ML20081J698

Responds to Generic Ltr 83-28 Re Generic Implications of Salem ATWS events.Post-trip Review & Analysis Program Described in Detail,Including Criteria for Determining Acceptability of Restart

ML20081J698
Person / Time
Site:	Farley
Issue date:	11/04/1983
From:	Clayton F ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
GL-83-28, NUDOCS 8311090080
Download: ML20081J698 (150)

Text

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r Malling Address Atb:ma Power Comp ny 600 North 18th Street .

Post Offica Box 2641 Birmingham, Alabama 35291 Telephone 205 783-6081 F. L. Clayton, Jr.

%"%;'*oS:%'"' AlabamaPower the southern electnc system November 4,1983 Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Units 1 and 2 Response to Generic Letter 83-28 Gentlemen:

Attached is Alabama Power Company's response to Generic Letter 83-28 dated July 8,1983 regarding the NRC positions on the Salem anticipated transient without scram (ATWS) events.

If there are any questions, please advise.

Yours very truly,

' 1 N

. Clayton, r.

FLCJr/RGW:ddr-D10 SWORN TO AND SUBSCRIBED BEFORE ME Attachment THIS 4fL DAYOF/[Mthe1983 cc: Mr. R. A. Thomas Mr. G. F. Trowbridge > ,

Mr. J. P. O'Reilly (kd(L tuyA Mr. E. A. Reeves Notary Public Mr. W. H. Bradford My Commission Expires: l -IC -8 7

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Page 1 Attachment I Required Actions Based on Generic -Implications of Salem ATWS Events NRC Request 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 (1alysis 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 equipment 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 Plant Operations Review Comittee, will be consulted

- prior.to authorizing ~ restart) and guidelines on -the preservation of physical evidence (both hardware and software) to support independent andlysis 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.

Page 2 APCo Response Based upon previous requests from the Nuclear Regulatory Commission (NRC), the Alabama Power Company (APCo) Post-Trip Review Procedures were submitted to the Commission by letter dated June 28, 1983. Based on telecons with the NRC Staff, it is Alabama Power Company's understanding that this procedural guidance adequately addresses the NRC concerns. Amplification of the information contained within the June 28, 1983 letter is outlined below.

The criteria for detarmining the acceptability of restart after an unscheduled reactor shutdown include:

a. Ensuring that the cause of the trip has been identified and '

all equipment and/or systems performed their intended functions, ,

b. Corrective actions required to correct the cause of the trip are taken,

c. A review of the events is performed by the Shift Supervisor and the results of the evaluation are discussed with and permission for restart obtained from the on-call Emergency Director (either the Plant Manager, Assistant Plant Manager or the Operations Superintendent).

The responsibilities and authorities of personnel who will

perform the review and analysis of these events include:

a. Review and analysis by the Shift Supervisor of events prior to the transient causing the trip, during the trip and i

subsequent to the trip, to determine the cause of the trip and to verify the proper operation and response of the reactor and associated equipment systems. The Shift Supervisor has the authority to call on any person (s) that he feels necessary to help in his assessment.

Typically, at a minimum, the Shift Supervisor of the unaffected unit and the Shift Foreman, Shift Technical Advisor and' plant operators of the affected unit are consulted.

b. -The Shift Supervisor must review the results of the trip assessment with and obtain permission from the on-call Emergency Director prior to returning the reactor to criticality.

Page 3 Report package (which documents the Shift Supervisor's review and analysis of the event) and forward it to the Systems Performance Group for their review within 30 days of the event.. The Operations Supervisor performs a review to verify proper action and assessment by the Shift Superviso r. The System Performance Group's review is for the purpose of independently identifying the cause of a reactor trip and verifying that proper corrective action has been planned or implemented. The System Performance Group is also responsible for verifying proper functioning of control and protection systems during the evaluation of reactor trips.

The qualifications and training for the responsible personnel are as follows:

a. Shift Supervisor (Restart)

1. High school education or equivalent.

2. Four years responsible power plant experience of which a maximum of two (2) years is academic or technical training. At least two (2) years experience shall be Nuclear Power Plant experience with six (6) months at Farley Nuclear Plant.

3. Participation in the Farley Nuclear Plant Senior Reactor Operator (SRO) training program which includes training in the areas of heat transfer, fluid flow, mitigating core damage and increased emphasis on plant transients.

4. USNRC Senior Reactor Operator's license.

b. On-Call Emergency Director (Restart)

The Emergency Director capacity is fulfilled by one of the three following positions (other qualified personnel designated by the Farley Nuclear Plant (FNP) Emergency Plan may also serve as the Emergency Director):

Plant Manager

1. A baccalaureate or higher degree in an engineering or scientific field.

2. A total of ten years of power plant experience, of which a minimum of three years is nuclear power plant experience. Four of the remaining seven years may be fulfilled by academic training generally associated with power production on a one-for-one basis.

I Page 4

3. Experience and training required for a senior reactor operator's license. ,

Assistant Plant Manager

1. A baccalaureate or higher degree in an engineering or scientific field.

2. A total of ten years of power plant experience, of which a minimum of three years is nuclear power plant experience. Four of the remaining seven years may be fulfilled by academic training generally associated with power production on a one-for-one basis.

3. USNRC senior reactor operator's license.

Operations Superintendent .

1. High school education or equivalent.

2. A total of eight years of power plant experience, of which a minimum of three years is nuclear power plant experience. Two of the remaining five years may be fulfilled by academic or technical training on a one-for-one basis.

3. USNRC senior reactor operator's license.

C. The qualifications and training for personnel responsible for post-restart review are:

Operations Supervisor

1. High school education or equivalent.

2. A total of eight years of power plant experience, of which a minimum of three years is nuclear power plant experience. Two of the remaining five years may be fulfilled by academic or technical training on a one-for-one basis.

3. USNRC senior reactor operator's license.

Systems Performance Engineer

1. A baccalaureate degree in engineering or the physical sciences.

Page 5 The sources of plant information necessary to conduct a review and analysis of a transient causing an unscheduled reactor trip

~

- include:

a. The plant computer alarm typewriter printout,

- b. The plant computer sequence of event report,

c. -The post-mortem report,

d. The main control board recorders, i e. An interview of on-duty plant operators,

, f. The plant operators log,

g. _The listing of any outstanding limiting condition of operation, and

l. h. The listing of any major maintenance currently in progress.

, . A description of the measures and equipment which provide the

, necessary detail and type of information to reconstruct the event accurately and in sufficient detail for proper understanding is given in APCo response to item 1.2.

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The methods and criteria for comparing the event information

'with known or expected plant behavior (e.g. , that safety-related equipment operates as required by the Technical Specifications or other performance specifications related to the safety function) include:

a. The Emergency Operating Procedure for Reactor Trip which provides the symptoms, automatic actions, immediate

!- operator actions and subsequent operator actions required for a reactor trip. This procedure provides guidance to the Shift Supervisor for ensuring that the plant is placed ,

in a safe condition.

[ b. The Emergency Operating Procedure for Anticipated Transients Without Trip (ATWT) which provides guidelines for operator action in the event a reactor trip or a turbine trip does not occur automatically, if a trip is

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required.

l - The Shift-Supervisor reviews the events to determine the cause of the trip and to verify the proper operation and response of -

the reactor and associated equipment systems. Following this

- review and analysis, the results are discussed with the on-call Emergency Director who must give permission prior to ,

1 - restart. If the review and' analysis by the Shift Supervisor does not positively determine the cause of the transient or verify _ proper operation and response of the reactor and associated equipment systems, it will be the responsibility of 4 the on-call Emergency. Director to determine the need for, and the appropriate individuals or group for, independent .

assessment of the trip. The Shift Supervisor is responsible

! for ensuring that the Reactor Trip Form (which documents the Shift Supervisor's review and analysis of the event) is 4

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Page 6 completed and that the computer port-mortem printout, the

. applicable section of the alarm typewriter printout, the sequence of events and incident report are attached. Following-the review of this package by the Operations Supervisor and the System Performance Group, this package is sent to Document Control. The recorder charts and plant operators log are also forwarded to Document Control for retention. Enclosure 1 contains a copy of the Reactor Trip Emergency Operating

, Procedure, ATWT Emergency Operating Procedure and the Conduct of Operation-Operations Group Procedure. These procedures describe post-trip review activities.

NRC Request 1.2 POST-TRIP REVIEW - DATA AND INFORMATION CAPABILITY Position Licensees and applicants 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 functionir, if 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 displayed in a for.n that permits ease of assimilation and analysis by persons trained in the use of systematic safety assessment procedures. A repet shall be prepared which describes and justifies the adequacy of ecuipment 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 (s) (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 computer, 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)

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

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

6. Power source (s) (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.

APCo Response Each unit at the FNP employs a P2500 central processor for supporting -

the process computer system. Each computer is powered by a class

' non-interruptable non-IE 7.5 KVA 120 VAC single phase 60 Hz inverter, shown on the following diagram as Inverter "E". Inverter "E" is pcwered by an AC and DC source, shown below as 600V M.C.C. "D" and safety-grade vital D.C. Bus "B", respectively. The preferred power source for Inverter "E" is the 600V M.C.C. "D". However, in case of loss of M.C.C. "D", the power source is automatically transferred to vital D.C.

Bus "B",. which is backed by diesel power. In the unlikely event of failure of Inverter "E" or its two power sources, the P2500 can be manually aligned to the 120V AC Instrument Panel "B".

Non-Vital 4160V Bus "D" Vital 4160V Bus "G" l l 600V L.C. "B" 600V L.C. "E" I Vital I 600V M.C.C."D" D.C. Bus "B" 600V M.C.C."B" l

l Inverter Solatron Regulator "B" E" -

l 120VAC Regulated Instrument Panel "B" l

120VAC Computer Distribution Panel

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Page 8 The two major. functions performed by the plant computer which provide significant post-trip / pre-trip data are the Sequence of Events Program and the Post-Trip Review (Post-Mortem) Program. The Sequence of Events Program utilizes digital inputs whereas the Post-Mortem Program utilizes analog inputs. Both programs provide a means of permanent hard copy data retention by printing out on the appropriate unit's system printers.

The Sequence of Events system detects and logs all changes in

. digital registers specified as non-periodic sequence of events registers. The program is initiated by an interrupt each time a contact changes within any digital register designated for sequence of events checking. The attached Table 1 lists the designated plant parameters for Sequence of Events printing. Sequence of Events interrupts are processed as the highest priority activity on the system. Processing is such that differentiation in event occurrence for intervals greater than 4 milliseconds can be made.

Events occurring within 4 milliseconds of each other are identified by asterisks, which denotes the inability to resolve the actual time of occurrence. A Sequence of Events interrupt occurs following any Sequence of Events contact change. A contact change initiates the Sequence of Events cycle counter which times out in one minute. All changes found within that minute are logged together as a recording. The print program executes each time a Sequence of Events one-minute recording has completed and prints the following information:

1. A one-line output for each change within a register.

2. A Sequence of Event header line that lists the register contact change that initiated the sequence and the time that it i occurred, noted in line cycles, each cycle representing 1/60th of a second.

3. A Sequence of Event end line and the time at which the sequence I was initiated.

i As discussed above, Table 1 lists the plant parameters that can trigger the sequence of events program. The parameters can be grouped into the following categories: reactor trip signals; safety injection signals; reactor trip breaker position; main feedwater pump status; plant transformer status; electrical generator status; turbine status; electrical bus status and diesel generator status.

Each reactor trip and safety injection signal is printed out followed by the phrase "CAUS RE", indicating that this directly caused the reactor trip breakers to open. Main feedwater, electrical bus, and turbine-generator parameters are monitored to indicate a turbine trip, a generator trip, or a loss of feedwater flow has occurred, which in turn may lead to a reactor trip, or which can result from a reactor trip. By scanning this

Page 9 information, the Sequence of Events program allows the plant staff to-immediately determine the protective feature that initiated a reactor trip or safeguards actuation.

The Post-Trip Review Program performs the automatic collection of pre-trip and post-trip data. The program consists of 2 data collection routines (2.5 second and 10 second interval data) and a print routine. Values of analog parameters included in the Post-Trip Review are stored on mass memory in a continuous circular pre-trip file. Upon detection of a reactor trip by the sequence of events system, the values being collected are then stored in a second continuous post-trip file. For selected parameters, pre-trip and post-trip data is collected for 10 seconds before and after the trip at 2.5 second intervals. Additionally, all parameters included in the Post-Trip Review are collected for 2 minutes before and 3 minutes after the trip event at 10 second intervals. Parameters trended at 2.5 second intervals include power range instrument inputs, turbine generator electrical output, turbine-impulse pressure and T-Ref. Parameters trended at 10 second intervals include the 2.5 second parameters, power range channel top and bottom detector inputs, source range and intermediate range detector inputs, Tavg anddT protection and control inputs, overpower and overtemperature AT setpoints, wide range Thot and Tcold, S/G steam flows, S/G feedwater flows, S/G feedwater inlet temperatures, steam generator header pressure, steam generator steam pressures, steam generator narrow and wide range levels, pressurizer level and level setpoint inputs, pressurizer pressure inputs, pressurizer steam space temperature, low range containment pressure inputs, RCP motor stator winding ,

temperatures and RCP seal injection flow and Reactor Coolant Loop flows.

Selection of the majority of the above parameters is based upon their being Reactor System Protection and Controls analog variables.

f The Post-Mortem review data is printed in blocks. Within each j

block the Post-Mortem review data is printed in columns, each I column being headed by the name of the reviewed point. The line l always begins with the group's scan time followed by the values.

The printing format for the values is: one space, a reserved space for a character specifying either removed-from-scan or unreliable status, and a numeric field width of five digits with a decimal point.

Printing begins with a one-line heading consisting of the current time followed by the message title: TRIP REVIEW STARTED, the current data, and the trip time. Blocks of data are then printed from the first 2.5 second block through the last 10-second block.

For each block, a title line is printed followed by a line of point names cach consisting of six alphanumeric characters. Below the point n3mes is printed a line of data values corresponding to the l

i

. . . . = . . . . . - - . ..- - . .-

Page 10 oldest pre-trip point information. The next oldest values are then printed continuing until all prc-trip information for the points is printed.

After the pre-trip data is printed, one-line'is upspaced.

Following this, all the post-trip data for the points is printed.

Data is always arranged in chronological order from oldest to newest.

When all information for the first block of points is printed, the program prints out the next block of data. This process continues until all the data for all the points is printed. The program then prints the end line and printing ceases. Data collection is then restarted.

In addition to the Sequence of Events and the Post-Trip Review Program, there is a variety of other information available to the plant staff to aid in determining the cause of a reactor trip. The First-Out Panel located on the main control board indicates the reactor trip' signal which resulted in the trip. There are MCB recorders .for steam flow, feedwater flow, steam generator level, RCS hot leg temperature, RCS cold leg temperature, auctioneered high TAVE, TREF, AT, 0 PAT setpoint, OTAT setpoint, pressurizer level, pressurizer. pressure, an excore NI recorder selectable to source range, intermediate range 'or power range detectors, and power range upper and lower flux recorders. There are turbine supervisory recorders, a generator temperature recorder, and a transformer temperature recorder in the control room. Metering and relay panels in the control room indicate generator protective relays which trip, thus causing a main generator trip. There are two trend recorders on the MCB which can trend any four analog

. inputs to the plant computer. There is a printer in the main control room which automatically prints alarm messages when process variables reach their alarm limits. The MCB Trip Status Light Boxes indicate which bistables in the SSPS cabinets are in a tripped condition, and the TSLB indication is independent of the plant computer. Another important source of information is 'the reactor operator's log, which is always reviewed following a reactor trip and prior to a return to power.

The only scheduled changes presently identified for implementation on the trip data system described above are those which may result-from addition of the SPDS system.

NRC Request i 2.1 EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE (REACTOR TRIP SYSTEM j COMPONENTS)

Position i

', Licensees and applicants shall confirm that all components whose 1 functioning is required to trip the reactor are identified as

Page 11 safety-related on do;uments, procedures, and information handling systems used in the plant to control safety-related activities which include work order and parts replacement. In addition, for these components, licensees and applicants shall establish, implement a'_ 'intain a continuing program to ensure that vendor information is complete, current and controlled throughout the life of the plant and is appropriately referenced or incorporated in plant instructions and procedures. Vendors of these components -

should be contacted and an interface 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 o' vendor backup, and assure reactor trip system reliability. The w 3r interface program shall include periodic communication witn 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 responsibilities 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 maintenanca work are provided.

APCo Response Westinghouse Electric Corporation is the vendor for all reactor trip system components employed by FNP. The following is a summary of the Westinghouse and FNP interface programs employed to ensure that reactor trip system components are properly documented and retained for the life of the plant.

A description of the Westinghouse Interface Program is given below:

a. Equipment Classification Equipment classification for Westinghouse supplied equipment is accomplished by following the guideliaes established in ANS 18.2 for fluid system components a"d t'e Class 1E definition provided in IEEE standards for electrical components. Lists of systems and major components resulting from this evaluation are typical 7 /

contained in Sections 3.2, 3.10, and 3.11 of the FNP

FSAR. It has been confirmed that the Reactor Trip Syuem l as defined in FNP FSAR Chapter 7.2 is classified by Westinghouse as safety related. These Reactor Trip System components are:

1. Procen Instrumentation and Control Systems i l

! a. Tran smitters/ sensors l I

l

Page 12

b. Cabinet mounted equipment

2. Nuclear Instrumentation System

a. Power Racge Detectors to isolation devices

b. Source and Intermediate (Startup) Range Detectors to isolation devices (A seismic design was not nececsary for Farley startup instrumentation since the plant can be placed in a safe shutdown condition following a seismic event, where this equipment is not required.)

3. Solid State (Logic) Protection System (SSPS)

4. Reactor Trip Switchgear (including Bypass Breaker switchgear)

5. Manual actuation circuits

b. Quality Assurance (QA) Program The Westinghouse QA program is described in WCAP-8370 and Chapter 17 of the FNP FSAR. This program applies to the design procurement and fabrication activities involving safety-related structures, systems and components and has been approved by the NRC. Westinghouse has also established a policy which ensures that all orders, including spare parts, that identify equipment for safety-related applications in nuclear plants will be processed through the Water Reactor Divisions for which this QA program was prepared.

c. Design Verification and Qualification Design verification is accomplished by a review of the design by a qualified individual or task group and by testing or analysis. This testing or analysis provides assurance that the system / component will perform properly during all anticipated service conditions. Guidance provided by TEEE standards 323, 344, and associated

" daughter" 26cuments, Regulatory Guide 1.89, and 1.100, NUREG-05C5, IE Bulletin 79-01B are considered as they apply to the uttlity receiving equipment. Where required, a qualified life is established as part of the qualification p rogram. Any maintenance, including replacement of parts, that is required to maintain this qualified life is communicated to the utility at the time when the equipment is received.

d. Vendor Interface (Technical Information)

It is the policy of the Westinghouse Electric Corporation to be a reliable supplier of equipment, parts, and services

Pags 13 needed by the utility for use in nuclear power plants.

Orders for such equipment, parts and services for safety-related applications are to be given the special attention which is required by applicable regulatory requirements as well as commercial practices. The following information summarizes pertinent parts of this Westinghouse policy on the Westinghouse / utility interface:

1. Definition of Safety-Related Equipment, Parts and Service Equipment, parts and services are safety-related if the utility customer for whom the equipment, parts, and services are intended indicates that he has responsibility under Nuclear Regulatory Commission Regulation 10CFR Part 21 for reporting any defects, as defined in that regulation, in the equipment, parts, or services as delivered to him, or which may subsequently occur.

2. Screening of Orders Entered All orders entered are screened by the Westinghouse District Sales Offices, Distributors, Engineering Service Offices, or Repair Plants to determine whether or not safety-related nuclear equipment, parts, or services are involved. APCo has been informed by Westinghouse that all procurement documents issued by APCo, its sub-contractors or agents to Westinghouse clearly indicate if the equipment, parts or services are for a nuclear plant, safety-related, and if Westinghouse is expected to ensure that applicable NRC regulatory requirements are met.

If an order is received for equipment, parts, or services for a nuclear plant without any indication of whether or not it is safety-related, then the customer will be asked the following question:

Does the customer have any responsibility under 10CFR Part 21 for reporting defects, as defined in that regulation, which exist in the equipment, parts or services at the time of delivery or which may

^

subsequently occur?

If the answer to this question is yes, the order is entered through an approved order entry channel. If the answer to this question is no, then normal commercial practices apply.

3. Approved Order Entry Channels All orders for equipment parts identified by the

Page 14 j'

purchaser or through screening for safety-related applications are processed through the Water Reactor Divisions (WRD). All safety-related service orders will be-placed with divisions who are on an approved supplier list for the particular services requested.

If no approved supplier is listed for requested services, then the order will be processed through WRD.

4. Qualification and Training NRC regulations place the responsibility for ensuring that regulatory requirements are met in the procurement of safety-related equipment, parts, or services on the utility. The utility is required to provide any

'special requirements to those providing safety-related equipment, parts, or services. Westinghouse will ask 1

for any special requirements or instructions from the customer when safety-related equipment,-parts, or

services are involved and ensure that the work done conforms to those special requirements or instructions.

4

. 5. Informing Customers - Instruction Books Instruction books are provided by divisions supplying equipment or parts. Such instruction baoks include information necessary for proper and safe installation, operation, maintenance and repair in ordinary commercial applications of such equipment and parts.

i Westinghouse divisions providing services obtain copies

of appropriate instruction books for the equipment and L- parts which they service from the divisions which

! originally supplied the equipment or parts. WRD j includes in its equipment specifications and purchase orders for equipment and parts appropriate requirements for copies of instruction books for customers and their i own use in developing recommendations to customers for

! installation, operation, maintenance and repair of the

equipment and parts in nuclear applications.

l Instruction books for safety-related equipment are r-subject to the quality assurance requirements of 10CFR Part 50 Appendix B and are included on the quality

, assurance release which must accompany any delivery of L safety-related equipment or parts.

Substantive errors discovered in instruction books for

! safety-related equipment after de'ivery to the customer are subject to the reporting requirements of 10CFR Part

(. 21. Correction of errors may be accomplished by WRD

! Technical Bulletins in lieu of revising the instruction i books, or in cases in which WRD is not involved, by l

l.

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

Page 15 supplementary information provided directly to customers by the involvea division.

6. Informing Customers - Technical Bulletins Information supplementing or revising the instruction books or other similar materials necessary for proper and safe installation, operation, maintenance, or repair of WRD-supplied equipment or parts in nuclear applications is provided by WRD in the form of Technical Bulletins. Preparation of Technical Bulletins has been centralized within WRD and is subject to the same design control process which applies to the equipment, parts and services to which they relate. Technical Bulletins which are safety-related are so identified. All Technical Bulletins are transmitted by WRD to the utility.

Responsibility for this distribution has been centralized in order to ensure that all Technical Bulletins are promptly distributed. All distributions of safety-related Technical Bulletins are now accompanied by a return receipt. The return receipts are pre-addressed to a central point in WRD for recording all Technical Bulletins transmitted and their status. Technical Bulletins for which receipts are not acknowledged within a reasonable time are retransmi tted.

2. The Farley Nuclear Plant Interface Program for the reactor trip system is described below:

The solid state protection system, its associated analog input channel and the reactor trip breakers are classified as safety related equipment. Parts procurement is handled under safety related Administrative Procedure FNP-0-AP-9. Maintenance work requests are handled under safety related Administrative Procedure FNP-0-AP-52. Vendor information (i .e. bulletins, etc.) is handled under safety related Administrative Procedure FNP-0-AP-65. The FNP "SEE-IN" program and "SEE-IN" procedures manual are used by the FNP to ensure that vendor information is reviewed and incorporated into plant design, maintenance, procedures, etc, if deemed necessary. This program can be changed by APCo in the future to enhance equipment reliability and safety. Vendor information is screened for applicability and appropriateness to the FNP. Corrective actions are identified to ensure safety and reliability of the FNP and tracked through completion. Upon completion, items are independently verified to fulfill the requirements specified.

The current "SEE-IN" procedure provides the following guidance:

a. Operating Experience Evaluation - (SEE-IN Program)

The Operating Experience Evaluation Program is that part of the SEE-IN Program which considers both industry and

Page 16 in-house events (and information related to those events),

and applies the information received to FNP design, procedures and training in an effort to improve safety and reliability to FNP units. The evaluation process consists of four segments:

1. receipt of information (sources)

2. screening

3. evaluation

4. corrective action The status of each item and action is kept in the Operating Experience Evaluation Status.

1) Receipt of Information (Sources)

Sources screened for applicability to FNP are:

Industry Events Industry Events are those occurrences or problems which are reported to FNP from outside sources. The reports received and the initiating organization include (but are not limited to):

INITIATOR REPORT (S)

INP0 SOER SER Westinghouse W Letters NSD Technical Bulletins NSD Data Letters Radar Responses Operation & Maintenance

) Memos Availability Improvement Bulletins NuPowSer's General Electric G.E. Letters EPRI Miscellaneous Info Other Vendors Vendor Bulletins, Notices, etc.

NETS Other information and request for information NRC NUREGS Notices Bulletins Circulars

Page 17 These reports are received by variows distribuj;jon. routes in APCo. Where possible, distribution to the SEE-IN Coordinator is made as directly as possible to allow timely processing.

In-House Events In-House Events are those which occur at FNP. These events are identified by review of FNP Incident Reports, the STA Log, failure trending and reporting from the various groups associated with plant operation and maintenance. Although logging of In-House Event Reports may be required, they are not required to be entered into the Operating Experience Evaluation status unless screened "significant".

2. Screening Screening is a review of industry events to determine the significance of the events as they relate to FNP, and a review of in-house events to determine if additional actions should be taken to prevent recurrence of the event.

The relative degree of significance of events or reported conditions considered for evaluation is determined by classification into four categories. These categories are:

a. Not Significant or Not Applicable

b. Notable

c. Response Required

d. Significant A Screening Cover Sheet is attached to each report for screening documentation and retained with the report throughout screening, evaluation, corrective action, and filing. The criteria for screening is as follows:

Not Significant or Not Applicable Wher. an event report does not contain any significant information involving design, systems, procedures, or operating practices which are similar or comparable to existing FNP design, systems, procedures or operating practices it will be classified as Not Significant or Not Applicable.

Page 18 Classifications of an event as Not Significant or Not Applicable requires an explanation of why the event can be classified in this category. The event report will be retained in the Systems Performance Group files for reference.

Notable Any event report which identifies a condition that may be of benefit for review purposes, but that does not pose significant questions concerning FNP design, systems, procedures or operating practices will be :lassified as Notable. Examples of event reports which could be classified as Notable would include:

1. A poor operating or maintenance practice on a system similar to that at FNP where the practice is not used at FNP.

2. A minor personnel error in operating a system similar to a FNP system.

3. Significant events which may be applicable to FNP, but which are currently under investigation by an authoritative engineering group such as design organizations or regulatory agencys.

4. Events which are not directly applicable to FNP, but which report events of high interest to the industry at large and may affect FNP through resulting design / regulatory actions.

The event report is routed to appropriate plant superintendents for review and information, and may be routed by the superintendents to personnel in their group as they deem appropriate. Upon completion of routing, the report is retained in the SEE-IN files for reference.

Response Required Many reports make recommendations or lead to conclusions about j improved design or operating practices which are worthy of

! consideration but are not necessary for safe and efficient plant operation. In this case, factors unknown to the individual responsible for screening play an important part in determining whether or not a recommendation should be implemented. Examples of reports which would be classified as Response Required include:

1. A report which recommends a design for improving operator convenience.

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2. A report which recommends a design change which will improve maintenance methods.

3. A report which recommends an operating or maintenance practice which may not be clearly superior to those currently in use at FNP.

A Problem Report will be written for reports classified as Response Required. The Problem Report is then forwarded to the appropriate plant superintendents for response.

Siginificant The following criteria is used as guidance to classify an event report as Significant:

1. The event or reported condition identifies a potential for degradation of a safety related system to the extent that it could not meet design performance requirements for accident functions.

2. The event or reported condition identifies a potentially unreviewed safety question.

3. Occurrence of the event or reported condition could result in execution of plant emergency procedures.

4. The event or reported condition identifies a procedural inadequacy applicable to plant emergency procedures.

5. The event or reported condition identifies a potential for an unplanned or unexpected release of radioactivity or personnel exposure.

6. Occurrence of the event or reported condition would cause a forced outage.

7. Important " lessons learned" or safety benefits would result from evaluation of the event or reported condition.

If the event or reported condition meets one or more of the above criteria, then an evaluation shall be performed and documented as a Plant Specific Event Evaluation Report.

3. Evaluation Events or reports selected through the screening process as significant (requiring evaluation) will be evaluated in the L

Page 20 form of a Plant Specific Event Evaluation (PSEE).

Specifically, the actual event and/or variations of the event sequence, are to be applied to existing FNP design, procedures, and operating practices and analyzed to assess consequences of the event, probabilities of occurrence of the event, and the adequacy of plant procedure design and operating practices to minimize probability of event occurrence and provide mitigating defenses for event consequences. Alternate event sequence paths are to be evaluated where appropriate. The individual assigned evaluation responsibility shall conduct investigations, interviews, and research as required for a thorough evaluation. If the individual performing the evaluation is confronted with areas of concern where his technical knowledge or experience is limited, he is to contact ind.viduals or organizations having sufficient technical ability and experience to assure appropriate evaluation objectives are selected and achieved and that sufficient corrective action measures are specified. The SEE-IN Coordinator shall provide assistance in establishing communication channels when additional technical knowledge and experience is required. Typical sources of technical knowledge and experience to be considered are members of the plant staff, design organizations, NETS personnel, INP0/NSAC, and vendors.

Where appropriate, recommended corrective actions and findings should include maintenance work request number, PCR/PCN number, inspection and test proposals, and training requirements.

The completed PSEE is to be reviewed initially by the SEE-IN Coordinator to determine the acceptability for further processing. Changes will be made as necessary prior to submittal for further review.

4. Corrective Action Upon completion of review and approval, the complete PSEE package will be copied for distribution to each reviewer.

Where a group is responsible for corrective action as specified in the PSEE, a memo will be attached to the PSEE being forwarded advising the group superintendent of the action required. This memo will also request that estimated i completion dates for each item be provided. (Note: Estimated completion dates are to be included in the Operating Experience Evaluation Status.) Each corrective action item will be tracked on the Operating Experience Evaluation status. Items will be left open until the PSEE approval sheet is received and signed off by the designated superintendent. Each item will be verified complete (either by an individual from the Operating Experience Evaluation Section or the QC Supervisor) and the

Page 21

" Completion Verification" space on the PSEE approval form initialed and dated.

Upon completion of all action items and verification thereof, the completed PSEE (along with all approval and verification signatures) will be copied. The original of the PSEE will be transmitted to Document Control for filing, and the copy will be filed in the PSEE files.

NRC Request 2.2 EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE (PROGRAMS FOR ALL SAFETY-RELATED COMP 0NENTS)

Position Licensees and 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 progr6m 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 part. 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 information 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 maintenance, surveillance, parts replacement, and other

• Safety-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 10CFR Pa rt 100.

Page 22 activities defined in the introduction to 10CFR50, 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 qualification testing is specified for procurement of safety-related components. The specifications shall include qualification testing for expected safety service conditions and provide support for the licensees' receipt of testing documentation to support the limits of life recormended by the supplier.

6. Licensees and applicants need only to submit for staff review the equipment 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 10CFR 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, 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 can not 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 and to assure reliability commensurate 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 nonnuclear 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.

Page 23 APCo Response (2.2.1)

APCo has reviewed and preliminarily determined that safety-related Administrative Procedures FNP-0-AP-9 " Procurement and Procurement Document Control", FNP-0-AP-21 " Identification and Control of Material, Parts and Components," FNP-0-AP-22 "Nonconformance Control Deficiency Reporting", FNP-0-AP-23 " Handling, Storage and Shipping of Materials, Components and Equipment", FNP-0-AP-52

" Equipment Status Control and Maintenance Authorization",

FNP-0-AP-65 "FNP SEE-IN Program" and the FNP Operations Quality Assurance Manual provide:

a) The criteria for identifying components as safety related within currently classified safey related systems, b) A description of the information handling system used to identify safety-related components.

c) The process by whicn plant personnel use appropriate information in determining safety-related activities which include maintenance, surveillance, and parts replacements, d) Existing management controls which verify that the procedures for preparation, validation and routine utilization of the information handling system are followed, and e) The necessary criteria to demonstrate that appropriate design verification and qualification testing is specified for procurement of safety-related components.

The above results are considered preliminary for the following reasons:

By letter dated September 6,1983, APCo requested an extension of time for responding to Section 2.2.1 of Generic Letter 83-28. This request was subsequently denied by the NRC in letter dated October 26, 1983. Due to the activities associated with the FNP Unit 2 outage, APC0 is unable to provide a final response to Section 2.2.1 by the requested date but will provide such information by Feburary 6, 1984.

APCo Response (2.2.2)

APCo is a member of the Nuclear Utility Task Action Committee (NUTAC) formed on September 1,1983 for the specific purpose

Page 24 of defining the provisions of an appropriate program for ensuring that adequate equipment information is determined. APCo will respond to Generic Letter, 83-28, Section 2.2.2, ninety (90) days after completion of the NUTAC study currently scheduled for completion in Feburary, 1984.

URC Request 3.1 POST-MAINTENANCE TESTING (REACTOR TRIP SYSTEM COMP 0NENTS)

Position, The 'ollowing actions are applicable to post-maintenance testing:

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 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 recomendations to ensure that any appropriate test guidance is included in the test and maintenance procedures or the Technical Specifications.

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.)

,APCo Response APCo has verified that FNP procedures covering testing and maintenance and Technical Specifications related to the reactor trip system require post-maintenance operability testing of safety-related components before the system is returned to service. Such testing demonstrates that the equipment is capable of performing its safety functions before being r eturned to service.

In addition, APCo has verified that applicable vendor and engineering recommendations relative to testing the reactor trip system have been implemented. APCo has not identified any Technical Specification post-maintenance operability testing requirements for the reactor trip system which may degrade safety. As a part of the Westinghouse Owner's Group (WOG) APCo is participating in a generic evaluation of the current Technical Specification requirements. As a part of this evaluation process, recommendations could be developed. Based on these recommendations APCo will make appropriate submittals.

Page 25 NRC Request 3.2 POST-MAINTENANCE TESTING (ALL OTHER SAFETY-RELATED COMP 0NENTS)

Position 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 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. Licensee 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.

APCo Reponse APCo has verified that FNP procedures covering testing and maintenance require post-maintenance operability testing of safety-related components before the system is returned to service. Such testing demonstrates that the equipment is capable of performing its safety functions before being returned to service.

Vendor and engineering recommendations were considered in the initial development of test and maintenance procedures currently in use at FNP. APCo is in the process of reviewing vendor and engineering recommendations to ensure that any appropriate test guidance is included in test and maintenance procedures or the Technical Specifications.

APCo is in the process of reviewing Technical Specification provisions for post-maintenance testing to identify any which may degrade safety. The results of this review will be submitted as stated below.

In addition, as a part of the Westinghouse Owner's Group (WOG),

APCo is participating in a generic evaluation of the current

Page 26 Technical Specification requirements to determine if such requirements could degrade safety. Dependent upon WOG recommendations, APCo will maKe submittals as appropriate. It should be noted that previous APCo evaluations have identified safety concerns which precipitated requests for Technical

- Specification changes (e.g., deisel generator (D/G) overload test deletion,- D/G test frequency change, turbine valve test deletion).

APCo originally requested an extension for response to Section 3.2. This extension request was denied by letter received by APCo on October 26, 1983. Due to the activities associated with the FNP

, Unit 2 outage, APCo is unable to provide a final response to Section 3.2 by the requested date but will provide such information by February 6,1984.

NRC Request' 4.1 REACTOR TRIP SYSTEM RELIABILITY (VENDOR-RELATED MODIFICATIONS)

Position

- All vendor-recomended reactor trip breaker modifications shall be reviewed to verify that either

(1) each modification has, in fact, been implemented; or (2) a written evaluation of the technical reasons for not implementing a modification exists.

For example, the modifications recomended by Westinghouse in NCD-Elec-18 for the 08-50 breakers and a March 31, 1983, letter for the DS-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 1- provided.

APCo Response All vendor recommended reactor trip breaker modifications issued after initial criticality of Unit 1 (August,1977) have been reviewed by APCo to verify that either (1) the modification has been implemented or (2) a written evaluation of the technical reasons for not implementing the modification has been performed.

i Westinghouse has verifed that all vendor recommendations for reactor trip breaker modifications issued prior to August,1977, were included in original plant design.

NRC Request 4.2 REACTOR TRIP SYSTEM RELIABILITY (PREVENTATIVE MAINTENACE AND SURVEILLANCE PROGRAM FOR REACTOR TRIP BREAKERS)

Position Licensees and applicants shall describe their preventive maintenance and surveillance program to ensure reliable reactor

Page 27 trip breaker operation. The program shall include the following:

1. A planned program of periodic maintenance, including lubrication, housekeeping, and other items recomended by the equipment supplier.

2. Trending of parameters affecting operation and measured during testing to forecast degradation of operability.

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

4. Periodic replacement of breakers or components consistent with demonstrated life cycles.

APCo' Response The preventative maintenance program contained in FNP-0-MP-28.114 includes provisions for periodic maintenance including lubrication and housekeeping. This program is in accordance with vendor technical bulletin NSD-TB-75-2 and IEB 83-03. The preventative maintenance procedure contains acceptance criteria for initial parameters affecting operation and requires corrective action if these parameters fall outside the acceptance criteria. Repeated failures of the as-found condition will be indicative of trends. APCo has worked with the Westinghouse Owners Group to develop a specific program for life testing of the reactor trip breakers and periodic maintenance and replacement of breakers'and components consistent with demonstrated life cycles. Based on the results of the Westinghouse testing, APCo will incorporate appropriate changes into its preventive maintenance and surveillance program for the reactor trip breakers.

-NRC Request 4.3 REACTOR TRIP SYSTEM RELIABILITY (AUTOMAfl0 ACTUATION 0F SHUNT TRIP ATTACHMENT FOR WESTINGH0USE AND B & W PLANTS)

Position Westinghouse and B & W reactors shall be modified by providing automatic reactor trip system actuation of the breaker shunt trip attachments. The shunt trip attachment shall be considered safety related (Class IE).

APCo Response By letter dated September 20, 1983 f rom Mr. S. A. Varga to Mr. F.

L. Clayton, Jr., the NRC approved the Farley Nuclear Plant Reactor Trip Breaker Automatic Shunt Trip design. This modification was implemented during the second refueling outage of Unit 2 and is i

scheduled for implementation on Unit i during the upcoming fifth refueling in 1984.

Page 28 NRC Request 4.4 REACTOR TRIP SYSTEM RELIABILITY (IMPROVEMENTS IN MAINTENANCE AND TEST PR f_.DURES FOR B & W PLANTS)

Position Licensees and applicants 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 environmental or seismic qualification of these components.

APCo Response Not applicable to Farley Nuclear Plant.

NRC Request 4.5 REACTOR TRIP SYSTEM RELIABILITY (SYSTEM FUNCTIONAL TESTING)

Position On-line functional testing of the reactor trip system, including independent testing of the diverse trip featurcs, shall be performed 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 pi lot valve and backup scram valves (including all initiating circuitry) on GE plants.

2. Plants not currently designed to permit periodic on-line testing shall justify not making modifications to permit such testing. Alternatives to on-line testing proposed by licensees

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

3. Existing intervals for on-line functional testing required by Technical Specifications shall be reviewed to determine that the intervals are consistent with achieving high reactor trip system availability when accounting for considerations such as:

1. uncertainties in component failure rates

2. uncertainty in common mode failure rates

Page 29

3. reduced redundancy during testing

4. operator errors during testing

5. component " wear-out" caused by the testing Licensees currently not performing periodic on-line testing shall determine appropriate test intervals as described above. Changes to existing required intervals for on-line testing as well as the intervals to be determined by licensees currently not performing on-line testing shall be justified by information on the sensitivity of reactor trip system availability to parameters such as the test intervals, component failure rates, and common mode failure rates.

APCo Response On-line functional testing of the breaker undervoltage and shunt trip features at Farley Nuclear Plant is being performed in i

accordance with APCo letters dated August 25, 1983 and September 13, 1983 and as mcdified by the NRC Safety Evaluation Report dated September 20, 1983.

APCo has reviewed the Farley Nuclear Plant Technical Specifications and determined that the intervals required for on-line testing may not be consistent with achieving high reactor trip system availability. Substantiating information was submitted to the NRC by the Westinghouse Owners Group in January,1983 under WCAP-10271. WCAP-10271, Supplement 1, was consequently submitted in response to the NRC rcquest for additional information. The conclusion of WCAP-10271 and Supplenent 1 is that less frequent testing of RPS components is warranted and will result in an improvement in overall plant safety and equipment reliability.

1 RGW/grs-D39 i

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TABLE I Sequence of Event Parameters F0403D RCL L0 F +P8 CAUS RE F04230 RCL L0 F +P7 CAUS RE F04930 STM LINE L0 P SI CAUS RE L0406D STM GEN 1 L0 L0 L CAUS RE LO4260 STM GEN 2 L0 L0 L CAUS RE LO446D STM GEN 3 L0 LO L CAUS RE LO4830 PRESSURIZER HI L +P7 CAUS RE N0005D PWR RNG CH HI Q HI SP CAUS RE N0010D PWR RNG CH HI Q L0 SP CAUS RE N0024D INTERM RNG HI Q CAUS RE N00290 PWR RNG CHAN HI Q RATE CAUS RE N0036D SOURCE RNG HI Q CAUS RE P0407D STEAMLINE DP LOW PI SI CAUS RE P04270 STEAMLINE DP LOW P2 SI CAUS RE P0447D STEAMLINE DP LOW P3 SI CAUS RE P0483D PRESSURIZER HI P CAUS RE P0488D PRESSURIZER L0 P CAUS RE P1003D CONTAINM HI P SI CAUS RE T04980 RCL OVERTEMP DT CAUS RE T0499D RCL OVERPWR DI CAUS RE V0324D RCP BUS UNDER VOLT + P7 CAUS RE Y0004D REAC MANUAL TR 1 CAUS RE Y0005D REAC MANUAL TR 2 CAUS RE Y0006D REAC MAIN TR BKR A Y0007D REAC MAIN TR BKR B Y0026D REAC AUX TR BKR A Y0027D REAC AUX TR BKR B Y0324D RCP BUS UNDER FREQ + P7 CAUS RE Y0335D UNIT ON LINE TIE OCB 810 BKR Y0336D UNIT ON LINE TIE OCB 914 BKR Y0390D TURB TRIP +P7 CAUS RE Y04010 STM GEN 1 LO L + FW F CAUS RE Y0421D STM GEN 2 L0 L + FW F CAUS RE Y0441D STM GEN 3 LO L + FW F CAUS RE Y04800 PRESURER L0 P SI CAUS RE YO9200 SFTY INJ SET MANUAL 1 CAUS RE YO921D SFTY INJ SET MANUAL 2 CAUS RE Y23010 SG FEED pump A TURBINE Y2302D SG FEED PUMP B TURBINE Y2303D BOTH SG FEED PUMP TURBINES

. Y2861D GEN DIFF AUX REL Y2862D GEN LOSS OF EXC AUX REL Y2863D GEN NEUT 0.C. AUX REL Y2864D MAIN POWER TRANS AUX REL Y2865D UNIT AUX TRANS 1A AUX REL

TABLE I Sequence of Event Parameters Cont'd Y2866D UNIT AUX TRANS 18 AUX REL Y2867D START-UP AUX TRANS 1A AUX REL Y2868D START-UP AUX TRANS IB AUX REL Y2869D GEN FIELD MAX EXCITATION Y28700 GEN VOLTS / HERTZ Y2871D TURBINE LOW VACUUM Y2872D TURBINE OVERSPEED Y2873D TURBINE VIBRATION Y2874D TURBINE LOW OIL PRESSURE Y2875D TURBINE EMERGENCY TRIP SWITCH Y2876D TURBINE EH FLUID LOW PRESSURE Y2877D TURBINE EH POWER SUPPLY Y2878D TURBINE MAIN STOP VALVES Y2879D DEH 24V Y2880D MAIN TRANSF SUDDEN PRESSURE Y2881D UNIT AUX TRANS 1A SUDDEN PRESS Y2882D UNIT AUX TRANS 1B SUDDEN PRESS Y2883D STARTUP AUX TRAN 1A SUDDEN PRESS Y2884D STARTUP AUX TRAN 1B SUDDEN PRESS Y2886D 230 KV BKR 810 Y28870 230 KV BKR 914 Y2888D 230KV BKR 800 Y2889D 230KV BKR 904 Y28900 230 KV BKR 820 -

Y28910 230 KV BKR 924 Y2892D 4160V BUS A TRANSFER Y2893D 4160V BUS B TRANSFER Y2894D 4160V BUS C TRANSFER Y2895D DIESEL GEN 1-2A Y2896D DIESEL GEN 1B Y2897D DIESEL GEN IC Y2885D DIESEL GEN 2C Y9000D TURBINE TRIP ATS-DEH TO R-1/AST Y9001D TURBINE TRIP DC-DEH TO R-1/AST Y9002D TURBINE TRIP 05-1-DEH TO R-1/AST Y9004D TURBINE TRIP SSPS A A.S. 20-1/AST Y9005D TURBINE TRIP MSIV A TO 20-1/AST Y9006D TURBINE TRIP MSIV TO 20ET

! Y9007D TURBINE TRIP MSIV TO 20-2/0PC Y90080 TURBINE TRIP A.S. 63-2AST TO 20ET Y9009D TURBINE TRIP SSPS B TO 20ET Y9010D TURBINE TRIP TB SSPS B TO 20-2/0PC Y9012D TURBINE TRIP TB 63TB T0 87T2-XX Y9013D TURBINE TRIP T/D GEN TRIP T0 62A Y9014D TURBINE TRIP T/D GEN TRIP T0 63A L

4 ENCLOSURE 1 I

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i VOLUME 5 FNP-1-EOP-5.0 May 6, 1983 Revision 6 J

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EMERGENCY OPERATING PROCEDURE FNP-1-EOP-5.0 l

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FNP-1-EOP-5.0 VOLUNE 5 LIST OF EFFECTIVE PAGES REVISION NO. 5 PAGE NO. 0 1 2 3 4 5 6 7 8 9 10 11 1 X. X X x x 2 X X X X  :( x 3 X X X X 4 X X 1

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VOLUME 5 FNP-1-EOP-5.0 FARLEY NUCLEAR PLANT UNIT 1 EMERGENCY OPERATING PROCEDURE EOP-5.0 REACTOR TRIP 1.0 Purpose This procedure provides Symptoms, Automatic Actions, Immediate operator Actions and Subsequent Operator Actions required for a reactor trip.

1 Symptoms 2.0 2.1 Any reactor trip indicated on the First-Out Annunciator Panel.

= 3.0 Automatic Actions i 3.1 Reactor Trip-Turbine Trip

+ 3.2 Turbine Trip-Generator Trip

!j NOTE 4

g When a step is completed place the operators initial or the value noted in the space provided

! in the left hand margin.

i 4.0 Immediate Operator Actions ,

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s Date of trip:

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4.1 Verify Reactor Tripped by observing all full L)j length rods fully inserted and nuclear power L decreasing. If not, refer to EOP-15.

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,s-hj 4.2 Verify the main turbine is tripped. If not, 3

refer to EOP-15.

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} 4.3 Verify RCS temperature is stable or decreasing.

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4.4 Verify 4160V buses 1A, 1B, 1C, 1D and 1E energized on the S/U transformers.

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5.0 Subsequent Operator Actions 5.1 Indicate the position of the Reactor Trip and Bypass Breakers immediately following the trip by circling f ., the appropriate response, and record Date/ time and

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initials. Manually open any breaker which failed t to automatically open.

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VOLUME 5 FNP-1-EOP-5.0 Reactor Trip Breakers Trip Bypass Breakers A- OPEN CLOSED A- OPEN CLOSED B- OPEN CLOSED B- OPEN CLOSED Date/ Time Initials 5.2 Announce on the plant paging system " Unit 1 Reactor Trip."

5.3 Trip the main feedwater pumps.

5.4 Start or verify started the motor driven Auxiliary Feedwater pumps. Feed as necessary to recover i

steam generator levels to 30 to 40 percent in the narrow of the range into cold water and the minimize Steamthe effect on T"Y9 Generators.

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5.4.1 If MDAFW pumps started automatically regain control of the FCV's per FNP-1-SOP-22.0.

5.4.2 If the TDAFW pump started, regain control of its FCV's and the turbine per FNP-1-SOP-22.0.

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L CAUTION b With insufficient decay heat =

lj available overfeeding the steam generators will result in

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i excessive cooldown with no  !

I apparent increase in Steam l} Generator level. AFW flow

% must be balanced to limit the cooldown rate and regain the l steam generator level.

l n 5.4.3 If Condensate Storage Tank level decreases to four (4) feet and Auxiliary Feedwater is required to maintain plant conditions shift the Auxiliary Feedwater pumps h ,

suctions to Service Water per FNP-1-SOP-22.0.

5.5 Verify proper steam dump operation and if T is less than or equal to 5470F, verify contf5fler

! PK464 in manual and demand on the steam pressure i i controller is adjusted to a setpoint of 1005 psig 3

Rev. 6 2/4 1

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VOLUME 5 FNP-1-EOP-5.0 and place the steam dump mode selector switch to the pressure position and place in Auto Manual controller PK464 in automatic.

m 5.5.1 If one or more steam dump valves fail to 9 close and cannot be shut from the MCB prepare to shut the Main Steam Isolation Valves.

I 5.6 If the condenser is not available verify proper i operation of the atmosphere relief valves. t 5.7 The following should be done as rapidly as possible and not necessarily in order. .

5.7.1 Transfer NR-45 to intermediate range and insure proper power decay. .

Isolate main steam drain pots by closing I 5.7.2 '

N1NllV555 A, B, C and D.

5.7.3 If the second stage of the MSR's are in operation push Reset on the Reheat Control Panel.

y 5.7.4 Secure Auxiliary Steam to Unit 2.

Evaluate the need for isolating steam to

( the Auxiliary Building, and if necessary ,

secure steam to the Auxiliary Building.

l 5.7.5 Secure Heater Drain Pumps lA and 1B. f

=

5.7.6 Secure all but one condensate pump.

5.7.7 If T decreases to 5430 F block the g

.q steaIYIne low pressure safety injection.

J l*I l 5.7.8 Maintain Pressurizer pressure and level  !

at the no-load values. ,

l=

S I

j 5.7.9 Secure one steam jet air ejector. i t , .

-1 1 .!

1.

l .I l

t' k

i i

d 1

II 2

I

', Rev. 6 i 3/4 m

l VOLUME 5 FNP-1-EOP-5.0 l

P 5.7.10 Verify Steam Generator Blowdown is I isolated.

1 CAUTION The intent of closing the MSIV's in Step 5.7 is to regain control of the cool-down rate and ensure against j

i exceeding 1000 F cooldown in

, one hour. If cooldown rate I

is under control, but tempera-l ture is decreasing the Shift Supervisor may decide not to i shut the MSIV's until a lower temperature is reached.

i i

1 5.8 If T rapidly decreases to 5000F close the MSIVI E9as follows:

I 5.8.1 Break condenser vacuum. -

} 5.8.2 Isolate gland sealing steam.

y

{

5.8.3 Close the MSIV's. .

t i '

5.9 Refer to FNP-1-SOP-28.1 to complete Turbine

){

Generator shutdown. ,

]

5.10 Complete plant shutdown to Hot Standby per FNP-1-UOP-2.1.

5.11 Start up Auxiliary Boiler using FNP-1-SOP-55.0 if required.

f 3

lj Rev. 6 j 4/4

FNP-1-EOP-15.0

( May 12, 1983 Revision 7 a.

FARLEY NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE FNP-1-EOP-15.0

- S A

F E

T Y

ANTICIPATED TRANSIENTS WITHOUT TRIP (ATWT)

[ R E

L A

T

• E D

ado 3 03TIOBINODNf1 Approved:

. Bh *???w OperationsSuperipendent Date Issued: J 2 P3 i

Diskette EOP-3

_ . = - - - - - - -

VOLUME 5 FNP-1-EOP-15.0 LIST OF EFFECTIVE PAGES REVISION NO. 2

.(

PAGE NO. 0 1 2 3

• 5 6 7 8 9 10 11 i

1 X- X y x X y x

.. 2 X X x x x G

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k h( '

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Page 1 of 1 l

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{ . . _ . . .

• ' FNP-1-EOP-15.0 FARLEY NUCLEAR PLANT

( UNIT 1 EMERGENCY OPERATING PROCEDURE EOP-15.0 ANTICIPATED TRANSIENTS WITHOUT TRIP (ATWT)

I 1.0 Purpose This procedure provides guidelines for operator action in the event a reactor trip and/or turbine trip does not occur automatically if either trip is required.

2.0 Symptoms 2.1 If entering this procedure from EOP-5 (Reactor Trip) AND any one of the following conditions

' exist (evaluate in the order given):

2.1.1 TSLB bistables tripped indication meeting the required coincidence for a reactor trip or 2.1.2 Indicators having reached a reactor trip MP setpoint.

2.2 If entering this procedure because Nuclear Power I is NOT decreasing and all full length rods are NOT fully inserted with a reactor trip being called for, as defined by: ,

2.2.1 TSLB Bistable tripped indication meeting the required coincidence for a reactor trip or 2.2.2 Any' condition requiring a reactor trip.

2.3 Failure to obtain a turbine trip following a turbine trip signal as indicated by the turbine throttle valves NOT closed.

3.0 Automatic Actions None i

Rev.6 1/2

FNP-1-EOP-15.0 NOTE

(

When a step is completed place the operators initial or the i value noted in the space provided in the left hand margin.

' Immediate Operator Actions 4.0 4.1 Reactor does not trip:

i 4.1.1 Manually trip the reactor from the Main Control Board. IF not successful, then:

open the supply breakers for the MG sets I with main control board handswitches.

,1 If not successful, then: Emergency Borate and Drive Rods in.

i 4.1.2 Go to local panel and manually open and

,: rack out Reactor trip breakers and

! Reactor trip bypass breaker.

4.2 Turbine does not trip:

4.2.1 Attempt to manually trip the turbine from the Main Control Board. IF the turbine does not trip, then:

(

4.2.2 De-energize the E.H. Pumps 1A & IB from the Main Control Board. Start all available auxiliary feed pumps and throttle as necessary to maintain S/G '

level in the narrow range. IF a turbine trip has not occurred, then:

4.2.3 Close the MSIV's.

5.0 Subsequent operator Actions 5.1 IF following an automatic turbine trip signal, the turbine does not trip and causes an uncontrolled cooldown, emergency borate in accordance with EOP-6.0.

5.2 When a reactor trip does occur, refer to EOP-5.0.

5.3 When a turbine trip does occur, refer to AOP-3.0.

l 5.4 IF a safety injection signal occurs, refer to I EOP-0.

Rev. 7 2/2

PROCEDURE REQUEST FORM FNP-0-AP-1

1. Procedure Number re'F-o- AP-/4 Revision Number /3 Procedure TitleC4cDve,r or ostas4 nest -OdtF44%N$ 7doup

/ Safety Related a Non-Safety Related -

0 New Procedure Request O Procedure Revision,'New Revision Number a Change of Intent V Temporary Procedure Change, Effective until next permanent change, TCN /36 0 Temporary Procedure Change, Reg'd. by Plant Condition a Temporary Procedure Change, One Time Use, TCN O Delete procedure

2. Change Summary Procedure Page Numbers Affected by Change /pMM(f AL;t,s ado 3 03T10WOM 2.1 " ' "

0-/8,/9 Yho ,

' I 2.2 Description of Changes a,c,6 /rtMedtiD i

2.3 Reason for Change "To~ Ata>v,es Asx46va er 4ece,,0c :mswer

! t % is ro Act.l% w SAG yrac- Asorov4 WDFU74A oc l'% C& : b Ss/4;C  ! ~5D CLA6/PY SeedDvA4f" Ad9 ht.Ds ASC VMN sinsurand Vggefamm of >xpecessistc 7MW /NM.

~

! ' 3. Prepared By , ' W .T , 4/7!f3-

'Date

, y 4 1gnatur4 Title ,

4. Reviewed By N N ,6/b $ 8 '

, /OdDate 6

Signature ' Title '

5. Cross-Disciplinary /PORC Review Group Signature Title Date j l

', iI ;

6. T orary Change Appro.'al (Signature /Date)

Member Group Staff e

, . _ _ ,r ._,,,3 'b'hf D Shift Foreman 7 ,

, / . ,

Senior Reactor Operator MfA / g/p/y3 Plant Manager 'g/ g/E , _ _ ' /f f).e.-g7

7. Final Approval (Signature /Date, required within 60 days of temporary '

approval)

O Group Supervisor /

D Plant Superintendent /

D / MSAER

/

F Vice President - '

(

-- Nuclear Generation /

O /

[ Plant Manager /

Figure 1 Rev. 12

- - - . - , , , . . - - - , - - - - - + , - - - - - - - - -

,- - . , . , , - . , - - - - , - ,.e.,

i

. ( - * -

• "~ ~

yggy.0.Ap.g

. FARLEY NUCLEAR PLA!iT n!UCLEAR SAFETY EVALUATIO:( CECK LIST 7 3

• r . . (1) UNIT C f.5 4ftaD / -

' t (2) Cli2CK LIST APPLICADLC To:o rw *W- /4 Revision /3 TCN 23 0 N ,4 (3) SAFETY EVALUATIO!! - PART A

} The procedure, procedure change or modifestion to which this evalusti::

? is applicable represents:

5

• l (3.1) Yes No , A change to the plant as described in the 7513.?

(3.2) Yes No # r A change to procedures as described in the II;2.7

) (3.3) Yes No 7 A test or experi:nent not described in the F3/J.?

(3.4) Yes No V A change to the Technical, Specifications?

, If the answer to sny of the above questions is "Yes," cc.nplete Iten U.) .

l 1. - and attach a 10CFR50.59 evaluation. If the answer to all of the abcve .

is "No." omit Item (4) and Item (9).

l .

.,,, (4) SAIITY EVALUATION - PART B .

( _s (4.1) Yes No Will the probability .of an accideqt previously I . 4 .. evaluated in the FSAR be ' increased?

( (4.2) Yes' No Will the consequences of an accident previcusly .

[ N *

• evaluated in the ISAR be increased?

? (4.3) Yes No May the possibility of an accident which is different than any already evaluated in the

. e FCAR be created?

(4.4) Yes

, , , No Will the probability of a malfunction of

( ~, j . , .

equipment important to safety previously 9 evaluated in the ISAR be increased?

,(4 5) Yes . No Will the consequences of a ms1 function of

, equipment important to ssfety different th :

any already evalusted in the TSAR be incressed?

. (4.6) Yes No May the possiblity of a malfunction of equi;::::

importsnt to safety different than any aires:y

' evaluated in the FSAR be created? .

. . (4.7) Yes No Will the margin of safety as defined in the

1

, , basis to any Technical Specifiestion be redscad?

[ If the answer to any of the above questions is ."Yes," an unreviewed safety question is involved. Explain the basis for each answer provided in Section 4.

(5) REMARKS: (Attsch additional pages if necessary) -

• L -

(6) PREPARED BY: de -

DATE *7 8--

. (7) REVIELTD BY: ' / OATE ' '

(8) PORC REVIEV: DATE (9) NORD REVIEW: DATE

' Distribution -

Origtnal: Document Control File A21 6226

- ( * %c.3 -

D~ Figure 3 Rev. 7 e

s ww w , y-- . . - - - _w,--,.,-- ,--,- , , --, .--. ,,,,..,,,e.,-w,,,, ,,--,-----_,_,,,m.,_,-,__..,,,,___,_-,-.,,_,,,,,,,m_-n,,,

,,-w.-- . _ ,, - . . --

PROCEDURE REQUEST FORM FNP-0-AP-1

1. Procedure Number FNP. O - AF./(, Revision Number /3 Procedure Title Co 3, d uJ ef flo c , 7Te n do c 9,77eme

m . Geavo I '

~

W Safety Related O Non-Safety Related D New Procedure Request a Procedure Revision, New Revision Number .

O Change of Intent 4 Temporary Procedure Change, Effective until next permanent change, TCN /74 0 Temporary Procedure Change, Reg'd. by Plant Condit D Temporary Procedure Change, One Time Use, TCN O Delete procedure ,

2. Change Summary i

2.1 Procedure Page Numbers Affected by ONTROLLED e . J.. / 2 ..( 3 a.tf ,,r_r COPY 33 Tel $~b a! #-% ,,,.e 1 t + 3 ', e-on) . B- W i9.'a r 's .1(,

y s i i _i i

s ,

l 2.2 Description of Changes 5"c e #r/,c/c d I =

2.3 Reason for Change To cle ,, . Pe L T ; , ,. O c e , 5 -

ese,, - , e & cei Wamt 4% -o ! ! v ' A f f e d k,' c o u r'o m eB on er,75'/r 14 dLov /14 if ele t/s afloh 4 A m. e t.e dare t i

( u

,"- 3. Prepared By ,Mb , ~

7 .29- @

gignature Date Title f

4. Reviewed By d, [du m- , 9 h Signature / Title / Date ~

5. Cross-Disciplinary /PORC Review Group Signature Title Date b a c. , , .

l .

6. Temporary Change Approval (Signature /Date)

Member Group Etaff / /0/7 2 0 Shift Foreman / /

D Senior Reactor Operator .

, /

7 Plant Manager GF.4., pc::ra / to-/ fy

7. Final Approval (Signature /Date, required within 60 days of temporary approval)

O Group Supervisor /

0 Plant Superintendent /

W MMR /

1. Vice President -

(' Nuclear Generation /

a /

Q" Plant Manager /

Figure 1 Rev. 12

i...g.. ,-

T3P-0-AP-1

<I m

s YARI:E 6 ?!. ANT

% ,- M Saar . I7AIEACCN C3ECI T.IST (1) UNIT I 4 P_ TCN M #

(2) CECI L 3T .APPMCAAE To: fvF- O. A #. / 4 Rav sion___

(3) SAar..; I7A17 ACON - PJut" A .

• The procadn=s, procadn=s change or modifcation ta whid ' d e evalution is apolicable esprases:s:

(3.1) Yes . ___ No

! A changs em -da plant as described.h da ISAR?

(3.2) Yes No ./ A change to precadurns' as dese:-bad h tha TSAR?

(3.3) Tas No / A cas: or espe 3 a=: son described is .ha ISAR?

(3.4) Tas No v" A changs to hs Ted d cal Spe* #d cations?- .

II =a answer to an7 of tsa aoove questions is. "Tas," coarplata Itas (6) and at.ach a 10C2350.59 evaluation. If the ansva: s an of the above is "No." omit Itasi (4) and Ites (9) .

• i (4) SA4 2 E7AIUA'."ICN - Palt? 3 (4.1) Tas No Will the probability of an accidas: previously evaluated is the ISAR be inc sased?

Win the consequances of an accidas: p viously (4.2) Yes No avaluacad is the ISAR be isc:aased?

(4.3) Tas Na May the possibility of an accidas: which is g~ d4!!a:a=: dan a=y al sad 7 ava12ated is -de O- F5AR. be c atad?

(4.4) Tas No Win the y=chab4':7 of a malfunc:fon of k .s*

eqtd-=-a Lspor.a=: .s safaq previously evaluated is the IIAR be'J.===sased?

W4 " -da consequencas of a salf:=ctio= of (4.3) Tas No equipment i=portan: .s safag diffs ::: chas

• - any al sady evalua ad is ca ISAR be isersased?

(4.5) Tas No May the possiblity of a salf :c.ics of equipnas important :s safa:7 diffa: == han any al:ssd7 avaluatad is da TSAR be c=sacad?

Will the marg-s of safety as defined is ,.ha (4.7) Tas No _

basis to any Ta+ d cal Specification be :sduced?

If tha answer to any of tha above ques ions is "Tas ," as un== viewed safsc7 question is i=vol-red. Izplais ce basis for each a=sve: ;;ov dad is section 4.

(3) N: (A :ach additional pages if secessary)

FRE?.GID 3T: [M66.JM--- CA' I T M- D (6) DAC 4 - 4 e -%

(7) 32.4.:.4E2 3T: DBW Uo

( . (3)  ? CRC E7 Z'4: O OA5 DAC (9) 3C33 3I*12*4:

~

31st: bc:1oc Cr:.3.=a. : 3cc me= Cant:sl Tile Al*, 6226 Tigure 3 Rev. 7

t

! FNP-0-AP-16 August 25, 1983 Revision 13 FARLEY NUCLEAR PLANT ADMINISTRATIVE PROCEDURE FNP-0-AP-16 S

A F

E T

Y CONDUCT OF OPERATION - OPERATIONS GROUP R

E L

A T

UNCONTROLLED COPYD Approved:

k LL<A.hk Manager' Safety Au 't & Engineering Review I. , -

['b- ( [ 4.C l

Vice President-Nuclear Generation j.t- ., -in Plant Manager l t Date Issued: [-2 / ' I$

Diskette AP-13

' FNP-0-AP-16 LIST OF EFFECTIVE PAGES s

REVISION NO i

.f 2 REV 7+g' PAGE NO. NO 12 13 14 15 16 17 18 19 20 21 22 1 X 2 X 1 X L 11 s 11 g 11 7 11 n 11 o 11 in 11 i1 7 to 11

'll k.-I' i3 11

,< 11 x

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11

/ $_ 3 11 .

18 11 19 11 .

20 11 1

1 21 11 77 11 71 11 I

94 11 E l 75 11 Y .

O ,.i Page 1 of 5 e

LIST OF EFFECTIVE PAGES FNP-O-AP-16

, REVISION NO i

'/' I ' PAGE NO.

REV.

No. 12 13 14 15 l 16 i 17 18 19 20 21 22 :

l

'y ?

26 11 l 27 11 l 28 to 29 to 30 7 31 7

. 32 11 I 33 x 34 11 35 x -

36 x

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(. 38 7 39 7 .

l 40 11 l '

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h .. _ _ . _ _ . . _ _ _ _ . _

FNP-0-AP-16

~

LIST OF EFFECTIVE PAGES

.\ REVISION NO l

,4

. .Ev.

1. '. ,;,l' PAGE NO. NO. 12 13 14 15 16 17 18 19 l 20 21 22 ,

51 11 52 11

% 11 FT f*tm F 1 1 w F T t*fM F 7 1 - x FIGURE 3 1 . r FIGURE 4 1 11

'( : FIGURE 5 1 7

. FTCURE 6  ;

1 x

/ FictmE 7 l

1 7 APPFMDIY A 1 in 9 o

, a i i i

r. o '

I APPENDIX B -

l  !

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r V - _ . - . . - . . - . . -.. _ -. . . . . . . . .. ..

FNP-0-AP-16 LIST OF EFFECTIVE PAGES

't REVISION NO i f

T =

/ REV.

PAGE NO. No. 12 13 14 15 16 17 18 19 20 21 22

' i( '.' .

2 11 3 10 4 7 5 11 6 7 7 10 8 7 -

9 11 10 x D * '

11 x 12 x l '4 7

.(: la 11 19 11

. m x l i i

17 7 l

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10 7 21 7 l

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,, , x

?A X 95 , X 4

9A , r . X , _

e L 27 X

, 28 i X Page 4 of 5 G

,-w----y w -

a-,

FNP-0-AP-16

, LIST OF EFFECTIVE PAGES

,'t REVISION NO i

' [.

' g' PAGE NO.

REV.

NO. 12 13 14 15 16 17 18 19 20 21 l 22j l 1

i, .,

TABLE I 1 7 3 7 APPENDIX C i

1 a 2 ,

3 in 4 10 5 10 6 x

. .. 7 10

. 8 10

\

%: 9 10 l 10 11

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• 11 R '

1L R 19 A 1A o 17 is IR 11 l

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

FNP-0-AP -

CONDUCT OF OPERATION - OPERATIONS GROUP

. 1.0 Purpose The purpose of this procedure is to provide instructions to ensure that plant operations are conducted in an effective, consistent manner in accordance with the operating license, plant procedures, and applicable regulatory requirements.

2.0 Scope

~

This procedure establishes the organizational and individual responsibilities of the Operations Group and provides administrative instructions necessary for the daily conduct of plant operations.

~

3.0 Organization and Responsibility The Operations Group is comprised of personnel in the following classifications: Operations Superintendent, Operations Supervisor, Unit Supervisors, Sector Supervisors, Shift Supervisor, Shift Foreman, Plant Operator, Systems operator, Systems Operator in Training, Switchboard Operator, Planner, Building and Grounds Supervisor, Utility Foreman, Nuclear Operative, Engineers, Engineering Aides, and Clerk. The Operations Group is organized as shown in Figure 1.

3.1 Qualifications and Responsibilities 3.1.1 Operations Superintendent - The Operations Superintendent is responsible for plant operations and maintaining the cleanliness of the plant. The Operations Superintendent reports to the Assistant Plant Manager and provides general supervision for the Operations Supervisor, the Planning and Scheduling Supervisor, and the Building and Grounds Supervisor. The Operations i

Superintendent serves as Emergency Director, Operations Manager and is a member of the PORC. This position also performs outage management functions as directed by the Assistant Plant Manager. The qualifications and responsibilities of the Operations Superintendent are delineated in FNP-0-AP-3.

TCN 13A l

1 l

l

~ . -. _

FNP-0-AP-16

! 3.1.2 Operations Supervisor - The Operations Supervisor is responsible to the Opera-tions Superintendent for the operation of both units. Plant operations are performed by the Operations Group under the general supervision of the Opera-tions Supervisor. This position serves as Operations Manager and as the Operations Superintendent'c alternate for the PORC.

Qualifications and responsibilities of the Operations Supervisor are delineated in FNP-0-AP-3.

3.1.3 Unit Supervisor - Two Unit Supervisors report to the Operations Supervisor and assist him in the general supervision of the Operations Group. Additional Sector Supervisors report to the Operations Superintendent to assist in the development of procedures, perform administrative functions and the accomplishment of special projects.

These positions may serve as Operations Manager.

i 3.1.3.1 Qualifications (1) High school education or equivalent.

' (2) A total of four years power plant experience of which a minimum of one year shall be nuclear power plant experience.

A maximum of two of the remaining three years of power plant experience may be fulfilled by academic or related technical l

training on a one-for-one basis.

(3) USNRC Senior Reactor Operator's '

License. ,

3.1.3.2 Responsibilities of Unit Supervisor: '-

For Unit 1.  ;

(1) Responsible to the Operations '

Supervisor for the oveiall cleanliness, and material condition of Unit 1 C6ntainment, Diesel Building, Switchyard, / .

Fire Protection House, and , , .

Unit 1 side of Auxiliarv ,

i Building and Turbine Bullding. ,

Rev.'12 2

~

-,---n- -- < , -. ,. - - - , - - - - . , . , . -..,-_..,,rac

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

FNP-0-AP-16 I (2) Assume the responsibilities of the Operations Supervisor, relative to Unit 1, in his absence.

(3) This position may serve as Operations Manager.

(4) During normal operations this Unit Supervisor provides a coordination function for the Operations Manager to the Shift Supervisor.

During off-normal conditions when the Operations Manager is not immediately available this Unit Supervisor may give direction to either Shift Supervisor as appropriate.

3.1.3.3 Responsibilities Unit Supervisor For Unit 2. -

(1) Responsible to the Operations Supervisor for the overall cleanliness and material condition of Unit 2 Containment, River Water and Service Water Structure, and the Unit 2 side of the Auxiliary Building and Turbine Building.

(2) Assume the responsibilities l

of the Operations Supervisor relative to Unit 2, in his l

' absence.

(3) This position may serve as l

Operations Manager.

[ (4) During normal operations this

. Unit, supervisor provides l

a coordination function for

', 'j . - the Operations Manager

- " to the Shift Supervisor.

During off-normal conditions

.- when'the operations Manager

', is not,immediately available

- ;_ this Unit Supervisor may givs direction to either

' r ,

Shift Supervisor as e aporopr2 ate.

[

' Rev. 12

, ,i

. i >

rI ,

. FNP-0-AP-16

, 3.1.3.4 Responsibilities Sector Supervisor - Administrative (1) coordinate schedule and document Operations Group training and qualifications.

(2) Develop shift schedules to meet manpower and license requirements of the Technical Specifications and expected operational activities.

(3) Coordinate investigations and development of Operations Group input to incident reports and LERs.

(4) Perform other projects as assigned.

(5) This position may serve as Operations Manager.

3.1.3.5 Responsibilities of Sector Supervisor - Special Projects (1) Supervise Engineers, Engineering Aides and other personnel assigned in the performance of Special Projects to include (a) Development of Operations Procedures (b) Coordination of daily work activities with other plant groups (c) Provide Operations Group input to ALARA program.

(2) This position may serve as Operations Manager.

3.1.4 Building and Grounds Supervisor - The Building and Grounds Supervisor is responsible to the Operation Superintendent for maintaining the cleanliness of the plant buildings and grounds, with the exception of the radiation control area.

This position will develop general cleaning plans and provide supervision

! Of the Utility Foremen.

Rev. 7 4

l l

l

. . - . . - _ . . . . ....__--......2.- ._. _ - , _ - . - - . _ _ . . . . . _ - _ _ _ _ - , , , - . - . - . . - . , - . . _ , _ , .

- ' FNP-0-AP-16  :

! 3.1.4.1 Qualifications (1) High school education or equivalent (2) Sufficient maintenance or operational work experience to provide: a good knowledge of plant layout and functional operation, and an understanding of radiation protection regarding decontamination activities.

3.1.4.2 Responsibilities (1) Establishing and conducting a general cleaning plan.

(2) Scheduling of Nuclear Operatives assigned to the Utility Group.

(3) Assignment of Nuclear Operatives to other plant groups.

(4) Periodic inspection of buildings and grounds.

1 (5) Initiate purchases requisition I for materials and equipment required by the Utility Group.

(6) Carry out special assignments as requested by the Operations Superintendent.

(7) Coordinate with the Training Superintendent to ensure the Utility Group personnel receive the required training in a timely manner.

3.1.5 Planning and Scheduling Supervisor The Planning and Scheduling Supervisor is responsible to the Operations Superintendent for planning, coordinating, scheduling,ive and repetit task maintenance.and tracking all corrective The Planning and Scheduling Supervisor provides general supervision for each of the functional group planners.

This position may serve as Operations Manager.

Rev. 11 5

l .- . . . _ . . _ _ . _ _

FNP-0-AP-16 t 3.1.5.1 Qualifications (1) High school education or equivalent.

(2) Sufficient maintenance and operational working knowledge to provide an understanding of an integrated approach toward planning and scheduling maintenance.

3.1.5.2 Responsibilities (1) Ensure that the duties and responsibilities of the Daily Planning and Scheduling .

Group are carried out as described in FNP-0-AP-52.

(2) Provide appropriate management reports concerning maintenance activities.

3.1.6 Group Planner (Operations, Mechanical, Electrical, and Instrument and Control)

Planners report to the Planning and Scheduling Supervisor.

3.1.6.1 Qualifications (1) High school education or equivalent.

t (2) Sufficient maintenance and/or operational working knowledge to provide an understanding of detailed job sequence planning.

3.1.6.2 Responsibilities (1) Process maintenance work requests and provide job sequence planning in accordance

' with FNP-0-AP-52.

3.1.7 Operations Manager During conditions that require implementation of the Emergency Implementing Procedures (EIP's) the Operations Manager is responsible to the Emergency Director and his duties are specified in FNP-0-EIP-0.

' Rev. 11 6

, FNP-0-AP-16 I

During normal operations the Operations Manager is responsible to the operations Superintendent for routine coordination of plant operation and administrative functions relating to the Operations Group.

The operations Manager is on-call as specified in FNP-0-EIP-8.

3.1.8 Shift Supervisor l During his shift, the responsibility and authority of the Shift Supervisor shall be to maintain a broad perspective of operational conditions affecting the safety of his assigned unit as a matter of highest priority at all times.

The Shift Supervisor should not become involved in any operation which distracts him when multiple operations are required in the control room. During plant transients or an emergency he should not become totally involved in any single operation which distracts him from the rest of the operations required in the Control Room.

As specified in paragraph 3.2.2, each unit shall have a shift Supervisor with a Senior Reactor Operators license l on the unit assigned.

The Shift Supervisor has three basic reporting chains. He is responsible to the Operations Supervisor for routine administrative functions as specified on Figure 1. He is responsible to the Operations Manager during normal plant operations for the overall implementation of plant operations as specified on Figure 2. He will keep the operations Manager informed of changes in the Units status,

< problems that occur or are corrected l that affect the units reliability l or availability and changes in scheduled i

operational events. During events l that require implementation of the l Emergency Implementing Procedures the Shift Supervisor shall report to the Emergency Director as specified

, on Figure 3.

Rev. 11 7

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

~ ' FNP-0-AP-16

! During accident situations the Shift Supervisor shall remain in the Control Room and direct the actions of the Control Room Operators. One of the two Shift Supervisors will be designated as the " Shift Supervisor in Charge" and will hold a Unit 1 and Unit 2 license.

This designation will be specified on the schedule specified in paragraph 4.1.

The Shift Supervisor in Charge will also be the interim Emergency Director who will function in the event of an emergency until the Plant Manager or other designated Emergency Director arrives on site. The Shift Supervisor in Charge will delegate the role of interim Emergency Director to the other Shift Supervisor if, in his .

judgment, the incipient or actual emergency principally involves the other unit. If the emergency affects both units, the shift Supervisor in Charge will normally not make such delegation.

i The Shift Supervisor shall remain in the Control Room unless relieved as specified in Section 4.2. His normal work station is inside the AT THE CONTROL AREAS as defined on Figure 4.

l l

3.1.8.1 Qualifications l

(1) High school education or equivalent.

(2) Four years responsible power plant experience of which a maximum of 2 years is academic or technical training.

At least 2 years experience shall be Nuclear Power Plant experience with 6 months at the Farley plant.

(3) Participation in the plant SRO training, program Uhich includes training in the areas of heat transfer, fluid flow, mitigating core damage and increased

, emphasis on plant transients.

l I

(4) Three months on shift training.

Rev. 11 8 .

FNP-0-AP-16 (5) One (1) year of experience as licensed operator. This experience may be obtained as follows:

(a) Military experience equivalent to a licensed Reactor Operator or Senior Operator, or (b) Experience as a licensed Reactor Operator or Senior Reactor Operator at another nuclear facility, or (c) One (1) year of experience as a licensed Reactor Operator at the Farley Plant, or (d) Possess a degree in engineering or science.

(6) USNRC Senior Reactor Operator's license.

3.1.8.2 Responsibilities l (1) In direct charge of unit operation during startup, power operation, and shutdown.

(2) Supervise the Shift Foreman Operating and Shift Foreman Inspecting to ensure proper performance of his assigned duties.

(3) Supervises the Unit. Operator and Operator-At-The-Controls to ensure proper performance of their assigned duties.

(4) Ensure shift operations are conducted in accordance with plant procedures and operating licenses.

(5) Approve the removal of equipment and systems from service for maintenance, testing or operational activities per Section 9.0 of this procedure.

Rev. 11 9

. - _ - - , . _ . , , ._..r_~ _-y-_,. ._y-._ _.y_, ___---.,,,y-._ . , _ - , , - , , _ - , , , , - . . - - - _ . _ . - _ _ , , _ _ . . _ - - _ - _ . _

FNP-0-AP-16

~

(6) Coordinate the activities of the operations, C&HP, Maintenance, I&C, and Security groups to accomplish the operating objectives for his shift.

(7) Notification of higher manage-ment authority as required by

" PLANT REPORTING REQUIREMENTS",

FNP-0-AP-49; and "OFFSITE NOTIFICATION", FNP-0-EIP-26.

(8) Determine the circumstances, analyze the cause, determine that operations can proceed safely and obtain approval from the Emergency Director before the reactor is returned to power after a trip or sub-stantial unscheduled or unexplained power excursion.

(9) Responsible for supervising the On-Shift Operations Groups functions required by the Emergency Plan, the Health Physics Manual, the Security Plan and their respective implementing procedures.

(10) Act as Emergency Director until relieved by higher management authority.

I 3.1.9 Shift Foreman There will normally be two Shift Foremen assigned to each shift per Unit. A Shift Foreman Operating and a Shift Foreman Inspecting.

3.1.9.1 Shift Foreman Operating 3.1.9.1.1 Qualifications (1) High school degree or equivalent.

(2) Four years responsible power plant experienc,e of which a maximum or 2 years is academic or technical training.

Rev. 11 10

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

FNP-0-AP-16

At least 2 years experience shall be Nuclear Power Plant experience with 6 months at the Farley plant.

(3) Participation in the plant SRO training program which includes training in the areas of heat transfer, fluid flow, mitigating core damage and increased emphasis on plant transients.

(4) Three months on shift training.

(5) One (1) year of experience as a licensed operator.

This experience may be obtained as follows:

(a) Military experience equivalent to a licensed Reactor Operator or Senior Operator, or (b) Experience as a licensed Reactor Operator or Senior Reactor Operator at another nuclear facility, or (c) One (1) year of l

experience as a j licensed Reactor Operator at the Farley Plant, or (d) Possess a degree in, engineering or science.

(6) USNRC Senior Reactor Operator's license.

l Rev. 7 11

FNP-0-AP-16 3.1.9.1.2 Responsiblities

(

(1) Supervise the Systems Operators and Systems Operator in Training in the performance of their duties.

(2) Supervise activities assigned by the Shift Supervisor in accordance with the operating licenses and plant procedures.

(3) Review shift records for compliance with section 6.0.

(4) Insure shift operating crews review changes to operating procedures, plant modifications, and revisions to the Technical Specifications in accordance with section 4.4.

(5) Ensure that on-shift training of personnel is conducted as scheduled.

(

(6) Ensure his shift is properly manned. Request or initiate call-out of personnel as required.

(7) Initiate reports of reactor trips and abnormal occurrences.

(8) Supervise implementation of radiological waste management program with respect to shift operations.

(9) Supervise implementation of the plant lubrication program with respect to shift operation.

3.1.9.2 Shift Foreman Inspecting 3.1.9.2.1 Qualifications (1) High school degree or equivalent.

I TCN 13A 12

FNP-0-AP-16

! (2) One year of Nuclear Power Plant experience of which at least two months must be at an operating plant and six months at Farley Nuclear Plant.

A B.S. degree in an engineering or scientific program may be substituted for up to 6 months of this power plant experience.

(3) Minimum training will be equivalent to the i 6 weeks system training course.

3.1.9.2.2 Responsibilities l (1) Authorize, with approval of Shift Supervisor as specified in 9.0 below, the removal of equipment and systems from service for maintenance, testing or operational activities.

i (2) Authorize, with the approval of the Shift Supervisor as specified in 9.0 below, the return to service of equipment and systems following maintenance, testing l or operational activities.

(3) Act as custodian of plant keys assigned to the Operations Group per section 4.17.

Rev. 11 13

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

FNP-0-AP-16 (4) If qualified, this position normally fulfills the responsibilities of the Shift Technical Advisor as specified in 3.1.10 3.1.10 Shift Technical Advisor 3.1.10.1 Qualifications (1) High school degree or equivalent.

(2) Degree in an engineering or scientific discipline or 60 semester hours of college level training in basic subjects in engineering and science.

(3) One year of Nuclear Power Plant experience, of which at least two months must be at an operating plant and six months at Farley Nuclear Plant. A B.S. degree in an engineering or scien-tific program may be substituted for up to 6 months of this power plant experience.

3.1.10.2 Responsibilities. l (1) During Emergency conditions the Shift Technical Advisor reports to the Shift Supervisor to serve in a technical advisory capacity and has no command and control function. Emergency conditions are defined as:

(a) Plant conditions exist that require operations to be governed by Emergency Operating Procedures.

Rev. 11 14

-,7. -.- --.-- ,-.--- .- , ,-,. . - - _ - , , . _ . _ - , , , _ _ - . - , _ - _ . . - - _ , - - - - - , . -

- FNP-0-AP-16 I (b) Plant conditions exist that is an Unusual Event, Alert, Site Emergency or General Emergency as defined in the Emergency Implementing Procedure.

(c) The Shift Supervisor feels conditions warrent.

(d) The Shift Technical Advisor feels condition warrant. I (2) The Shift Supervisor will -

- refer possible significant reactor coolant system abnormalities such as may be observed during steady state or transient operation to the Shift Technical Advisor for assessment of safety significance.

The Shift Technical

' Advisor will make an immediate " quick look" technical / engineering review to assess the safety significance and to provide such assessment to the Shift Supervisor.

The Shift Technical Advisor is not tasked to make recommendation concerning operational steps to be performed.

The Shift Technical Advisor will maintain a log of assessments made with a brief statement of the l

' condition assessed l and report made to the Shift Supervisor l including time, date l and Shift Technical Advisor signature.

l t Rev. 11 15

. FNP-0-AP-16

! (3) The Shift Technical Advisor must respond to the control room within 10 minutes. If the STA is not in tae control room at th"; time of event initiation, his presence must be requested

, and acknowledged by plant page.

3.1.11 Shift Support Supervisor  !

There will normally be one Shift Support Supervisor assigned to each shift and will report to the Shift Supervisors. He will provide supportive co-ordination between .

the Mechnical; Instrumentation and Control; Electrical; Health Physics; Building and Grounds; Document Control and Warehouse Group on shift at Farley Nuclear Plant to assist in ensuring the maximum efficiency of the plant.

3.1.11.1 Qualifications I (1) High school education or equivalent (2) Four years responsible power plant experience of which a maximum of 2 years is academic or l technical training. At least 2 years experience shall be Nuclear Power Plant experience with

' 6 months at the Farley Nuclear Plant.

3.1.11.2 Responsibilities (1) Assist in identifying and communicating work sequence i priorities between groups j to support job priorities I and to provide feedback g I to the Shift Supervisor.

l Rev. 11 l

16 l

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

FNP-0-AP-16

( (2) Assist in strengthening inter-departmental relation-ships, and essential communi-cations to ensure positive and effective response to Plant's critical needs.

(3) Anticipate potential problem areas by keeping abreast of major plant conditions and change of work trends.

(4) Assist in planning and co-ordinating activities, paying particular attention to continuity of critical path, or significant activities.

(5) Provide co-ordinating functions between concerned groups, monitoring work progress to ensure resources are appropriate, including proper level of expertise.

i (6) Monitor procedures and standards used for perfor-mance of work and make recommendations for improve-ment in the areas of productivity and quality, ensuring recommendations are submitted to manage-ment of the group involved.

(7) Monitor areas for house-l keeping and materials l control.

l 3.1.12 Unit Operator 3.1.12.1 Qualifications.

(1) High school education or equivalent.

(2) A total of two years of power plant experience of which a minimum of one year is nuclear power plant experience.

Rev. 11 i

17

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

. FNP-0-AP-16 I (3) USNRC Reactor Operator's license.

3.1.12.2 Responsibilities I (1) The Unit Operator (UO) is responsible to the Shift Supervisor for the operation of the unit. He is to coordinate the activities of the Operator-at-the-Controls (OATC), with other operating and plant personnel to achieve safe and efficient unit operation. Unit operation is interpreted to mean:

(a) Coordinate operation of plant equipment and systems during startup, shutdown and steady state conditions.

(b) Coordinate conduct of Surveillance Testing.

(c) Conducting tagging operations.

(d) Assisting the OATC in Control Board operations during periods of operation requiring more than one operator at the board.

l (2) Documentation of plant evolutions.

}

Taking of BOP log readings.

(3)

(4) Initiation of immediate operator actions and coordination /perfor-mance of subsequent operator actions required by plant Emergency Operating Procedures, Abnormal Operating Procedures and Annunciator Response Procedures.

i 3.1.12.3 While the Unit Operator is g responsible to the Shift Supervisor for unit operation, it is to be understood that he l has the authority to:

i Rev. 11 18

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FNP-0-AP-16 (1) Initiate power reduction if plant parameters indicate that a such action is required to prevent a unit trip or damage to equipment.

(2) Initiate a reactor trip if indications exceed automatic reactor trip settings and trip has not occurred.

(3) Initiate Engineered Safety Systems actuation if indications exceed automatic actuation setpoints and actuation has not occurred.

(4) Initiate holds during plant evolutions which are required to ensure that the evolution does not threaten the stability of the unit; result in damage to equipment; threaten personnel safety; or violate adminis-trative controls such as Unit Operating Procedures, Technical Specifications, etc.

3.1.12.4 The Unit Operators watch station is in the Control Room. However, he may be granted permission by the Shift Supervisor to leave the Control Room for operational matters, such as performance of STP's, clearance, verification, etc.

3.1.13 Operator-At-The-Controls (OATC) l 3.1.13.1 Qualifications.

(1) High school education or equivalent.

(2) A total of two years of power plant experience of which a minimum of one year is nuclear power plant experience.

(3) USNRC Reactor Operator's license.

Rev. 11 19

FNP-0-AP-16

3.1.13.2 Responsibilities Operator-At-The- l Controls (1) The Operator-At-The-Controls (OATC) is responsible to the Shift Supervisor for operation of all equipment controlled from the At the Controls Area (ATC) as defined by Figures 4. Operation is interpreted to mean:

(a) Actual controls manipulation.

(b) Monitoring equipment and systems parameters.

(c) Documentation of evolutions and significant events related to those systems and/or components controlled from the ATC.

(d) Initiating or performance of operator actions required by plant Emergency Operating Procedures, Abnormal Operating Procedures and Annunciator Response Procedures applicable to the ATC.

(2) Taking of Control Room log readings.

3.1.13.3 During periods when more than i one Plant Operator is required at the Control Board such as startups, shutdowns and similar major evolutions, the OATC will normally man the reactor controls section of the MCB.

3.1.13.4 While the OATC is responsible l to the Shift Supervisor for unit operation, it is to be understood

that he has the authority to

i (1) Initiate power reduction if I plant parameters indicate that such action is required to prevent a unit trip or damage to equipment.

Rev. 11 20

FNP-0-AP-16 I

(2) Initiate a reacter trip if indications exceed automatic reactor trip settings and trip has not occurred.

(3) Initiate Engineered Safety Systems actuation if indications exceed automatic actuation setpoints and actuation has not occurred.

(4) Initiate holds during plant evolutions which are required to ensure that the evolution does not threaten the stability of the unit; result in damage to equipment; or violate administrative controls such as Unit Operating Procedures, Technical Specifications, etc.

3.1.13.5 The Operator-At-The-Controls I shall not under any circum-stances leave the at the controls area for any reason without obtaining a gualified relief operator. Prior to assuming responsibility for being Operator-At-The-Controls, the relief operator shall be properly briefed on the plant status. As a minimum, the relief operator will be informed of any evolutions in progress which might effect plant operation, any special instructions which are in effect, and the overall status of the plant, I i.e., any off-normal or unusual i

system lineups. A single operator will not assume the Operator-At-The Controls responsibility for both units at die same time.

3.1.14 shift Engineering Aide I 1

3.1.14.1 Qualifications l The qualifications for Shift Engineering Aide shall be

, determined by APCo policy.

! Rev. 11 21

FNP-0-AP-16

~

3.1.14.2 Responsibilities The Shift Engineering Aide performs the following administrative duties under the direction of the Shift Supervisor.

(1) Performs scheduling functions for regular and overtime shifts.

(2) Performs timekeeping functions for payroll records.

(3) Keeps a current overtime list for determining overtime personnel selections.

(4) Initiates callouts of personnel for overtime I work.

(5) Schedules personnel for training events such as fire brigade training, radiation worker training and other training requirements which occur.

(6) Maintains Control Room, TSC, Shift Foreman and Shift Supervisors' copies of procedures, drawings and manuals current by incorporating revisions.

(7) Performs various administrative tasks as directed by the Shift Supervisor.

3.1.15 Operations Clerk i The Operations Clerk reports to the Operations Superintendent.

l 3.1.15.1 Qualifications l l

t The qualifications for Opera-tions Clerk shall be deter-L mined by APCo policy.

l Rev. 11 22 i

i l

FNP-0-AP-16

( 3.1.15.2 Responsibilities (1) Maintain operation files, records and controlled documents current.

(2) Perform typing functions for the Operations Group.

(3) Route shift records and logs to the appropriate reviewing authorities.

(4) Handle administrawive and clerical tasks as directed by the Operations Superintendent.

3.1.16 Systems Operator 3.1.16.1 Qualifications l (1) High school education or equivalent.

(2) A total of six months of power plant experience or applicable experience.

3.1.16.2 ResponsibilitIies l

(1) There will normally be nine Systems Operators on shift for two unit operation:

Unit 1 Turbine Building Operator -

Unit 2 Turbine Building Operator ,

Unit 1 A Man Unit 2 A Man Unit 1 B Man Unit 2 B Man Units 1 & 2 Rover.

I Diesel Building Operator i Outside Operator I (a) Turbine Building Operator - -

The Turbine Building operator is responsible to the Shift Foreman L

' Operating for the monitoring of equipment, performance of unit evolution and cleanliness of equipment in his assigned

- side of the Turbine Building including the Low Voltage Switchyard for his unit.

( Also the Unit Two Turbine Building Operator will be responsible for the Unit 2 circulating water pumps.

l TCN 13A 23 l

1

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- -,w- - - -y------v u-pe< T- - ------- -m--r a em s-- e

FNP-0-AP-16 (b) A Man - The A Man is

( responsible to the Shift Foreman Operating for the monitoring of equipment, performance of unit evolution, and cleanliness of equipment in his assigned side of the Radiation Controlled Area of the Auxiliary Building below the 121 foot elevation.

(c) B Man - The B Man is responsible to the Shift Foreman Operating for the monitoring of equipment, performance of unit evolution, and cleanliness of equipment in his assigned l

side of the Radiation Controlled Area of the Auxiliary Building on the 121 foot level and above.

(

(d) Rover - The Rover is responsible to the Shift Foreman Operating for the monitoring of equipment, performnace of unit evolution and cleanliness of equipment on the Non-Radiation Controlled Area of the Auxiliary l Building.

(e) Diesel Building Operator -

Diesel Building Operator will be responsible to the Unit 1 Shift Foreman

- Operating for the monitoring of equipment, performance of unit evolution and cleanliness of equipment l in the Diesel Building and Unit 1 circulating water pumps.

(f) Outside Operator. The l Outside Operator is  !'

responsible to the Unit

( 2 Shift Foreman Operating TCN 13A 24

FNP-0-AP-16 for the monitoring of

(. equipment, performance of unit evolution and cleanliness of equipment in the River Water and Service Water Structure, the Unit 1 & 2 Cooling Towers and the Fire Protection Building.

(2) Maintain satisfactory progress towards qualification as Plant Operator.

3.1.17 Systems Operator in Training 3.1.17.1 Qualifications (1) High school education or equivalent.

~

3.1.17.2 Responsibilities Maintain satisfactory progress ,

towards qualification as a  !

Systems Operator.  !

( 3.1.18 Switchboard Operator 3.1.18.1 Qualifications (1) High school education or equivalent.

I (2) A total of two years of power l

plant experience or applicable experience.

~

3.1.18.2 Responsibilities (1) Operation of the plant switch-yard functionally under the direction of the System Load Dispatcher and supervised by the Shift Supervisor.

l-I (

TCN 13A 25

, FNP-0-AP-16 (2) Coordinate with Unit Operator as necessary.

3.1.19 Utility Foreman The Utility Foreman is responsible to the Buildings and Grounds Supervisor for the conduct of housekeeping, grounds maintenance and general labor activities.

3.1.19.1 Responsibilities I (1) Scheduling of Nuclear Operatives to meet plant requirements.

(2) Preparation of procedures and schedules to support housekeeping, -

grounds maintenance and general labor activities.

(3) Supervision of activities as specified above.

! 3.1.20 Nuclear Operative 3.1.20.1 Responsible to the Utility Foreman for housekeeping within Plant structures, maintenance of plant grounds and general labor activities as essigned.

i 3.2 Operations Shift Complement, Functions and Responsibilities 3.2.1 Refer to the following table for minimum manning levels for various l modes.

l Rev. 11 26 l

l

FNF-0-AP-16 I MINIMUM SHIFT CREW COMPOSITION FARLEY UNIT 2 e WITH UNIT 1 IN MODE 5 OR 6 DE-FUELED POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3&4 MODES 5 & 6 Shift Supervisor l a/c ya /c Shift d Foreman 1 none Plant Operator 2 1 System b I Daerator 2 2 Saift Technical Advisor 1 none WITH UNIT 1 IN MODES 1, 2, 3 OR 4 POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION MODES 1, 2, 3&4 MODES 5 & 6 Shift Supervisor l a/c ya /c Shift Foreman 1 a/d none Plant 3 Operator 2 1 l System b I

Daerator 2 1 Salft rechnical 8 Advisor 1 none a) Individual may fill the same position on Unit 1.

b) One of the two required individuals may fill the same position on Unit 1.

c) A Shift Supervisor will be assigned to each unit who

! is licensed on that unit.

i d) This position at a minimum will be licensed on Unit 1.

As a part of his responsibilities he will perform l

routine inplant equipment inspections and walkdowns in Unit 2 and report the results to the Unit 2 Shift Supervisor.

Rev. 11 l

l l

27 l - - . - . - , -. . -_. . - _ -

FNP-0-AP-16 e) The Shift Crew composition may be one less than the minimum requirements for a period of time not to .

exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the Shift Crew Composition to within the minimum requirements. This provision does not permit any shift crew position to be unmanned upon shift change due to an oncoming shift crewman being late or absent.

3.2.2 For each unit, at least one licensed operator will be in the at-the-controls area of the control room when fuel is in the reactor. An additional licensed person will be present in the control room when one or both units is operating in Mode 1 or 2. All core alterations after the initial fuel loading will be directly supervised by a licensed Senior Reactor Operator who has no other concurrent responsibilities during the operation.

3.2.3 Deviations in shift complement may be l made so long as the minimum manning and i license requirements of Technical Specifi-cations are met and a Shift Technical Advisor is on-site.

3.2.4 Additional Operations Group personnel may be required on shift because'of unusual plant conditions or operational l

needs. The Shift Foreman Operating shall obtain the additional personnel as necessary.

Activities requiring additional personnel l will not be undertaken until the shift is properly manned.

' 3.2.5 The on-shift complement will be shown by name on the Shift Organization Chart located at the entrance to the ATC. .

3.2.6 Duties of plant personnel not in the licensed chain of command, are defined in other plant procedures. These personnel shall perform these duties so as not to interfer with the performance of duties f

assigned in this section.

Rev. 10 28

\

I e + -.-_,,m

FNP-0-AP-16 1

3.2.7 Personnel assigned to shift operations perform or are prepared to perform three general functions:

(1) Protecting plant personnel, the health and safety of the public, and plant equipment during and following an emergency situation.

(2) Maintaining the plant in a safe condition during abnormal conditions.

(3) Continuous normal operation of the plant and its associated equipment.

3.2.8 Plant operations are conducted in accor-dance with the shift Supervisor's instruc-tions. All operating instructions are to be consistent with provisions of plant procedures.

3.2.9 The following responsibilities are delineated for Operations Group personnel:

(1) All Senior Reactor Operators, Operating Supervisors and Plant Operators on shift must be aware of and responsible for the plant status at all times.

This includes supervisors being responsible for the performance of all personnel assigned to their shift who could affect plant safety, regardless of specialty affiliation. Knowledge of the plant's status must be assured during shift changes by a formal watch turnover and relief.

(2) All Senior Reactor Operators, Operating Supervisors and Plant Operators must be alert within their immediate areas of responsibility until properly relieved, and be particularly attentive to the l Instrumentation and controls

located within these areas at all times. They are responsible for taking timely and proper actions that will not create or cause a hazard to safe operation of the facility (i.e.,

actions or activities, including Rev. 10 29

- - - - - ~ , - . - - _ . _ _ - . _ - . . - ~ , - . - - - ~ _ _ _ _ . .,~ ,, -. ,.,,. , , , . , - - _.,--..,---....,-------,---._..--,---~,,7-

~

FNP-0-AP-16 '-

( failure to take action, related to the facility that could have an adverse effect on the health r

and safety of the public, plant workers, or the individuals)." -

They are responsible for' shutting the reactor down when they determine that the safety of the reactor is in jeopardy or when operating parameters exceed any of the reactor protection system set-points.

(3) Only licensed operators are permitted ,

to manipulate the controls that directly affect the reactivity or power level of a reactor except-for training purposes as specified by 10 CFR 55. [10 CFR 50.54 (L)].

(4) Licensed operators are required to be present at the controls at all times during the operation of the facility (10 CFR 50.54(k)].

(5) Operation of mechanisms and apparatus other than controls that may indirectly affect the pcwer level or reactivity of a reactor shall only be accomplished with the knowledge and consent of an operator licensed in accordance with Part 55 (10 CFR 50.54(j)].

(6) The NRC-licensed individual shall observe all applicable rules, regualtions and orders of the Commission, whether or not-stated in the license [10 CFR 55.31(d)].

(7) The operating test, to the extent applicable to the facility, requires i

the applicant to demonstrate an l

understanding of:

i .

The necessity for a careful approach to the responsibility associated with the safe operation of the j

facility [10 CFR 55.23(1)].

' Rev. 7 l

30

' )) .

~

7 -- .. . . . . . . -

) /

, FNP-0-AP-16 '

is s

t ) ,

_I r i' (6) In order for'the operator at the

_;1 ', j

' controls or a nuclear power plant f , '- t . to be able to carry out these

/, , /

,/

< and ot:her responsibilitias in

,- - a timely fashion, he must give t' ,

his*sttention to the condition

' \' ,

of the plant at all times. He ~

< > f, must be alert to ensure that'the o plant is operating sa?ely and

, ,/, must be ' capable of taking action to prevent any progrest toward

/' 'L. c I [; ,

/ <

< a, condition that might be unhafe.

'/

\ ,

< /! (Regulatory'cuide 1.114.B).

,i ~j? .l

[ (9) All Operations Group, Personnel are

. ^ e .

responsible to believe and respond i

^

~,

conservatively to instrument indications .

r . r until they are proven to'be, incorrect.

i

/ .-!

}

(10) All Operations Group personnel are

,,li

!' responsible for assuring that the

', / '

. facility is operated safely and within

,the requirements of the licehse, technical specifications,, rules,

'tM ' ' regulations, and orders of the

' NRC, and for the' actions of their on-duty employees while on site.

I , >

f j t e ,

t >

[

l

! f 1,

l l

l l

l l Rev. 7 f

31

1..

' FNP-0-AP-16 3.2.10 The normal shift complement is as follows:

{' .

Unit 1 Shared Unit 2 ..

1 1 Shift Supervisor 3hift Foreman OperatingI "I 1 1 Shift Foreman Inspecting IDI 1 1 i

1 1 Shift Technical Advisor (c)

Shift Support Supervisor 1 1 1 Unit Operator 1 1 Operator-At-The-Control Systems operator: l 1 1 A Man 1 1 B Man Turbine Building 1 1

1 Rover l( 1 Diesel Building Operator 1

Outside Operator 1 l Switchboard Operator l

(a) The Shift Foreman Operating may l

be the same individual for both units.

(b) The Shift Foreman Inspecting may l be the same individuals for both I

units and if qualified may be the shift Technical Advisor.

(c) The Shift Technical Advisor may be the same individual for both i units and may also be the Shift Foreman Inspecting.

TCN 13A

(

32 i

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~

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. =. ---..w==a:=.: .=

FNP-0-AP-16 I 3.3 Notification of Absences Personnel expecting to be late or unable to report for shift duty at the scheduled time shall at the earliest possible moment inform the Shift Supervisor of the situation. The Shift Supervisor shall make necessary arrangemeats for obtaining a replacement in accordance wich provisions of Section 3.2 and 4.1.

3.4 Personnel Recall (1) Maintenance Personnel If maintenance 1ersonnel must be called out for work, the Shift Foreman Operating will contact designated maintenance supervisory personnel and initiate the call out. The designated maintenance supervisory personnel will call out maintenance personnel and maintenance supervision as required.

(2) Chemistry and Health Physics Personnel The Shift Foreman Operating will have the on duty C&HP Foreman or Lead Technician initiate callout of C&HP as required.

(3) Security Personnel The Senior Plant Guard will normally call out security personnel as required.

He will ensure that the Shift Supervisor is kept informed of such matters.

(4) Instrumentation and Controls Personnel

..If I&C personnel must be called out for work, the Shift Foreman operating will contact designated I&C supervisory per-sonnel and initiate the call out. The

' designated I&C supervisory personnel will call out I&C personnel and super-vision as required.

4.0 Shift Operations 4.1 Shift Schedule and Overtime.

Shift schedules will be completed to ensure that the requirements of paragraph 3.2 are met.

Rev. 12 33 .

r, -y - , - - ,,.___,,,.-,_,,---y%,, ,,,, 'm-,,,_.-,,--.,.,n,_r-.-, ,,_,_~__,.y. ,,_ - ,, ._-.y--.. .. , - , , , , . - - - - - , . . . , . _ - . - ,

FNP-0-AP-16 Overtime of Operations Personnel is governed

{ by FNP-0-AP-64.

4.2 Shift Relief shift operating personnel, when on duty, are to remain on duty, with full responsibility for their position, until properly relieved. shift relief is to be a formal turnover with documen-tation. A Shift Supervisor, Shift Foreman, Plant Operator, Systems Operator, or Switchboard Operator is considered to be properly relieved when the individual assigned to relieve him has been informed of the status of the plant, operations in progress, and special instructions, if any are applicable. It is the responsibility of the relieving individual to adequately inform himself of these items by reviewing logs and data sheets, dis-cussing operations with on-duty personnel, and reading special instructions, if any are applicable, and walking down the area of responbility with the off-going individual. Detailed instructions for shift relief are included in Appendix B.

4.3 Notification Notification shall be made as specified in

" PLANT REPORTING REQUIREMENTS", 5'NP-0-AP-49; and "OFFSITE NOTIFICATION", FNP-0-EIP-26.

l 4.4 Change Notices I

It is important that operating personnel be in-formed of plant modifications, procedure revisions, and license changes that have operational or safety significance. Such notification will normally be made by one of three methods:

l 1. On-shift formal instruction by Plant Instructors or supervisory personnel.

2. Issuance of Training Change Notice.

3. Covered as a part of regular scheduled license retraining.

l TCN 13A

(

l 34 l

FNP-0-AP-16 The urgency of the notification and the possible impact of the operational or safety significance involved with the notification will dictate which of the above methods is utilized. The Operations Supervisor is responsible for deter-mining the method of notification to be made on a case-by-case basis. When a Training Change Notice is utilized, the Shift Foremen will insure that all shift personnel designated to review the notice are so informed and they sign the notice form indicating they have reviewed the notice. The Training Change Notice will then be forwarded to the Training Superintendent who will be responsible for routing it to all additional licensed personnel as applicable.

4.5 When a Reactor Trip occurs, the Shift Supervisor will take the following actions:

1. Ensure that the plant is placed in a safe condition by directing that necessary operations be performed in accordance with approved procedures.

2. Notify Emergency Director.

3. Make required notifications per FNP-0-EIP-26, "OFFSITE NOTIFIC* TION".

, 4. Direct a review of events prior to the transient causing the trip, during the transient and subsequent to the trip, to determine the cause of the trip and to verify the proper operation and response of the reactor and associated equipment systems.

The Reactor Trip Report (Figure 6) will be completed to document this review.

This review of events will include:

a) the computer alarm typewriter print out b) the sequence of event report c) the post mortem report d) applicable main control board recorder e) interview of onduty plant operators Rev. 12 35

FNP-0-AP-16 f) plant operator log g) listing of any outstanding Limiting Conditions of Operation h) listing of major /significant maintenance in progress This review shall be conducted to insure that the cause of the trip is identified and that all equipment / systems that should have operated did so in their intended manner. This review should be conducted with an open and inquisitive mind, and all facts shall be verified.

5. When the Reactor Trip Report and Incident Report (FNP-O-AP-30) are completed, the on call Emergency Director must give permission prior to returning the reactor to criticality. The plan for return to power operation will include:

a) any corrective action required to correct the cause of the trip or any malfunction during the trip b) any maintenance to be accomplished c) any surveillance to be performed

6. Ensure the Reactor Trip Form (Figure 6) is completed with the computer post mortem printout, the applicable section of the alarm typewriter printout, t the sequence of events and Incident Report attached. Forward this package to the

. Operations Supervisor for review. The operations Supervisor will review the package and forward it to the System Performance Group. The System Performance Group will review the package per FNP-0-AF-63 and send it to Document Control for retention within 30 days of the trip.

l 1

4.6 Manipulation of Reactor Controls (1) The reactor controls will be manipulated only by licensed personnel except for l

individuals who manipulate the controls of the reactor as a part of training to  :

l qualify for an operator's license and such manipulation is under the direction of and in the presence of a licensed reactor operator or senior reactor operator. For purposes of this section, l

Rev. 12 36

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

4 FNP-0-AP-16

~._

reactor controls mean apparatus and mechanisms the manipulation of which directly effect the reactivity or power level of the reactor. (10 CFR 55)

(2) Automatic control of the reactor is always the preferred mode but the Plant Operator must be prepared to take manual control at any time as circumstances may dictate. The Shift Supervisor will be informed anytime the reactor control system is placed in manual control when it would normally be in automatic control.

4.7 Generator Load Changes Generator load changes will normally be directed -

by the System Load Dispatcher. When directed to change load and if plant operating conditiors and operational orders permit, the Unit Operator will comply with the Dispatcher's request if approved by the Shift Supervisor. The Load Dispatcher will be notified by the Unit Operator when the requested load change is completed.

The Unit Operator will inform the Shift Supervisor when all load changes are complete.

s 4.8 Operation and Maintenance of Plant Equipment During Peak Load Periods It is essential from a system operation stand-

! point that generating units remain "on the line" I carrying load as necessary at all times with their operation being especially vital during peak loads. Maintenance and operating activi-ties in which there is a likelihood of inter-rupting unit operation should be performed during off-peak hours.

4.9 Instrumentation and Control 1

Personnel shall not adjust or operate any set points, etc., inside the control panels unless i

such action is specifically called for in an l approved procedure.

l l 4.10 Operation During Abnormal or Emergency Conditions Always believe the instruments until the indica-tions are proven to be false. When operations j are not as expected, return to known safe condi-tions. Reduce power level as required until the cause of the condition has been determined and Rev. 11 37

FNP-0-AP-16 the status ofInitiate the corea ismanual known to be in a safe condition. reactor trip or '

Safety Injection if the actuation parameters for '

reactor trip or Safety Injection exceed their actuation setpoint and automatic actuation does not occur.

4.11 Switching Instructions - Switchyard All switching operations in the 230/500 KV switchyard shall be in accordance with the Farley Substation Operating Procedure and the APCo Electric System Operating Procedure.

4.12 Control Room References To assist shift operating personnel in the conduct of their duties, reference information related to plant operation, safety, and adminis-tration is permitted in the control room.

However, for the actual conduct of operations only controlled, approved documents are to be used. The Operations Supervisor is responsible for ensuring that the controlled reference information is maintained current.

To meet these needs, the controlled reference information listed below will be available in the control room.

(1) Plant Operating Procedures l

) (2) Final Safety Analysis Report (3) Technical Specifications (4) Selected Tech Manuals (5) Selected D&U prints f

(6) Emergency Plan l

4.13 Housekeeping The control room will be maintained in a clean and orderly condition in the interest of safe and efficient operations. The responsibility for keeping the control room in this condition

is that of the shift operating personnel. All l

dusting and cleaning of control consoles, instrument panels, and computer consoles, and the orderly storage of books, drawings, and records will be It is performed by shift operating personnel. Rev. 7 l

l 38

FNP-0-AP-16 sometimes advisable not to clean or dust in some areas of the control room during plant power operations because of the risk of bumping or otherwise moving critical controls. Operations Group housekeeping requirements are delineated in FNP-0-AP-35.

4.14 Security and Fire Protection Operations personnel as part of their normal operating duties will have certain responsibi-11 ties in the areas of plant security and fire protection. These responsibilities are deli-neated in and will be conducted in accordance with FNP-0-SP-4, FNP-0-SP-21, FNP-0-SP-24, FNP-0-AP-39, FNP-0-EIP-13, and FNP-0-AP-37.

4.15 Bypass of Safety Functions and Jumper Control All activities involving the bypass of safety functions and jumper control will be conducted in accordance with FNP-0-AP-13.

4.16 Safety Clearance and Tagging All safety clearance and tagging activities will

. be conducted in accordance with FNP-0-AP-14. For any tagging operations order which affects equipment and systems under the control of the Shift Supervisor, the Tagging Official will obtain the permission of the Shift Supervisor prior to authorizing the clearance order.

Similarly, the release of clearance and restoration of such equipment to service requires the Shift Supervisor's permission immediately upon releasing a safety related system, subsystem, train, component or device. The Tagging Official

! shall notify the Unit Operator. These measures aid the Shift Supervisor in retaining effective control over the operatina status of equipment and system under his cognizance. At least quarterly the operations Supervisor will direct an audit of the safety tagging system to be performed.

A written report of the audit, including any discrepancies and their resolution, will be made to the Operations Superintendent.

- 4.17 Key Control

- Key lock position limiting and interlock devices will be employed in various areas of the plant to control the position of particularly critical components. The supervisory keys for these Rev. 7 39

,_ - - - , ~ . - - , - - - - - - - - - - - - - - , - ,-----,---.n, ---,--gw .m, , -

FNP-0-AP-16 locking devices shall be kept in the key cabinet in the control room along with a listing of locations where a lock is in service and the current position of the valve or component. The Shift Foreman Inspecting will authorize the use of keys and maintain responsibility. The Shift Foreman Inspecting will issue keys to authorized personnel and insure that records of use and position of valves or components are maintained current. Transfer of responsibility for these keys will be at shift relief.

Access to plant areas will be controlled to prevent entry by unauthorized personnel.

Access to keys for entry into such areas will be authorized and the keys will be issued by the Shift Foremen Inspecting. .

Access to vital areas will be authorized by the Shift Supervisor and the keys issued as specified in FNP~0-SP-9.

4.18 Area Access Control l Operations Group responsibilities concerning area access control are delineated in FNP-0-SP-1 i and FNP-0-AP-42.

1..

4.19 Control Room Access-Routine Operation The Control Room is an area used as the central control point for a highly complex facility.

l The image reflected in its appearance should, therefore, be one of professionalism. For this reason, the following rules will be implemented:

1. Potentially distracting activities in the control room and other watch stations must be prohibited (for example:

l radios, TV, alcohol use or drug abuse, l

games, horseplay, hobbies, and reading that is not directly job related).

l

2. Control room access must be limited to those persons on official business only and loitering in this area must be prohibited.

3. All necessary plant-related technical /

administrative control room business must be conducted at a location and in such a manner that neither licensed control room operator attentiveness -

nor the professional atmosphere will be compromised.

Rev. 11 40 l

FNP-0-AP-16 s 4. No posting of signs, notes, pictures, etc. except for official company business.

5. The At the Controls Area will be blocked off for restricted access and casual access for non-work related reasons will be prohibited.

6. Permission to enter the At the Controls Area for personnel other than the shift complement and the license chain of command must be obtained from the Unit Operator or the Operator-At-The-Controls.

During, periods of abnormal or emergency operations, permission shall be obtained from the Shift Supervisor.

7. The Shift Supervisor has the authority to restrict access to the Control Room during routine and emergency operation to those personnel necessary for evolutions in progress. EIP-0 further describes this authority during emergency conditions.

8. The Control Room doors will be locked or guarded at all times.

4.20 Equipment Status Control and Maintenance Authorization.

4.20.1 Equipment status control and maintenance authorization will be performed as specified in FNP-0-AP-52.

4.20.2 Upon remo' val and return to service of equipment important to safety, a verification of the lineup will be conducted.

1) " Equipment important to safety" is any piece of equipment that could render a system, subsystem, train, component or device of a system listed in Table 1 inoperable, so that it could not perform its intended safety function.

2) " Removal and return to service" includes the removal and return to service of equipment for any reason: e.g. Work Requests, Work Authorizations, STPs (any group), UOPs, etc.

Rev. 11 41

FNP-0-AP-16

' 3) " Verification" is a confirmation that the lineup is as it should be. In many cases, the removal and return from service of equipment is verified from the control room using alarms, meter reading

' changes, status light changes and/or various light indication changes. If these indications are not adequate to confirm the proper lineup the Shift Supervisor will direct a second properly qualified individual to verify the resultant lineup. If the indicators in the control room are not adequate to verify the lineup the resultant verification .

will be documented on the Work l Request, Work Authorization, or a

controlling procedure.

4) If the system listed in Table 1 is not required by Technical Specification for the current plant Mode no verification is required. The lineup must be verified prior to entering its applicable Mode.

5) Lineup includes valves, breakers, switches, links, gags, etc. on l the removed or returned to service piece of equipment.

4.20.3 Responsibility

1) The Plant Operator is required to log the removal and return to service of equipment important l

to safety.

The Shift Supervisor should verify proper implementation during his review of the Plant Operators log.

Rev. 11 42 l

FNP-0-AP-16 10 l 5.0 Plant Operating Procedures f

f Plant operating procedures are controlled documents

which govern the operation of the plant. Plant proce-

?

dures shall be adhered to in the conduct of all plant

operations except as the Plant Operator or licensed supervisory personnel determine that due to extenuating

circumstances, adherence to the procedure will create 1 an undue hazard to personnel, equipment or the health and safety of the general public.

This allowable deviation from procedures includes allowable deviation from license requirements or Technical Specifications if in the opinion of the Emergency Director, if available, or the Shift Supervisor, such action is required immediately to protect the

' health and safety of the public with insufficient time

!. to obtain prior NRC approval. Under such circumstances, 1* NRC notification and other appropriate emergency notifications must be made as soon as possible and prior to taking such action if possible.

5.1 Procedure Implementation Procedures that control extensive operations where reliance on memory cannot be trusted and

( where operations must be performed in a specified l, sequence shall be followed step by step with the j procedure present. Examples of such procedures are Unit Operating Procedures, Emergency Operating Procedures, Abnormal Operating Procedures, Surveillance Test Procedures, and other Operations Group procedures which qualify as stated above.

Routine procedural actions that are frequently performed will not necessitate the presence of the procedure. If there is any doubt as to the procedural action by the individual performing the job, the procedure must be present. Immediate operator actions of emergency procedures shall be committed to memory.

Controlled copies of operating procedures and appropriate temporary procedures shall be avail-able to all Operations Group personnel for inplant use.

4 5.2 Procedure Sign-Off Procedure sign-offs are used as an aid in confirming the completion of steps in proper sequence as required. In addition, they provide formal documentation of the completion of critical

( steps in the procedure and thus aid in any subsequent determination of equipment or system TCN 13A 43

FNP-0-AP-16 Sign-offs associated with superseded copies I of UOP-1.2 are forwarded to the Technical Supervisor ,

for review and subsequent transmittal to Document Control. Others are forwarded by the Operations Supervisor to Document Control.

5.3 System Check Lists System check lists are used for establishing and

confirming the status of epipment and systema.

System check lists are performed as a prerequisite requirement for the associated system operation and periodically for equipment status verification.

The instructions of Appendix C will be followed in conducting such check lists. In addition, the Shift Supervisor may direct the performance of check lists as he deems prudent.

Appendix C of this procedure is intended for use following refueling outages or after major maintenance is performed on or in the vicinity of a system. Equipment status control for maintenance will be performed as specified in par. 4.20 of this procedure and FNP-0-AP-52.

5.4 Periodic Review of Operating Procedures The following procedure categories are defined as operating procedures:

(1) Unit Operating Procedures j (2) System Operating Procedures (3) Annunciator Response Procedures (4) Emergency Operating Procedures (5) Fuel Handling Procedures l (6) Safety Related Surveillance Test Procedures

! (Operations Group)

(7) Abnormal Operating Procedures After initial review and approval, safety related operating procedures will be reviewed periodically in accordance with FNP-0-AP-1. The Operations l

l Supervisor is responsible for conducting periodic i

review of operating procedures. When the review l

is completed for a period, it will be documented per FNP-0-AP-1 and such documentation will be reviewed by the Operations Superintendent and forwarded to the Tn.chnical Group for filing.

Rev. 11 44

- -- ._. . , -. _ ..____. -_ ___ _ , _ _ _ _ . _ _ _ _ _ . . _ . _ . - - ~ _ _ . . _ , _ - - _ _ - - _

FNP-0-AP-16 Applicable procedures will be reviewed following an unusual incident, such as an accident, an unexpected, transient, significant operator error or major equipment malfunction where inadeguate procedural controls contributed to the incident.

Applicable procedures will be reviewed following modification to a plant system. When procedures are determined to be inadequate through review or during use, the procedure will be revised in accordance with FNP-0-AP-1, as applicable.

5.5 Temporary Procedure Revisions Temporary revisions to operating procedures may be issued: to direct operations during testing and maintenance; to provide guidance in unusual situations not within the scope of the operating procedures; and to ensure orderly and uniform operations for short periods when the unit, system, or component of a system is performing in a manner not covered by existing procedures or has been modified in such a manner that i portions of existing procedures do not apply.

t l Temporary revisions to operating procedures shall be subject to review and approval as l

specified in FNP-0-AP-1. The Operations Superintendent will have permanent revisions developed to incorporate temporary revisions if necessary and will ensure that all temporary revisions are removed from the affected procedures as specified in FNP-0-AP-1 upon their expiration.

6.0 Shift Records Shift records are comprised of the logs, data sheets, check lists, sign-off lists, recorder charts, and computer printouts that describe or record operating information and actions. Shift records are important for analysis of safety and efficiency of operation and l

for the documentation of equipment and system status.

The following practices are applicable to shift records:

except in emergency or abnormal plant conditions where l circumstances might dictate suspension of log taking, review, etc. i (1) All shift records must be legible, accurate, complete and understandable. They will be re-corded in ink, preferably black, to facilitate microfilming.

Rev. 9 l

45 i

y....-. . . . . . - . . . . . . .- --. . . - . ..N........-..-..-. . . . . .. - . -

FNP-0-AP-16 I Errors in shift records are corrected by drawing a single line through the incorrect information and writing the correct information adjacent or in space available with reference to the deleted information. The individual making the correction

will initial and date the deleted information.

(2) The individuals responsible for maintaining logs

! and data sheets are responsible for signing and dating the portions of the records that cover i their shift assignments.

l (3) Each recorder chart in operation should be checked at least once per day to verify that the marking -

is clearly visible and the timing is correct.

At a minimum, the recorder charts shall be suffic ently marked such that any data can be readily correlated -

to a time and date. The individual making this check will mark the chart noting the time and date.

(4) Each recorder chart will be marked with the date, time, and recorder identification number before the chart is placed on the recorder.

Strip charts will be marked with the same infor-mation when the chart is removed. Pen and range selection will be marked as necessary to facilitate interpretation of the chart.

(5) When significant events or unusual trends in parameters occur, the resulting recorder traces should be identified, if possible, as to the time and event to assist in operations analysis.

(6) Each Shift Foreman Operating will periodically review the logs taken by Shift personnel outside the control room during his shifts to detect unusual or abnormal trends or readings that require investigation or remedial action and to check on the completeness and accuracy of the records. The Shift Foreman Operating signifies completion of this review by initialing the data sheet or log record. While it is preferable that this review be conducted once on each shift, it is recognized that shift activities may preclude this from taking place. However, this technical review must be performed at least once a day. The shift Supervisor will perform a similiar review of logs maintained by control room personnel.

(7) At the end of each day completed log sheets, data sheets, and recorder charts, will be assem-bled and checked for completeness by the Shift Foreman Inspecting on duty. He will signify Rev.12 46

FNP-0-AP-16 completion of his review by initialing the log sheets. Shift records will then be forwarded to the Operations Supervisor. shift logs will be kept for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and then forwarded to the Operations supervisor. If a technical review has not been completed, he will give the log to the Shift Foreman-Operating or Shift Supervisor in order for him to complete the review of (6) i above.

(8) The Operations Supervisor is responsible for having shift records reviewed. He advises the respective Shift Foreman of any deficiecies in compiling the information and initiates measures to eliminate the deficiencies.

(9) The Operations Supervisor will ensure that shift records are forwarded for review and disposition in accordance with FNP-0-AP-4 and FNP-0-AP-32.

6.1 Plant Operators Log By the end of each shift, the Unit Operator shall have included in this log the sequence of events or functions performed during the shift.

The log will be kept in the main control room and will be maintained as follows:

l (1) At the time of relief, the Unit Operator going off duty will end the log by signing his name below the last entry.

l (2) After shift relief, the Unit Operator on duty will start the log for the shift by placing the date and shift hours.

(3) Unit status at the start of the shift, major evolutions in progress, or orders

. received which will change unit status will be recorded.

(4) The time that each event or function occurs will be placed on the left hand side of the log page next to the entry.

l (5) Removal and return to service of safety related equipment.

(6) Entries in the log will include, but are not limited to, the following:

Rev.ll 47

,---~c-- -

,,,-v-,_,,,,..,-,-,,,.,,,,,--,_.,,w,,-,,,.e,,--,.m,-,,--e.--

FNP-0-AP-16 (a) Times of reactor startup and shutdown.

(b) Times of starting and completing power changes and power levels.

(c) Times for starting and stopping major equipment.

(d) Times for removing from and returning to service of equipment in systems of Table 1 as well as other significant plant equipment or syctems.

(e) Pertinent entries as the operators may deem necessary to provide adequate information to the following shifts and management or that could -

be of significant historical value.

(7) When a log book is used up it will be replaced with a new book. The completed book will remain in the control room for a period of approximately six weeks for reference and then forwarded to the Operations Supervisor.

6.2 Night Orders Book The Operations Superintendent, Operations Supervisor, Sector Supervisor for each unit, Operations Manager and Emergency Director will from time to time issue night orders and the Shift Supervisor will be responsible for implementing these I

orders. Night orders are written in a bound record booi . The Night Orders Book will normally be kept in the Shift Foreman's Office. The individual issuing the night orders will record the date on the left side of the page and his signature below the entry.

6.3 Containment Entry Record

All containment entries will be recorded in the l Containment Entry Record per FNP-0-AP-42. The name of the individual, time of containment entry and time of exit from containment will be recorded. This record will be maintained by security.

l l

l l

l Rev.11 48 i

FNP-0-AP-16 g 6.4 Limiting Conditions for Operation The Shift Foreman Operating will initiate an LCO Status Sheet Figure 7 for any LCO which becomes effective during his shift. This will be accomplished by filling out Section I of the LCO Status Sheet with the following information.

(1) Date and time LCO became effective.

(2) Condition initiating LCO.

(3) Reference to applicable section of Technical Specifications for the particular LCO.

(4) Required time for completion of restoration (maximum time allowed by Technical -

Specifications to continue operations in present mode with LCO in effect).

(5) Required action if time exceeded (Action required by Technical Specifications if restoration is not made by time specified in "4" above).

(6) Testing or other actions required by Technical Specifications while LCO in effect (Any limitations on plant opera-tion or special surveillance testing).

(7) Shift Foreman Operating's signature.

Section I of the status sheet will then be reviewed and signed by the Shift Supervisor and filed in the LCO Status Binder. A copy will be forwarded to the designated individual on the Technical Group Staff for reporting purposes at the time the LCO is initiated. Subsequently, for as long as the LCO is in effect, the Shift Foreman Operating will insure that the required time for completion of restoration will not be exceeded during his shift.

The Shift Foreman Operating will initial Section II indicating that any testing or actions (specified in Section I) required by Technical Specifications have been completed as applicable to his shift.

When the LCO is no longer in effect, the Shift Foreman Operating will complete section III of the status sheet and forward Rev.11 l

49 l

FNP-0-AP-16

• ( it to the Shift Supervisor for review. The Shift Supervisor will forward the status sheet to the Operations Supervisor. If cummulative inoperative restrictions 3

apply to the LCO, the Shift Foreman Operating

will have a copy made for the control room files prior to forwarding the status sheet to the Operations Supervisor.

6.5 Log Sheets I

Shift log sheets are utilized by operating personnel to provide a method for recording system and equipment operating data and character-istics during routine performance of their j assigned duties.

6.6 Operations Memorandum Operations memorandum will be used as a vehicle for disseminating information or instructions relative to the conduct of operations of an intermediate to long term nature. Operations memorandums will be issued by the Operations Superintendent, or the Operations Supervisor.

These memorandums will be serialized for a

( period of one year (i.e. 79-01, 79-02, etc.).

Acknowledgement of receipt and understanding

- will be accomplished via a signature sheet for each memorandum.

7.0 Inspection of Operating Activities Inspection of operating activities which are done as an integral part of plant operating evolutions in accordance with approved procedures by, Operations Group personnel are considered to be intrinsic operating functions and as such are the responsibility of the Operations Supervisor.

Operations Group personnel shall be qualified to perform inspections of operating activities for the job position (s) for which they are qualified; Senior Reactor Operator, Reactor Operator, Systems Operator, Shift Technical Advisor. Any Operations Group personnel who are not qualified in one of the above categories will be certified in accordance with FNP-0-AP-31.

Inspection activities performed by Operations personnel which are not an integral part of plant operating evolutions in accordance with approved operations procedures shall be accomplished in accordance I with FNP-0-AP-31.

TCN 13A 50

E FNP-0-AP-16 Surveillance Tests 8.0 t

The Systems Performance Supervisor is responsible for overall control and coordination of the plant surveillance testing program to ensure compliance with the admin-istrative controls of FNP-0-AP-5.

8.1 Operations Surveillance Tests The Operations Group is responsible for the performance, documentation and initial review of operations surveillance tests in accordance with FNP-0-AP-5.

The shift Supervisor's approval will be obtained prior to the commencement of any surveillance testing. The performer of the test will record -

the information required by the test procedure in the appropriate space and initial each step as it is completed. The performer will affix his signature and date on the procedure upon completion of the test. All items will be written in ink. If a step is not completed for any reason, the reason must be recorded on the procedure. All statements will be factual and -

readings will be as accurate as possible. When a test is performed and does not meet the specified

, acceptance criteria, the Shift Supervisor will be notified and corrective action will be initiated in accordance with FNP-0-AP-52.

The Shift Foreman Operating will review all operations surveillance tests performed on his shift for completeness and accuracy and shall so indicate by signing and dating the l procedure in the appropriate space. In addition, I

he will insure that an entry is made on the control room surveillance test schedule to document the completion of the tests.

l 8.2 Conditional or Off-normal Surveillance Requirements The Shift Foreman Operating is responsible for establishing the schedule of surveillance testing to comply with Technical Specification requirements in conditional or off-normal situations.

If the surveillance testing is a result of a Limiting Condition for Operation becoming effective, the requirements will be documented in accordance with section 6.4. The surveillance testing will be conducted, reviewed and documented in accordance with section 8.1.

3 Rev.ll 51

~ ^ ~ ~ ^

. . . .^ . . . . . ~ :. . =.2.; . -. = . --...._ .

FNP-0-AP-16 t 9.0 Activities Requiring Shift Supervisor Approval The Shift Supervisor will be cognizant of the overall status of his unit at all times. Prior to the start of and after the completion of activities affecting the operational availability of his unit eguipment the Shift Supervisor will initial the controlling document under which the activity is performed (i.e.: MWR, WA, STP, FSP, ETP, Operations Tagging Orders, Release

' Permits or Procedure Change Request Forms) thus signifying his approval.

10.0 References 10.1 Title 10 Code of Federal Regulations Chapter 50 ,

(10CFR50) .

10.2 . Title 10 code of Federal Regulations Chapter 55 (10CFR55) 10.3 American National Standard Selection and Training of Nuclear Power Plant Personnel (ANSI 18.1) 10.4 American National Standard Administrative Controls for Nuclear Power Plants. (ANSI 18.7) 10.5 Alabama Power Company Safe Practice Manual 10.6 Joseph M. Farley Nuclear Plant Operation Quality Assurance Policy Manual (OQAPM) 10.7 Joseph M. Farley Nuclear Plant Final Safety Analysis Report (FSAR) 10.8 Appendix A and Appendix B Technical Specifications 10.9 Alabama Power Company Electrical System Operating Procedure 10.10 Farley Nuclear Plant Procedures 10.10.1 Development, Review, and Approval of Plant Procedures (FNP-0-AP-1) 10.10.2 Plant Organization and Responsibility (FNP-0-AP-3) 10.10.3 Control of Plant Documents (FNP-0-AP-4) 10.10.4 Surveillance Program Administrative Control (FNP-0-AP-5) 10.10.5 Procedure Adherence (FNP-0-AP-6)

Rev.ll 52

FNP-0-AP-16

10.10.6 Control of Temporary Alterations (FNP-0-AP-13) 10.10.7 Safety Clearance and Tagging (FNP-0-AP-14) 10.10.8 Maintenance Conduct of Operations (FNP-0-AP-15) 10.10.9 Conduct of Operations - Training Group (FNP-0-AP-27) 10.10.10 Review of Operating Data (FNP-0-AP-32) 10.10.11 General Plant Housekeeping and Cleanliness Control (FNP-0-AP-35) 10.10.12 Fire Patrols and Watches (FNP-0-AP-39) 10.10.13 Access Control (FNP-0-AP-42) 10.10.14 Access Control (FNP-0-SP-1) 10.10.15 Challenging Procedures (FNP-0-SP-4) 10.10.16 Lock and Key Control Procedures (FNP-0-SP-9) 10.10.17 Surveillance Requirements and Procedures (FNP-0-SP-21) 10.10.18 Visitor Control (FNP-0-SP-24) 10.10.19 Fire Emergencies (FNP-0-EIP-13) 10.10.20 Equipment Status Control and Maintenance Authorization (FNP-0-AP-52) 10.10.21 Plant Reporting Requirements (FNP-0-AP-49) 10.10.22 Offsite Notification (FNP-0-EIP-26)

Rev. 11 53

.m  %

i FNP-0-AP-16 i .

OPERATIONS GROUP ADMINISTRATIVE ORGANIZATION I

OPERATIONS SUPERINTENDENT OPERA' IONS OPERATIONS CLERK SUPERVISOR PIJUGIING & UNIT UNIT ENGINEERS AND BUIlEING SCHEDULING SUPERVISOR SUPERVISOR

- ENGINEERING AND i SUPERVISOR UNIT 1 UNIT 2 AIDES GROUND

SUPERVIS0li i

PLANNERS SIIFT SHIFT SHIFT SUPERVISOR SUPPORT SUPERVISOR UNIT 1 SUPERVISOR UNIT 2 UTILITY i .

FOREMAN l SHIFT SHIFT SHIFT SHIFT FOREMAN FOREMAN FOREMAN FOREMAN

OPERATING INSPECTING /STA INSPECTING /STA OPERATING j

NUCLEAR ,

OPERATIVES PLANT PLANT j

OPERATOR OPERATOR r

I

SYSTEMS I

SYSTEMS SYSTEMS SYSTEMS  !

OPERATOR OPERATOR OPERATOR OPERATOR I IN TRAINING IN TRAINING SWITCHBOARD SHIFT AIDE ,

OPERATOR

/

TCN 13A Figure 1 l

- n .,

FNP-0-AP-16 ,

ON SHIFT OPERATIONAL ORGANIZATION OPERATIONS

^

SUPERINTENDENT OPERATIONS OPERATIONS MANAGER SUPERVISOR i

SHIFT SWITCHBOARD SHIFT SUPERVISOR -

y OPERATOR ( -

SUPERVISOR UNIT 1 UNIT 2 SHIFT J. > SUPPORT SUPERVISOR 1 SHIFT SHIFT SHIFT SHIFT FOREMAN FOREMAN FOREMAN FOREMAN INSPECTING /STA OPERATING OPERATING INSPECTING /STA UNIT OPERhTOR UNIT OPERATOR OPERATOR AT THE OPERATOR AT THE CONTROLS CONTROLS

'~

ROVER SYSTEMS SYSTEMS OPERATORS SYSTEMS OPERATORS OPERATOR IN TRAINING TCN 13A Figure 2

FWP-CD-AP-16 ON SHIFT EMERGENCY CONDITION ORGANIZATION EMERGENCY DIRECTOR OPERATIONS

-~-

MANAGER SHIFT SUPERVISOR IN CHARGE .

SHIFT SUPPORT SUPERVISOR Unaffected Units operational

, organizations as shown on Figure 2.

SHIFT SHIFT TECHNICAL SUPERVISOR ADVISOR AFFECTED UNIT I

SHIFT UNIT OPERATOR OPERATING OPERATOR AT THE CONTROLS g

SYSTEMS OPERATOR IN TRAINING SYSTEMS OPERATORS

• May be same individual.

Supervisor In Charge. If so the unaffected units Shif t Supervisor controls his unit and reports to the Shif t TCN 13A rigure 3

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- ALTEAMATE TECMMtCAL 5,iPromT CSETER Figure 4 Rev. 11

FNP-0-AP-16 .

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, ItIYPE: K2.13

(

j .

TRAINING CEGGE NOTICE

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./

• DAE

• Document Number /Name '

(XRET) -

Discription of change 1

s Reason for change'

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l l

1 =

Special instructions (if any) l

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l Initial appropriate space on back of this fo= upon completion of reading this change notice. ,

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• Indexing Inforsstion FIGURE 5 Rev. 7 V . - - - - , _ . _ . - - . . . , , - . - - , - - _ _ , , , _ , , , . , - - - - ,.,,,.--,--m.-- -

1. - ------_,-..,.------y y

- . . _ . _,7 Reictpr Trip No. I /

" FNP-0-AP-16

' ~

REACTOR TRIP REPORT r, '

, JOSEPH M. FARLEY NUCLEAR PLANT .,

( / UNIT NO.  ? i Time Date Thersal Power (*.)

Electrical Load (MWe Gross) ' -

O

' Plant Conditions or Evolutions in Progress (include LCO, & s'ajor/significant maintenance) prior to trip '

( 4-9 l

' Protection Function Causing Reactor Trip -

Protection Functien Cansing Turbine / Gen. Trip Cause of Trip-

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< Corrective Action to allow return to critical

)

Corrective' Action-to preclude recurrehce i~

R earks >

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Checklist , SS Initial E0P 5.0 Performed

,. Shift Supervisor Plant Stable

! ED Notified j< NRC OPS Center Notified Operations Supervisor Computer Postmortem Reviewed and attached Alarm Printout / Sequence

^

Systems Performance Supervisor of Events Reviewed and attached Incident Report attached On Call ED permissica to take reactor critical

~

, FIGURE 6 Rev. 12

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

l'.-. _

FNP-0-AP-16

• LCO STATUS SMEET ,

. \

SECTION I-l LCO EFEECTIVE 1 ,

RESTORATION REQUIPIDI TECH SPEC REF (; MODES l

DATE TIME I DATE I TIME . ... .

l l CONDIT"ON INITIATING LCO:

i f

l REQUIRED ACTION IF RESTORATION TD1E IS EXCEEDED:

I REQUIRED ACTION WHILE LCO IN EFFICT:

i

(*

SHIFT FOREMAN -

SHIFT SUPERVISOR i

( SECTION II SHIFT FOREMAN' S INITIALS INDICATE THAT ANY TESTING OR ACTIONS REQUIRED HAVE BEEN COMPLETED.

i i i i 110 iTH I I I I I I I I l I DATE i i i i I i i  ! I I i i I i i I j NIGHT I ' I I I L l DAY l I i l i i l i I I l l i EVENING I I I I I I I I l i I i i i I I MONTH I I I I I l l '

l I DATE I l ll 1 J l i I

NIGHT l l l l I I I I DAY l I  ! l I I l I  ! l I I i i i I EVEIING I I I I ( l l  ! I SECTION III LCO NO LCNGER IN EFFECT: DATE TIME TIME LCO IN EFFECT: DAYS ECURS CORRECTIVE ACTION REQUIRED:

i,

(

SHIFT FOREMAN SHIFT SUPERVISOR OPERATION SUPERVISOR REVIEW

..gg.; , .y.

-:--- - .--- -- = n = : . . . . - - _ _ - ... . _ _ _ _ _ = - - _ , _ _ _ _ .- . _

FNP-0-AP-16 Appendix A APPENDIX A 1.0 Purpose The purpose of this appendix is to provide instructions to ensure that construction, maintenance and testing activities on Control Room boundary penetrations do not adversely affect the safe operation of Unit 1 and/or 2.

2.0 Scope The requirements of this appendix are applicable to both the Unit 1 and the Unit 2 Control Room.

3.0 References 3.1 FNP Units 1 and 2 Technical Specifications, Appendix A, Section 4.7.7.1.e.4 and Section 4.7.7.e.3.

i 3.2 FNP-0-STP-26.2, " Control Room Pressurization /

l Filtration Operability Test".

l 3.3 FNP-0-STP-26.0, " Control Room Train A(B)

Ventilation Operability Test".

4.0 Instructions 4.1 Administrative Controls 4.1.1 The removal of any cap, sealant, or filler material from a Control Room boundary penetration will require the written approval of the appropriate l Shift Supervisor if such action will result in, or has the potential for, increasing the outleakage of air from the Control Room. The procedure for granting approval for any such action will be as follows:

l 4.1.1.1 The individual requesting re-l lease will initiate two copies l of the Penetration Release Form, l Figure A-1 (an original and a work l

copy). He will completely fill out Section I of the form and present them to the appropriate Shift Supervisor.

Rev. 10 A-1 l

- FNP-0-AP-16

- App;ndix A t 4.1.1.2 The appropriate Shift Supervisor will review the file of outstanding Penetration Release Form and if the work on the requested penetration will not cause the total allowable open penetration area to exceed 150.0 inz will signify approval by signing and dating section II on the original and on the work copy. (20, 3 inch penetrations) 4.1.1.3 The appropriate Shift Supervisor will give the approved work copy to the individual requesting release and file the original in the ,

outstanding portion of the Penetration Release file.

4.1.1.4 Upon completion of the work on the penetration, the work copy and the original will be signed and dated in Section III by the individual completing the resealing of the penetration. The

penetration will then be inspected and verified to be resealed by a Construction Electrical QC Inspector or, if the penetration I work was performed by APCO, by

! appropriate APCO Group Foreman, l

Supervisor or other approved certified personnel. The inspector will document his inspection in Section III of the original and the work copy.

4.1.1.5 The work copy will be placed in the work package and routed to document control along with the work package.

The original will be placed in the completed section of the file.

4.2 Surveillance 4.2.1 The Operations Supervisor will, on a quarterly basis, direct that an audit of the above Administrative Controls be

- performed. The audit will include an inspection of the outstanding portion Rev. 9 A-2

FNP-0-AP-16 Appendix A

( the Penetration Request file and a comparison of the outstanding requests with the work in progress. The audit will also include a review of the completed section of the file. A record of the audit will be forwarded to Document control, and the copies audited will be discarded.

4.2.2 In addition to the audit, the operations Supervisor will periodically schedule the conduct of the applicable portions of reference 3.3 in order to verify the outleakage from the control room is maintained within acceptable limits.

This surveillance will be performed at least quarterly.

)

l 1

t Rev. 9 A-3

n . . . . . . . . . . .

FNP-0-AP-16

- Appendix A

, FARLEY NUCIEAR PLANT PENETRATION RELEASE FORM Section I MWR or CWR Number Penetration Number Penetration Size Equivalent square inches open area Work to be performed:

Requested by: Date:

Section II Shift Supervisor Approval: Date/ Time Section III i

Work completed, penetration resealed.

Performed by: Date/ Time verified by: Date COMMENTS:

l Original - Penetration Release Form File Work Copy - To individual requesting release.

Figure A-1

- Rev. 9 A-4

FNP-0-AP-16 Appendix B i APPENDIX B Shift Turnover and Relief Procedures The shift relief for all on-shift classifications will be conducted using formal checklists. The shift relief will be conducted in such a manner that the Shift Supervision shift relief is completed prior to the beginning of the remainder of the shift complement shift relief. The off-going individual will not leave his work area until his on-coming counterpart has satisfied himself that he is fully aware of existing conditions.

If additional room is needed for comments, the Shift Relief Checklist Continuation Form may be used - Page B-26 Rev. 12 B-1

- FNP-0-AP-16 Appendix B f

SHIFT SUPERVISOR / SHIFT RELIEF INSTRUCTIONS 1.0 Purpose These instructions are provided to enhance the transfer of information to an oncoming Shift Supervisor so that there is assurance that the oncoming Shift Supervisor obtains the required level of knowledge prior to assuming the responsibility for his unit.

l' l 2.0 References 2.1 FNP-0-AP-16 Conduct of Operations, Operations i- Group 3.0 Instructions For Shift Relief 3.1 Shift Supervisor relief shall normally commence one-half hour prior to the start of the relief of other operations shift classifications and shall be of sufficient duration to assure that the oncoming Shift Supervisor does not assume the independent responsibility for the unit until he has obtained the required information.

3.2 The information passed on shall be sufficient to l present relatively detailed status and information about the previous 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of operation and be expanded as necessary if the oncoming Shift Supervisor was not on duty within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.3 The Shift Supervisor Relief Checksheet, (B-4 and B-5), shall be used during the relief as an aid to ensuring all applicable topics are addressed in the turnover conversation and information contained in various sources is reviewed by the oncoming Shift Supervisor. Items contained in Part I of the checksheet shall be reviewed by the oncoming Shift Supervisor prior to the departure of the offgoing Shift Supervisor. Items contained in Part II shall be reviewed by the oncoming Shift Supervisor as early in the shift as practical but not necessarily prior to the departure of the offgoing Shift Supervisor.

3.4 After assuming the shift responsibility, the Shift Supervisor shall initiate a new relief checksheet to be used during the next relief.

To the extent possible, the relief checksheet should be maintained throughout the shift as opposed to completing the checksheet just prior to relief time.

Rev. 11 B-2 e .-- . - , .-,.,---v.---. .- -- -

. FNP-0-AP-16 Appendix B t

RTYPE G7.63 SHIFT SUPERVISOR RELIEF CHECKSHEET Unit Offgoing Supv. Oncoming Supv. N D E Date Part I - To be reviewed prior to oncoming Supervisor assuming the chift.

Unit Status Keys Turned Over a Evolutions (completed /in progress / planned)

General Information Equipment Status i

i Waste Management Status LCO Status Night Orders Shift Crew Composition Rev. 10 i B-3

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

[ _ _ _ _ _ _ . . . . _ .

FNP-0-AP-16 Jg)pendix B

(

Pert II - To be completed as early in shift as possible.

SS and P0 Log Opas Memorandum Book Chem / Radio ches. Plots Bypassed /Inop. Equip. Panel Fire Brigade Members Unit Status Board General Information:

Abnormal lineups Off normal conditions General Chronology of events (Special emphasis last 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)

Special instructions / considerations V:ste Management Status:

Waste inventories-Short and intermediate range plans

(

Special evolutions Equipment Status:

STP's or tests in progress Problems identified in STP's of tests Significant equipment deficiencies identified Equipment currently out of service / measures required as a result Maintenance released and its impact / schedule for completion Maintenance completed / restoration measures outstanding i

Rev. 7 B-4

L_ _._ . . . . _ . - _ . _ _...___ . _ . _ . . . . _ _ _ _ . . . .

- - FNP-0-AP-16 Appendix B

~

' SHIFT FOREMAN / SHIFT RELIEF INSTRUCTIONS 1.0 Purpose These instructions are provided to enhance the transfer of information to an oncoming Shift Foreman so that there is assurance that the oncoming Shift Foreman obtains the required level of knowledge prior to assuming the responsibility for his unit.

2.0 References 2.1 FNP-0-AP-16 Conduct of Operations, Operations Group 3.0 Instructions For Shift Relief i 3.1 Shift Foreman relief shall normally commence one-half hour prior to the start of the relief of other operations shift classifications and i

shall be of sufficient duration to assure that the oncoming Shift Foreman does not assume the independent responsibility for the unit until he has obtained the required information.

3.2 The Shift Foreman shall include information oriented I toward the specific operating unit, or operating function such as refueling SRO, for which the Foreman is assuming responsibility. The information passed on shall be sufficient to present relatively detailed status and information about the previous 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of operation and be expanded as necessary if the oncoming Shift Foreman was not on duty within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i I 3.3 The Shift Foreman Operating shall provide l sufficient information on current job assignments and job status of the System Operators (50) and Equipment Operators (EO) to allow the oncoming Shift Foreman Operating to coordinate their actions without having to rely on the SO's and EO's to describe their assignment. l Rev. 11

(

i B-5

~ '

' FNP-0-AP-16 Appendix B t

3.4 The Shift Foreman Relief checksheet, (B-8 and '

B-9), shall be used during the relief as an aid to ensuring all applicable topics are addressed in the turnover conversation and information contained in various sources is reviewed by the oncoming Shift Foreman. Items contained in Part I of the checksheet shall be reviewed by the oncoming Shift Foreman prior to the departure of the i offgoing Shift Foreman. Items contained in Part II shall be reviewed by the oncoming Shift Foreman as early in the shift as practical but not necessarily prior to the departure of the offgoing Shift Foreman. Items contained in Part III shall be completed by the offgoing Shift Foreman.

the 3.5 After assuming the shift responsibility, f checksheet Shift Foreman shall initiate a new relie to be used during the next relief. To the extent possible, the relief checksheet should be maintained throughout the shift as opposed to completing the checksheet just prior to relief time.

3.6 Completed Shift Relief Checksheets for all shift positions shall be accummulated by the Shift Foreman Inspecting, assembled and transmitted to Document Control for retention along with other shift records.

l 3.7 The Shift Foreman Operating shall routinely evaluate the effectiveness of the shift personnel under his supervision in making good turnovers and take corrective measures as appropriate. The objective of the controls established by the shift relief procedures is to maximize the level of knowledge possessed by the oncoming crew members.

O Rev. 7 B-6

FNP-0-AP-16 Appendix B i

RTYPE G7.63 Operating O SHIFT FOREMAN RELIEF CHECKSHEET Inspecting O Unit Offgoing Foreman Oncoming Foreman N D E Date Part I - To be reviewed prior to oncoming Foreman assuming the shift.

Unit Status Keys Turned Over a Evolutions (completed /in progress / planned)

General Information l

l l

l l

Equipment Status l

Waste Management Status l

8

• LCO Status Night Orders Shift Crew Composition Rev. 10 l

B-7

.- ~ ; . . _ . .

FNP-0-AP-16 Appendix B f

Part II - To be completed as early in shift as possible.

Tagging Order Inder Open Flame Permits SS and PO Log (initial log) Training Change Notices Opas Memorandum Book Lubrication Schedule i

STP Schedule Board Bypassed /Inop. Equip. Panel Chem / Radio chem. Plots Unit Status Board Fire Brigade Members s Part III - To be completed prior to leaving shift STP Schedule Review (E Shift) - This includes nonsafety related STP's and FSP's (E Shift)

(

Review / Sign STP-1.0 Review / Sign Logs (N Shift)

General Information:

Abnormal lineups Off normal conditions General Chronology of events (Special emphasis last 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)

Special instructions / considerations Administrative information Personnel matters Housekeeping matters Weste Management Status:

Waste inventories History of evaporater and recombiner operation History of filter replacement Short and intermediate range plans Special evolutions Equipment Status:

STP's or tests in progress Problems identified in STP's of tests Significant equipment deficiencies identified Equipment currently out of service / measures required as a result Maintenance released and its impact / schedule for completion Maintenance completed / restoration measures outstanding Rev. 7 B-8

- - , , - . . . _ - - . . - _ - _ , , _ _ , . , -- --.m,. . _.._._.,,.,,,-,,,.,..,,,,,.,-ym,..__.,,,,--,-,,,_,,,,,,_,-__-.-,-w._m.-,,,,.,%%,-- -

FNP-0-AP-16 Appendix B

PLANT OPERATOR SHIFT RELIEF INSTRUCTIONS 1.0 Purpose These instructions are orovided to enhance the transfer

' of information to an oncoming Plant Operator and provide assurance that the oncoming Plant Operator obtains the required level of knowledge prior to assuming the responsibility for his unit.

2.0 References 2.1 FNP-0-AP-16 Conduct of Operations, Operations Group 3.0 Instructions For Shift Relief .

3.1 Plant Operator relief shall normally commence after the completion of Shift Foreman relief and shall be of sufficient duration. To assure that the oncoming Plant Operator does not assume the independent responsibility for the unit until he has the required information.

3.2 Plant Operators shall normally relieve in the control room. The turnover shall normally be held with both the " unit" operators and "at the controls" operators transferring information together so that the oncoming operators in each position receive a status from both the offgoing positions.

The status information passed to the oncoming shift shall be detailed with particular emphasis on the previous 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of operation. Special i consideration of what information must be passed l on is necessary if an oncoming Plant Operator has not been on duty within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Sufficient informatin shall be passed .

on concerning current job assignments and job status of the System Operators (SO) and Equipment i Operators (EO) to allow the oncoming Plant Operators to coordinate their actions without having to rely on the SO's and EO's to describe i their assignment.

3.3 The Plant Operator's Relief Checksheet (B-12 and B-13) shall be used during the relief as an aid to ensure all applicable topics are addressed in l

the turnover conversation and information contained l

in various sources is reviewed by the oncoming l Plant Operator. Items contained in Part I of the Checklist shall be reviewed by the oncoming Rev. 11 i

B-9 l

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

FNP-0-AP-16 Appendix B

' Plant Operator prior to the departure of the offgoing Plant Operator. Prior to assuming the shift, the oncoming " unit" and "at the controls" operators shall walk down the main control board and the Unit Operator shall walk down the balance of plant panels. Annunciators, indicators, switch positions, position indicating lamps and controller status shall be observed for correctness and off normal conditions shall be discussed with the off going operators. The following valves, important to safety, are important enough to require increased visibility and attention. A blue or yellow dot is on the nameplate on the side of the switch that the valve position should be in for normal operation.

If the valve is in other than the desired position inform the Shift Supervisor immediately.

MCB

1. CS Pump A & B Suctions MOV 8827A & 8827B

2. RER Pump Suctions from RWST MOV 8809A 8809B

3. AFW to S/G A, B, C Stop Valves MOV 3350A, B, C

4. TDAFW to S/G A, B, C FCV 3228A, B, C

5. MDAFW to S/G A, B, C FCV 3227A, B, C

6. TDAFW 3228A, B, C Controllers

7. MDAFW 3227A, B, C Controllers

8. Accumulator A, B, C Outlet Valves MOV 8808A, B, C

9. SW to CTMT Coolers MOV 3019A, B, C, D

10. Chg. Pump Recirc to Hot Legs MOV 8884, 8886, 8885

11. RHR to RCS Hot Legs MOV 8889

12. RER to RCS Cold Legs MOV 8888A

& 8888B

13. SW to/from Diesel Bldg.

1 BOP

1. CTMT Sump to WHT MOV 3394

2. Fire Protection Header Valves M003, M004, M001, M002

3. CTMT Cooler SW Disch Valves MOV 3023A, B,C,D

4. CTMT Sump Disch. Valves HV 3376, 3377

5. CTMT Sump Recirc Valve HV 3380

6. Rx Cavity Cooling Damper HV 3999A, B

7. AFW SW Intake MOV 3209A, B; 3210A, B

8. TDAFW SW Intake MOV 3216

9. MDAFW to S/G MOV 3764A, B, C, D, E, F

10. Inst Air to Pent Room HV 3885, 3825

11. SFP to PRF HV 3538A, B

12. CTMT Inst Air Supply HV 3611

13. TDAFW Trip / Throttle Valve MOV 3406

• Rev. 12 B-10 c7

FNP-0-AP-16 Appendix B

~

I Section III shall be completed by the off-going operator. Section.II shall be completed as early in the shift as practical but not necessarily prior to the departure of the off-going operator.

3.4 After assuming the shift responsibility the Plant Operator shall check with the Shift Supervisor for any special instructions relating to his shift, also he shall initiate a new relief checksheet to be used during the next relief.

To the extent possible, the relief checksheet be maintained throughout the shift as opposed to completing the checksheet just prior to relief time.

3.5 Completed Shift Relief Checksheets shall be -

accumulated by the Plant Operators and forwarded to the Shift Foreman.

i i

Rev. 12 l

B-ll

FNP-0-AP-16 Appendix B L

i

- RTYPE G7.63 UO O PLANT OPERATOR RELIEF CECKSEET OATC 0 Unit Offgoing Plant Operator Oncoming Plant Operator N D E Date Part I'- To be reviewed prior to oncoming Plant Operator assuming the shift. l Keys Turned Over a Unit Status Evolutions (completed /in progress / planned) General Information e

4 s

i n

Rev. 12 B-12

- FNP-0-AP-16 Appendix B

(

Part I - Continued.

Equipment / Waste Management Status LCO Status Shift Crew Composition Board Walkdown Part II - To be completed as early in shift as possible.

Review Tagging Order Index Lube Schedule Status Review Plant Operator Log Review & Update Bypassed /Inop. Equip Board Review Opas. Memo Book Review & Update Unit Status Board Review STP Schedule Board Review & Update Shift Organization Review TCN's Part III - To be completed prior to leaving shift Sign P.O. Log Review / Sign STP-1.0 General Information: Abnormal lineups - Off normal conditions - General Chronology of events (Special emphasis last 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />) - Special instructions / considerations Administrative information - Personnel matters - Housekeeping matters - AP0/E0 job assignments & current status W:ste Management Status: Waste inventories - History of evaporater and recombiner operation Filter replacement - Special evolutions - Short and intermedicta range plans Equipment Status: STP's or tests in progress - Problems identified in STP's of tests l

l Significant equipment deficiencies identified - Equipment currently out of service / ,

measures required as a result - Maintenance released and its impact / sche.fule for l '

completion - Maintenance completed / restoration measures outstanding l

Rev. 7 B-13

e O FNP-0-AP-16 Appendix B SYSTEMS OPERATOR SHIFT RELIEF INSTRUCTIONS 1.0 Purpose These instructions are provided to enhance the transfer

. of information to an oncoming System Operator (50) so that there is assurance that the oncoming SO obtains the required level of knowledge prior to assuming the responsibility for his unit.

2.0 References 2.1 FNP-0-AP-16 Conduct of Operations, Operations Group 3.0 Instructions For Shift Relief 3.1 The 50 relief shall normally commence after the completion of Shift Foreman relief and shall be of sufficient duration to assure that the oncoming SO's do not assume the independent responsibility for their unit until they have received the required information.

3.2 The Auxiliary Building A and B Man positions and the rover shall normally conduct their reliefs together as a group by having one position at a time given his turnover status to the group.

l This relief shall normally be made at the B Man

! position shift station. The turbine building position shall normally conduct a separate relief in the Turbine Building. The Diesel Building Operator and Outside Operator will normally conduct their relief together as a group in the Diesel Building. The information passed to the oncoming SO's shall be detailed with particular emphasis on the previous 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> of operation. Special consideration of what information must be passed on is necessary if an oncoming so has not been on duty within the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.3 The appropriate System Operator Relief Checksheet, l

(B-16 through B-25), shall be used during the relief I as an aid to ensuring all applicable topics are addressed in the turnover conversation and inform-ation contained in various sources is reviewed by the oncoming SO's. Items contained in Part I of l

the checksheet shall be reviewed by the oncoming l

50 prior to the departure of the offgoing SO.

Items contained in Part II shall be reviewed by the oncoming 50 as early in the shift as possible t

but not necessarily prior to the departure of l

offgoing SO.

• l TCN 13A B-14 i ___ . _ . _ _ _ _ _ _ _ . . . - _ . . _ _ _ . - _ _ _ _ _ . . _ _ _ _ _ . _ . _ . _ _ _ _ . . _ _ _ _ . _ _ _ _ _ . , _

FNP-0-AP-16 Appendix B 3.4 Immediately after assuming responsibility for his shift position, the oncoming 50 shall I notify the Unit Operator that he has completed his relief, pass on what position he is assuming, and obtain any special instructions relating to his shift.

3.5 As soon as possible after completing the relief, the oncoming SO shall initiate a walkdown of  ;

the areas under his responsibility noting the status of areas, equipment, indications, switch positions, controllers and annunciators.

3.6 After assuming the shift responsibility, each So shall initiate a new relief checksheet to be I used during the next relief. To the extent possible, the relief checksheet shall be maintained throughout the shift as opposed to completing the checksheet just prior to relief time from memory.

3.6 Completed Shift Relief Checksheets shall be accumulated at each SO watch station and I forwarded to the Shift Foreman.

Rev. 11 B-15

- FNP-0-AP-16 Appendix B s

RTYPE G7.63 SYSTEM OPERATOR - A L B POSITION - SHIFT RELIEF CECKSEET Unit Offgoing SO Oncoming SO N D E Date Part I - To be reviewed prior to oncoming SO assuming the shift.

Unit Status Keys Turned Over a Evolutions (completed /in progress / planned)

General Information Equipment Status Waste Management Status RE on to WE on to GDT WGC H2 Rec WHT  % FDT  %

WCT  % LHS  %

CDT  % WMT 1 %2  %

RHT 1 %2 %3  %

LCO's affecting area Y/F PO notified relief is complete Rev. 12 B-16

. FNP-0-AP-16 Appendix B e

Part II - To be completed as early in shift as possible.

Walkdown of areas Lube Schedule Status Review area logsheets Review Operations Memos Review panel logs Review Training Change Notices Update CR Status Board General Information:

Equipment inservice Abnormal lineups Off normal conditions General Chronology of events (Special emphasis last 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)

Special instructions / considerations Administrative information Personnel matters Housekeeping matters Conditions requiring special attention Status of jobs Items you are responsible for that you didn't complete Waste Management Status:

1 l

Waste inventories History of evaporater and recombiner operation History of filter replacement Short and intermediate range plans Special evolutions Sample's requested Sample results Current lineups Equipment Status:

l STP's or tests in progress Problems identified in STP's or tests Significant equipment deficiencies identified and their impact Equipment currently out of service / measures required as a racult Maintenance being performed in your area Maintenance that was completed in your area l

l Rev. 7 B-17

FNP-0-AP-16 Appendix B RTYPE G7.63

' SYSTEM OPERATOR - ROVER POSITION - SHIFT RELIEF CECKSEET 0ffgoing SO Oncoming SO N D E Date Part I - To be reviewed prior to oncoming 50 assuming the shift.

Unit Status Keys Turned Over o j

, Evolutions (completed /in progress / planned)

General Information

Equipment Status l

i LCO's affecting area Y/N PO notified relief is complete Rev. 12 ,

B-18 ,

' , FNP-0-AP-16 Appendix B t

Part II - To be completed as early in shift as possible.

Walkdown of areas Lube Schedule Status Review area logsheets Review Operations Memos Update CR Status Board Review Training Change Notices General Information:

Equipment inservice Abnormal lineups Off normal conditions General Chronology of events (Special emphasis last 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)

Special instructions / considerations Administrative information Personnel matters Housekeeping matters Conditions requiring special attention Status of jobs Items you are responsible for that you didn't complete Equipment Status:

STP's or tests in progress Problems identified in STP's or tests Significant equipment deficiencies identified and their impact Equipment currently out of service / measures required as a result Maintenance being performed in your area Maintenance that was completed in your area l

j Rev. 7 B-19

FNP-0-AP-16 Appendix B RITPE G7.63 SYSTEM OPERATOR - TURBINE BUILDING POSITION - SHIFT RELIEF CHECKSHEET Unit Offgoing SO Oncoming S0 N D E Dte Part I - To be reviewed prior to oncoming S0 assuming the shift.

Unit Status --

i Keys Turned Over 0 i Evolutions (completed /in progress / planned)

General Information l

l Equipment Status l

l PO notified relief is complete LCO's affecting area Y/N Rev. 12 B-20

FNP-0-AP-16 Appendix B Part II - To be completed as early in shift as possible.

Walkdown of areas -Lube Schedule Status Review area logsheets Review Operations Memos Review panel logs Review Training Change Notices Update CR Status Board General Information:

Equipment inservice

• Abnormal lineups Off normal conditions General Chronology of events (Special emphasis last 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)

Special instructions / considerations

, Administrative information Personnel matters i Housekeeping matters Conditions requiring special attention Status of jobs Items you are responsible for that you didn't complete i

Equipment Status:

STP's or tests in progress i Problems identified in STP's or tests Significant equipment deficiencies identified and their impact Equipment currently out of service / measures required as a result Maintenance being performed in your area Maintenance that was completed in your area Sump Status:

Sump levels Which sump is onservice Samples requested and when results expected Sample results Releases in progress Rev. 7 B-21

FNP-0-AP-16 Appendix B i

RTYPE G7.63 SYSTEM OPERATOR - DIESEL BUILDING POSITION - SHIFT RELIEF CHECKSHEET Unit Offgoing SO Oncoming SO N D E Date Part I - To be reviewed prior to oncoming S0 assuming the shift.

Unit Status Keys Turned Over O Evolutions (completed /in progress / planned)

General Information Equipment Status LCO's affecting area Y/N PO notified relief is complete Rev. 13 B-22

o______- . . . . _ _ _ . . . . . _ . . . .. . _ _ .

i FNP-0-AP-16 Appendix B f.

Part II --To be completed as early in shift as possible.

f. ,

Walkdown of areas Lube Schedule Status /

Review area logsheets Review Operations Memos Review panel logs 1 s Review. Training. Change Notices

\

Update CR Status Board "

GIneral Information:

Equipment inservice Abnormal lineups Off normal conditions t General Chronology of events (Special emphasis last 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)

Special instructions / considerations Administrative informat' ion Personnel matters Housekeeping matters Conditions requiring special attention Status of jobs Items you are responsible for that you didn't complete

. Equipment Status:

STP's or tests in progress Problems identified in STP's or tests Significant equipment deficiencies identified and their impact Equipment currently out of service / measures required as a result Maintenance being performed in your area Maintenance that was completed in your area A

1 s.

I d Rev. 13 B-23

, O FNP-0-AP-16 Appendix B

( '

RTYPE G7.63 SYSTEMS OPERATOR-0UISIDE OPERATOR SHIFT RELIEF CHECKSHEET Unit Offgoing SO Oncoming SO N D E Date Part I - To be reviewed prior to oncoming SO assuming the shift.

Unit Status Keys Turned over o Evolutions (completed /in progress / planned)

General Information l

Equipment Status I

LCO's affecting area Y/N PO notified relief is complete TCN 13A B-24 L

FNP-0-AP-16 Appendix B

(

, Part II - To be completed as early in shift as possible.

Walkdown of areas Lube Schedule Status Review area logsheets 0 Review Operations Memos Update CR Status Board Review Training Change Notices General Information:

Equipment inservice Abnormal lineups Off normal conditions General Chronology of events (Special emphasis last 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)

Special instructions / considerations Administrative information Personnel matters Housekeeping matters Conditions requiring special attention Status of jobs Items you are responsible for that you didn't complete Equipment Status:

STP's or tests in progress Problems identified in STP's or tests Significant equipment deficiencies identified and their impact Equipment currently out of service / measures required as a result Maintenance being performed in your area Maintenance that was completed in your area TCN 13A

'B-25 ,

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

3

. . FNP-0-AP-16 Appsndix B t

( SHIFT RELIEF CHECKSHEET CONTINUATION POSITION-N D E Date UNIT i

i e

I e

9 I

I I

TCN 13A B-26

- - FNP-0-AP-16 Appendix B t

Part II - To be completed as early in shift as possible.

Walkdown of areas Lube Schedule Status Review area logsheets Review operations Mesos Update CR Status Board Review Training Change Notices General Information:

Equipment inservice Abnormal lineups Off normal conditions General Chronology of events (Special emphasis last 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />)

Special instructions / considerations Administrative information Personnel matters Housekeeping matters Conditions requiring special attention Status of jobs Items you are responsible for that you didn't complete Equipment Status:

STP's or tests in progress Problems identified in STP's or tests Significent equipment deficiencies identified and their impact Equipment currently out of service / measures required as a result Maintenance being performed in your area Maintenance that was completed in your area Rev. 13 B-27 l

l

. =

' FNP-0-AP-16 Appendix B t-SHIFT RELIEF CHECKSHEET CONTINUATION POSITION N D E Date UNIT M

suudup I

I l

t f

1

+

Rev. 13 B-28 l

FNP-0-AP-16 e

TABLE I Systems Requiring Verification of line up to be performed prior to release for maintenance and prior to return to service.

SOP TITLE 1.lA & B Reactor Coolant System 1.2A Reactor Coolant Pressure Relief System 2.lA Chemical and Volume Control System Plant Startup and Operation 2.3 Chemical and Volume Control System Reactor Makeup Control System 2.6A Boric Acid 7.0A Residual Heat Removal System 8.0A Safety Injection System - Accumulators 8.lA High Head Safety Injection System 9.0A Containment Spray System 10.0A Post LOCA Coutainment Pressurization and Vent System 12.2A Containment Purge and Pre-access Filtration System l

l 22.0A Auxiliary Feedwater System 23.0A Component Cooling Water System 24.0A & 24.2A Service Water System 25.0A & 25.2A River Water System 36.0A Plant Electrical Distribution Lineup l 36.lA & B Startup Auxiliary, Unit Auxiliary and Main Transformers Preparation for Operation 36.2 4160 VAC Distribution System i

36.3 600, 480, 208/120 volt AC Electrical Distribution System l

l PAGE 1 Rev. 7

i I . . . . _ _ . . . . . . _ _ _ . . . _ . _ _ .. _ .. _ . . .

FNP-0-AP-16 SOP Title 36.4A 120 V AC Instrumentation Distribution System 36.5A & B Plant Lighting 37.lA 125 V DC Auxiliary Building Distribution System 37.3A Service Water Building 125 V DC Distribution System 38.0A, B, C, & D Diesel Generators 39.0 Nuclear Instrumentation System 40.0 Reactor Control and Protection System 42.0A Diesel Fuel Oil Storage and Transfer System 44.2 Core Subcooling Monitoring System 45.0A Radiation Monitoring System 56.0A Control Room KVAC System 60.0A Penetration Room Filtration System 62.0A Emergency Air System 64.0 Control Rcom Chlorine Detector PAGE 2 Rev. 7

(

FNP-0-AP-16 Appzndix C I

APPENDIX C Return to Service and Systems Lineup To assist management in insuring that all work and actions necessary are completed prior to returning from service, following a refueling outage an extended maintenance outage (greater than 28 days) or when plant management deems it necessary, a Return to Service Checklist will be prepared.

The Return to Service Checklist does not replace any existing procedural guidance. Rather, it serves as an additional level ofItems insurance that actions necessary to change modes are completed.

to be included on the Return to Service Checklist are, because of their nature, not covered under existing procedural guidance or they are felt by management to be important enough to require an increase awareness over existing procedures.

Due to the many different actions that take place from outageUsing to outage a common Return to Service Checklist cannot be developed.

the guidance of Attachment 1, the Operations Superintendent will have the Return to Service Checklist prepared for the Plant Managers approval.

As a part of the Return to Service Checklist the " System Checklist Summary" will be completed. The Operation Superintendent will The signify which Shift systems require lineup by initialing in the designated block.

Supervisor shall ensure that the system lineups are completed to support the plant schedule.

The approved Return to Service Checklist will be maintained by the Shift Supervisor. When it is completed it will be forwarded to Document Control via the Operations Supervisor.

System Lineups The first person to lineup a system will not position any valves, switches, devices etc. He.will personally check the status of the listed component. If it is not in the desired condition he will note

.the actual condition in the column provided and initial. If the i

component is in the desired condition he need only initial.

Various positions are defined in Table I. If there is any doubt, refer the question to the Shift Foreman Operating for resolution.

After the first lineup is performed the Shift Foreman Operating will review it. Any discrepancies will be resolved by either:

a) Having the component properly positioned and the lineup sheet so anotated and initialed or by t

b) Completing a System Checklist Exception Sheet.

Rev. 8 C-1 1 -

- - - ,. -,m_~_r~._ _._..,..~,_._-_r.

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

FNP-0-AP-16 Appendix C It is recognized that components may be found in positions other than the position specified by the System Checklists due to system configurations (operating, shutdown, etc) or due to danger tags and that the as found position may be the desired position.

After the discrepancies are resolved, (even if the as found position is the desired position) a verification lineup will be performed if required. Any discrepancies found shall be noted on the lineup and the Shif t Foreman Operating promptly informed. Upon completion of the verification lineup (or after discrepancies have been resolved if a verification is not required) the completed System Checklist and System Checklist Exception Sheets (if any) will be reviewed by operations supervision (Shift Foreman or above). This review will be signified by signing the System Checklist Title Sheet and initialing on the appropriate line in the System Checklist Swamary. Prior to entering a new plant mode, the Shift Supervisor will verify that all specified System Checklists required for that mode have been completed and will sign on the System Checklist Summary Coversheet. Upon completion of all System Checklists and Exception Sheets they will be filed in the Control Room for reference.

Superceded Checklist will be transmitted to Document Control via the Operations Supervisor. The System Checklist Summary is part of and will be transmitted with the Return to Service Checklist.

At anytime during plant operation that the Shift Supervisor deems it appropriate he may have all or part of a System Checklist performed. He should record the reason the checklist is being performed on the title sheet and maintain the completed checklist in the Control Room for reference.

If qualified to fill a shift position as Equipment Operator, System Operator, or Plant Operator, the individual is qualified to perform verifications of the systems he is qualified to operate.

Operations supervisory personnel are qualified to perform all verifications.

Tag Outs When conducting Tag Outs, Table I will be used.

STP When conducting verifications for STP, Table II will be used.

Rev.12 C-2

RTTPE G7.93 FNP-0-AP-16 Attachm3nt I l

TYPICAL RETURN TO SERVICE CHECKLIST RETURN TO SERVICE CHECKLIST Approved:

Plant Manager Date Opers. Supt.

Verified By/Date Review /Date Prior to Mode 4

1. Verify completion of committaents for Mode 4 made to NRC in IE Bulletins /

NUREGS.

(Systems Perf Supt) / /

(Tech Supt) / /

2. Verify completion of PCN required / /

prior to Mode 4.

(Sys Perf Supt)

3. Verify proper oil / /

level in RCP's and RCDT pumps. Verify Auto level & pressure control of RCDT.

(Ops Supv)

4. Verify operability Diesel / /

Generator Air Compressors (Ops Supv)

5. Tag out main purge isolation / /

valve air supply to Plant Manager.

(Ops Supv)

6. Inspect CTNT for Security / /

(Sec Supv)

7. Inspect CTMT for Fire / /

Protection.

(Fire Marshall)

C-3 Rev. 10

. RTYPE G7.93 FNP-0-AP-16 Attachment I g

Ops. Supt.

Ites Verified By/Date Review /Date

8. Verify proper alignment of / /

instrument valves for instruments in CTMT and Acxiliary Building (I&C Supv)

9. Cold shutdown STP completed / /

satisfactory.

(Ops Supv)

10. MCB, BOP, and all Protection / /

and other cabinets in the l Control Room vacuumed.

l (Maint Supt)

11. Complete CTMT inspection / /

per STP-34.0 prior to establishing CTMT integrity.

(Ops Supt)

12. Verify STP-14.0 (CTMT / /

Integrity Verification) completed.

(Ops Supv)

13. Verify STP-15.0 completed / /

on personnel airlocks.

(Ops Supv)

14. Verify MP-38 on / /

Equipment Hatch completed (Maint Supt)

15. All hanger and anchor bolt / /

PCN work completed (System Perf Supt)

16. Containment sump pump / /

l operability verified l (Ops Supv)

17. Verify proper oil / /

level in all plant equipment l (Ops Supv) l C-4 Rev. 10

RTYPE G7.93 FNP-0-AP-16 Attachment I I Ops Supt Item Verified By/Date Review /Date

18. Inspection of following areas for cleanliness, fire protection, security and systems integrity (Ops Supv)

a. Aux Bldg (Rad Side) / /

b. Aux Bldg (Non-Rad Side) / /

c. Diesel Bldg / /

d. Service Water Bldg / /

19. Clean Electrical Switchgear / /

(Maint Supt)

20. TCN on Design Changes / /

have been issued.

(Trng Supt)

21. RCP inspected for no oil / /

leaks per Westinghouse letter.

(Maint Supt)

22. IMP-0.7 has been / /

reinstated.

(I&C Supv) l Prior to Mode 3

1. Complete RER portion of ETP-168, / /

Leak Reduction Inspection.

(Requires both Trains of RER in service)

(Sys Perf Supv)

2. Complete RHR portion of ETP-223, / /

Piping Thermal Expansion &

Restraint Test. (Requires both Trains of RHR in service @~3500F)

( (Sys Perf Supv)

3. Main Steam Valve Room / /

l inspected air supplies

& limit switches for MSIV's.

(Ops Supt)

4. Verify PCN required for / /

Mode 3 complete.

(Sys Perf Supt)

C-5 Rev. 10

FNP-0-AP-16 RTYPE G7.93 Attachment I Ops Supc Item Verified By/Date Review /Date Prior to Mode 2

1. Complete SOP-1.4, RCS Leak / /

Test.

2. Complete ETP-223, Piping Thermal / /

Expansion and Restraint Test.

(Requires PLT at ~5470 F.)

(Sys Supv)

3. Complete STP-158 RCS Pressure / /

Isolation Leak Test.

(Sys Perf Supv)

4. Verify completion of committments for Mode 2 made to NRC in IE Bulletins /

NUREGS.

(Systems Perf Supt) / /

(Tech Supt) / /

5. Verify PCN required for / /

Mode 2 are complete (Sys Perf Supt)

6. Verify by independent audit / /

completeness of procedure revisions necessitated by plant modification (Systems Perf Supt)

7. Have appropriate personnel make lists of all open breakers on Motor Coatrol Centers and resolve all discrepancies. / /

Prior to Turbine Roll

1. Turbine work completed / /

(Maint Supt)

2. Take necessary valve position / /

readings per STP-151.0 prior to rolling turbine.

(Ops Supv)

3. Complete backwash of Turbine / /

Lube oil coolers & Generator Hydrogen Coolers & align for normal operation.

(Ops Supv)

C-6 Rev. 12

RTYPE G7.93 FNP-0-AP-16 Attachment I Ops Supt Item Verified By/Date Review /Date

4. Verify Operability of PCCV's / /

after turbine is latched and prior to Turbine roll (STP-150.0)

(Ops Supv)

5. Inspection of following areas for cleanliness, fire protection, security and systems integrity (Ops Supv)

a. Turbine Bldg / /

b. Cire pump area and / /

Cooling Towers

6. Water Boxes inspected prior / /

to condenser close out (Ops Supv)

7. Condensate flush has been / /

completed (Ops Supv)

8. Lube oil flush has been / /

completed (Ops Supv)

9. Complete Turbine Water ,

/ /

induction valve lineup (SOP-28.0)

(Ops Supv)

Prior to Mode 1

1. Low power physics testing / /

complete.

(Tech Supt)

Prior to Exceeding 50% Power

1. Walkdown Secondary System and / /

resolve any problems (Systems Perf Supt)

2. Not Channel factors / /

verified.

(Tech Supt)

C-7 Rev. 10

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

FNP-0-AP-16

. RTYPE G7.93 Attechnent I Ops Supt e Verified By/Date Review /Date Item Prior to Exceeding 75% Power Walkdown Secondary and / /

1.

resolve any problems (Systems Perf supt)

/ /

2. Incore-Excore cross cal performed results evaluated.

(Tech Supt)

Prior to Exceeding 90% Power Walkdown Secondary and / /

1.

resolve any problems.

(Systems Perf Supt)

/ /

2. Leak measurement and reduction program complete.

C-8 Rev. 10

.-- - - - . , . , , , - - - - - - - - , , - ,m, - , . - . - - , .

RTYPE G7.93 FNP-0-AP-16 4

Attachment I O

Plant Manaaer Date t

Cleared for Mode 4 Cleared for Mode 3 Cleared for Mode 2 Cleared for Mode 1 Cleared for Exceeding 50% Power Cleared for Exceeding 90% Power i

(

l t

l l

l I

i l

l Rev. 10 I

C-9 l

l

b i --

FNP-0-AP-16 System Checklist Summary Appendix C t

System Checklists Summary Coversheet I. Preparation A. Condition requiring completion of checklist (s)

B. Required checklist (s) annotated by initials on Summary pages:

Operations Superintendent Date II. Completion A. Required checklist (s) completed: (Shift Supervisor) (Date)

Fill & vent prerequisites Mode 5 prerequisites Mode 4 prerequisites Mode 3 prerequisites Mode 2 prerequisites Mode 1 prerequisites C-10 Rev. 11

FNP-0-AP-16 System Ch2cklist Suma:ry Appendix C

~.

I SOP SYSTEM 2ND COMPLETED DATE PERFORMANCE MODE VER. &

REQUIRED REQUIRED (OPERATIONS FOR REQUIRED APPROVED (YES, (SHIFT SUPERINTEN-NO) SUPERVISOR)

DENT)

Fill & Vent 1.1A RCS Y Fill & Vent 1.1B RCS Y 5 7.0A RHR Y 4 9.0A CTNT. Spray Y 4 10.0A Post LOCA CTNT. Press.

& Vent Y 4 12.2A CTMT Purge & Preaccess Y Filt.

4 16.1A SGBD Processing N 4 16.2A SGBD Demin. N 4 23.0A CCW Y 4 24.0A SW Y 4 24.2A SW Auxiliary Systems Y 4 25.0A RW Y ,

4 25.2A RW Auxiliary Systems Y 4 31.0A Compressed Air N 4 31.0B Compressed Air N 4 31.0C Compressed Air N 4 31.0D Compressed Air N 4 31.1A Service Air N 4 33.0A Nitrogen N 4 33.0B Nitrogen N Required to be performed after all' refueling outage or major maintenance outage.

C-11 Rev. 8

'. FNP-0-AP-16 System Checklist Summary Appendix C f

PERFORMANCE MODE S0P SYSTEM 2ND COMPI.ETED DATE REQUIRED REQUIRED VER. &

, (OPERATIONS FOR REQUIRED APPROVED SUPERINTEN- (YES, (SHIFT DENT) NO) SUPERVISOR) 4 33.0C Nitrogen N 4 34.0A H, - 0, N 4 34.0B H, - 0, N 4 34.0C H, - 0, N 4 34.0D H, - 0, N 4 36.0A Plant Electrical Dist. Y 4

• 36.1A S/U Aux., Unit Aux., &

Main Trans. Y 4

• 36.1B S/U Aux., Unit Aux., &

Main Trans. Y 4

• 36.4A 120V AC INST. Dist. Y 4 37.1A 125V DC Aux. Bldg. Y 4 37.2A 250/125V DC T.B. N 4 37.3A SW Bldg. 125V DC Y 4 37.4A 125V DC Misc. Dist. N 4 38.0A Diesel Gen. Y 4 38.0B Diesel Gen. Y 4 38.0C Diesel Gen. Y 4 38.0D Diesel Gen. Y ,

4

• 38.0E Diesel Gen. Y 4 *38.0F Diesel Gen. Y 4 *41.0A CRDM Position Y Indication System 4 42.0A Diesel Fuel Oil Y 4 43.0A DG Bldg. KVAC N O

Required to be performed after all refueling outage or major maintenance outage.

C-12 Rev. 12 i

FNP-0-AP-16

. System Checklist Summary Appendix C i

PERFORMANCE MODE S0P SYSTEM 2ND COMPLETED DATE REQUIRED REQUIRED VER. &

(OPERATIONS FOR REQUIRED APPROVED SUPERINTEN- (YES, (SHIFT DENT) NO) SUPE 3 VISOR) 4 45.0A RM Y 4 53.0A SW Bldg. HVAC N 4 55.1A AS & Condensate N 4 56.0A Control Room HVAC Y 4 60.0A Pen. Rs. Filtration Y 4 60.1A Pen. Rs. Air Cond. N 4 61.0A Fire Protection Y

! 4 61.1A Fire Protection Y 4 61.2A HP CO, Y 4 61.3A LP CO, Y 4 61.3,B LP CO, Y 4 61.3C LP CO, Y l 4 62.0A Emergency Air Y 4 62.IA Backup Air or N2*

PZR. PORV. Y 3 2.1A CVCS Y l

• 3 2.4A CVCS Boron Recycle Y 3 2.6A CVCS Boric Acid Y 3 4.0A Reactor Makeup Water N l

3 8.0A SI Accumulators Y 3 8.1A HHSI Y 3 12.1A CTMT Air Cooling Y 3 22.0A AFW Y o

Required to ber performed after all refueling outage or major maintenance outage.

C-13 Rev. 8

.,,..rr- . . - - - . - . . . - - . - .

• FNP-0-AP-16 System Checklist Summary Appendix C MODE S0P SYSTEM 2ND COMPLETED DATE PERFORMANCE REQUIRED VER. &

REQUIRED (OPERATIONS FOR REQUIRED APPROVED SUPERINTEN- (YES, (SHIFT DENT) NO) SUPERVISOR) 2 1.2 RCS Pressure Relief Y 1 3.0A BTRS N 1 5.0A Demin. Makeup Water N 1 5.0B Demin. Makeup Water N 1 17.0A Main & Reheat Steam Y I 19.0A Condenser Cleaning N 1 20.0A FW Heat Ext. Vent &

j Drain N 1 21.0A Condensate & Feed Y 1 26.0A Cire. Water N 1 27.0A Generator Gas N 1 28.1A Turbine Generator N 1 28.2A Main Lube Oil N 1 28.3A Seal Oil (Hydrogen) N i

i 1 28.4A Gland Seal Steam N l

l 1 28.5A Condenser Air Removal N 1 36.5A Plant Lighting Y 1 36.5B Plant Lighting Y l

1 49.0A Solid Waste N 1 49.0B Solid Waste N 1 50.0A Liquid Waste N 1 50.0B Liquid Waste N x

Required to be performed after all refueling outage or major maintenance outage.

C-14 Rev. 8

• FNP-0-AP-16 System Checklist Summary Appendix C

(

PERFORMANCE MODE S0P SYSTEM 2ND COMPLETED DATE REQUIRED REQUIRED VER. &

(OPERATIONS FOR REQUIRED APPROVED SUPERINTEN- (YES, (SHIFT DENT) NO) SUPERVISOR) 1 50.0C Liquid Waste N 1 50.0D Liquid Waste N 1 50.0E Liquid Waste N 1 50.0F Liquid Waste N 1 50.0G Liquid Waste N 1 50.0H Liquid Waste N 1 50.0I Liquid Waste N 1 50.01A WMT N

, 1 50.2A Liquid Waste - Sump Pump N 1 50.3A WE N 1 50.5A TB Sump N 1 50.6A Liquid Waste - Misc.

Sump N 1 51.0A Waste Gas N 1 54.0A SFP Cooling Purification N 1 55.0A AS Boiler N 1 55.0B AS Boiler N 1 56.1A Tech. Support HVAC N 1 57.0A TB HVAC N 1 58.0A Aux. Bldg. HVAC N 1 59.0A Plant Hot Water N 4

O Required to be performed after all refueling outage or major maintenance outage.

C-15 Rev. 8

FNP-0-AP-16 Appendix C f

System Checklist Exceptions SOP system CONDITION CONDITION COMPONENT DESCRIPTION SPECIFIED TO BE REASON Number BY SOP LEFT IN I

L REVIEWED TIME /DATE APPROVED SHIFT SUPERVISOR TIME /DATE C-16 Rev. 8

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

FNP-0-AP-16 '-

TABLE 1 APPENDIX C

'( - ,

TABLE I Component Position Verification During Valve Lineups and Performing Taqqing Operations Orders Normally Closed Manual Valves -

Attempt to close. If valve is in correct closed position no motion will occur.

Normally Open Manual Valves -

Attempt to move handwheel or operator in closed

,, direction. In this case the stem should move indicating the valve is open. Return valve to original position.

Locked closed -

Attempt to move handwheel or operator in the closed direction. If valve is in the correct position no motion will occur. If unable to move the operator because of the locking device, remove the locking device and attempt to move the operator in the closed direction. Re-install the locking device and verify that it is securely locked and in good condition. If the locking device was unlocked a second verification

( of the locking device installation is required. This requirement will be hoted by the individual unlocking the valve in the margin on the appropriate line of the valve check sheet or tagging operations order by writing the words

" LOCK verification required ."

The individual performing the lock verification will initial in the space provided.

Locked Open -

Each person performing a locked valve verification shall remove the locking device. Move handwheel in the closed position enough to verify valve movement. The handwheel or operator should turn

, indicating the valve is open. Return valve to open position. Complete and initial the apprcpriate columns of the valve check sheet or tagging order and reinstall the locking device. Upon completion of all required valve position verifications a separate individual shall then verify proper installation of the locking device i and initial to the right of the person that performed the final valve position verification.

s

, C-17 TCN 13B

FNP-0-AP-16 TABLE 1~

. APPENDIX C

(

Normally Throttled- Visually verify valve stem-is in the specified inter-mediate throttle position. Do not move the valve stem.

Locked Throttled - Verify locking device is securely locked and in good condition. Visually verify that valve stem is in

' the intermediate specified throttle position. Do not move the valve stem.

Tagged Closed - Verify safety tag attached to valve. Attempt to close. If valve is in correct position no motion will occur.

Tagged Open - Verify safety tag attached to valve. Attempt to ,

close only enough to verify valve movement. In this case handwheel or operator should turn indicating

• the valve is open. Return valve to original position.

Inaccessible - Tagged valves inside enclosures, behind barricades or Tagged valves otherwise physically inaccessible may be checked by verifying the associated tagging order is active and properly completed and by verifying the enclosure or barricade is properly secured.

Automatic Valves - i.e. Air Operated, Solenoid Operated and Motor Operated Valves.

The initial check will be performed by local indication of valve or valve actuator. The verification will

( be performed by observation of remote indication.

If the valve is in an inaccessible area the initial check and verification will be performed using remote indication.

Breakers - The initial check will be performed by local observation of the breaker panel for position indication.

The verification will be performed by observation i:

of remote indication if provided. Otherwise the verification will be performed by local observation of the breaker panel for position indication.

Switches - Verify position by direct observation of switch.

(

l C-18 TCN 13B 1

l

FNP-0-AP-16 TABLE 1 -

APPENDIX C ,

(

TABLE II

'[ .

Component Position Verification Required by STP 4

,, Normally Closed

. Manual Valves -

Attempt to close. If valve is in correct closed

! position no motion will occur. <

Normally Open

Manual valves -

Attempt to move handwheel or operatbr in closed j direction. In this case the stem should move

t indicating the valve is open. Return valve to j original position.

i If Locked Closed -

Attempt to move handwheel or operator in the closed

.! direction. If valve is in the correct position i.j no motion will occur. If unable to move the operator

.; because of the locking device, remove the locking device and attempt to move the operator in the i ;' closed direction. Re-install the locking device and verify that it is securely locked.and in good condition. If the locking device was unlocked a second verification of the locking device instal-(

lation is reguired. This requirement will be noted by the individual unlocking the valve in the margin on the appropriate line of the STP by writing the words

" LOCK verification required .

ll The individual performing the lock verification will jj initial in the space provided.

l i.

1 Locked Open -

Each person performing a locked valve verification i shall remove the locking device. Move handwheel in the closed position enough to verify valve movement. The handwheel or operator should turn indicating the valve is open. Return valve to open position. Complete and initial the appropriate columns of the STP and reinstall the locking device. Upon completion of all required valve position verifications a separate individual shall then verify proper install-ation of the locking device and initial to the right of the person that performed the final valve position verification.

Normally Throttled- Visually verify valve stem is in the specified inter-mediate throttle position. Do not move the valve stem.

i e

L l-l l

C-19 TCN 13B r m~,m- e - e, - - . - . w --.---e - e.,,.--e,,,-,..w, e.-- -w ee.w+-e, ,-sr-.----,-ww - r , . --~--w--, ---.-,..--.-we--~-e--r,-wr----=-.aw------.-ee--,------n-~

. .. . . . . . ~ .. . ..

FNP-0-AP-16

'a TABLE 2 APPENDIX C Locked Throttled - Verify locking device is securely locked and in good

-( condition. Visually verify that valve stem is in the intermediate specified throttle posit. 1. Do not move the valve stem.

Tagged Closed - Verify safety tag attached to valve. Attempt to close. If valve is in correct position no motion will occur.

Tagged Open - Verify safety tag attached to valve. Attempt to close only enough to verify valve movement. In this case handwheel or operator should turn indicating the valve is open. Return valve to original position.

Automatic Valves - Verification will be performed by remote indication unless otherwise specified in the STP.

Breakers - Breaker verification may be performed by either remote indication or local observation of breaker panel for position indication.

Switches - Verify position by direct observation of switch.

i

(

I t.

C-20 Rev. 11

-. .. ._ _ _ ~ ~ 11 1,

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