE-N006B FP-5159 D12-RE-N006C FP-5159 D12-RE-N006D FP-5159 D12-RE-N010A FP-5159 D12-RE-N010B FP-5159 D12-RM-K601A FP-5159 D12-RM-K601B FP-5159 D12-RM-K603A FP-5159 D12-RM-K603B FP ."159 D12-RM-K603C FP-5159 D12-RM-K603D FP-5159 69 Volume XI Rev. 24

I Voluma XI - Table I

21. 2-D12 - Process Radiation Monitoring System (cont'd)

Instrument No. Drawing No.

D12-RM-K609A FP-5159 D12-RM-K609B FP-5159

2. Panel H12-P604 and all items mounted in/on it are Q-list items except for nameplates, indicating lamps, internal lighting, utility outlets, panel ventilation systems, and non-Q-list instrumentation (F-9503, Rev. 16).

3. All items mounted in case D12A-ZIA and case D12A-Z1B at node JH9 for H12-P606 are Q-list-(FP-50054-2, Rev. B).

4. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

70 Volume XI Rev. 24

1 l

i Volume XI - Table I

22. 1-D22 - Area Radiation Monitoring <

A. Instrument Components:

1. All of the following instruments (including their controls,"

power supplies, mountings, and interconnecting wiring) for monitoring the radiation of the Control Room operating area and Unit Nos. 1 and 2 electronic equipment rooms are Q-list items.

These detectors are located in the mechanical equipment room and the Control Building. These are shown on drawings F-4080 (Rev.10) and FP-5152 (Rev. 6) .

. Instrument No. Drawing No.

D22-N001 ch.1-1 F-4080 D22-N001 ch.1-2 F-4080 D22-N001 ch.1-3 F-4080 D22-K600 FP-5152 sh.1

2. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

i 71 Volume XI Rev. 24

- - - - - , - - g . -- - .- - - , , - . .ne, -- ,-,--.w---, , , - - - -- - - - - --

Volume XI - Table I

23. 2-D22 - Area Radiation Monitoring l A. Instrument Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) for monitoring the radiation of the Drywell Area are Q-list.

These are shown on drawing D-7218 (Rev.13).

Instrument No. Drawing No.

D22-RI-4195 D-7218 D22-RI-4196 D-7218 D22-RI-4197 D-7218 D22-RI-4198 D-7218 D22-RM-4195 D-7218 D22-RM-4196 D-7218 D22-RM-4197 D-7218 D22-RM-4198 D-7218 D22-RR-4195 D-7218 D22-RR-4197 D-7218

2. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses,. cables, wiring, and panels, etc.) that provide a safety function are Q-list.

72 Volume XI Rev. 24

Volume XI - Table I Unit Nos. 1 and 2

23. Plant Electrical Systems

1. Auxiliary ac power systems associated with plant safety-related items are Q-list.

t

2. 125/250 volt de power systems associated with plant safety-related items are Q-list.

3. Cable trays, control boards, motor control centers, panels, electrical penetrations, etc. , that are used for supporting, housing, or mounting Q-list components (such as breakers, cables, control switches, etc.) are Q-list items, except the items specifically listed below:

a. Electrical penetrations (1) Stainless steel covers, bolts / screws, washers, and clips.

l (2) Galvanized locknuts, washers, hubs, and flex conduit bushings.

(3) Gaskets.

b. Pull boxes, junction boxes, and terminal boxes (1) Covers, bolts / screws, and washers.

(2) Locknuts, hubs, and flex conduit bushings.

(3) Gaskets.

c. Condulet and LB (1) Covers, bolts / screws, and washers.

(2) Gaskers.

d. Raceway (1) Conduit.

(2) Conduit fittings and mounting hardware.

e. Limitorque valve actuator cover (1) Bolts / screws and washers.

(2) Gaskets.

73 Volume XI Rev. 24

T 1

Volume XI - Table I Unit Nos. 1 and 2

23. Plant Electrical Systems (cont'd)

f. Motor termination box .

(1) Covers, bolts / screws, and washers.

(2) Gaskets.

1 4

.s

}

)

i l

74 Volume XI Rev. 24

Volume XI - Table I

24. 1-E11 - Residual Heat Removal System A. Mechanical Comoonents:

1. All piping, fittings and their supports, valves and their operators [ pneumatic including their controlling solenoid valve (s), manual and electric] that are designated E11 on drawings D-25025 (Rev. 14), D-25026 (Rev. 15), and D-25037 (Rev. 21) are Q-list items except for the portions listed below:

a. Test lines downstream of valves:

E11-F059A (D-25025)

E11-F059B (D-25026)

E11-F077 (D-25026)

b. Demineralized water lines upstream of valves:

E11-F082B (D-25026)

E11-F083 (D-25025)

E11-F086A (D-25025)

E11-F086B (D-25025)

E11-F090 (D-25026)

E11-V192 )D-25025)

c. Valve leak-off lines, and system and equipment vents / drains downstream of the following valves:

E11-F041 D-25025 E11-F062 D-25026 E11-F064 D-25025 E11-V58 D-25025 E11-V60 D-25025 E11-V62 D-25026 ~

E11-V64 D 25026~

E11-V65 D-25025 E11-V66 D-25025 E11-V67 D-25026 E11-V68 D-25026 -

E11-V69 D-25025 -

E11-V71 D-25026 E11-V78 D-25025 E11-V79 D-25026 E11-V81 D-25025 E11-V83 D-25026 E11-V85 D-25026 E11-V86 D-25026 E11-V87 D-25025 75 Volume XI Rev. 24 i

1 l

i l

Volume XI - Table I

24. 1-E11 - Residual Heat Removal System (cont'd)

E11-V88 D-25025 E11-V90 D-25025 E11-V91 D-25025 E11-V92 D-25025 E11-V93 D-25025 E11-V94 D-25025 E11-V95 D-25025 E11-V96 D-25025 E11-V97 D-25025 E11-V98 D-25025 E11-V99 D-25025 E11-V100 D-25025 E11-V104 D-25025 Ell-Vill D-25025 E11-V115 D-25025 E11-V116 D-25025 E11-V119 D-25025 E11-V120 D-25025 E11-V121 D-25025 E11-V125 D-25026 E11-V126 D-25026 E11-V127 D-25026 E11-V129 D-25026 E11-V131 D-25026 E11-V133 D-25026 E11-V134 D-25026 E11-V136 D-25026 E11-V137 D-25026 E11-V138 D-25026 E11-V139 D-25026 E11-V140 D-25026 E11-V141 D-25026 E11-V142 D-25026 E11-V144 D-25026 E11-V147 D-25026 E11-V152 D-25025 E11-V154 D-25025 E11-V159 D-25026 E11-V164 D-25025 E11-V165 D-25026 E11-V166 D-25025 E11-V167 D-25026 E11-V168 D-25026 E11-V170 D-25026 E11-V187 D-25026 E11-V190 D-25026 76 Volume XI Rev. 24

Volume XI - Table I

24. 1-E11 - Residual Heat Removal System (cont'd)

d. All lines and components downstream of valves:

E11-F040 (D-25026)

E11-F071A (D-25025)

E11-F071B (D-25026)

E11-F071C (D-25025)

E11-F071D (D-25026)

E11-F072A (D-25025)

E11-F072B (D-25026)

E11-F072C (D-25025)

E11-F072D (D-25026)

e. All of lines 37-4-300 and 72-4-160 as shown on drawings D-25025 and D-25026.

f. RHR full flow test line to suppression pool downstream of

'l penetrations X-210A (D-25025) and X-210B (D-25026).

3

g. Suppression chamber inlet lines (including spray headers) downstream of penetrations X-211A (D-25025) and X-211B j- (D-25026).

h. Lines and components downstream of valves E11-V41, V42, V45 and V46 (D-25037).

2. All of the following components shown on drawings D-25025,

, D-25026 and D-25037 are Q-list.

a. RHR pumps.

b. RHR heat exchangers.

c. RHR service water pumps.

d. RHR service water pump motor coolers.

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) that are shown on drawings D-25025 (Rev. 15), D-25026 (Rev. 15),

4 D-25037 (Rev. 21), and F-70083 (Rev. 10) are Q-list:

Instrument No. Drawing No.

E11-CE-N001A D-25025 E11-CE-N0013 D-25026 77 Volume XI Rev. 24

Volume XI - Table I

24. 1-E11 - Residual Heat Removal System (cont'd)

Instrument No. Drawing No.

E11-CIS-R001A D-25025 E11-CIS-R001B D-25026 E11-FE-N006A D-25037 E11-FE-N006B D-25037 E11-FE-N012 D-25026 E11-FE-N014A D-25025 E11-FE-N014B D-25026 E11-FI-R603A D-25025 E11-FI-R603B D-25026 E11-FI-3338 D-25026 E11-FI-3339 D-25026 E11-FR-R608 D-25026 E11-FT-N013 D-25026 E11-FT-N015A D-25025 E11-FT-N015B D-25026 E11-FT-3338 D-25026 E11-FT-3339 D-25026 E11-FY-K600A D-25025 E11-FY-K600B D-25026 E11-FY-3338- D-25026 E11-LIC-Rc04A D-25025 E11-LIC-R604B D-25026 E11-LT-N008A D-25025 E11-LT-N008B D-25026 E11-LY-K001A D-25025 E11-LY-K0013 D-25026 E11-PDI-3344 D-25026 E11-PDIC-R600A D-25025 E11-PDIC-R6008 D-25026 E11-PDIS-N021A D-25025 E11-PDIS-N021B D-25026 E11-PDS-N003A D-25025 E11-PDS-N003B D-25026 E11-PDT-N002A D-25025 E11-PDT-N002B D-25026 E11-PDT-N002BX D-23026 l E11-PIC-R609 D-25026 l

-- E11-PIR-R600-1A D-25025 E11-PIR-R600-1B D-25026 E11-PS-N010A D-25025 E11-PS-N010B D-25026 E11-PS-N010C D-25025 E11-PS-N010D D-25026 78 Volume XI Rev. 24 l

Volume XI - Table I

24. 1-E11 - Residual Heat Removal System (cont'd)

Instrument No. Drawing No.

E11-PS-N011A D-25025 E11-PS-N011B D-25026 E11-PS-N011C D-25025 E11-PS-N011D D-25026 E11-PS-N016A D-25025 E11-PS-N016B D-25026 E11-PS-N016C D-25025 E11-PS-N016D D-25026 E11-PS-N018 D-25026 E11-PS-N019A D-25025 E11-PS-N019B D-25026 E11-PS-N019C D-25025 E11-PS-N019D D-25026 E11-PS-N020A D-25025 E11-PS-N020B D-25026 E11-PS-N020C D-25025 E11-PS-N020D D-25026 E11-PSH-N022A D-25025 E11-PSH-N022B D-25026 E11-PSL-2679 D-25026 E11-PSL-2746 D-25025 E11-PT-N026A D-25025 E11-PT-N026B D-25026 E11-PT-N028 D-25026 E11-PY-K003A D-25025 E11-PY-K003B D-25026 E11-TE-N004A D-25025 E11-TE-N004B D-23026 i E11-TE-N005A D-25037 E11-TE-N005B D-25037 E11-TE-N009A F-70083 E11-TE-N009B F-70083 E11-TE-N027A D-25025 E11-TE-N027B D-25026

E11-TE-N029A F-70083 E11-TE-N029B F-70083 E11-TE-NO30A F-70083 E11-TE-NO30B F-70083 E11-SS-K605A D-25025 E11-SS-K605B D-25026 E11-TS-N600A F-70083 E11-TS-N600B F-70083 E11-TS-3298 F-70083

- E11-TS-3299 F-70083 E11-TS-3300 F-70083 79 Volume XI Rev. 24

Volume XI - Table I

24. 1-E11 - Residual Heat Removal System (cont'd)

Instrument No. Drawing No.

E11-TS-3301 F-70083 E11-TS-3302 F-70083 E11-TS-3303 F-70083 E11-TS-3304 F-70083 E11-TS-3305 F-70083 E11-TS-3306 F-70083 E11-TS-3307 F-70083 E11-TS-3308 F-70083 E11-TS-3309 F-70083 E11-TS-3310 F-70083 E11-TS-3311 F-70083 E11-TS-3312 F-70083 E11-TS-3313 F-70083 E11-TSD-N601A F-70083 E11-TSD-N601B F-70083 E11-ZY-S600A D-25025 E11-ZY-S600B D-25026

2. All RHR System initiation and trip logic circuit elements are Q-list.

3. Motors for all motor driven Q-listed equipment unless specifically identified below are non-Q:.

Motors for Q-list valves E11-V32 (D-25025) and V33 (D-25026) r.re non-Q.

4. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

80 Volume XI Rev. 2a

VOLUME XI - Table I

25. 2-E11 - Residual Heat Removal System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators [ pneumatic including their controlling solenoid valve (s), manual and electric] that are designated Ell on drawings D-2525 (Rev. 17), D-2326 (Rev. 18), and D-2537 (Rev. 19) are Q-list items except for the portions listed below:

a. Test lines downstream of valves:

E11-F059A (D-2525)

E11-F059B (D-2526)

E11-F077 (D-2526)

b. Demineralized water lines upstream of valves:

E11-F082B (D-2526)

E11-F083 (D-2525)

E11-F086A (D-2525)

E11-F086B (D-2525)

E11-F090 (D-2526)

E11-V192 (D-2525)

c. Valve leak-off lines, and system and equipment vents / drains downstream of the following valves:

Instrument No. Drawing No.

E11-F041 D-2525 E11-F062 D-2526

! E11-F064 D-2525 E11-V58 D-2525 E11-V60 D-2525 E11-V62 D-2526 E11-V64 D-2526 E11-V65 D-2525 E11-V66 D-2525 E11-V67 D-2526 E11-V68 D-2526 E11-V69 D-2525 E11-V71 D-2526 E11-V78 D-2525 l E11-V79 D-2526 l E11-V81 D-2325 E11-V83 D-2526 E11-V85 D-2526 E11-V86 D-2526 E11-V87 D-2525 81 Volume XI Rev. 24 l

- .- - . . . _ -1

~.

?

Volume XI - Table I  : . s

25. 2-E11 - Residual Heat Removal System (cont'd) '

~

Instrument No. Drawing N'o".

E11-V88 D-2525 E11-V90 D-2525 E11-V91 D-2525 -

E11-V92 D-2525 E11-V93 D-2525 ^ -

E11-V94 D-2525 -

E11-V95 D-2525 ~

E11-V96 D-2525 '

E11-V97 D-2525 E11-V98 D-2525 '

E11-V99 D-2525 . .

E11-V100 D-2525 _

E11-V104 D-2525 ' '.

E11-V115 D-2525 . -

E11-V116 D-2525 -

E11-V119 D-2525 ~- ' ^'

E11-V120 D-2525 .

E11-V121 D-2525 E11-V125 D-2526 E11-V126 D-2526 '

E11-V127 D-2526 E11-V129 D-2526

• E11-V131 D-2526 7- -

E11-V134 D-2526 "T - ~ --

E11-V136 D-2526~

E11-V137 D-2526 .

E11-V138 D-2526 '

E11-V139 D-2526. , y.. ,

E11-V140 D-2526 -

E11-V141 D-2526 E11-V142 D-2526 -

E11-V144 D-2526 *'

E11-V147 D-2526 E11-V152 D-2525 E11-V154 D-2525 E11-V159 D-2526 E11-V164 D-2525 E11-V165 D-2526 -

E11-V166 D-2525 E11-V167 D-2526 E11-V168 D-2526 E11-V170 D-2526 -

~

E11-V187 D-2526 '

E11-V190 D-2326 ,

W 82 Volume XI Rev. 24

~,-

r.

~

' ;f >hrrx- '

,7

, AG ]

., e n.. ~

+. -

g-

'Q%:w"a }m< . .

[ $ 4'_) ,

,P Volume XI - Table I

[jy, /C5. 7.-E11 - Residual Heat Removal System (cont'd)

^

v d.~ All lines and components downstream of valves:

m  % ,.

~

' E11-F040 (D-2526) 1 E11-F071A (D-2525) ~

4 E11-F071B (D-2526) '

' f...-

t. 'E11-F071C (D-2525) f.

Mg ~

E11-F071D (D-2526) '

,/'f }

.. E11-F072A (D-2525)

_l C E11-F072B (D-2526)

% Ell,-F072C (D-2525)

.* E11-F072D (D-2526)

• p e. ,All of lines 37-4-300 and 72-4-160 as shown on drawings

• **' ,, / D-2525 and D-2_526p -

., /

'/

f/# f. RHR full flow test line to suppression pool downstream of

~

, penetrations X-210A (D-2525) and .Y210,-B (Df2526).

) .

s

-e

- - ~ -# /

g.-Suppress. tor chamber 17.let lines (including spray headers) w h, e' downstream of penetxations X-211A (D-2525) and X211-B

~*/

4 ,"

e. ,, f-(D-2526) . j, y/.$ h. Lines and compone, tics downstream of valves E11-V41, V42, y l' V45'and V46,(D-2537). i,,

7 l'l j' -'  ;

'; ' i,,

2. All of the following components shown on drawings D-2525, D-2526 and D-2537;are Q-list. .

a. RHR Pumps 'j ,

^ ~

~ b. RHR heat exchangers

.. v.

/ ~ c. RHR service water pumps , <

g d. RHR service water pump motor coolery m , -

,. , 37 7 nstrumentation I and Electrical Components:

~

1. All of the following instruments (including their controls,

, power supplies, meuntings, and interconnecting wiring) shown on

(, s dra:iings D-2525. (Rev.17), D-2526 (Rev. 18), D-2537 (Rev. 20),

~;

and F-7083 (Rev.'13) are Q-list:

/ "Insteumant No . r

Drawing No.

E11-CE-N001A D-2525 E11-CE-N001B ~

D-2526

/ . E11-CIS-R001A ,

D-2525 '

/ E11-CIS:R001B D-2526~

' I

,A F 83" Volume XI l ,

. j< ', , -

Rev. 24

. I I r: . ' A (4 0

i f

l. / L_ . - . - . - . - , - -

Volume XI - Table I

25. 2-E11 - Residual Heat Removal System (cont'd)

Instrument No. Drawing No.

E11-FE-N006A __ D-2537 E11-FE-N006B D-2537 E11-FE-N012 D-2526 E11-FE-N014A D-2525 E11-FE-N014B D-2526 E11-FI-R603A D-2525 E11-FI-R603B D-2526 E11-FI-3338 D-2526 E11-FI-3339 D-2526 E11-FR-R608 D-2526 E11-FT-N013 D-2526 E11-FT-N015A D-2525 E11-FT-N015B D-2526 E11-FT-3338 D-2526 E11-FT-3339 D-2526 E11-FY-K600A D-2525 E11-FY-K600B D-2526 E11-FY-3338 D-2526 E11-LIC-R604A D-2525 E11-LIC-R604B D-2526 E11-LT-N008A D-2525

• E11-CT-N008B D-2526 E11-LY-K001A D-2525 E11-LY-K001B D-2526 E11-PDI'-3344 D-2526 E11-PDIC-R600A D-2525 E11-PDIC-R600B D-2526 E11-PDIS-N021A D-2525 E11-PDIS-N021B D-2526 E11-PDS-N003A D-2525 E11-PDS-N003B D-2526 E11-PDT-N002A D-2525 E11-PDT-N002B D-2526 E11-PDT-N002BX D-2526 E11-PIC-R609 D-2526 E11-PIR-R600-1A D-2525 E11-PIR-R600-1B D-2526 E11-PS-N010A D-2525 E11-PS-N010B D-2526 E11-PS -N010C D-2525 E11-PS-N010D D-2526 L11-PS-N011A D-2525 E11-PS-N011B D-2526 E11-PS-N011C D-2525 E11-PS-N011D D-2526 84 Volume XI Rev. 24

Volume XI - Table I

25. 2-E11 - Residual Heat Removal System (r.ont'd)

Instrument No. Drawing No.

E11-PS-N016A D-2525 E11-PS-N016B D-2526 E11-PS-N016C . D-2525 E11-PS-N016D D-2526 E11-PS-N018 D-2526 E11-PS-N019A D-2525 E11-PS-N019B D-2526 E11-PS-N019C D-2525 E11-PS-N019D D-2526 E11-PS-N020A D-2525 E11-PS-N020B D-2526 E11-PS-N020C D-2525 E11-PS-N020D D-2526 E11-PSH-N022A D-2525 E11-PSH-N022B D-2526 E11-PSL-2679 D-2526 E11-PSL-2746 D-2525 E11-PT-N026A D-2525 E11-PT-N026B D-2526 E11-PT-N028 D-2526 E11-PY-K003A D-2525 E11-PY-K003B D-2526 E11-TE-N004A D-2525 E11-TE-N004B D-2526 E11-TE-N005A D-2537 E11-TE-N005B D-2537 E11-TE-N009A F-7083 E11-TE-N009B F-7083 E11-TE-N027A D-2525 E11-TE-N027B D-2526 E11-TE-N029A F-7083 E11-TE-N029B F-7083 ~

E11-TE-N030A F-7083 E11-TE-NO30B F-7083 E11-SS-K605A D-2525 E11-SS-K605B D-2526 E11-TS-N600A F-7083 E11-TS-N600B F-7083 E11-TS-3298 F-7083 E11-TS-3299 F-7083

-E11-TS-3300 F-7083 E11-TS-3301 F-7083 E11-TS-3302 F-7083 E11-TS-3303 F-7083 E11-TS-3304 F-7083 85 Volume XI Rev. 24

-_.__a__

Volume XI - Table I

25. 2-E11 - Residual Heat Removal System (cont'd)

Instrum'ent No. Drawing No.

E11-TS-3305 F-7083 E11-TS-3306 F-7083 E11-TS-3307 F-7083 E11-TS-3308 F-7083 E11-TS-3309 F-7083 E11-TE-3310 F-7083 E11-TS-3311 F-7083 E11-TS-3312 F-7083 E11-TS-3313 F-7083 E11-TSD-N601A F-7083 E11-TSD-N601B F-7083 E11-ZY-S600A D-2525 E11-ZY-S600B D-2526

2. All RHR System initiation and trip logic circuit elements are Q-list.

3. Motors for all motor driven Q-listed equipment unless specifically identified below are non-Q.

Motors for Q-list valves E11-V32 (D-2525) and V33 (D-2526) are non-Q.

4. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

86 Volume XI Rev. 24

Volume XI - Table I

26. '1-E21 - Core Spray System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated E21 on drawing D-25024 (Rev. 14) are Q-list items except for the portions listed below:

a. System test return lines to suppression chamber downstream of suppression chamber penetrations X-223A and X-223B.

b. Valve stem leak-off lines downstream of valves E21-V71, V73, V74, and V76.

c. Domineralized water keep fill lines upstream of check valves E21-F029A & B.

d. System vents, drains and test lines downstream of valves E21-V1, V9, V21, V23, V26, V28, V33, V35, V38, V40, V43, V45, V47, V49, V51, V53, V56, V58, V63, V65, V68, V70, V78, and V80; E21-F008A & B; E21-F009A & B; E21-F014A & B; and E21-F035A & B.

2. All of the following components shown on D-25024 are Q-list:

a. Core spray spargers b .' Core spray pumps (E21-C001)

c. Strainers S2A and S2B B. . Instrumentation and Electrical Components:

4

1. All of the following instruments (including their controls, power' supplies, mountings, and interconnecting wiring) shown on drawing D-25024 (Rev. 14) are Q-list:

Instrument No. Drawing No.

E21-FE-N002A D-23024 E21-FE-N002B D-25024 E21-FI-R601A D-25024 E21-FI-R601B D-23024 E21-FS-F018A D-25024 E21-FS-F018B D-25024 87 Volume XI Rev. 24

(

d Volume XI - Table I

26. 1-E21 - Core Spray System (cont'd)

Instrument No. Drawing No.

E21-FS-N006A D-25024 E21-FS-N006B D-25024 E21-FT-N003A D-25024 E21-FT-N003B D-25024 E21-PDS-N004A D-25024 E21-PDS-N004B D-25024 E21-PS-N008A D-25024 E21-PS-N008B D-25024 E21-PS-N009A D-25024 E21-PS-N009B D-25024 E21-PSH-N007A D-25024 E21-PSH-N007B D-25024 E21-PSL-2677 D-25024 E21-PSL-2678 D-25024 E21-PT-N001A D-25024 E21-PT-N001B D-25024

2. All components that are part of the incident detection and system initiation logic circuits are Q-list.

3. Motors for all motor driven Q-listed equipment unless specifically identified below as non-Q-list.

Motors for motor operated Q-list valves E21-V17 and V18 are non-Q.

4. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring and panels, etc.) that provide a safety function are Q-list.

88 Volume XI Rev. 24 i

Volume XI - Table I

27. 2-E21 - Core Spray System A. Methanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated E21 on drawing D-2524 (Rev.16) are Q-list items except for the portions listed below:

a. System test return lines to suppression chamber downstream of suppression chamber penetrations X-223A and X-223B.

b. Valve stem leak-off lines downstream of valves E21-V71, V73, V74, and V76.

c. Demineralized water keep fill lines upstream of valves E21-F029A & B.

d. System vents, drains and test lines downstream of valves E21-V1, V9, V21, V23, V26, V28, V30, V33, V35, V38, V40, V42, V43, V45, V47, V49, VS1, V53, V56, V58, V63, V65, V68, V70, V78, and V80; E21-F008A & B; E21-F009A & B; E21-F014A & B; and E21-F035A & B.

2. All of the following components shown on D-2524 are Q-list:

a. Core spray spargers

b. Core spray pumps (E21-C001)

c. Strainers S2A and S2B B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and intercennecting wiring) shown on drawing D-2524 (Rev. 16) are Q-list:

i l Instrument No. Drawing No.

l E21-FE-N002A D-2524 E21-FE-N002B D-2524 E21-FI-R601A D-2524 E21-FI-R601B D-2524 i E21-FS-F018A D-2524 I

E21-FS-F018B D-2524 l

l l

89 Volume XI Rev. 24

_ - - . - -. , _ . , , . . _. _ - , _ _ . _ _ . . - _ . _ , . ~ . ._ _ ._. ._ _ _.

Volume XI - Table I

27. 2-E21 - Core Spray System Instrument No. Drawing No.

E21-FS-N006A D-2524 E21-FS-N006B D-2524 E21-FT-N003A D-2524 E21-FT-N003B D-2524 E21-PDS-N004A D-2524 E21-PDS-N004B D-2524 E21-PS-N008A D-2524 E21-PS-N008B D-2524 E21-PS-N009A D-2524 E21-PS-N009B D-2524 E21-PSH-N007A D-2524 E21-PSH-N007B D-25'24 E21-PSL-2677 D-2524 E21-PSL-2678 D-2524 E21-PT-N001A D-2524 E21-PT-N001B D-2524

2. All components that are part of the incident detection and system initiation logic circuits are Q-list.

3. Motors for all motor driven Q-listed equipment unless specifically identified below as non-Q-list.

Motors for motor operated Q-list valves E21-V17 and V18 are non-Q.

4. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring and panels, etc.) that provide a safety function are Q-list.

4 j

90 Volume XI Rev. 24 g ,9 ,

7-, p g - _ . _ _ , - - _ - - y _, , .- - -

Volume XI - Table I

28. 1-E41 - High Pressure Coolant InjeEtion System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated E41 on drawing D-25023 (Rev. 15) are Q-list items except for the portions' listed below:

a. HPCI turbine exhaust drain pot. drain line inside the suppression chamber at penetration X-222 (line No. 37-2-153).

b. Demineralized water keep fill lines upstream of valve E41-V94.

c. System vents, drains, and test lines downstream of valves E41-F015, F017, F043, F044, F056', F065, F078, F090, F091, V16, V18, V23, V54, V56, V57, V58, V59, V62, V63, V64, V67, V69, V71, V77, V81, and V83.

d. Line and components upstream of test connection at E41-V14 and V20.

e. Turbine bearing seal drain piping between the turbine and the barometric condenser.

f. Stem leak-off lines from valves E41-V8 and V9 to the barometric condenser.

g. Piping between E41-FO-D008 and the barometric condenser.

i h. Piping between E41-SV-F053 and the barometric condenser.

f

1. Piping between the barometric condenser vacuum pump and valve E41-V60.

j. Piping between the barometric condenser condensate pump and valve E41-F052.

k. The barometric condenser vent to Radwaste. '

1. The Barometric Condenser Vacuum System recirculation line.

l i

i l

l 91 Volcme XI l Rev. 24 f

I l

Volume XI - Table I

28. 1-E41 - High Pressure Coolant In_iection System (cont'd)

2. All of the following components shown on drawing D-25023 are Q-list: .

a. HPCI turbine and its auxiliary equipment (excluding vacuum tank, condensate pump, vacuum pump, and barometric condenser).

b. HPCI booster pump.

c. HPCI main pump (E41-C001).

d. HPCI turbine inlet and exhaust drain pot.

a. Rupture diaphragms E41-PSE-D003 and D004.

B. Instrumentation and Electrical Components

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings D-2040 (Rev.13), D-25023 (Rev.15), and F-70083 (Rev. 10) are Q-list:

Instrument No. Drawing No.

E41-FE-N007 D-25023 E41-FIC-R600 D-25023 E41-FS-F024A D-25023 E41-FS-F024B D-25023 E41-FS-F024C D-25023 E41-FS-F024D D-25023 E41-FSL-N006 D-25023 E41-FT-N008 D-25023 E41-FY-K601 D-25023 E41-LS-N002 D-2040 E41-LS-N003 D-2040 E41-LSH-5015A D-25023 l E41-LSH-N015B D-25023 E41-LSH-N018 D-25023 E41-LT-N014 D-25023 E41-LTM-N014 D-23023 E41-PDS-N004 D-25023 E41-PDS-N005 D-25023 E41-PI-R601- D-25023 E41-PI-R602 D-25023 E41-PI-R603 D-25023 E41-PI-R606 D-25023 92 Volume XI Rev. 24

Volume XI - Table I

28. 1-E41 - High Pressure Coolant Injection System (cont'd)

Instrument No. Drawing No.

E41-PS-N001A D-25023 E41-PS-N001B D-25023 E41-PS-N001C D-25023 E41-PS-N001D D-25023 E41-PS-N010 D-25023 E41-PS-N017A D-25023 E41-PS-N017B D-25023 E41-PSH-N012A D-25023 E41-PSH-N012B D-25023 E41-PSH-N012C D-25023 E41-PSH-N012D D-25023 E41-PSH-N027 D-25023 E41-PSH-NO31 D-25023 E41-PT-N009 D-25023 E41-PT-N013 D-25023 E41-PT-N016 D-25023 E41-PT-N019 D-25023 E41-TE-N024 F-70083 E41-TE-N028A F-70083 -

E41-TE-N028B F-70083 E41-TE-N029A F-70083 E41-TE-N029B F-70083 E41-TE-NO30A F-70083 E41-TE-NO30B F-70083 E41-TR-R605 D-25023 E41-TS-N600 F-70083 E41-TS-N602A F-70083 E41-TS-N602B F-70083 E41-TS-3314 F-70083 E41-TS-3315 F-70083 E41-TS-3316 F-70083 E41-TS-3317 F-70083 E41-TS-3318 F-70083 E41-TS-3354 F-70083 E41-TS-3488 F-70083 E41-TS-3489 F-70083

2. HPCI turbine control and supervisory instrucents that provide a safety function are Q-list.

3. All HPCI System initiation and trip logic system elements are Q-list.

93 Volume XI Rev. 24

Volume XI - Table I

28. 1-E41 - High Pressure Coolant Injection System (cont'd)

4. Motors for all motor driven Q-listed equipment are Q-list.

5. All power and contol circuit elements (such as circuit

• breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

94 Volume XI Rev. 24

Volume XI - Table I

29. 2-E41 - High Pressure Coolant Injection System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling soienoid valve (s), manual and electric) that are designated E41 on drawing D-2523 (Rev. 14) are Q-list items except for the portions listed below:

a. HPCI turbine exhaust drain pot. drain line inside the suppression chamber at penetration X-222 (line No. 37-2-153).

b. Deminieralized water keep fill lines upstream of valve E41-V94.

c. System vents, drains, and test lines downstream of valves E41-F015, F017, F043, F044, F056, F065, F078, F090, F091, V16, V18, V23, V54, V56, V57, V58, V59, V62, V63, V64, V67, V69, V71, V77, V81, and V83.

d. Line and components upstream of test connection at E41-V14 and V20.

e. Turbine bearing seal drain piping between the turbine and the barometric condenser,

f. Stem leak-off lines from valves E41-V8 and V9 to the barometric condenser.

g. Piping between E41-FO-D008 and the barometric condenser.

h. Piping between E41-SV-F053 and the barometric condenser.

i. Piping between the barometric condenser vacuum pump and valve E41-V60.

( j. Piping between the barometric condenser condensate pump l and valve E41-F052.

k. The barometric condenser vent to Radwaste.

1. The barometric condenser vacuum system recirculation line.

95 Voluue XI Rev. 24

Volume XI - Table I

29. 2-E41 - High Pressure Coolant Injection System (cont'd)

2. All of the following components shown on drawing D-2523 are Q-list: .

a. HPCI turbine and its auxiliary equipment (excluding vacuum tank, condensate pump, vacuum pump, and barometric condenser).

b. HPCI booster pump.

c. HPCI main pump (E41-C001).

d. HPCI turbine inlet and exhaust drain pot.

e. Rupture diaphragms E41-PSE-D003 and D004.

B. Instrumentation and Electrical Components

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings D-2040 (Rev. 13), D-2523 (Rev. 14), and F-7083 (Rev. 13) are Q-list:

Instrument No. Drawing No.

E41-FE-N007 D-2523 E41-FIC-R600 D-2523 E41-FS-F024A D-2523 E41-FS-F024B D-2523 E41-FS-F024C D-2523 E41-FS-F024D D-2523 E41-FSL-N006 D-2523 E41-FT-N008 D-2523 E41-FY-K601 D-2523 E41-LS-N002 D-2040 E41-LS-N003 D-2040 E41-LSH-N014 D-2523 E41-LSH-N015A D-2523 E41-LSH-N015B D-2523 E41-LSH-N018 D-2523 E41-PDS-N004 D-2523 E41-PDS-N005 D-2523 E41-PI-R601 D-2523 E41-PI-R602 D-2523 E41-PI-R603 D-2523 E41-PI-R606 D-2523 E41-PS-N001A D-2523 E41-PS-N001B D-2523 96 Volume XI Rev. 24

--. - - w.- w- ,y - 4 s- uP'

Volume XI - Table I

29. 2-E41 - High Pressure Coolant In_iection System (cont'd)

Instrument No. Drawing No.

E41-PS-N001C D-2523 E41-PS-N001D D-2523 E41-PS-N010 D-2523 E41-PS-N017A D-2523 E41-PS-N017B D-2523 E41-PSH-N012A D-2523 E41-PSH-N012B D-2523 E41-PSH-N012C D-2523 E41-PSH-N012D D-2523 E41-PSH-N027 D-2523 E41-PSH-NO31 D 2523 E41-PT-N009 D-2523 E41-PT-N013 D-2523 E41-PT-N016 D-2523 E41-PT-N019 D-2523 E41-TE-N024 F-7083 E41-TE-N028A F-7083 E41-TE-N028B F-7083 E41-TE-N029A F-7083 E41-TE-N029B F-7083 E41-TE-NO30A F-7083 E41-TE-NO30B F-7083 E41-TR-R605 D-2523 E41-TS-N600 F-7083 E41-TS-N602A F-7083 E41-TS-N602B F-7083 l E41-TS-3314 F-7083 l E41-TS-3315 F-7083 E41-TS-3316 F-7083 E41-TS-3317 F-7083 l E41-TS-3318 F-7063 E41-TS-3354 F-7083 E41-TS-3488 F-7083 E41-TS-3489 F-7083

, 2. HPCI turbine control and supervisory instruments that provide a l safety function are Q-list.

3. All HPCI System initiation and trip logic system elements are Q-list.

4. Motors for all motor driven Q-listed equipment are Q-list.

5. All power and contol circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.)

that provide a safety function are Q-list.

I 97 Volume XI Rev. 2/*

Volume XI - Table I

30. 1-E51 - Reactor Core Isolation Cooling System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated E51 on drawing D-25029 (Rev. 19) are Q-list items except for the portions listed below:

a. Test lines downstream of valves E51-F032, F035, F037, F052, F058, V15, V17, V44, and V45.

b. System vents and drains downstream of valves E51-F048, F060, F061, F065, V33, V35, V37, V39, V41, V47, V58, and V60.

c. Components downstream of the reducer joining lines 43-1-152 and 43-2-152.

d. Components downstream of valves E51-F027 and E51-V32.

e. Valve stem leak-off line Nos. 27-1-152 and 21-1-152 of valves V9 and V8, respectively. Valve stem leak-off line of valve V8 to turbine casing,

f. Components upstream of valves E51-F028, E51-V72, and E51-V31.

g. The barometric condenser vent to Radwaste.

h. Test connection at line No. 43-2-152, containing valves V18 and V19.

i. Turbine bearing seal drain line Nos. 28-1-152. _ _ _ ._ _.

j. The barometric condenser vacuum system recirculation line.

2. All of the following components are Q-list:

a. RCIC pump drive turbine and its auxiliary equipment (excluding vacuum tank, condensate pump, vacuum pump, and barometric condenser).

b. RCIC pump (E51-C001).

c. Rupture diaphragms E31-PSE-D001 and PSE-D002.

d. RCIC turbine inlet and exhaust drain pots.

98 Volume XI Rev. 24

Volume XI - Table I

30. 1-E51 - Reactor Core Isolation Cooling System (cont'd)

B. Instrumentation and Electrical Components:

1. All of the following M uruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings D-25029 (Rev. 19) and F-70083 (Rev. 10) are Q-list:

Instrument No. Drawing No.

E51-DTS-N601A F-70083 E51-DTS-N601B F-70083 E51-DTS-N604A F-70083 E51-DTS-N604B F-70083 E51-DTS-N604C F-70083 E51-DTS-N604D F-70083 E51-FE-N001 D-25029 E51-FIC-R600 D-25029 E51-FIC-3325 D-25029 E51-FS-F044A D-25029 '

E51-FS-F044B D-25029 E51-FS-F044C D-25029 E51-FS-F044D D-25029 E51-FS-N002 D-25029 E51-FT-N003 D-25029 E51-FY-K601 D-25029 E51-FY-3408 '

D-25029 E51-LTM-N010-1 D-25029 E51-LT-N010 D-25029 E51-PDS-N017 D-25029 E51-PDS-N018 D-25029 E51-PI-R003 D-25029 E51-PI-R602 D-25029 E51-PS-N019A D-25029 E51-PS-N019B D-25029 E51-PS-N019C D-25029 E31-PS-N019D D-25029 E51-PSH-N012A D-25029 E51-PSH-N012B D-25029 E51-PSH-N012C D-25029 E51-PSH-N012D D-25029 E51-PSH-N009A D-25029 E51-PSH-N009B D-25029 E51-PSH-N020 D-25029 E51-PSL-N006 D-25029 E51-PT-N007 D-25029 E51-TE-N011 F-70083 99 Volume XI Rev. 24 l

l

Volume XI - Table I

30. 1-E51 - Reactor Core Isolation Cooling System (cent'd)

Instrument No. Drawing No.

E51-TE-N021A F-70083 E51-TE-N021B F-70083 E51-TE-N022A F-70083 E51-TE-N022B F-70083 E51-TE-N023A F-70083 E51-TE-N023B F-70083 E51-TE-N025A F-70083 E51-TE-N025B F-70083 E51-TE-N025C F-70083 E51-TE-N025D F-70083

~

E51-TE-N026A F-70083 E51-TE-N026B F-70083 E51-TE-N026C F-70083 E51-TE-N026D F-70083 E51-TE-N027A F-70083 E51-TE N027B F-70083 E51-TE-N027C F-70083 E51-TE-N027D F-70083 E51-TS-N600 F-70083 E51-TS-N602A F-70083 E51-TS-N602B F-70083 E51-TS-N603A F-70083 E51-TS-N603B F-70083 E51-TS-N603C F-70083 E51-TS-N603D F-70083 E51-TS-3319 F-70083 E51-TS-3320 F-70083 E51-TS-3321 F-70083 E51-TS-3322 F-70083 E51-TS-3323 F-70083 E31-TS-3355 F-70083 E51-TS-3487 F-70083 E51-TDS-M602A F-70083 E51-TDS-M602B F-70083

2. RCIC turbine control and supervisory instrumentation are Q-list.

3. All RCIC System initiation and trip logic circuit elements are Q-list.

100 Volume XI Rev. 24 1

. l

Volume XI - Table I

30. 1-E51 - Reactor Core Isolation Cooling System (cont'd) 4 Motors for all motor driven Q-listed equipment are Q-list. In addition, motors for the vacuum and condensate pumps are Q-list.

5. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

101 Volume XI Rev. 24

o Volume XI - Table I

31. 2-E51 - Reactor Core Isolation Cooling System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated E51 on drawing D-2529 (Rev. 20) are Q-list items except for the portions listed below:

a. Test lines downstream of valves E51-F032, F035, F037, F052, F058, V15, V17, V44, and V45.

b. System vents and drains downstream of valves E51-F048, F060, 7061, F065, V33, V35, V37, V39, V41, V42, V47, V58, and V60.

c. Components downstream of the reducer joining lines 43-1-152 and 43-2-152.

d. Components downstream of valves E51-F027 and E51-V32.

e. Valve stem leak-off line Nos. 27-1-152 and 21-1-152 of valves V9 and V8, respectively. Valve sten leak-off line of valve V8 to turbine casing.

f. Components upstream of valves E51-F028, E51-V72, and E51-V31.

g. The barometric condenser vent to Radwaste.

h. Test connection at line No. 43-2-152, containing valves V18 and V19.

r

1. Turbine bearing seal drain line Nos. 28-1-152.

j. The barometric condenser vacuum system recirculation line.

2. All of the following components are Q-list:

I

a. RCIC pump drive turbine and its auxiliary equipment

! (excluding vacuum tank, condensate pump, vacuum pump, and barometric condenser).

l b. RCIC pump (E51-C001).

c. Rupture diaphragms E51-PSE-D001 and E51-PSE-D002.

d. RCIC turbine inlet and exhaust drain pots.

l 102 Volume XI l Rev. 24 l

1 p ,_ w - -

Volume XI - Table I

31. 2-E51 - Reactor Core Isolation Cooling System (cont'd)

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls,*

power supplies, mountings and interconnecting wiring) shown on drawings D-2529 (Rev. 20), D-2040 (Rev. 13) and F-7083 (Rev. 13) are Q-list:

Instrument No. Drawing No.

E51-DTS-N601A F-7083 E51-DTS-N601B F-7083 E51-DTS-N604A F-7083 E51-DTS-N604B F-7083 E51-DTS-N604C F-7083 E51-DTS-N604D F-7083 E51-FE-N001 D-2529 i E51-FIC-R600 D-2529 E51-FIC-3325 D-2529 E51-FS-F044A D-2529 E51-FS-F044B D-2529 E51-FS-F044C D-2529 E51-FS-F044D D-2529 E51-FS-N002 D-2529 E51-FT-N003 D-2529 E51-FY-K601 D-2529 E31-FY-3408 D-2529 E51-LSH-N010 D-2529 E31-LSL-4463 D-2040 E51-LSL-4464 D-2040 E51-PDS-N017 D-2529 E51-PDS-N018 D-2529 E51-PI-R003 D-2529 E51-PI-R602 D-2529 E51-PS-N019A D-2529 E51-PS-N019B D-2529 E31-PS-N019C D-2529 E51-PS-N019D D-2529 E51-PSH-N012A

• D-2529 E51-PSH-N012B D-2529 E51-PSH-N012C D-2529 E51-PSH-N012D D-2329 E51-PSH-N009A D-2529 E51-PSH-N009B D-2529 E51-PSH-N020 D-2529 E51-PSL-N006 D-2529 E51-PT-N007 D-2529 E51-TE-N011 F-7083 E31-TE-N021A ,

F-7083 103 Volume XI Rev. 24

l Volume XI - Table I 2-E51 - Reactor Core Isolation Cooling System (cont'd)

~

31.

Instrument No. Drawing No.

E51-TE-N021B F-7083 E51 ~'.-N022A F-7083 E51-Tt-N022B F-7083 E51-TE-N023A F-7083 E51-TE-N023B F-7083 E51-TE-N025A F-7083 E51-TE-N025B F-7083 E51-TE-N025C F-7083 E31-TE-N025D F-7083 E51-TE-N026A F-7083 E51-TE-N026B F-7083 E51-TE-N026C F-7083 E51-TE-N026D F-7083 E51-TE-N027A F-7083 E51-TE-N027B F-7083 E51-TE-N027C F-7083 E51-TE-N027D F-7083 E51-TS-N600 F-7083 E51-TS-N602A F-7083 E31-TS-N602B F-7083 E51-TS-N603A F-7083 E51-TS-N603B F-7083 E51-TS-N603C F-7083 E51-TS-N603D F-7083 E31-TS-3319 F-7083 E51-TS-3320 F-7083 E31-TS-3321 F-7083 E51-TS-3322 F-7083 E51-TS-3323 F-7083 I E51-TS-3355 F-7083 l

E51-TS-3487 F-7083 E51-TDS-M602A F-7083 E51-TDS-M602B F-7083

2. RCIC turbine control and supervisory instrumentation are Q-list.

3. All RCIC System initiation and trip logic circuit elements are Q-list.

4. Motors for all motor driven Q-listed equipment are Q-list. In addition, motors for the vacuum and condensate pumps are Q-list.

5. All power and control circuit elements (such as circuit breakers , switches, relays , timers , fuses , cables , wiring, and panels, etc.) that provide a safety function are Q-list.

104 Volume XI Rev. 24

i l

Volume XI - Table I Common - All Units Prefixed as Unit No. 2

32. 2-F0 - Fuel Oil System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their -

operators (pneumatic including their controlling solenoid '

valve (s), manual and electric) that are designated F0D on drawings D-2268 (Rev. 10) and D-2269 (Rev. 10) are Q-list items except for the portions listed below:

a. All components downstream of valves:

2-F0D-V65 D-2268 2-F0D-V66 D-2268 2-F0D-V67 D-2269 2-F0D-V68 D-2269 2-F0D-V173 D-2268 2-F0D-V174 D-2268 2-F0D-V175 D-2269 2-F0D-V176 D-2269

b. All Fuel Oil System components external to the Diesel Generator Building and the diesel fuel oil storage tank chamber.

2. All of the following components shown on drawings D-2268 and D-2269 are Q-list items:

a. The following pumps:

(1) Fuel oil transfer.

(2) Motor-driven auxiliary fuel oil booster.

(3) Engine-driven booster.

b. The following tanks:

(1) Four-day storage tanks.

, (2) Fual oil day tanks.

c. Day tank flame arrestors.

d. Four-day tank flame arrestors.

e. Fuel oil duplex filter.

105 Volume XI Rev. 24

Volume XI . Table I Common - All Units Prefixed as Unit No. 2 32, 2-F0 - Fuel Oil System (cont'd)

f. The following strainers:

(1) Fuel oil duplax suction.

(2) Fuel oil duplex discharge.

B. Instrumentation and Electrical Components:

I

1. All of the following instruments (including their controls, '

power supplies,taountings, and interconnecting wiring) shown on drawings D-2268 (Rev. 10) and D-2269.(Rev. 10) are Q-list:

Instrument No. Drawing No.

FO-FIQ-3724 D-2268 FO-FIQ-3725 D-2268 4 FO-FIQ-3726 D-2269 i

FO-FIQ-3727 D-2269 2

FO-LG-1997 D-2268 FO-LG-2009 D-2268 FO-LG-2021 D-2269 FO-LG-2033 D-2269 t FO-LS-SLLS (1) D-2758 FO-LS-5LLS (2) D-2268 FO-LS-SLLS (3) D-2269 FO-LS-5LLS (4) D-2269 FO-LS-6LLS (1) D-2268 FO-LS-6LLS (2) D-2268 FO-LS-6LLS (3) D-2269 FO-LS-6LLS (4) D-2269 FO-LS-7LLS (1) D-2268 l FO-LS-7LLS (2) D-2268 FO-LS-7LLS (3) D-2269 FO-LS-7LLS (4) D-2269 FO-LS-2000 D-2268 FO-LS-2012 D-2268 FO-LS-2024 D-2269 FO-LS-2036 D-2269 FO-LS-2285 D-2268 FO-LS-2286 D-2268 FO-LS-2287 D-2269 FO-LS-2288 D-2269 FC-LSH-1LLS (1) D-2268 FO-LSH-1LLS (2) D-2268 FO-LSH-1LLS (3) D-2269 FO-LSH-ILLS (4) D-2269 106 Volu:ne XI Rev. 24

Volume XI - Table I Common - All Units Prefixed as Unit No. 2

32. 2-F0 - Fuel Oil System (cont'd)

Instrument No. Drawing No.

FO-LSL-3LLS (1) D-2268 FO-LSL-3LLS (2) D-2268 FO-LSL-3LLS (3) D-2269 FO-LSL-3LLS (4) D-2269 FO-PDS-9PS (1) D-2268 FO-PDS-9PS (2) D-2268 FO-PDS-9PS (3) D-2269 FO-PDS-9PS (4) D-2269 FO-PDS-11PS (1) D-2268 FO-PDS-11PS (2) D-2268 FO-PDS-11PS (3) D-2269 FO-PDS-11PS (4) D-2269 FO-PDS-12PS (1) D-2268 FO-PDS-12PS (2) D-2268 FO-PDS-12PS (3) D-2269 FO-PDS-12PS (4) D-2269 FO-PI-28-29 (1) D-2268 FO-PI-28-29 (2) D-2268 FO-PI-28-29 (3) D-2269 FO-PI-28-29 (4) D-2269

. FO-PI-1241 D-2268 FO-PI-1242 D-2268 FO-PI-1243 D-2268 FO-PI-1244 D-2268 FO-PI-1245 D-2269 FO-PI-1246 D-2269 FO-PI-1247 D-2269 FO-PI-1248 D-2269 FO-PI-1989 D-2268 FO-PI-1990 D-2268 FO-PI-1992 D-2268 FO-PI-1993 D-2268 l FO-PI-1994 D-2268 FO-PI-2001 D-2268 FO-PI-2002 D-2268 FO-PI-2004 D-2268 FO-PI-2005 D-2268 FO-PI-2006 D-2268 FO-PI-2013 D-2269 FO-PI-2014 D-2269 FO-PI-2016 D-2269 FO-PI-2017 D-2269 FO-PI-2018 D-2269 FO-PI-2025 D-2269 107 Volume XI Rev. 24

Volume XI - Table I Common - All Units Prefixed as Unit No. 2

32. 2-F0 - Fuel Oil System (cont'd)

Instrument No. Drawing No.

FO-PI-2026 D-2269 FO-PI-2028 D-2269 FO-PI-2029 D-2269 FO-PI-2030 D-2269

2. Motors for all motor driven Q-listed equipment are Q-list.

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

i i

108 Volume XI Rev. 24

Volume XI - Table I

33. 1-G16 - Radwaste System Prefilter Deep Bed A. Mechanical Components:

E 1. All piping, fittings and their supports, vtaves and their operators (pneumatic including their controlling solenoid

valve (s), manual and electric) that are designated G16 on drawing D-25045 (Rev.11) within the boundaries listed below are Q-list items

a. Downstream of valve G16-F018 up to and including G16-F020.

b. Downstream of valves G16-F002A and G16-F002B up to and including valve G16-F004.

c. Test connections from lines G16-502-3-152 and G16-504-3-152 up to and including valves G16-V1111 and G16-V1113, respectively.

d. Valve stem leak-off lines of containment isolation valves F003, F004, F019, and F020 up to and including valves V738, V739, V740, and V741, respectively,

e. Drain line from equipment drain tank heat exchanger up to and including valve G16-V695.

2. Equipment drain tank heat exchanger is a Q-list item.

l B. Instrumentation and Electrical Components:

Motors for all cotor driven Q-listed equipment are Q-list.

109 Volume XI Rev. 24 v w. , ,. -% -..y. .._ -_ _g.- m -

._.,r. - .-

i e

"'^

Volume XI - Table I Unit No. 2 and Common

34. 2-G16 - Radwaste System Prefilter Deep Bed A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid ,

valve (s), manual and electric) that are designated G16 on drawings D-2545 (Rev. 11), D-2531 (Rev. 27), D-2534 (Rev. 18),

D-2535 (Rev. 26), and D-2569 (Rev.16) within the boundaries listed below are Q-list items: '

a. Downstream of valve G16-F018 up to and including G16-F020, (D-2545). + t

. 'r

b. Downstream of valves G16-F002A and G16-F002B up to and including valve G16-F004 (D-2545).

c. Test connections from lines G16-502-3-152 and , ,

G16-504-3-152 up to and including valves G16-V1111 and G16-V1113, respectively (D-2545). A

d. Valve stem leak-off lines of containment isolation valves F003, F004, F019, and F020 up to and including valves V738, V739, V740, and V741, respectively (D-2545).

e. Drain line from equipment drain tank heat exchanger up to and including valve G16-V695 (D-2545).

f. From waste collector tank up to and including valves l G16-F034 and G16-V338 (D-2531).

g. From waste surge tank up to and including valves G16-V339, G16-F063, and G16-F061 (D-2531).

h. From waste neutralizer tanks up to and including valves G16-V600 through G16-V603 and G16-F225A through G16-F225D (D-2534).

i. From concentrated waste tank up to and including valve G16-F294 (D-1. 3). , ,

l j. From auxiliary surge tank up to and including valve G16-V448 (D-2569).

t

2. All of the following components are Q-list:

a. Equipment drain tank heat exchangers (D-2545).

l 110 Volume XI Rev. 24

7 --

+ -

l' y,f * ,

v -

,l

-. r F

Volume XI - Table I' . ,

Unit No. 2 and Common

\-'

34. 2-G16 - Radwaste System Prefilter Deep Bed (cont'd)

, i

)<

/ bi Waste collector tank ACO2 (D-2531),

i[ ,s 'i >

~

l

/ / /^

c. Wast's surge' tank A005 (D-2531).

f',J i, ' ".

, d. Waste' neutralizer tanks A025A, B, C, and D (D-2534).

1 ,

. r,.

/  !

e. Concentrated waste tank A026 (D-2535).

f. Auxiliary surge tank (D-2569).

g. Biological shielding.

~

B. Instrumentation and ElectricalTComponents: ,

4 Motors for all motor driven Q-listed equipment are Q-list.

f k

r

• i l f f,.

111 Volume XI i -

Rev. 24 e

Volume XI - Table I

35. 1-G31'- Reactor Water Cleanup - Filter Demineralizer System A. Mechanical Components:

1. 'All piping, fittings and their supports, valves and their

• operators (pneumatic including their controlling solenoid valve (s), ranual and electric) that are designated G31 on drawing D-25027-(Rev. 12) within the boundaries listed below are Q-list items:

a. System inlet line through primary containment up to and including valve G31-F004.

b. Reactor vessel drain line 16-2-603.

c. System inlet to and including test root valve G31-F003.

d. System outlet line downstream of and including valve G31-F042.

e. System outlet to and including test root valve G31-F038.

f. Leak-off lines upstream of and including valves G31-V41 through G31-V44.

B. Instrumentation and Electrical Comoonents:

1. All of the following instruments (including their controls, l power supplies, mountings, and interconnecting wiring) shown on drawings D-25027 (Rev. 12) and F-70083 (Rev. 10) are Q-list:

Instrument No. Drawing No.

G31-FDS-N603-1A D-25027 G31?FDS-N603-1B D-25027 G31-FE-N011 D-25027 G31-FE-N035 D-25027 G31-FE-N040 D-25027 G31-FT-N012 D-25027 G31-FT-NO36 D-25027 G31-FT-N041 D-25027 G31-FY-K602 D-25027 G31-FY-K603 D-25027 G31-FY-K604 D-25027 G31-FY-K605 D-25027 G31-TDS-N602A F-70083 j G31-TDS-N602B F-70083 G31-TDS-N602C F-70083 G31-TDS-N602D F-70083 G31-TDS-N602E F-70083 G31-TDS-N602F F-70083 i 112 Volume XI Rev. 24

Volume XI - Table I

35. 1-G31 - Reactor Water Cleanuo - Filter Demineralizer System (cont'd)

Instrument No. Drawing No.

G31-TE-N007 D-25027 G31-TE-N016A F-70083 G31-TE-N016B F-70083 G31-TE-N016C F-70083 G31-TE-N016D F-70083 G31-TE-N016E F-70083 G31-TE-N016F- F-70083 G31-TE-N022A F-70083 G31-TE-N022B F-70083 G31-TE-N022C F-70083 G31-TE-N022D F-70083 G31-TE-N022E F-70083 G31-TE-N022F F-70083 G31-TE-N023A F-70083 G31-TE-N023B F-70083 G31-TE-N023C F-70083 G31-TE-N023D F-70083 G31-TE-N023E F-70083 G31-TE-N023F F-70083 G31-TS-N008 D-25027 G31-TS-N600A F-70083 G31-TS-N600B F-70083 G31-TS-N600C F-70083

,G31-TS-N600D F-70083 G31-TS-N600E F-70083 G31-TS-N600F F-70083 l 2. Instruments pertaining to systems other than RWCU System that j provide isolation signals to RWCU System isolation valves are Q-list.

3. Motors for all motor driven Q-listed equipment are Q-list.

4. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list. ,

l l

l 113 Volume XI Rev. 24

l Volume XI - Table I

36. 2-G31 - Reactor Water Cleanup - Filter Demineralizer System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated G31 on drawing D-2527 (Rev. 18) within the boundaries listed below are Q-list items:

a. System inlet line through primary containment up to and including valve G31-F004.

b. Reactor vessel drain line 16-2-603.

c. System inlet to and including test root valve G31-F003.

d. System outlet line downstream of and including valve G31-F042.

e. System outlet to and including test root valve G31-F038.

f. Leak-off lines upstream of and including valves G31-V41 through G31-V44.

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on i drawings D-2527 (Rev. 18) and F-7083 (Rev. 13) are Q-list:

Instrument No. Drawing No.

G31-FDS-N603-1A D-2527 G31-FDS-N603-1B D-2527 G31-FE-N011 D-2527

- ~

G31-FE-NO35 D-2527 G31-FE-N040 D-2527 G31-FT-N012 D-2527 G31-FT-NO36 D-2527 G31-FT-N041 D-2527 G31-FY-K602 D-2527 G31-FY-K603 D-2527 G31-FY-K604 D-2527 G31-FY-K605 D-2527 j G31-TDS-N602A F-7083 G31-TDS-N602B F-7083 G31-TDS-N602C F-7083.

G31-TDS-N602D F-7083 114 Volume XI Rev. 24

Volume XI - Table I

36. 2-G31 - Reactor Water Cleanup - Filter Demineralizer System (cont'd)

Instrument No. Drawing No.

G31-TDS-N602E F-7083 G31-TDS-N602F F-7083 G31-TE-N007 D-2527 G31-TE-N016A F-7083 G31-TE-N016B F-7083 G31-TE-N016C F-7083 G31-TE-N016D F-7083 G31-TE-N016E F-7083 G31-TE-N016F F-7083 G31-TE-N022A F-7083 G31-TE-N022B F-7083 G31-TE-N022C F-7083 G31-TE-N022D F-7083 G31-TE-N022E F-7083 G31-TE-N022F F-7083 G31-TE-N023A F-7083 G31-TE-N023B F-7083 G31-TE-N023C F-7083 G31-TE-N025D F-7083 G31-TE-N023E F-7083 l G31-TE-N023F F-7083 G31-TS-N008 D-2527 G31-TS-N600A F-7083 G31-TS-N600B F-7083 G31-TS-N600C F-7083 G31-TS-N600D F-7083 G31-TS-N600E F-7083 G31-TS-N600F F-7083

2. Instruments pertaining to systems other than RWCU System that provide isolation signals to RWCU System isolation valves are Q-list.

3. Motors for all motor driven Q-listed equipment are Q-list.

4. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.  !

l 115 Volume XI

, Rev. 24

l Volume XI - Table I

37. 1-G41 - Fuel Pool Cocling and Filtering System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated G41 on drawing D-25049 (Rev. 9) within the boundaries listed below are Q-list items:

a. The following line numbers:

G41-1-8-154 G41-33-2-161 G41-2-8-154 G41-34-4-154 G41-3-12-154 G41-35-2-154 G41-12-8-300 G41-36-2-161 G41-13-6-152 G41-37-2-161 G41-13-8-152 G41-38-2-161 G41-15-8-152 G41-39-2-161 ,

G41-16-6-163 G41-40-4-154 G41-17-6-152 G41-41-2-154 G41-18-6-163 G41-42-2-154

! G41-28-4-154 G41-105-2-161 G41-29-2-154 G41-106-2-161 G41-30-2-161 G41-109-2-161 G41-31-2-161 G41-110-2-161 G41-32-2-161

b. Portions of line G41-3-8-154 from skimmer surge tank 1A to valve G41-F004.

c. Portions of line G41-74-3-154 downstream of valve G41-F014.

116 Volume XI Rev. 24

. _-- . .-,-. .-_,r. - , - _ . , -

Volume XI - Table I

37. 1-G41 - Fuel Pool Cooling and Filtering System (cont'd)

d. Portions of instrument lines between valves G41-V29 and V30 and the skimmer surge tank 1A.

e. The following valves:

G41-F004 G41-V9 G41-F011 G41-V10 G41-F014 G41-V24 G41-F016 G41-V29 G41-F036 G41-V30 G41-V8

2. Skimmer surge tanks 1A and 1B and their supports are Q-list items.

3. Pool cleanup return diffusers are Q-list items.

117 Volume XI Rev. 24 h

Volume XI - Table I

38. 2-G41 - Fuel Pool Cooling and Filtering System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their '

operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated G41 on drawing D-2549 (Rev. 11) within the boundaries listed below are Q-list items:

a. The following line numbers:

G41-1-8-154 G41-33-2-161 G41-2-8-154 G41-34-4-154 G41-3-12-154 G41-35-2-154 G41-12-8-300 G41-36-2-161 G41-13-6-152 G41-37-2-161 G41-13-8-152 G41-38-2-161 G41-15-6-152 G41-39-2-161 G41-16-6-163 G41-40-4-154 G41-17-6-152 G41-41-2-154 G41-18-6-163 G41-42-2-154 G41-28-4-154 G41-105-2-161 G41-29-2-154 G41-106-2-161 G41-30-2-161 G41-109-2-161 G41-31-2-161 G41-110-2-161 G41-32-2-161

b. Portions of line G41-3-8-154 from skimmer surge tank 2A to valve G41-F004.

c. Portions of line G41-74-3-154 downstream of valve G41-F014.

118 Volume XI Rev. 24

Volume XI - Table I

38. 2-G41 - Fuel Pool Cooling and Filtering System (cont'd)

d. Portions of instrument lines between valves G41-V29 and V30 and the shimmer surge tank.

e. The following valves:

G41-F004 G41-V9 G41-F011 G41-V10 G41-F014 G41-V24 G41-F016 G41-V29 G41-F036 G41-V30 G41-V8

2. Skimmer surge tanks 2A and 2B and their supports are Q-list items.

3. Pool cleanup return diffusers are Q-list items.

119 Volume XI Rev. 24

l l

i Volume XI - Table I I

39. 1-IA - Instrument Air System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valves, manual and electric) that are designated RNA (and associated air tubing) on drawings D-70029 (Rev.14), D-70077 (Rev. 8), D-70007 (Rev. 7), D-72006 (Rev. 11), and D-72009 l (Rev. 6) are Q-list except for those portions listed below:

a. Lines upstream of IAN-V56 and IAN-V57 (D-70029).

b. Drain lines from standby compressors 1A and IB after cooler traps (D-70029 and D-72006).

2. All valves and their operators, piping, fittings and their supports, that are shown on drawings D-25042 (Rev. 6),

F-2587 (Rev. 11), and D-72008 (Rev. 9) within the boundaries listed below are Q-list items:

a. Primary containment isolation valves SA-V448 and SA-V449 and piping between them (D-25042). -

b. Valve RIA-V452 and all components downstream of this valve including damper operators and instrumentation which are not shown on the drawing (F-2587).

c. Line 1-RNA-201-2-170 (D-72008).

d. Line 227-3/4-170 and air supply tubing to instruments 1-RIP-PSL-1200 and to operators for valves 1-CAC-PV-1200B, 1-CAC-PV-1261, 1-CAC-PV-3441, and 1-CAC-PV-3442 (D-72008).

3. All of the following components shown on drawings D-70029 (Rev. 14) and D-72006 (Rev. 11) are Q-list:

a. Standby compressors 1A and IB and their ancillaries such as oil filters, aftercoolers, and compressed air traps (D-70029 and D-72006).

b. Vibration isolators used in conjunction with the standby compressors (D-70029 and D-72006).

120 Volume XI Rev. 24

l l

1

~

Volume XI - Table I

39. 1-IA - Instrument Air System (cont'd)

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings D-70029 (Rev. 14), D-70077 (Rev. 8), D-72006 (Rev. 11) l and D-72008 (Rev. 9) are Q-list:

Instrument No. Drawing No.

IA-PI-3785 D-72006 IA-PI-3786 D-70029 IA-PSL-3594 D-72006 IA-PSL-3595 D-70029 IA-PSL-3596 D-72006 IA-PSL-3597 D-70029 RIP-PSL-1200 D'-72008 RIP-PSL-1201 D-72006 RIP-PSL-1203 D-72006 RIP-PSL-1204 D-70029 RIP-PSL-1205 D-70029 RIP-PSL-1206 D-70077 RIP-PSL-1207 D-70077 RIP-PSL-1208 D-70077 RIP-PSL-1209 -

D-70077 RIP-PSL-1210 D-70077 RIP-PSL-1211 D-70077 RIP-PSL-1212 D-70077 RIP-PSL-1214 D-70029 RIP-PSL-1215 D-70029 RIP-PSL-1217 D-72006 RIP-PSL-1218 D-70029 RIP-PSL-1219 D-70029 RIP-PSL-1220 D-70029 RIP-PSL-1221 , D-70029 '

RIP-PSL-1222 D-70077 RIP-PSL-1223 D-70077 RIP-PSL-1224 D-70077 RIP-PSL-1225 D-70077 RIP-PSL-1226 D-70077 RIP-PSL-1227 D-70077 RIP-PSL-1228 D-70029 RIP-PSL-1229 D-70029 RIP-PSL-1231 D-70029 RIP-PSL-1232 D-70029 RIP-PY-1200 D-72008

- RIP-PY-1201 D-72006 RIP-PY-1203 D-72006 RIP-PY-1204 D-70029 121 Volume XI Rev. 24

Volume XI - Table I-1

39. 1-IA - Instrument Air System (cont'd)

Instrument No. Drawing No.

RIP-Pi-1205 D-70029 RIP-PY-1206 D-70077 RIP-PY-1207 D-70077 RIP-PY-1208 D-70077 RIP-PY-1209 D-70077 RIP-PY-1210 D-70377 RIP-PY-1211 D-70077 RIP-PY-1212 D-70077 RIP-PY-1214 D-70029 RIP-PY-1215 D-70029 RIP-PY-1217 D-72006 RIP-PY-1218 D-70029 RIP-PY-1219 D-70029 RIP-PY-1220 D-70029 RIP-PY-1221 D-70029 RIP-PY-1222 D-70077 RIP-PY-1223 D-70077 RIP-PY-1224 D-70077 RIP-PY-1225 D-70077 RIP-PY-1226 D-70077 RIP-PY-1227 D-70077 RIP-PY-1228 D-70029 RIP-PY-1229 D-70029 RIP-PY-1231 D-70029 RIP-PY-1232 D-70029

2. Panels at nodes 1-J58, 1-J59, 1-JU6, 1-JU9, 1-JX2, 1-JX3, and all items mounted in/on them are Q-list items except for nameplates, indicating lamps, internal panel lighting, and panel ventilation systems are Q-list.

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

4. Motors for all motor driven Q-listed equipment are Q-list.

122 Volume XI Rev. 24

Volume XI - Table I

- 40. 2-IA - Instrument Air System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valves, manual and electric) that are designated RNA on drawings D-7029 (Rev. 19), D-7077 (Rev. 9), D-7007 (Rev. 15),

D-7206 (Rev.16), and D-7209 (Rev. 7) are Q-list items except for those portions listed below:

a. Lines upstream of IAN-V56 and IAN-V57 (D-7029).

b. Drain lines from standby compressors 2A and 2B after cooler traps (D-7029).

2. All valves and their operators, piping, fittings and their supports that are shown on drawings D-2542 (Rev. 4),

F-2587 (Rev.11), and D-7208 (Rev.12) within the boundaries listed below are Q-list items: ,

a. Primary containment isolation valves SA-V448 and SA-V449 and piping between them (D-2542).

b. Valve RIA-V452 and all components downstream of this valve including damper operators and instrumentation which are not shown on the drawing (D-2587).

c. Line 2-RNA-201-2-170 (D-7208).

d. Line 227-3/4-170 and air supply tubing to bastrument 2-RIP-PSL-1200 and to operators for valve 2-CAC-PV-1200B (D-7208).

e. Line 2-RNA-305-3/4-172 and supply air piping to the operator for valve 2-CAC-PV-1261 (D-7208).

i

3. All of the following components shown on drawings D-7029 (Rev. 19) and D-7206 (Rev. 16) are Q-list:

{ a. Standby compressors and their ancillaries such as oil

filters, afterccolers, and compressed air traps (D-7029).

_ b. Vibration isolators used in conjunction with the standby compressors (D-7029).

i 123 Volume XI Rev. 24 4

e v v r- --

pep ww,wmm~--4-.py-w .e-+-

~

n., ---+n,,g-- - n , men,--.. m--m-g,,, ,,.--~-,,nm- r.J-

i Volume XI - Table I

40. 2-IA - Instrument Air System (cont'd)

B. Instrumentation and Electrical Components

1. All of the following instruments (including their controls,'

power supplies, mountings, and interconnecting wiring) shown on drawings D-7029 (Rev. 19), D-7077 (Rev. 9), D-7206 (Rev. 16),

D-7208 (Rev. 12), and F-2587 (Rev. 11) are Q-list:

4 Instrument No. Drawing No.

IA-PI-3785 D-7029 IA-PI-3786 D-7029 IA-PSL-3099 F-2587 IA-PSL-3168 F-2587 IA-PSL-3594 D-7029 IA-PSL-3595 D-7029 IA-PSL-3596 D-7029 IA-PSL-3597 D-7029 IA-PT-3097 F-2587 RIP-PSL-1200 . D-7208 RIP-PSL-1201 D-7206 RIP-PSL-1203 D-7206 RIP-PSL-1204 D-7029 RIP-PSL-1205 D-7029 RIP-PSL-1206 D-7077 RIP-PSL-1207 D-7077 RIP-PSL-1208 D-7077 RIP-PSL-1209 D-7077 RIP-PSL-1210 D-7077 .

RIP-PSL-1211 D-7077 RIP-PSL-1212 D-7077 RIP-PSL-1214 D-7029 RIP-PSL-1215 D-7029 RIP-PSL-1217 D-7206 RIP-PSL-1218 " ' " - ' ~ ~ - ~

D-7029 xir-esL-1219 D-7029 RIP-PSL-1220 D-7029 RIP-PSL-1221 D-7029 RIP-PSL-1222 D-7077 RIP-PSL-1223 D-7077 RIP-PSL-1224 D-7077 RIP-PSL-1225 D-7077 RIP-PSL-1226 D-7077 RIP-PSL-1227 D-7077 RIP-PSL-1228 D-7029 RIP-PSL-1229 D-7029 '

RIP-PSL-1231 D-7029 RIP-PSL-1232 D-7029 l

124 Volume XI Rev. 24 l

Volume XI - Table I

40. 2-IA - Instrument Air System (cont'd)

Instrument No. Drawing No.

RIP-PY-1200 D-7208 RIP-PY-1201 D-7206 RIP-PY-1203 D-7206 RIP-PY-1204 D-7209 RIP-PY-1205 D-7209 RIP-PY-1206 D-7077 RIP-PY-1207 D-7077 RIP-PY-1208 D-7077 RIP-PY-1209 D-7077 RIP-PY-1210 D-7077 RIP-PY-1211 D-7077 RIP-PY-1212 D-7077 RIP-PY-1214 D-7029 RIP-PY-1215 D-7029 RIP-PY-1217 D-7206 RIP-PY-1218 D-7029 RIP-PY-1219 D-7029 RIP-PY-1220 D-7029 RIP-PY-1221 D-7029 RIP-PY-1222 D-7077 RIP-PY-1223 D-7077 RIP-PY-1224 D-7077 RIP-PY-1225 D-7077 RIP-PY-1226 D-7077 RIP-PY-1227 D-7077 RIP-PY-1228 D-7029 RIP-PY-1229 D-7029 RIP-PY-1231 D-7029 RIP-PY-1232 D-7029

2. Panels at nodes 2-J58, 2-J59, 2-JU6, 2-JU9, 2-JX2, 2-JX3, and all items mounted in/on them are Q-list items except for nameplates, indicating lamps, internal panel lighting, and panel ventilation systems are Q-list.

3. All power and control circuit elements (such as circuit breakers , switches , ' relays , timers , fuses , cables , wiring, and panels, etc.) that provide a safety function are Q-list.

4. Motors for all motor driven Q-listed equipment are Q-list.  ;

i l

l 125 Volume XI Rev. 24 i I.

-9

.. -s-y------vi-i---4,-, -- -a---- -+ m 9 -.i-- i me-w- - -mmy-- w--* -

g --m+-r-.

Volume XI - Table I Comeen - All Units Prefixed as Unit No. 2

41. 2 Lube Oil System A. Mechanical Components:

1. All piping, fittings, and their supports, valves and their operators (pneumatic including their controlling solenoid valves (s), manual and electric) that are designated LO on drawings D-2270 (Rev. 6) and D-2271 (Rev. 6)-are Q-list items except for the portions listed below:

a. All components downstream of the following lube oil valves:

Instrument No. Drawing No.

2-LO-IV-1153 D-2270 2-LO-IV-1163 D-2270 2-LO-IV-1173 D-2271 2-LO-IV-1183 D-2271 2-LO-V249 D-2270 2-LO-V253 D-2270 2-LO-V254 D-2270 2-LO-V266 D-2270 2-LO-V270 D-2270

. 2-LO-V272 D-2270 2-LO-V273 D-2270 2-LO-V285 D-2270 2-LO-V289 D-2270 2-LO-V290 D-2270 2-LO-V302 D-2270 2-LO-V306 D-2270 2-LO-V308 D-2270 2-LO-V309 D-2270' 2-LO-V321 D-2271 2-LO-V325 D-2271 2-LO-V326 D-2271 2-LO-V338 D-2271 2-LO-V342 D-2271 2-LO-V344 D-2271

~

2-LO-V345 D-2271 2-LO-V357 D-2271 2-LO-V361 D-2271 2-LO-V362 D-2271 2-LO-V374 D-2271 2-LO-V378 D-2271 2-LO-V380 D-2271 2-LO-V381 D-2271 126 Volume XI Rev. 24

Volume XI - Table I Common - All Units Prefixed as Unit No. 2

41. -LO - Lube Oil System (cont'd)

2. All of the following components shown on drawings D-2270 and D-2771 are Q-list items:

a. The following pumps:

(1) Motor-driven auxiliary lube oil.

(2) Engine-driven lube oil.

(3) Filter and prelube.

b. Lube oil bypass filters.

c. Lube oil bypass heaters,

d. The following strainers:

(1) Lube oil suction.

(2) Lube oil duplex.

a. Lube oil coolers.

B. I_nstrumentation and Electrical Components: .

i 1. All of the following instruments (including their controls, i- power supplies, mountings, and interconnecting wiring) shown on drawings D-2270 (Rev. 6) and D-2271 (Rev. 6) are Q-list:

Instrument No. Drawing No.

LO-FG-2618 D-2270 LO-FG-2622 D-2270 LO-FG-2626 D-2271 LO-FG-2630 D-2271 LO-LG-2615 D-2270 LO-LG-2619 D-2270 LO-LG-2623 D-2271 LO-LG-2627 D-2271 LO-LS-4LLS (1) D-2270 LO-LS-4LLS (2) D-2270 LO-LS-4LLS (3) D-2271 LO-LS-4LLS (4) D-2271 LO-PDS-8PS (1) D-2270 LO-PDS-8PS (2) D-2270 LO-PDS-8PS (3) D-2271 LO-PDS-8PS (4) D-2271 127 Volume XI Rev. 24 s

l l

Voluma XI - Table I l Common - All Units Prefixed as Unit No. 2 41, 2-LO - Lube 011 System (cont'd)

Instrument No. Drawing No.

LO-PDS-10PS (1) D-2270 LO-PDS-10PS (2) D-2270 LO-PDS-10PS (3) D-2271 LO-PDS-10PS (4) D-2271 LO-PI-22-23 (1) D-2270 LO-PI-22-23 (2) D-2270 LO-PI-22-23 (3) D-2271 LO-PI-22-23 (4) D-2271 LO-PI-1450 D-2270 LO-PI-1451 D-2270 LO-PI-1452 D-2270 LO-PI-1453 D-2270 LO-PI-1455 D-2270 LO-PI-1465 D-2270 LO-PI-2039 D-2270 LO-PI-2041 D-2270 LO-PI-2043 D-2270 LO-PI-2044 D-2270 LO-PI-2045 D-2270 LO-PI-2046 D-2270 LO-PI-2047 D-2270 LO-PI-2055 D-2270 LO-PI-2056 D-2270 LO-PI-2058 D-2270 LO-PI-2064 D-2271 LO-PI-2066 D-2271 LO-PI-2067 D-2271 LO-PI-2069 D-2271 LO-PI-2070 D-2271 LO-PI-2078 D-2271 LO-PI-2079 D-2271 LO-PI-2081 D-2271 LO-PI-2087 D-2271 LO-PI-2089 D-2271 LO-PI-2090 D-2271 LO-PI-2092 D-2271 LO-PI-2093 D-2271 LO-PI-2101 D-2271

• LO-PI-2102 D-2271 LO-PI-2104 D-2271 LO-PS-14PS (1) D-2270 LO-PS-14PS (2) D-2270 LO-PS-14PS (3) D-2271 l LO-PS-14PS (4) D-2271 l l

128 Volume XI Rev. 24

. . . . . - _ , - - - _ ~ - , . - _ - -.

Volume XI - Table I Common - All Units Prefixed as Unit No. 2

41. 2-LO - Lube Oil System (cont'd)

Instrument No. Drawing No.

LO-PS-ISPS (1) D-2270 LO-PS-ISPS (2) D-2270 LO-PS-ISPS (3) D-2271 LO-PS-ISPS (4) D-2271 LO-PS-200PS (1) D-2270 i

LO-PS-200PS (2) D-2270 LO-PS-200PS (3) D-2271 LO-PS-200PS (4) D-2271

2. Motors for all motor driven Q-listed equipment are Q-list.

, 3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

4

l. .

i 129 Volume XI Rev. 24 f

[.

Volume XI - Table I

42. 1-MS - Main Steam A. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls,'

power supplies, countings, and interconnecting wiring) shown on drawings D-20020 (Rev. 17) and D-20024 (Rev. 4) are Q-list:

- Instrument No. Drawing No.

EHC-PSL-1756 D-20020 EHC-PSL-1757 D-20020 EHC-PSL-1758 D-20020 EHC-PSL-1759 D-20020 MS-PSL-890 D-20024

2. All power and control circuit elements (such as circuit-breakers, switches, relays, timers, fuses, cables, wiring,.

panels, etc.) that provide a safety function are Q-list.

l 130 Volume XI Rev. 24 n

Volume XI - Table I

43. 2-MS - Main Steam A. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings D-2020 (Rev. 17) and D-2024 (Rev. 5) are Q-list:

Instrument No. Drawing No.

EHC-PSL-1756 D-2020 EHC-PSL-1757 D-2020 EHC-PSL-1758 D-2020 EHC-PSL-1759 D-2020 MS-PSL-890 D-2024

2. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, panels, etc.) that provide a safety function are Q-list.

i r

4 4

131 Volume XI Rev. 24

Volume XI - Table I Common - All Units Prefixed as Unit No. 2 44, 2-MUD - Make-up Demineralizer System l

A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated MUD on drawings D-2272 (Rev. 3), D-2273 (Rev. 3), and D-2274 (Rev. 5) are Q-list items except for the portions listed below:

a. Jacket water expansion tank vent lines.

b. Jacket water expansion tank overflow lines.

c. All components downstream of the following valves:

2-MUD-V100 D-2272 2-MUD-V101 D-2272 2-MUD-V102 D-2273 2-MLT-V103 D-2273 2-E'D-V139 D-2272 2-MUD-V145 D-2272 2-E'D-V148 D-2272 2-MUD-V168 D-2272 2-MUD-V169 D-2272 2-MUD-V175 D-2272 2-MUD-V181 D-2272 2-MUD-V184 D-2272 2-MUD-V204 D-2272 2-MUD-V205 D-2272 2-MUD-V211 D-2273 2-MUD-V217 D-2273 2-MUD-V220 D-2273 2-MUD-V240 D-2273 2-MUD-V241 D-2273 2-MUD-V247 D-2273 2-MUD-V253 D-2273 2-MUD-V256 D-2273 2-MUD-V276 D-2273 2-MUD-V277 D-2273 2-MUD-IV-1155 D-2272 2-MUD-IV-1165 D-2272 2-MLT-IV-1175 D-2273 2-MUD-IV-1185 D-2273

d. Chemical injection and fill connections upstream of valves 2-MUD-V104 th' rough V107 for jacket water expansion tanks.

132 Volume XI Rev. 24

Volume XI - Table I Common - All Units Prefixed as Unit No. 2

44. 2-MUD - Make-up Demineralizer System (cont'd)

e. Portions of the demineralized water supply line external to the Diesel Generator Building and the diesel fuel oil storage tank chamber.

2. All of the following components shown on drawings D-2272, and D-2274 are Q-list:

i a. The following pumps:

(1) Motor-driven auxiliary jacket water.

(2) Engine-driven jacket water.

(3) Heater circulating.

b. Jacket water expansion tanks.

c. Jacket water coolers.

d. Jacket water heaters.

B. Instrumentation and Electrical Comoonents:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings D-2272 (Rev. 3) and D-2273 (Rev. 3) are Q-list:

Instrument No. Drawing No.

, MUD-LG-2132 D-2272 MUD-LG-2158 D-2272 MUD-LG-2186 D-2273 MUD-LG-2213 D-2273 MUD-PI-21 (1) D-2272 ET-PI-21 (2) D-2272 MUD-PI-21 (3) D-2273 MUD-PI-21 (4) D-2273 ET-PI-2108 D-2272 MUD-PI-2111 D-2272 MUD-PI-2113 D-2272 MUD-PI-2115 D-2272 MUD-PI-2119 D-2272 MUD-PI-2120 D-2272 MUD-PI-2121 D-2272 MUD-PI-2128 D-2272 E'D-PI-2135 D-2272

- ET-PI-2138 D-2272 ET-PI-2140 D-2272 E'D-PI-2142 D-2272 MUD-PI-2146 D-2272 133 Volume XI Rev. 24

_- ..a.__ , -_ _ , _ - _ _ _

Volume XI - Table I Common - All Units Prefixed as Unit No. 2

44. 2-MUD - Make-up Demineralizer System (cont'd)

Instrument No. Drawing No.

MUD-PI-2147 D-2272 MUD-PI-2148 D-2272 MUD-PI-2154 D-2272 MUD-PI-2163 D-2273 MUD-PI-2165 D-2273 MUD-PI-2167 D-2273 MUD-PI-2169 D-2273 MUD-PI-2173 D-2273 MUD-PI-2174 D-2273 M'JD-PI-2175 D-2273 MUD-PI-2182 D-2273 MUD-PI-2189 D-2273 MUD-PI-2192 D-2273 MUD-PI-2194 D-2273 MUD-PI-2196 D-2273 MUD-PI-2200 D-2273 MUD-PI-2201 D-2273 MUD-PI-2202 D-2273 MUD-PI-2209 D-2273 MUD-PS-2PS (1) D-2272 MUD-PS-2PS (2) D-2272 MUD-PS-2PS (3) D-2273 MQ-PS-2PS (4) D-2273 MUD-PS-201PS (1) D-2272 MUD-PS-201PS (2) D-2272 MUD-PS-201PS (3) D-2273 MUD-PS-201PS (4) D-2273

2. Motors for all motor driven Q-listed equipment are Q-list.

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety functicn are Q-list.

r i

I l

l 134 Volume XI

[ Rev. 24 i

Volume XI - Table I

45. 1-0G - Off-Gas System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated OG and AR on drawings D-20025 (Rev. 18) and D-4104 (Rev. 12) within the boundaries listed below are Q-list items:

a. From valve OG-V41 to valve D12-F010 including valve OG-V41 (D-20025).

b. From valves OG-V35 and OG-V36 to valves D12-F011 and F012 including valves OG-V35 and OG-V36 (D-20025).

c. Valves AR-V9, AR-V10, and OG-V7 through OG-V13 (D-20025) and OG-HCV-102.

d. Solenoid operated valves OG-SV-249 and OG-SV-251 through OG-SV-253 (D-4104).

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls., -

power supplies, mountings, and interconneccing wiring) shown on drawing D-20025 (Rev. 18) are Q-list:

Instrument No. Drawing No.

OG-PSH-240 D-20025 OG-PSH-241 D-20025 OG-PSH-2754 D-20025 OG-PSH-2755 D-20025 OG-TE-242 D-20025 OG-TE-243 D-20025 OG-TE-2752 D-20025 OG-TE-2753 D-20025 OG-TIS-242 D-20025 OG-TIS-243 D-20025 OG-TIS-2752 D-20025 OG-TIS-2753 D-20025

2. Radiation Monitors (refer to Process Radiation Monitoring System) that provide auto trip signals to mechanical vacuum pumps and valves AR-V9, AR-V10, and OG-V7 are Q-list (D-4104).

135 Volume XI Rev. 24

l Volume XI - Table I

45. 1-0G - Off-Gas System 3 '. Main steam instrumentation (refer to Main Steam Syst?.m) that provide auto trip signals to valves OG-V8 through OG-V13 are 4

Q-list.

4. Motors-for all motor driven Q-listed equipment are Q-list.

5. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, panels, etc.) that provide a safety function are Q-list items.

i 136 Volume XI Rev. 24 .

Volume XI - Table I

46. 2-0G - Off-Gas System A. Mechanical Components:

1. All piping, fittings and their supports, valves and tL._r

• operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated OG and AR on drawings D-4104 (Rev. 12) and D-2025 (Rev. 18) within the boundaries listed below are Q-list items:

a. From valve OG-V41 to valve D12-F010 including valve OG-V41 (D-2025).

b. From valves OG-V35 and OG-V36 to valves D12-F011 and F012 including valves OG-V35 and OG-V36 (D-2025).

c. Valves AR-V9, AR-V10, OG-V7 through OG-V13 (D-2025) and OG-HCV-102.

d. Solenoid operated valves OG-SV-249 through OG-SV-253 (D-4104).

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawing D-2025 (Rev. 18) are Q-list:

Instrument No. Drawing No.

OG-PSH-240 D-2025 OG-PSH-241 D-2025 OG-PSH-2734 D-2025 OG-PSH-2755 D-2025 OG-TE-242 D-2025 OG-TE-243 D-2025

-"~ OG-TE-2752 D-2025 OG-TE-2753 D-2025 OG-TIS-242 D-2025 OG-TIS-243 D-2025 OG-TIS-2752 D-2025 OG-TIS-2753 -

D-2025

2. Radiation monitors (refer to Process Radiation Monitoring System) that provide auto trip signals to mechanical vacuum pumps and valves AR-V9, AR-V10, and CG-V7 are Q-list (D-2025).

l 137 Volume XI l Rev. 24

2 Volume XI - Table I .

46. 2-0G - Off-Gas System (cont'd)

[

3. Main steam instrumentation (refer to Main Steam System) that ,

provides auto trip signals to valves OG-V8 through OG-V13 are Q-list.

4. Motors for all motor driven Q-listed equipment are Q-list.

5. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, panels, etc.) that provide a safety function are Q-list items.

138 Volume XI Rev. 24

(r k

f .,

t i Volume XI b Table-I 4 47. 1 and 2 '. Primary Containment Penetratichs All primary'centain' ment penetrations assemblies (including all piping, personnel and' equipment hatches, and electrical penetrations) are Q-1,ist

(

~

items. 0/ g, i

.d hl> *

(

8, c

.c 4'

'. I f

1. s L J s

, _. 1, y s .

\

4 r

6 l

l

\1

.i j .' ,

s

g s

i

. s

\

r; -

t

'Jn

(

139 Volume XI Rev. 24 4

4-w ,--r _-->e-e-c-. - . . + * - + - t ----- r w-- c--v+--r-+--v= - - - - - ,=~v-+ -r-- - - - --- - e ----- <-- --+~-*-- =-

Volume XI - Table I

48. 1-RCC - Reactor Building Closed Cooling Water A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated RCC on drawings D-25038 (Rev. 9), and D-25045 (Rev.11) within the boundaries listed below are Q-list items:

a. From and including valve RCC-V52 up to the containment cooling coils, recirculation pump heat exchangers, and drywell equipment drain heat exchangers and from these items to and including valves RCC-V28 and RCC-PV-1222B and C (D-25038).

b. Cooling coil vents up to and including valve; p 'C-V254 through RCC-V261 (D-25038).

c. Drain lines RCC-89-1-152 through RCC-96-1-152 (D-25038).

d. Vent line RCC-131-1-152 and valve RCC-V182 (D-25038).

e. Lines RCC-188-4-152 and RCC-189-4-152 (D-25038).

f. Equipment drain tank heat exchanger vent line up to and including RCC-V95 (D-25045),

2. All penetration cooling piping, fittings, and their supports and valves which are designated RCC on drawing 9527-D-25041 (Rev. 2) are Q-list items except those portions of vents and drains downstream of the following valves:

RCC-V197 RCC-V218 RCC-V237 RCC-V201 RCC-V220 RCC-V239 RCC-V203 RCC-V222 RCC-V241 RCC-V204 RCC-V224 RCC-V243 RCC-V206 RCC-V226 RCC-V245 RCC-V208 RCC-V228 RCC-V246 RCC-V210 RCC-V230 RCC-V248 RCC-V213 RCC-V232 RCC-V250 140 Vclume XI Rev. 24

l l

l Volume XI - Table 1

48. 1-RCC - Reactor Building Closed Cooling Vater (cont'd)

RCC-V215 RCC-V234 RCC-V252 RCC-V217 RCC-V235 RCC-V262 - RCC-V293

3. Air operators and their associated solenoid valves for the following non-Q-list valves shows. on drawing D-25038 are Q-list items:

RCC-V75 RCC-TV-695

4. The following components shown on drawing D-25038 are Q-list:

RBCCW heat exchangers A, B, and C.

B. Instrumentation and Electrical Components:

Motors for all motor driven Q-listed equipment are Q-list.

I 141 Volume XI Rev. 24

l l

l Volume XI - Table I '

49, 2-RCC - Reactor Buildina Closed Coolina Water A. Mechanical Components:

, 1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated RCC on drawings D-2538 (Rev. 10), and D-2545 (Rev. 11) within the boundaries listed below are Q-list items:

a. From and including valve RCC-V52 up to the containment cooling coils, recirculation pump heat exchangers, and drywell equipment drain heat exchangers and from these items to and including valves RCC-V28 and RCC-PV-1222B and C (D-2538).

b. Cooling coil vents up to and including valves RCC-V254

.through RCC-V261 (D-2538).

c. Drain lines RCC-89-1-152 through RCC-96-1-152 (D-2538).

d. Vent line RCC-131-1-152 and valve RCC-V182 (D-2538).

e. Lines RCC-188-4-152 and RCC-189-4-152 (D-2538).

f. Equipment drain tank heat exchanger vent line up to and including RCC-V95 (D-2545).

2. All penetration cooling piping, fittings, and their supports and valves .which are designated RCC on drawing 9527-D-2541 (Rev. 2) are Q-list items except those portions of vents and drains downstream of the following valves:

RCC-V197 RCC-V218 RCC-V237 RCC-V201 RCC-V220 RCC-V239 RCC-V203 RCC-V222 RCC-V241 RCC-V204 RCC-V224 RCC-V243 RCC-V206 RCC-V226 RCC-V245 RCC-V208 RCC-V228 RCC-V246 RCC-V210 RCC-V230 RCC-V248 RCC-V213 RCC-V232 RCC-V250 142 Volume XI Rev. 24

s Volume XI - Table I

49. 2-RCC - Reactor Building Closed Cooling Water (cont'd)

RCC-V215 RCC-V234 RCC-V252 RCC-V217 RCC-V235 RCC-V262 - RCC-V293

3. Air operators and their associated solenoid valves for the following non-Q-list valves shown on drawing D-2538 are Q-list items:

RCC-V73 RCC-V74 RCC-TV-695

4. The following components shown on drawing D-2538 are Q-list:

RBCCW heat exchangers A, B, and C.

B. Instrumentation end Electrical Components:

Motors for all motor driven Q-listed equipment are Q-list.

143 Volume XI Rev. 24

I I

Volume XI - Table I

50. 1-SGT - Standby Gas Treatment System A. Mechanical Components:

1. All piping, fittings and their supports, and valves and the'ir operators (pneumatic, including their controlling solenoid valve (s), manual and electric) that are designated SGT on drawings F-40073 (Rev. 16) and D-4104 (Rev. 11) within the boundaries listed below are Q-list items.

a. Lines Nos.:

SGT-CD-1-2-159A (D-4104) SGT-6-24 (F-40073)

SGT-1-18 (F-40073) SGT-oA-24 (F-40073)

SGT-1A-1/2 (F-40073) SGT-6B-24 (F-40073)

SGT-1A-1 1/2 (F-40073) SGT-7-24 (D-4104, F-40073)

SGT-2-18 (F-40073) SGT-8-24 (F-40073)

SGT-3-18 (F-40073) SGT-9-24 (F-40073)

SGT-4-18 (F-40073) SGT-10-30 (F-40073)

SGT-5-18 (F-40073) SGT-11-18 (F-40073)

b. Discharge duct underground to stack.

c. Loop seal from demisters (D-4104).

d. Valve Nos.:

A-BFCV-RB (F-40073) I-BFV-RB (F-40073)

B-BFCV-RB (F-40073) N-BFV-RB (F-40073)

A-BFV-RB (F-40073) SGT-V1 (F-40073)

B-BFV-RB (F-40073) SGT-V2 (F-40073)

C-BFV-RB (F-40073) SGT-V3 (D-4104)

D-BFV-RB (F-40073) SGT-V8 (F-40073)

E-BFV-RB (F-40073) SGT-V9 (F-40073)

F-BFV-RB (F-40073) SGT-V10 (F-40073)

G-BFV-RB (F-40073) SGT-Vil (F-40073) i H-BFV-RB (F-40073)

~2. All of the following components shown on drawing F-40073 are Q-list items:

a. SGT Filter Systems A-RB and B-RB.

b. Blowers A-SBGT-EF-RB and B-SBGT-EF-RB.

c. System piping expansion joints.

144 Volume XI Rev. 24

Volume XI - Table I

50. 1-SGT - Standby Gas Treatment System (cont'd)

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls,'

power supplies, mountings, and interconnecting wiring) shown on FP-4404 (Rev. 0) are Q-list:

Instrument No. Drawing No.

SGT-TS-1A FP-4404 SGT-TS-1B FP-4404 SGT-TS-2A FP-4404 SGT-TS-2B FP-4404 SGT-TS-3A FP-4404 SGT-TS-3B FP-4404 SGT-TS-4A FP-4404 SGT-TS-4B FP-4404 SGT-TS-5A FP-4404 SGT-TS-5B FP-4404 SGT-TS-6A FP-4404 SGT-TS-68 FP-4404 SGT-TS-7A FP-4404 SGT-TS-7B FP-4404

2. Motors for all motor driven Q-listed equipment are Q-list.

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function.

i 145 Volume XI Rev. 24

, r , , c - - ---. - - - - - ,- . , , - - , - , . - , .

l l

Volume XI - Table I

51. 2-SGT - Standby Gas Treatment System A. Mechanical Components:

1. All piping, fittings and their supports, and valves and the'ir i operators (pneumatic, including their controlling solenoid valve (s), manual and electric) that are designated SGT on drawings F-4073 (Rev.18) and D-4104 (Rev.11) within the boundaries listed below are Q-list items. I

a. Lines Nos.:

SGT-CD-1-2-159A (D-4104) SGT-6-24 (F-4073)

SGT-1-18 (F-4073) SGT-6A-24 (F-4073)

SGT-1A-1/2 (F-4073) SGT-6B-24 (F-4073)

SGT-1A-1 1/2 (F-4C73) SGT-7-24 (D-4104, F-4073)

SGT-2-18 (F-4073) SGT-8-24 (F-4073)

SGT-3-18 (F-4073) SGT-9-24 (F-4073)

SGT-4-18 (F-4073) SGT-10-30 (F-4073)

SGT-5-18 (F-4073) SGT-11-18 (F-4073)

b. Discharge duct underground to stack.

c. Loop seal from demisters (D-4104).

d. Valve Nos.: ,

A-BFCV-RB (F-4073) I-BFV-RB (F-4073)

B-BFCV-RB (F-4073) N-BFV-RB (F-4073)

A-BFV-RB (F-4073) SGT-V1 (F-4073)

B-BFV-RB (F-4073) SGF-V2 (F-4073)

C-BFV-RB (F-4073) SGF-V3 (D-4104)

D-BFV-RB (F-4073) SGT-V6 (F-4073)

E-BFV-RB (F-4073) SGT-V7 (F-4073)

F-BFV-RB (F-4073) SGT-V8 (F-4073)

G-BFV-RB (F-4073) SGT-V9 (F-4073)

H-BFV-RB (F-4073) SGT-V10 (F-4073)

SGT-Vil (F-4073)

2. All of the following components shown on drawing F-4073 are Q-list items:

a. SGT Filter Systems A-RB and B-RB.

b. Blowers A-SBGT-EF-RB and B-SBGT-EF-RB.

c. System piping expansion joints.

146 Volume XI Rev. 24

Volume XI - Table I

51. 2-SGT - Standby Gas Treatment System (cont'd)

B. Instrumentation and Electrical Comconents:

1. All of the following instruments (including their controls,*

power supplies, mountings, and interconnecting wiring) shown on FP-4404 (Rev. 0) are Q-list:

Instrument No. Drawing No.

SGT-TS-1A FP-4404 SGT-TS-1B FP-4404 SGT-TS-2A FP-4404 SGT-TS-2B FP-4404 SGT-TS-3A FP-4404 SGT-TS-3B FP-4404 SGT-TS-4A FP-4404 SGT-TS-4B FP-4404 SGT-TS-SA FP-4404 SGT-TS-5B FP-4404 SGT-TS-6A FP-4404 SGT-TS-6B FP-4404 SGT-TS-7A FP-4404 SGT-TS-7B FP-4404

2. Motors for all motor driven Q-listed equipment are Q-list.

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function.

g.oa I

147 Volume XI Rev. 24 1

i

Volume XI - Table I l

52. 1-SW - Service Water System i

A. Mechanical Components:

1. All piping, fittings, and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric] that are designated SW on drawings D-20041 (Rev. 21), D-25037 (Rev. 21), and D-2274 (Rev. 5) are Q-list items exceot for the portions listed below:

a. All components downstream of the following valves:

SW-PV116 (D-20041)

SW-PV118 (D-20041)

SW-PV120 (D-20041)

SW-PV138 (D-20041)

SW-PV140 (D-20041)

SW-RV4 (D-20041)

SW-RV5 (D-20041)

SW-RV6 (D-20041)

, SW-RV7 (D-20041)

SW-RV8 (D-20041)

SW-RV9 (D-20041)

SW-RV10 (D-20041)

SW-RV11 (D-20041)

SW-RV12 (D-20041)

SW-RV13 (D-20041)

SW-V58 (D-20041)

SW-V59 (D-20041)

SW-V60 (D-20041)

SW-V61 (D-20041)

SW-V62 (D-20041)

SW-V88 (D-20041)

SW-V89 (D-20041)

SW-V90 (D-20041)

SW-V91 (D-20041)

SW-V92 (D-20041)

SW-V149 (D-25037)

SW-V151 (D-25037)

SW-V158 (D-25037)

SW-V160 (D-25037)

SW-V161 (D-25037)

SW-V162 (D-25037)

SW-V163 (D-25037)

SW-V164 (D-25037)

SW-V165 (D-25037) 148 Volume XI Rev. 24

Volume XI - Table I

52. 1-SW - Service Water System (cont'd)

SW-V167 (D-25037)

SW-V168 (D-25037)

• SW-V169 (D-25037)

SW-V110 (D-25037)

SW-V171 (D-25037)

SW-V172 (D-25037)

SW-V189 (D-25037)

SW-V190 (D-25037)

SW-V194 (D-25037)

SW-V195 (D-25037)

SW-V196 (D-25037)

SW-V197 (D-25037 SW-V307 (D-20041) 4 SW-V310 (D-25037)

SW-V313 (D-25037) ,

SW-V314 (D-25037)

SW-V317 (U-25037)

SW-V318 (D-25037)

SW-V321 (D-25037)

SW-V322 (D-25037)

SW-V325 (D-25037)

SW-V326 (D-25037)

SW-V329 (D-25037)

SW-V403 (D-20041)

SW-V404 (D-20041)

SW-V405 (D-20041)

SW-V406 (D-20041)

SW-V407 (D-20041)

SW-V408 (D-20041)

SW-V409 (D-20041)

SW-V410 (D-20041)

SW-V411 (D-20041)

SW-V412 (Di20041)

b. Service water pump motor cooling water discharge lines

, (D-20041).

149 Volume XI Rev. 24

Volume XI - Table I

52. 1-SW - Service Water System (cont'd)

c. Service water pump lubricating water drain lines from cyclone sept.ators (D-20041).

d. Line 15-12-R-2A (D-20041).

e. Service water supply / discharge lines to TBCCW heat exchangers (downstream of SW-V3) (D-20041).

f. Bearing lubricating supply / discharge water lines to '

circulating water pumps and screen wash pumps (downstream of SW-V37) (D-20041).

3 Portions of line 350-10-157 outside the service water intake structure wall (D-20041).

h. Portions of lines 31-30-R-1 and 31-20-R-1 outside the Turbine Building pipe tunnel wall (D-25037).

i. Drains from RHR service water pumps to Radwaste (D-25037).

j. Service water pump splash guard drain lines (253-1/2-157A through 257-1/2-157A) (D-20041).

2. All of the following components shown on drawing D-20041 are Q-list:

a. All conventional and nuclear service waoer pumps. .

b. Service water lubricating water pumps.

c. Service water pump lubricating water cyclone separators.

1 d. Self-cleaning strainers.

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings D-20041 (Rev. 21) and D-25037 (Rev. 21) are Q-list:

i Instrument No. Drawing No.

SW-FG-2276-1 D-20041 SW-FG-2276-2 D-20041 SW-FG-2277-1 D-20041 150 Volume XI Rev. 24

Volume XI - Table I

52. 1-SW - Service Water System (cont'd)

Instrument No. Drawing No.

SW-FG-2277-2 D-20041 SW-FG-2278-1 D-20041 i SW-FG-2278-2 D-20041 l SW-FG-2279-1 D-20041 SW-FG-2279-2 D-20041 ,

SW-FG-2280-1 D-20041 SW-FG-2280-2 D-20041 SW-FSL-825 D-25037 SW-FSL-834 D-25037 SW-FSL-835 D-25037 SW-FSL-836 D-25037 ,

SW-PDIC-116 D-20041 SW-PDIC-118 {

D-20041 SW-PDIC-120 D-20041 SW-PDIC-138 D-20041 SW-PDIC-140 D-20041 SW-PS-129 D-20041 SW-PS-136 D-20041 SW-PS-271 D-20041 SW-PS-1175 D-25037 SW-PS-1176 D-25037 SW-PS-1316 D-20041 SW-PS-3213 D-20041 SW-PS-3214 D-20041

2. Motors for all motor driven Q-listed equipment are Q-list.

l 3. All power and control circuit elements (such as circuit i breakers, switches, relays, timers, fuses, cables, wiring, panels, etc.) that provide a safety function are Q-list.

151 Volume XI Rev. 24

l l

l l

Volume XI - Table I

53. 2-SW - Service Water System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their

• operators [ pneumatic incloding their controlling solenoid valve (s), manual and electric] that are designated SW on drawings D-2041 (Rev. 25), D-2537 (Rev. 20), and D-2274 (Rev. 5) are Q-list items except for the portions listed below:

a. All components downstream of the following valves:

SW-IV-1151 (D-2274)

SW-IV-1161 (D-2274)

SW-IV-1171 (D-2274)

SW-IV-1181 (D-2274)

SW-PV116 (D-2041)

SW-PV118 (D-2041)

SW-PV120 (D-2041)

SW-PV138 (D-2041)

SW-PV140 (D-2041)

SW-RV4 (D-2041)

SW-RV5 (D-2041)

SW-RV6 (D-2041)

SW-RV7 (D-2041)

SW-RV8 (D-2041)

SW-RV9 (D-2041)

SW-RV10 (D-2041)

SW-RV11 (D-2041)

SW-RV12 (D-2041)

SW-RV13 (D-2041)

SW-V58 (D-2041)

SW-V59 (D-2041)

SW-V60 (D-2041)

SW-V61 (D-2041)

SW-V62 (D-2041)

SW-V88 (D-2041)

SW-V89 (D-2041)

SW-V90 (D-2041)

SW-V91 (D-2041)

SW-V92 (D-2041)

SW-V149 (D-2537)

SW-V151 (D-2537)

SW-V158 (D-2537)

SW-V160 (D-2537)

SW-V161 (D-2537)

SW-V162 (D-2537)

SW-V163 (D-2537) 152 Volume XI Rev. 24

._. y , _ _ , _ - . _ . -

Volume XI - Table I

53. 2-SW - Service Water System (cont'd)

SW-V164 (D-2537)

SW-V165 (D-2537)

• SW-V167 (D-2537)

SW-V168 (D-2537)

SW-V169 (D-2537)

SW-V170 (D-2537)

SW-V171 (D-2537)

SW-V172 (D-2537)

SW-V189 (D-2537)

SW-V190 (D-2537)

SW-V194 (D-2537)

SW-V195 (D-2537)

SW-V196 (D-2537)

SW-V197 (D-2537 SW-V235 (D-2274)

SW-V236 (D-2274)

SW-V237 (D-2274)

SW-V238 (D-2274)

SW-V239 (D-2274)

SW-V240 (D-2274)

SW-V241 (D-2274)

SW-V242 (D-2274)

SW-V307 (D-2041)

SW-V310 (D-2537)

SW-V313 (D-2537)

SW-V314 (D-2537)

SW-V317 (D-2537)

SW-V318 (D-2537)

SW-V321 (D-2537) 4 SW-V322 (D-2537)

SW-V325 ,D-2537)

SW-V326 (D-2537)

SW-V329 (D-2537)

SW-V403 (D-2041)

SW-V404 (D-2041)

SW-V405 (D-2041)

SW-V406 (D-2041)

SW-V407 (D-2041)

SW-V408 (D-2041)

SW-V409 (D-2041)

SW-V410 (D-2041)

SW-V411 (D-2041)

SW-V412 (D-2041)

b. Service water pump motor cooling water discharge linea (D-2041).

153 Volume XI Rev. 24

Volume XI - Table I

53. 2-SW - Service Water System (cont'd)

c. Service water pump lubricating water drain lines from cyclone separators (D-2041). ,

d. Line 15-12-R-2A (D-2041).

e. Line 272-12-R-1 (D-2041).

f. Service water supply / discharge lines to TBCCW heat exchangers (downstream of SW-V3) (D-2041).

g. Bearing lubricating supply / discharge water lines to circulating water pumps and screen wash pumps (dewnstream of SW-V37) (D-2041),

h. Portions of line 350-10-157 outside the service water intake structure wall (D-2041).

i. Portions of line 2-SW-37-18-R-1 outside the diesel generator tank vault wall (D-2274).

j. Portions of lines 31-30-R-1 and 31-20-R-1 outside the Turbine Building pipe tunnel wall (D-2537).

k. Drains from RHR service water pumps to Radwaste (D-2537).

1. Jacket water cooler drain lines downstream of valves 2SW-V281, V283, V285, and V287 (D-2274).

m. Service water pump splash guard drain lines (282-1/2-157A through 286-1/2-157A) (D-2041).

2. All of the following components shown on drawing D-2041 are Q-list:

a. All conventional and nuclear service water pumps,

b. Service water lubricating water pumps.

c. Service water pump lubricating water cyclone separators.

d. Self-cleaning strainers.

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting wiring) shown on drawings (D-2041 (Rev. 25), D-2537 (Rev. 20), and D-2274 (Rev. 5) are Q-list:

154 Volume XI Rev. 24

Volume XI - Table I

53. 2-SW - Service Water System (cont'd)

Instrument No. Drawing No.

SW-FG-2276-1 D-2041 SW-FG-2276-2 D-2041 SW-FG-2277-1 D-2041 SW-FG-2277-2 D-2041 SW-FG-2278-1 D-2041 SW-FG-2278-2 D-2041 SW-FG-2279-1 D-2041 SW-FG-2279-2 D-2041 SW-FG-2280-1 D-2041 SW-FG-2280-2 D-2041 SW-FSL-825 D-2537 SW-FSL-834 D-2537 SW-FSL-835 D-2537 SW-FSL-836 D-2537 SW-PDIC-116 D-2041 SW-PDIC-118 D-2041 SW-PDIC-120 D-2041 SW-PDIC-138 D-2041 SW-POIC-140 D-2041 SW-PS-129 D-2041 SW-PS-136 D-2041 SW-PS-271 D-2041 .

SW-PS-1175 D-2537 SW-PS-1176 D-2537 SW-PS-1316 D-2041 SW-PS-1995 D-2274 SW-PS-1996 D-2274 SW-PS-1998 D-2274 SW-PS-1999 D-2274 SW-PS-3213 D-2041 SW-PS-3214 D-2041

2. Motors for all motor driven Q-listed equipment are Q-list.

3. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, panels, etc.) that provide a safety function are Q-list.

155 Volume XI Rev. 24

I Volume XI - Table I 54 1-TD - Torus Drain and Keep-Fill System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated TD on drawing D-26098 (Rev. 2) within the boundaries listed below are Q-list items:

a. Line TD-1-3-166.

b. Line TD-2-3/4-166.

c. Line TD-3-3-BMW.

d. Line TD-3-3-150 up to valve TD-V23. '

e. Line TD-6-3/4-150- up to valve TD-V33.

f. The following valves:

TD-Vi TD-V2 TD-V3 TD-V22 TD-V23 TD-SV-3598 TD-SV-3601 TD-V32 TD-V33 l

156 Volume XI Rev. 24

Volume XI - Table I

55. 2-TD - Torus Drain and Keep-Fill System A. Mechanical Components:

1. All piping, fittings and their supports, valves and their

• operators (pneumatic including their controlling solenoid valve (s), manual and electric) that are designated TD on drawing D-2698 (Rev. 3) within the boundaries listed below are Q-list items:

a. Line TD-1-3-166.

b. Line TD-2-3/4-166.

c. Line TD-3-3-BMW.

d. Line TD-3-3-150 up to valve TD-V23.

e. Line TD-6-3/4-150 up to valve TD-V17.

f. The following valves:

TD-V1 TD-V2 TD-V3 TD-V22 TD-V23 TD-V16 TD-V17 TD-SV-3598 TD-SV-3601 i

r _

l

[

l i

i i

l 157 Volume XI i

Rev. 24 l

_ _ _ _ _ _ _ _ _ _ _ _ .- ~ _ ..-

Volume XI - Table I t

56. 1-VA - Ventilation Air System A. Mechanical Components:

1. All mechanical components such as piping, fitting, ducts, filters, valves, fans, dampers, fire dampers, cooling units, air compressors and their supports and operators (pneumatic including their controlling solenoid valve (s), manual and electric) shown on drawing F-4080 (Rev. 10) are Q-list items except those portions that are listed below:

a. Return air ducting from the Unit No. I computer room to the Contrcl Room return air plenum.

b. Supply ducting from the Control Room supply plenum to the Unit No. I computer room.

2. All of the following mechanical components and their supports and operators (pneumatic including their controlling solenoid valve (s), manual and electric) shown on drawings F-40073 (Rev. 16) and F-4024 (Rev 9) are Q-list items:

a. Reactor Building core spray pump area fan cooling units 1C-FCU-RB and 1D-FCU-RB (F-40073). ,

b. Reactor Building RHR heat exchanger room fan cooling units 1A-FCU-RB and IB-FCU-RB and their supply ducting, dampers, and damper operators (F-40073).

c. Reactor Building supply isolation valves 1A-BFIV-RB and i 1B-BFIV-RB and their interconnecting piping (F-40073).

d. Reactor Building exhaust isolation valves 1C-BFIV-RB and ID-BFIV-RB and their interconnecting and discharge piping up to and including its penetration through the building

! roof (F-40073) .

e. Service water intake structure exhaust fan 1A-EF-SWIS and their exhaust backdraft dampers (F-4024).

i B. Instrumentation'and Electrical Components:

1. All of the .following instruments (including their controls, i- power supplies, mountings, and interconnecting wiring) shown on

drawings F-4024 (Rev. 9), F-40073 (Rev. 16), F-4080 (Rev. 10),

FP-4321, FP-4353, and FP-4376 are Q-list:

j.

158 Volume XI Rev. 24

Volume XI - Table I

56. 1-VA'- Ventilation Air System (cont'd)

Instrument No. Drawing No.

VA-FE-2577 F-40073 '

VA-FR-2577 F-40073 VA-FT-2577 F-40073 VA-FT-3150 F-40073 VA-FT-3151 F-40073 VA-KS-1026 FP-4321 VA-MC-1026 FP-4321-E VA-PC-924 FP-4321-B VA-PC-925 FP-4321-B VA-PDS-3579 F-4080 VA-PS-1026 FP-4321 VA-PS-1026A FP-4321 VA-PS-1313-1 FP-4321-A VA-TC-924 FP-4321-B VA-TC-925 FP-4321-B VA-TC-1026 FP-4321 VA-TS-919 FP-4353 VA-TS-936A FP-4376 sh.3 VA-TS-936B FP-4376 sh.3 VA-TS-936C FP-4376 sh.3 VA-TS-936D FP-4376 sh.3 VA-TS-936E FP-4376 sh.3 VA-TS-936F FP-4376 sh.3

~

-VA-TSL-3455 F-40073 VA-TSL-3456 F-40073 VA-TY-1026A FP-4321-E VA-TY-1026B FP-4321-E VA-TY-1313-1 FP-4321-E

2. Motors for all motor driven Q-listed equipment are Q-list.

3. Panels at nodes 1-H91 and 1-H92 and all items mounted in/on them are Q-list items exceot for nameplates, indicating lamps, internal panel lighting, and panel heaters (F-4024).

139 Volume XI Rev. 24

Volume XI - Table I Unit No. 2 and Common

57. 2-VA - Ventilation Air System A. Mechanical Components:

1. All mechanical components such as piping, fittings, ducts, filters, valves fans, dampers, fire dampers, cooling units, air

, compressors and their supports and operators (pneumatic including their controlling solenoid valve (s), manual and electric) shown on drawings F-4080 (Rev.10) and D-4101 (Rev. 3) are Q-list items except those portions that are listed below:

a. Return air ducting from the Unit No. 2 computer room to the Control Room return air plenum.

b. Supply ducting from the Control Room supply plenum to the Unit No. 2 computer room, the vistors' gallery, and the electronic workshop.

c. Control Building mechanical equipment room supply ducting downstream of dampers 2K-D-CB, and exhaust ducting upstream of damper 2T-D-CB.

d. Electric unit heaters UH-1 and UH-2 for the Control Building mechanical equipment room.

e. Diesel Generator Building exhaust fans E-EF-DG, F-EF-DG,

-G-EF-DG, H-EF-DG, J-EF-DG, K-EF-DG, L-EF-DG, M-EF-DG, and N-EF-DG.

f. Diesel Generator Building supply filters A-SAF-DG and B-SAF-DG.

2. All of the following mechanical components and their supports and operators (pneumat'ic including their controlling solenoid valve (s), manual and electric) shown on drawing F-4073 (Rev. 18) and F-4024 (Rev. 9) are Q-list items:

a. Reactor Building core spray pump area fan cooling units

-2C-FCU-RB and 2D-FCU-RB (F-4073).

l b. Reactor Building RHR heat exchanger room fan cooling units 2A-FCU-RB and 23-FCU-RB and their supply ducting, dampers, and damper operators (F-4073),

c. Reactor Building supply isolation valves 2A-BFIV-RB and 2B-BFIV-RB and their interconnecting piping (F-4073).

le0 Volume XI Rev. 24

l Volume XI - Table I '

Unit No. 2 and Coomon

57. 2-VA - Ventilation Air System (cont'd)

, d. Reactor Building exhaust isolation valves 2C-BFIV-RB and 2D-BFIV-RB and their interconnecting and discharge pip'ing up to and including its penetration through the building roof (F-4073).

3. Service water intake structure exhaust fan 2A-EF-SWIS and their exhaust backdraft dampers (F-4024).

B. Instrumentation and Electrical Components:

1. All of the following instruments (including their controls, power supplies, mountings, and interconnecting ciring) shown on drawings F-4073 (Rev. 18), F-4080 (Rev. 10), FP-4321 (Rev. 1),

FP-4353, FP-4357, and FP-4375 (Rev.1), LL-9251 sh.29 (Rev. 6),

and LL-92051 sh.29 (Rev. 4) are Q-list:

Instrument No. Drawing No.

VA-FE-2577 F-4073 VA-FR-2577 F-4073 VA-FT-2577 F-4073 VA-FT-3150 F-4073 VA-FT-3151 F-4073 VA-KS-1027 FP-4321-C VA-MC-1028 FP-4321-E VA-PC-926 FP-4321-B VA-PC-927 FP-4321-B VA-PDS-3579 F-4080 VA-PS-1027 FP-4321 VA-PS-1027A FP-4321 VA-PS-1028 FP-4321 VA-PS-1028A FP-4321 VA-PS-1313-2 FP-4321-A VA-PS-1632 LL-0251, sh.29 VA-PS-1633 LL-92051, sh.29 VA-PSL-1646 FP-4321-B VA-TC-926 FP-4321-B VA-TC-927 FP-4321-B VA-TC-1028 FP-4321 VA-TC-1606 FP-4357 VA-TC-1607 FP-4357 VA-TC-1608 FP-4357 VA-TC-1609 FP-4357 VA-TC-1611 FP-4357 VA-TC-1612 FP-4357 VA-TC-1613 FP-4357 VA-TC-1614 FP-4357 161 Volume XI Rev. 24

l l

Volume XI - Table I Unit No. 2 and Common

57. 2-VA - Ventilation Air System (cont'd)

Instrument No. Drawing No.

VA-TC-1615 FP-4357 VA-TC-1616 FP-4357 VA-TC-1617 FP-4357 VA-TC-1618 FP-4357 VA-TS-920 FP-4353 VA-TS-936A FP-4375 sh.3 VA-TS-936B FP-4375 sh.3 VA-TS-936C FP-4375 sh.3 VA-TS-936D FP-4375 sh.3 VA-TS-936E VA-TS-936F VA-TS-1606 FP-4357 VA-TS-1607 FP-4357 VA-TS-1608 FP-4357 VA-TS-1609 FP-4357 VA-TS-1611 FP-4357 VA-TS-1612 FP-4357 VA-TS-1613 FP-4357 VA-TS-1614 FP-4357 VA-TS-1615 FP-4357 VA-TS-1616 FP-4357 VA-TS-1617 FP-4357 VA-TS-1618 FP-4357 VA-TSL-3455 F-4073 VA-TSL-3456 F-4073 VA-TY-1027A FP-4321 VA-TY-1027B FP-4321 VA-TY-1028A FP-4321-E VA-TY-1028B FP-4321-E VA-TY-1313-2 FP-4321-A VA-TY-1606 FP-4357 VA-TY-1607 FP-4357 VA-TY-1608 FP-4357 VA-TY-1609 FP-4357 VA-ZY-1027A FP-4321 '

VA-ZY-1027B FP-4321

2. Motors for all motor driven Q-listed equipment are Q-list.

3. Panels at nodes 2-H90, 2-H91, 2-H92, 2-HD8, 2-PT2, and 2-RT3 and all items mounted in/on them are Q-list items except for nameplates, indicating lamps, internal panel lighting, and panel heaters.

162 Volume XI Rev. 24 t - . . - - . _ ~ . , -

.- - . , , - . .m.-- , - . , -- . - - - . - . , , , , - - - . - - . , - - - - - -- . ,, , , . , .

l i

l l

Volume XI - Table I

58. 1-X - Miscellaneous Instruments A. Instrument Components:

1. All of the following instruments (including their controls,'

power supplies, mountings, and interconnecting wiring) shown on drawing F-4080 (Rev. 10) are Q-list items:

Instrument No. Drawing No.

X-AT-2977 F-4080

2. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

163 Volume XI Rev. 24

Volume XI - Table I

60. 2-X - Miscellaneous Instruments A. Instrument Components:

1. All of the following instruments (including their controls, .

power supplies, mountings, and interconnecting wiring) shown on drawings F-4080 (Rev.10), D-2274 (Rev. 5), and D-7218 (Rev.

13) are Q-list items:

Instrument No. Drawina No.

X-AT-2977 F-4080 X-LSH-3120 D-2274 X-LSHH-3121 D-2274 X-LSHH-3122 D-2274 X-LSH-3123 D-2274 X-LSHH-3124 D-2274 X-LSHH-3125 D-2274 X-LSH-3126 D-2274 X-LSHH-3127 D-2274 X-LSHH-3128 D-2274 X-LSH-3129 D-2274 X-LSHH-3130 D-2274 X-LSHH-3131 . D-2274 X-XY-4354A D-7218 X-XY-4354B D-7218 X-XY-4355A D-7218 X'-XY-4355B D-7218 X-XY-4368A D-7218

, X-XY-4368B D-7218' X-XY-4369A D-7218 X-XY-4369B D-7218-

2. All power and control circuit elements (such as circuit breakers, switches, relays, timers, fuses, cables, wiring, and panels, etc.) that provide a safety function are Q-list.

164 Volume XI Rev. 2 4

Volume XI - Table II Unit Nos. I and 2 plant Structures

1. The entire Pressure Suppression System and all associated components such as vent lines, headers, etc., are Q-list.

2. The following parts of the Reactor Building are Q-list:

a. Concrete,

b. Reinforcing steel.

c. Structural steel.

d. Exterior sheet metal siding.

e. Exterior doors, frames, and hardware

f. Seals for secondary containment.

g. Biological shielding.

3. The following parts of the Diesel Generator Building, including fuel oil tank chamber, are Q-list:

a. Concrete.

b. Reinforcing steel.

c. Structural steel

d. Exterior doors, frames, and hardware

4. The following parts of the service water intake structure are Q-list:

a. Concrete.

b. Reinforcing steel.

c. Structural steel

d. Exterior doors, frames, and hardware i i

i l

l 165 Volume XI Rev. 24 j l

Volume XI - Table II Unit Nos. 1 and 2 Plant Structures (cont'd)

5. The following parts of the Centrol Building are Q-list: ,

s. Concrete.

b. Reinforcing steel.

c. Structural steel, i

, d. Biological shielding.

6. The following parts of primary containment (drywell and extensions of drywell) are Q-list:

a. Concrete.

b. Reinforcing steel,

c. Containment liner.

d. Structural steel.

e. Biological shielding.

7. The following parts of the Fuel Pools / Refueling System are Q-list:

_n.. y.

a. Liners,

b. Refueling System.

(1) Fuel hoists and associated equipment.

(2) Spent fuel pool.

(3) Cask handling equipment.

(4) Biological shielding.

c. Refueling equipment, assembly platform.

d. New fuel storage racks.

e. Spent fuel storage racks.

f. Steam line plugs.

i 166 Volume XI Rev. 24

i Volume XI - Table II Unit Nos. I and 2 Plant Structures (cont'd)

8. The following parts of the Nitrogen and Off-Gas Services Building are Q-list: -

• , 3

a. Concrete.

i

.b . Reinforcing steel.

4 s

- s c. 'Structuralisteel.

+

, d. Exterior doors,' frames, and hardware.

9. The hea.ctor vessel support pedestals are Q-list.

t 4

4

\

\-

\

J s

s s

1 p , , 167 Volume XI

-( -

Rev. 24 l

, g J

Volume XI - Table III Unit Nos. 1 and 2 Consumable / Expendable Items A. The following consumable / expendable items are Q-list:

1. Grease for 4160 switchgear

2. Grease for Limitorque operators

3. Diesel generator jacket water fluid

4. Diesel generator fuel oil

5. Diesel generator lube oil

6. Snubber hydraulic oil -

7 Sodium tetraborate and boric acid for SLC System

8. Gaskets and gasket material

9. Packing for valve scems and pump shafts I

10. 0-rings

11. Spot Check cleaner

12. Spot Check developer

13. Spot Check penetrant

14. Nuclear fuel

15. Consumable inserts

16. Welding electrodes

17. Filters (HEPA and charcoal for Control Room ventilation and SBGT) 168 Volume XI Rev. 24

APPENDIX A-Volume XI - Book 2 List of Drawings Title of Drawing Drawing No. Rev. No.

Piping Diagram - Main Steam, Turbine 9527-D-2020 17 Bypass, and Reheater Protection Steam Systems - Unit No. 2 Piping Diagram - Main Steam to RFP 9527-D-2024 5 Turbine and Steam Jet Air Ejector -

Unit No. 2 Piping Diagram '- Off-Gas Removal 9527-D-2025 18 and Condenser Water Box Air Removal Systems - Unit No. 2

-Piping Diagram - Condensate ari 9527-D-2040 13 Domineralized Water Transfer systems -

Sheet 1 - Unit Nos. I and 2 Piping Diagram - Service Water 9527-D-2041 25 System - Unit No. 2 Piping Diagram - Starting Air for 9527-D-2265 8 Diesel Generators - Sheet 1-Unit Nos. 1 and 2 Piping Diagram - Starting Air for 9527-D-2266 7 Diesel Generators - Sheet 2 -

Unit Nos. I and 2 Piping Diagram - Diesel Generator 9527-D-2267 4 Air Intake, Exhaust and Crankcase Vacuum System - Unit Nos. 1 and 2 Piping Diagram - Fuel Oil to Diesel 9527-D-2268 10 Generator - Sheet 1 - Unit Nos. I and 2 Piping Diagram - Fuel Oil to Diesel 9527-D-2269 10 Generator - Sheet 2 - Unit Nos. 1 and 2 Piping Diagram - Diesel Generator 9527-D-2270 6 Lube Oil System - Sheet 1-Unit Nos. I and 2 169 Volume XI

, Rev. 24

- - , - 4 -

,-v.- , -- - - . - , - +- , , ,,,-.-m.---. -----,----,--e-,...,.,, - ,, ,,.---y , , -e--

APPENDIX A (CONT'D)

Volume XI - Book 2 List of Drawings Title of Drawing Drawing No. Rev. No.

Piping Diagram - Diesel Generator 9527-D-2271 6 Lube Oil System - Sheet 2 -

Unit Nos. I and 2 Piping Diagram - Diesel Generator 9527-D-2272 3 Jacket Water System - Sheet 1 -

Unit Nos. 1 and 2 Piping Diagram - Diesel Generator 9527-D-2273 3 Jacket Water System - Sheet 2 -

Unit Nos. 1 and 2 Piping Diagram - Diesel Generator 9527-D-2274 5 Service Water cad Dcmineralized Water Systems - Unit Nos. 1 and 2 Reactor Building - Piping Diagram - 9527-D-2515 19 Containment Atmospheric Control System - Sheet 1 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2516 14 Control Rod Drive Hydraulic System -

Sheet 1 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2517 12 Control Rod Drive Hydraulic System -

Sheet 2 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2518 14 Reactor Coolant Recirculation System - Sheet 1 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2520 12 Nuclear Steam Supply System -

Sheet 3 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2521 15 Nuclear Steam Supply System -

Sheet 1 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2522 15 Nuclear Steam Supply System -

Sheet 2 - Unit No. 2 170 Volume XI Rev. 24

APPENDIX A (CONT'D)

Volume XI - Book 2 List of Drawings Title of Drawing Drawing No. Rev. N'o.

Reactor Building - Piping Diagram - 9527-D-2523 14 High Pressure Coolant Injection System - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2524 16 Core Spray System - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2525 17 Residual Heat Remcval System -

Sheet 1 - Unit IIo. 2-Reactor Building - Piping Diagram - 9527-D-2526 18 Residual Heat Removal System -

Sheet 2 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2527 18 Reactor Water Cleanup System -

Sheet 1 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2529 20 Reactor Core Isolation Cooling System - Unit No. 2 Reactor Building-- Piping Diagram - 9527-D-2531 27 Waste Collector System - Unit Nos. I and 2 Radwaste Building - Piping Diagram - 9527-D-2534 18 Waste Neutralizer System -

Unit Nos. I and 2 Radwaste Building - Piping Diagram - 9527-D-2535 26 20 gpm - Waste Concentrator -

Unit Nos. 1 and 2 Reactor Building - Piping Diagram - 9527-D-2537 20 Service Water System - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-25's 8 10 Closed Cooling Water System -

Unit No. 2

. Reactor Building - Piping Diagram - 9527-D-2541 2 Penetration Cooling - Unic No. 2 171 Volume XI Rev. 24 i

- - - - - , , . - - - - - - , -,,,,+v -- -- - -- * = --e

APPENDIX A (CONT'D)

Volume XI - Book 2 List of Drawings Title of Drawing Drawing No. Rev. No.

Reactor Building - Piping Diagram - 9527-D-2542 4 Service Air System - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2545 11 Drywell Drains - Sheet 3 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2547 10 Standby Liquid Control System -

Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2548 16 Reactor Coolant Recirculation System - Sheet 2 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2549 11 Fuel Pool Cooling and Filtering System - Sheet 1 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-2560 13 Containment Atmospheric Control System - Sheet 2 - Unit Nos. I and 2 Radwaste Building - Piping Diagram - 9527-D-2569 16

-Auxiliary Surge System - Unit Nos. 1 and 2.

Nitrogen and Off-Gas Services Building - 9527-F-2587 10 Piping Diagram - Miscellaneous Services -

Sheet 2 Reactor Building - Piping Diagram - 9527-D-2698 3 Torus Drain and Keep-Fill Charging System - Unit No. 2 Service Water Intake Structure - 9527-F-4024 9 Ventilation System and Drainage Piping -

Unit Nos. I and 2 Reactor Building - Air Flow Diagram - 9527-F-4073 18 Ventilation System - Unit No. 2 Control Building - Air Flow Diagram - 9527-F-4080 10 Unit Nos. 1 and 2 .

172 Volume XI Rev. 24

APPENDIX A (CONT'D)

Volume XI - Book 2 List of Drawings Title of Drawing Drawing No. Rev. N'o.

Diesel Generator Building - Air Flow 9527-D-4101 3 Diagram - Ventilation System -

Unit Nos. I and 2 Turbine Building - Off Gas and Drain 9527-D-4104 12 Piping and Flow Diagram - Filter House -

Unit Nos. 1 and 2 Piping Diagram - Instrument Air Supply 9527-D-7007 15 System - Sheet 1 - Unit No. 2 Piping Diagram - Instrument Air Supply 9527-D-7029 19 System - Sheet 2 - Unit No. 2 Piping Diagram - Instrument Air Supply 9527-D-7077 9 System - Sheet 3 - Unit No. 2 Reactor Building - Leak Detection Flow 9527-F-7083 13 Diagram - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-7206 16 Instrument Air Supply System -

Sheet 4 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-7208 12 Instrument Air Supply System -

Sheet 5 - Unit No. 2 Reactor Building - Piping Diagram - 9527-D-7209 7 Fnstrument" Air ' Supply System -

Sheet 6 - Unit No. 2 Reactor Building - Containment Atmos- 9527-D-7218 13 pheric Monitoring System - Unit No. 2 Main Steam Leak Detection Flow 9527-D-7278 4 Diagram - Unit No. 2 Process Radiation Monitor Instrument 9527-F-9503 16 Rack - Interconnection Wiring Diagram -

Unit No. 2 173 Volume XI Rev. 24

I

[-

APPENDIX A (CONT'D)

Volume XI - Book 2 List of Drawings Title of Drawing Drawing No. Rev. N'o.

Piping Diagram - Main Steam, Turbine 9527-D-20020 17 Bypass, and Reheater Protection Steam Systems - Unit No. 1 Piping Diagram - Main Steam to RFP 9527-D-20024 4 Turbine and Steam Jet Air Ejector - ,

Unit No. 1 Piping Diagram - Off-Gas Removal 9527-D-20025 18 and Condenier Water Box Air Removal l

Systems - Unit No. 1 i 1

Piping Diagram - Service Water 9527-D-20041 21

! j System - Unit No. 1  !

Reactor Building - Piping Diagram - 9527-D-25015 25 l Containment Atmospheric Control

! System - Sheet 1 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25016 8 Control Rod Drive Hydraulic System -

Sheet 1 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25017 7 Control Rod Drive Hydraulic System -

Sheet 2 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25018 11 Reactor Coolant Recirculation System - Sheet 1 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25020 7 Nuclear Steam Supply System -

Sheet 3 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25021 13 Nuclear Steam Supply System -

Sheet 1 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25022 11 Nuclear Steam Supply System -

Sheet 2 - Unit No. 1 174 Volume XI Rev. 24

APPENDIX A (CONT'D)

Volume XI - Book 2 List of Drawings Title of Drawing Drawing No. Rev. No.

Reactor Building - Piping Diagram - 9527-D-25023 15 High Pressure Coolant Injection System - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25024 14 Core Spray System - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25025 15 Residual Heat Removal System -

Sheet 1 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25026 15 Residual Heat Removal System -

Sheet 2 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25027 12 Reactor Water Cleanup System -

Sheet 1 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25029 19 Reactor Core Isolation Cooling System - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25037 22 Service Water System - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25038 9 Closed Cooling Water System -

Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25041 2 Penetration Cooling - Unit No. 1 Reactor Building - Piping Diagram -

• 9527-D-25042 6 Service Air System - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25045 11 Drywell Drains - Fheet 3 -

Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25047 13 Standby Liquid Control System -

Unit No. 1 175 Volume XI Rev. 24

l APPENDIX A (CONT'D)

Volume XI - Book 2 List of Drawings Title of Drawing Drawing No. Rev. No.

Reactor Building - Piping Diagram - 9527-D-25048 13 Reactor Coolant Recirculation System - Sheet 2 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-25049 9 Fuel Pool Cooling and Filtering System - Sheet 1 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-26098 2 Torus Drain and Keep-Fill Charging System - Unit No. 1 Reactor Building - Air Flow 9527-F-40073 16 Diagram - Ventilation System -

Unit No. 1 Reactor Building - Piping Diagram - 9527-D-70007 7 Instrument Air Supply System -

Sheet 1 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-70029 14 Instrument Air Supply System -

Sheet 2 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-70077 8 Instrument Air Supply System -

Sheet 3 - Unit No. 1 4

Reactor Building - Leak Detection Flow 9527-F-70083 10 Diagram - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-72006 11

't Instrument Air Supply System -

Sheet 4 - Unit No. 1 Reactor Building - Piping Diagram - 9527-D-72008 9 Instrument Air Supply System -

Sheet Unit No. 1 Reactor Building - Piping Diagram - 9527-D-72009 6 Instrument Air Supply System -

Sheet 6 - Unit No. 1 176 Volume XI Rev. 24

APPENDIX A (CONT'D)

Volume XI - Book'2 List of Drawings Title of Drawing Drawing No. Rev. No.

Reactor Building - Containment 9527-D-72018 10 Atmospheric Monitoring System -

Unit No. 1 Main Stem Leak Detection Flow 9527-D-72078 3 Diagram - Unit No. 1 Process Radiation Monitor Instrument 9527-F-95003 8 Rack - Interconnection Wiring Dingram -

Unit No. 1 Control Building: FP-9527-01-4321 0 Unit No. 1 - Control Room No. 1; Unit No. 2 - Control Room No. 2 Control Building: FP-9527-01-4321A 1 Emergency Recirculation Fans -

Make-up Dampers - Cable Spread Room Nos. 1 and 2 Control Building: FP-9527-01-4321B 1 Building Exhaust Fan - Battery Room Ventilation - Mechanical Room Venti-lation - Control Air Compressors Control Building Equipment Location- FP-9527-01-4321C 1 i

Control Building Equipment Location FP-9527-01-4321E 1 Service Water Intake Structure FP-9527-01-4353 B Diesel Generator Building - FP-9527-4357 1 Supply Air - Units Nos. I and 2 Reactor Building - Equipment FP-9527-4375 1 Location - RHR Pump Rooms and Core Spray Area - Sheet 3 - Unit No. 2 Reactor Building - Equipment FP-9527-4376 2 Location - RHR Pump Rooms -

Sheet 3'- Unit No. 1 Standby Gas Treatment System - FP-9527-4404 0 Unit Nos. 1 and 2 177 Volume XI Rev. 24

APPENDIX A (CONT'D)

Volume XI - Book 2 List of Drawings Title of Drawing Drawing No. Rev. N'o.

IED - Area Radiation Monitoring FP-9327-5152 6 System - Unit Nos. 1 and 2 Process Radiation Monitoring System FP-9527-5159 4 IED - Neutron Monitoring System - FP-9527-5224 7 Sheet 1 - Unit Nos. 1 and 2 IED - Neutron Monitoring System - FP-9527-5224 7 Sheet 2 - Unit Nos. I and 2 Feedwater Control System - FP-9527-50014-1 A Sheet 4 - Unit No. 1 Feedwc:er Control System - FP-9527-50014-2 A Sheet 4 - Unit No. 2 Elementary Diagram - Reactor Protection FP-9527-50015 System - Unit No. 2 Process Radiation Monitoring FP-9527-50054'1 B System - Unit No. 1 Process Radiation Monitoring FP 9527-50054-2 B System - Unit No. 2 Power Range Monitoring System - FP-95?. 50462 1 Unit Nos. 1 and 2 Elementary Diagram - Reactor Protection FP-9527-55046 System - Unit No. 1 Unit No. 2 - MSC "2CA" - COMPT "2-C16" - 9527-LL-9251 4 Instrument Air Compressor 2A-AC-CB -

Control Wiring Diagram - Sheet 29 Unit No. 1 - MSC "2CA" - COMPT "2-C16" - 9527-LL-92051 4 Instrument Air Compressor 2A-AC-CB -

Control Wiring Diagram - Sheet 29 I

178 Volu=e XI l Rev. 24  :

.