ML17055B525

Draft Rev 4 to Administrative Procedure AP-4.0, Administration of Operations.

ML17055B525
Person / Time
Site:	Nine Mile Point
Issue date:	03/01/1986
From:	Abbott R, Hansen W, Roman T NIAGARA MOHAWK POWER CORP.
To:
Shared Package
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References
AP-4.0-DRFT, NUDOCS 8604280275
Download: ML17055B525 (40)

Text

Enclosure NINE MILE POINT NUCLEAR STATION ADMINISTRATIVE PROCEDURE PROCEDURE NO. AP-4.0 ADMINISTRATION OF OPERATIONS DATE AND INITIALS APPROVALS SIGNATURES REVISION 3. REVISION 4".REVISION >

Station Superintenden NMPNS Unit 1 T. W. Roman Station Superintendent NMPNS Unit 2 i/R R. B. Abbott General Superintendent Nuclear Generation T. J. Perkins Quality Assurance Concurrence

Manager, Q.A. Nuclear W. A. Hansen Summa of Pa es Revision 4 (Effective PAGE DATE 1,3-10,12-19 January 1986 2,11 March 1986 NIAGARA MOHAWK POWER CORPORATION THIS PROCEDURE NOT TO BE USED AFTER SUBJECT TO PERIODIC REVIEW.

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RP-4. 0 ADMINISTRATION OF OPERATIONS 1.0 PURPOSE This. procedure describes the conduct of operations, the rules for conduct in the control room, the procedures for shift changeover, the procedures for overtime control, the records maintained by operators, and other administrative controls directly the responsibility of the Superintendent Operations. It conforms with the guidelines, provided in ANSI/ANS-3. 2 - 1982 as referenced in the procedures.

2.0 GENERAL SUPVERVISION OF OPERATIONS The Superintendent Operations and Assistant Superintendent Operations provide overall guidance to the day to day shift operation. They are responsible for the preparation of schedules for personnel and the allocation of operational tasks between shifts. Within the guidelines provided by Technical Specifications, the Superintendent Operations is responsible for determining the priorities and schedule for surveillance, maintenance and testing. While he may prepare daily wx'itten instructions to the Station Shift Supervisors his direction of the operating shift should normally be channeled through an Assistant Supervisor Operations.

When the Station Superintendent delegates a portion of the station operation to a licensed senior reactor operator (SRO) other than the Station Shift Supervisor SSS, the division of duties shall be clearly established at that time and a single senior licensed operator such as the Superintendent Operations or another Station Shift Supervisor shall be delegated the overall command function. An ezample is when a SRO with the Station Shift Supervisor title is assigned supervision of the refueling area activities. Personnel shall at all times be kept informed as to who is in charge of their activity.

Under the general direction of the Superintendent Operations, the Supervisor Radwaste Opex'ations shall direct Radwaste Operators and activities related to waste processing, packaging, storage and shipment.

3.0 SHIFT OPERATIONS (Ref: ANS3.2-1982 Section 5.2. 2) 3.1 Adherence to Procedures All operations shall be conducted in accordance with approved, procedures. Any deviation from established procedures which may be deemed necessary to assure the safety of the station or the general public shall be approved and documented as soon as possible in accordance with Technical Specifications 6.8.3.

AP-4. 0 -1 January 1986

3.2 Deviation from Procedures Whenever action is taken which is needed to protect the public health and safety and which may depart from a license or Technical Specification condition, prior approval of a licensed senior operator must be obtained. Ef time permits prior SORC review and notification to the NRC shall be made in accordance with 10CFR 50.72c.

3.3 0 eratin Guidelines When performing operating maneuvers operators shall be guided by redundant or corroborating instrumentation when available and in the absence of other definite operational evidence, they shall always believe instrument indications.

No automatic engineered safety feature shall be manually overridden unless there is sufficient operational or instrumented evidence to show that the system is not performing its intended function and is operating so that continued operation will prolong or produce an unsafe condition.

No motor operated valve shall be electrically backseated nor shall electrical circuits be over-ridden or gumpered to backseat any motor operated valve unless a prior valve operability evaluation has been performed.

All operators , and other personnel authorized to operate and manipulate equipment associated with safty related systems or components shall perform these duties in accordance with approved procedures unless unforseen emergency action is required to prevent injury to personnel or damage to the plant. Zn accordance with 10CFR50.54(i) only licensed operators are permitted to manipulate the controls of the facility, except as provided in 10CFR55.9.

Whenever the safety of the reactor is in immediate )eopardy or when operating parameters exceed any of the reactor protection set points and automatic shutdown should but does not occur; the SRO in charge of the control room, the Chief Shift Operator CSO, or the Nuclear Auxiliary Operator E acting as CSO have the responsibility and authority to order shutdown of the reactor or to personally effect the shutdown.

Restart of a Station Unit following an unscheduled shutdown shall proceed only following the direct order of the Superintendent Operations and by authority of the Station Superintendent.

3.4 Station Shift Su ervisor Conduct The Station Shift Supervisor (SSS) is overall commander of operations on his shift. He shall not relinquish his control of the station except to a Senior Reactor Operator of higher rank or his authorized shift relief. He should avoid becoming personally involved in tKe manipulative tasks or details of operation of any one portion of the plant so that he may retain a comprehensive perspective of general station conditions at all times. Station operations should be AP-4.0 -2 March 1986

3.4 Station Shift Su ervisor Conduct (Cont'd) exercised through the Assistant Station Shift Supervisor (AS ) when the AS is assigned as Control Room Supervisor or through the Chief Shift Operator when there is no other assigned Control Room Supervisor present. (Ref: ANS-3.2-1982 Section 5.2.1.3)

The Station Shift Supervisor or other Senior Reactor Operator (SRO )

shall be required to be in the control room during power operations and when the emergency plan is activated. During power operatiogs the SRO in the control room may be either the SSS or the AS however, when the Emergency Plan is activated the AS becomes the Shift Technical Advisor and cannot be used as the required SRO in the control room. Under emergency plan conditions, the SSS must accordingly immediately return to or remain in the control room until relieved by the oncoming SSS or by a SRO designated by the Superintendent Operations or higher authority. Prom the control room, the SSS shall continuously assess the condition of the Station and provide general direction for all operating actions. Zn an emergency situation, should the Station Shift Supervisor choose to perform manipulative functions to ensure that the plant is in a safe condition he shall coordinate his actions with the Chief Shift Operator. Whenever he determines that the safety of the reactor is in immediate jeopardy or when operating and parameters exceed any of the reactor protection system set points an automatic shutdown should but does not occur, he has the responsibility and the authority to order shutdown of the reactor, or to personally effect the shutdown.

3.5 Assistant Station Shift Su ervisor Conduct When assigned as the SRO in charge of the control room, the Assistant Station Shift Supervisor shall have full charge of the station operations sub)ect to the general supervision of the Station Shift Supervisor. He shall not relinquish his position in the control room except to an authorized Senior Reactor Operator.

When the Emergency Plan i,s activated, the AS shall be relieved of duty as SRO in charge of the control room as soon as practical and shall assume the duties of Shift Technical Advisor. (Ref:

ANS-3.2-1982 section 3.4.3) As such, he wi11 provide the Shift Supervisor as requested with an assessment of station conditions and advise concerning actions to terminate or mitigate the consequences of off normal conditions. As Shift Technical Advisor, he shall perform no other duties unrelated to assessment or diagnosis.

3.6 Chief Shift 0 erator NAOE and 0 erator Conduct The Chief Shift Operator (CSO) is the principal reactor operator.

Unless properly relieved by a qualified SRO or licensed reactor operator (RO), the CSO shall be continuously present in the control room for the duration of his assigned shift unless relieved by the oncoming CSO. His duties and authorities are. described in AP-1.2 Section 2.4. Normally the Nuclear Auxiliary Operator E (NAOE) serves.

as the relief for the CSO. The duties and authorities of the NAOE are described in AP-1.2 Section 4.4 AP-4.0 -3 January 1986

3.6 (Cont'd)

The duties and authorities of other operators are described in AP-1.2 Section 4.5. The Chief Shift Operator, Nuclear Auxiliary Operator E and other operators shall be continuously present at their assigned stations or in the plant until properly relieved by a qualified relief or replacement.

3.7 The Radwaste Auxiliary Operator "D" is responsible for processing and packaging of radioactive waste materials in the Radwaste Facility.

The duties and authorities are described in AP-1.2, Section 4.5.

Their responsibility includes maintaining the control room awareness of activities taking place in the Radwaste Facility at Unit II. They shaLl be responsible to monitor the local conditions to ensure effective operations of the LWS computer.

3.8 Reactor Anal st and Technician Conduct The Reactor Analyst Technicians perform routine and special surveillance on the reactor core and analysis of thermal cycle operation. They work under the general technical direction of the Unit Reactor Analyst Supervisor and perform their duties with the concurrence and permisson of the Station Shift Supervisor and the Chief Shift Operator. During power changing and flux shaping maneuvers,,the technicians prepare and issue rod pattern schedules in accordance with approved procedures and conduct prescribed surveillance of results. The Station Shift Supervisor and operating staff use the results of the Reactor Analyst surveillance to document compliance with Technical Specifications and the reactor fuel warranty requirements.

4.0 CONTROL ROOM PROCEDURE 4.1 ~Sco e This section establishes rules for the conduct of operations within the Control Room.

4.2 Authorization for Ent The number of personnel in the Control Room shall be kept to a minimum, consistent with Station Operations. Members of the Station staff, Technicians, and Shift Operators are allowed free access only in the performance of their duties. Others may enter only by authority of the Station Superintendent or of the Station Shift Supervisor. (Ref: ANS 3.2-1982 Section 5.2.1.5)

AP-4.0 -4 January 1986

4.3 Conduct in the Control Room The Control Room is always under the general supervision of a Niagara Mohawk Power Corporation Station Shift. Supervisor. He shall maintain proper discipline consistent with safe plant operation. The Station Shift Supervisor and in his absence the Assistant Station Shift Supervisor (Control Room Supervisor) oz Chief Shift Operator shall enforce efficient and businesslike conduct in the operation of the Station. All personnel in the Control Room, not actively engaged in the operation in progress, shall be required to refrain fzom loud talking and unnecessarily moving about the room. They shall not be in front of the main operating control panels or computer consoles unless perfozming a required function and shall remain behind a rope barrier when provided. Any time the number of personnel in the Control Room interferes with Station operation, the Station Shift Supervisor and/or the SRO in charge of the control room or Chief Shift Operator shaU. ask the unessential personnel to leave the Control Room. Control Room Operators, while on duty, shall refrain from lengthy engagements in conversations that distract their attention from the control panels and also refrain from reading material not associated with employment or station responsibilities.

4,4 Visitors Normally visitors will not be allowed access to the Control Room. As a vital area, access to the Control Room must be according to AP-3.1 and the Security Plan and Procedures. Visitors must be accompanied by their sponsor. A visitor is defined as anyone not assigned to work at Nine Mile Point.

4.5 0 erator Com lement 4.5.1 The function and composition of the Shift Organization shall be as given in Technical Specifications 6.2.2. Note that the minimum shift crew composition changes with station conditions.

4.5.2 Additional senior licensed operators present on the site may be Niagara Mohawk Station Shift Supervisors or other supervisory personnel. Additional licensed operators may be designated as Auxiliary Operators, or Relief Operators.

4.5.3 Except when responding to alarms or when tending an emergency needing his immediate attention, the Chief Shift Operator, while on duty, shall remain at all times in the azea of the control room which is encompassed by the instrument and control panels surrounding his station and which are visible to him from that station. He shall require a licensed relief when he must travel to the interior of duplex panels, the control room kitchen, lavatory, SSS office, training room or when performing routine operations at other locations which are out of sight of his normal station.

AP-4.0 -5 . January 1986

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4.5. 3 (Cont'd)

With reference to the Technical Specification requirement concerning the presence of a Senior Reactor Operator in the control room, the Station Shift Supervisor or the Assistant Stat1on Shift Supervisor will also be considered to be in the control zoom when located in the glassed in Station Shift Supervisor's Office, kitchen, auxiliary 3 control room, interior of duplex panels, or lavatory at Unit 81 or in the glassed in SSS office or training room at Unit 82. When serving as the operator of the reactor, the SRO on duty must comply with the rules pertaining to the Chief Shift Operatoz.

4.5. 4 Duties of the Station Shift Supervisor, Assistant Stat1on Shift Supervisor (when SRO in charge of the control room) or Chief Shift Operator as referred to in this procedure shall be applicable to senior licensed operators or licensees who are properly assigned for relief to the SSS, AS3, or CSO.

4.5.5 0 eration Outside the Control Room The operation of the station 1s regulated from the Control Room.

There shall be no manipulation of valves, controls, or instrumentation pertaining to reactor operation or station safety without first notifying the Control Room of the condit1ons and receiving approval.

No operations, except in an extreme emergency, which affect the stat1on process systems should be performed without informing the Chief Shift Operator and receiving his prior permission.

4.6 Shift Chan cover Procedure

4. 6.1 To accomplish an efficient shift turnover, the incoming shift shall relieve the shift going off duty in the Control Room, or at the1r point of work. Prior to the Station Shift Supervisor, Assistant Station Shift Supervisor and Chief Shift Operator leaving, the incoming Station Shift Supervisor, Assistant Station Sh1ft Supervisor and Chief Shift Operator must read their log book and sign the bottom of the last page. The signature shall signify that the operator has read all logs since that operator was last on duty.

AP-4.0 -6 January 1986

4. 6.2 In addition to the narrative logs which must be signed on shift transfer, a shift turnover check sheet sha11 be signed by the oncoming SSS, AS , CSO, NAOE as applicable. The check sheet will be prepared and updated as required by the Superintendent 3 Operations. As a minimum it will provide documentation that the

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I following have been reviewed by the oncoming SSS and CSO.

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1) Status of tests or special operations in pzogress. Special valve/switch line-ups.

2) Status and location of jumpers and blocks.

3) Acknowledgement of instructions from the Superintendent 3 Operations.

4) Equipment status as reflected in the Equipment Status Log.

5) A tabulation of key data or special items as required by the Superintendent Operations.

4.6.3 Additional information on the status of the station shall be included in a verbal exchange between the outgoing and oncoming shift personnel.

5.0 LOG BOOKS AND'RECORDS 5.1 Narrative Lo Books The Contol Room Log Book and the Station Shift Supervisor's Log Book shall be maintained in the Control Room until completed. The 3 Radwaste Control Room Log Book shall be maintained in the Radwaste Control Room. After completion, they shall be maintained in the Administrative Office Active Pile until the file is purged and the log books aze forwarded to Central Files foz permanent storage on microfilm.

These log books shall be in duplicate with the original remaining bound in a book and the duplicate routed to the Station Supervisory Staff. Log books, which have been completed and forwarded to Central Piles for microfilm storage, may be removed from their original bindings to accommodate microfilming.

To assist in documentation of authorship and transfer, the following shall be written or stamped at the close of each record:

"The above is a true record of events on the preceding shift SSS, CSO" "I have read and understand the events recorded in this log since I was last on shift SSS, CSO" AP-4.0 -7 January 1986

5.1.1 Control Room Lo Book The Control Room Log Book shall contain all information pertaining to changing core reactivity during all modes of reactor operation, including zod manipulation, orifice modifications, control zod testing, etc.. Also, entries affecting Station outputs, changes in auxiliary equipment, unusual condition, line trips, annunciator signals not recorded on data logger, etc. will be entered in this log. The log shall contain the date and time of all entries and the name of the Chief Shift Operator or alternate on duty. The Control Room log book is to be treated as a legal document subject to being entered in a couzt record. All entries in this log book shall be by the Operator on duty or his Supervisor. No other entries aze authorized. Included with the control room log book is a Fuel Log Book in which specific detailed fuel moves, channel changes, poison curtain moves and in core instrumentation changes are recozded.

5.1.2 Station Shift Su ervisors Book The SSS Log Book shall contain an overall summary of Station Operation including the .name of the Station Shift Supervisor on duty, the Operators and Auxiliary Operators on duty, major equipment not in service or inoperable, and the date and time of all entries. Also note any op'ezator surveillance tests conducted and deviations from acceptance criteria. The log may be written by the Assistant Station Shift Supervisor as an aid to the Station. Shift Supervisor but must be signed and acknowledged by the SSS.

5.1.3 Radwaste Control Room Lo Book The Radwaste Control Room shall maintain a log book in the Radwaste Control Room that shall contain information pertinent to the activities in the Radwaste Facility. The entries shall include the date and time of activities.

5.2 E ui ment Status Lo (Ref: ANS 3.2 1982, Section 5.2.6) log of all station equipment which may limit station output or which must be normally operable as defined in Technical Specifications or which may require cognizance of Quality Control prior to placing in service, shall be. maintained in the Station Shift Supervisor's office whenever the equipment or system is not capable of performing its intended function in its required manner. All equipment which is "not operable" per Technical Specifications shall be tagged at all controlling points with a zed, blue or yellow tag per AP-3.3.1.

AP-4. 0 -8 January 1986

5.2 (Cont'd)

The Status Log shall include the following:

a) Date and time start of equipment ma1function or outage.

b) E.P. Number of principal component.

c) Name of equipment or system and nature of malfunction or failure.

d) 'Applicable Tech. Spec. paragraph, and verification of review.

e) M:W. reduction required.

f) Surveillance tests which must be run while subject equipment is not available per Technical Specifications.

g) Tests or inspections required prior to placing equipment in service.

h) Q.C. verification required prior to placing in service.

i) W.R. number calling for corrective action.

5) Date W.R. completed and equipment ready for service.

When equipment is returned to normal, the record may be purged from the control room. A wall posting or computer printout may be used.

During extended station outages, the Equipment Status Log as here described need not be maintained, however, records shall be maintained on the status of equipment so that documentation available at startup will provide evidence that all systems placed in service have met the quality and Technical Specification requirements for operability.

5.3 Marku s Radiation Work Permits and Work Re uests Log of outstanding Markups and Radiation Work Permits shall be kept in the control room or station shift supervisor area. These shall be maintained current whenever an addition or termination takes place.

At least once each quarter a review of all active markups shall be

~ made to determine continued applicability and need. A physical check of all blue and red markups shall be made at least once per quarter year. (See AP 3.3.1 and 3.3.2)

A file of all current work requests issued with the cognizance of the Station Shift Supervisor shall be maintained in the Shift Supervisor's office. This file should be maintained current so that it contains only the work requests which have been issued but not completed.

5.4 Other records some of which originate in the control room shall be maintained as described in AP-10.1, 10.2.1, and 10.2.2.

AP-4. 0 -9 January 1986

5.5 Documents re uired in the Control Room The following publications shall be in the control room available for the Operators on duty:

a. Administrative Procedures

b. Operating Procedures for the applicable Unit C ~ Special Operating Procedures or Emergency Operating Procedures for the applicable Unit

d. Standing Orders

e. Site Emergency Plan and Procedures

f. Radiation Protection Procedures g ~ Operator Performed Surveillance Procedures

h. Reactor Analyst Procedures for Operators

i. Technical Specifications P & I Drawings For Unit 01 or FSK, ESK, LSK Drawings for Unit f2

k. Electrical drawings sufficient to describe station functions.

These documents shall not be removed from the control room at any time.

6.0 . SUPP&2KNTAL PERSONNEL 6.1 At least three members of the Site Supervisory staff (other than the Station Shift Supervisor on duty) are available on call or present at the site at all times.

6,2 Whenever there is a requirement for additional or replacement operators, maintenance personnel or technicians, the Station Shift Supervisor or an on-call Supervisor has the authority to call in offMuty personnel on a callmut basis.

7.0 OFF NORMAL RESPONSE (Ref: ANS-3.2, Section 5.3.9)

The Site Emergency Plan and Procedures designate actions to be taken in the event of an unplanned release or unplanned potential release of radioactivity from the Site. The object of this section is to outline the actions to be taken which will tend to preclude the occurrence of such an emergency or damage to the reactor core. The administrative provisions for a prolonged emergency and the resolution of an accident which threatens to harm the station or the general public is covered in Section 9.0 7.1 As already stated, operations shall always proceed according to approved procedures. Changes shall be made only in accordance with Technical Specification 6.8.3.

7.2 The Station Superintendent, Supervisor Operations and/or Operations On Call Supervisor shall be also notified in the following circumstances:

7 ~ 2.1 Whenever there is occasion to use a special operating or emergency operating procedure.

AP>>4.0 -10 January 1986

7.2.2 Whenever automatic controls should function but fail to function.

7.2.3 Whenever the reactor is scrammed or there is an unscheduled shutdown of the turbine generator or reactor.

7.2.4 Whenever"'a 'safety system becomes inoperable or fails to function as designed.

7.2.5 Whenever there is an unscheduled shutdown of any ma)or component in the process or safety systems.

7.3 In the event an off normal condit1on is not resolved the provis1ons of Section 9 shall be activated.

7,4 The criteria in which the station superintendent will use for determining the acceptability of restart, after an unscheduled shutdown, shall be as follows:

7.4.1 The plant is shown to be in a safe condition.

7.4.2 The cause of the event is either understood or, after a detailed investigat1on, is considered to have been a spurious trip with a reasonably low potential for reoccurrence.

7.4.3 The need for correct1ve action has been determined and appropriately implemented.

7.4.4 The expected automatic operation of plant safety related systems has been observed.

8.0 OVERTIME PROCEDURES FOR STATION PERSONNEL (Ref ANS-3.2 1982, Section 5.2.1.6 and Technical Specificat1ons 6.2.2)

Each supervisor responsible for implementing and ma1ntaining work schedules shall be responsible for ensuring compliance with the guidelines outlined in th1s section. The ob]ective shall be to have personnel work a normal 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> day, 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> week while the station is operating .

In the event that overtime must be used on temporary basis because of unforseen problems, during extended periods of shutdown for refueling, ma)or ma1ntenance or ma)or plant modifications, the following guidelines for overtime shall be followed: The overtime work of designated members of the station staff who perform safety related functions shall be 11mited. This shall include the on shift overtime work of on duty Station Shift Supervisors, assistant sh1ft supervisors and operators and the regular and scheduled work periods of personnel who are responsible for the correct performance of maintenance, repair, modification or calibration of safety-related structures, systems or components, and who are performing or immediately supervising the performance of such activities involving radiation protection, chemistry, reactor analyst, instrument and control and maintenance personnel.

AP-4.0 -11 MarcH '1986

8.0 (Cont')

a) An individual should not b'e permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight (not including shift turnover time).

b) There should be a break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (which can include shift turnover time) between all work per1ods.

c) An 1ndividual should not work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period excluding shift turnover time.

d) An 1ndividual should not be permitted to work more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period excluding shift turnover time.

e) Except during extended shutdown periods, the use of overtime should be considered on an 1ndividual basis and not for the entire staff on shift.

f) If a reactor operator is required to work in excess of 8 continuous hours, he should be period1cally relieved of primary duties at the control board, such that periods of duty at the board do not exceed about 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at a time.

8. l If circumstances during normal office hours arise requiring deviation from these overtime restrictions, prior approval shall be obtained from the Station Superintendent or General Superintendent before making the assignment. Appropriate documentation as to cause shall be made when confirming restrictions during other than normal office hours. When the Station Superintendent or General Superintendent is not present at the station, the supervisor responsible for implementing the work or the SSS may arrange temporary schedules necessary to meet Technical Specification requirements and/or to ensure safe and zeliable operation and maintenance of the station.

8. 1.1 When work schedules deviate from the restrictions noted in this section such work schedules shall be reported to the Station Superintendent or h1s alternate during his first normal work period following initiat1on of the temporary schedule. The Superintendent shall then signify his approval of the schedule change or direct that alternate action be taken. The attached form, P1gure 1, is provided for facilitating documentation of deviation from the overtime hours restrictions.

If other than the individual's supervisor arranges the exception to the overtime restriction, the supervisor concerned shall be notified as soon as practical by copy of the Deviation from Overtime Form.

Individual supervisozs shall be responsible for maintaining records to substantiate compliance with and authorization for exception to these rules concerning overtime.

Overtime assignents shall be reviewed monthly by the Stat1on Superintendent, Nuclear Generation or designee to assure that excessive hours have not been assigned.

AP-4.0 -12 January 198 6

FIGURE 1 DEVIATION FROM OVERTIME HOURS RESTRICTIONS More than 16 consecutive hours authorized.

2. ~ Less than 8 hour break between work periods.

3. ~ More than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

4. / / More than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 7 day period authorized.

s. Over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> period authorized.

Names Code(1-5) Names Code(1-5)

Reason for Deviation Supervisor Date Temporary Schedule Change Approved: /

Station Superintendent/ / Date General Superintendent / Date Alternate Action Ordered:

Station or General Superintendent Date AP>>4.0 -13 January 1986

9.0 OPERATION WHEN THE EMERGENCY PLAN IS ACTIVATED The NMPNS Site Emergency Plan aad Procedures descxfbe the provisions for safeguarding the station and the public in the event of fire or release of radioactivity other than the normal effluent operations.

The Special Operating Procedures describe operator action in the event of certain postulated abnormal operating condf tfons. This procedure treats administrative provision which will be in place in the event that circumstances will require the application of the Site Emergency Plan 6 Procedures, Special Operating Procedure, Emergency Operating Procedure, or compaxable conditions.

9.1 Personnel Re ortfn Centers 9.1.1 Normal Re ortin Centers Dur1ag normal station operations personnel may be anywhere within the statfoa. However, the foLlowing reporting centers are established and are referred to as normal work headquarters in this procedure:

1. Administrative and Technical Staff Assi ed offices fn the Administration Buildfa

2. Clerfcal Personnel Assigned offices fn the Admin1stratfon Building

3. ~Oarators The Control Room

4. Instrument and Control Technfcfans The Control Room Instrument Shop

5. Radfatfon Protection Technic1ans The Radfat1on Protectfoa Office in the Administration Building

6. Chemist and Radiochemist Technicians The Chemfstry Lab office fn the Turbine Bu11d1ng

7. Mechanical and Electrical Maintenance Personnel The Maintenance Sho fn the Administration Buildfn

8. Reactor Anal st Technicians Assi ed office s ace fn the Administration Buildin

9. Stores Personnel Storeroom office AP-4.0 -14 January 1986

9.1.2 During an incident for which this procedure may be applicable, the following Emergency Response centers have been established.

9.1.2.1 Control Room During normal station operation and during events in the Unusual Event category, which have a low potenital for increasing risk to public safety, the station is operated and managed from the Control Room by the Station Shift Supervisor (SSS). During other categories of events, advice and management direction will come from the emergency response facilities (TSC and EOF), but station manipulations will continue to be performed from the Control Room.

The Control Room is equipped with readouts and controls for major process and safeguards systems. A portion of this system is designated as the Safety Parameter Display System whose purpose is to I3 provide a display of plant parameters from which the safety status of station operation may be assessed in the Control Room and TSC. Zn addition, zeadouts and assessment aids interrelated with meteorological and radiological dose calculation data are also provided, as well as access to emergency communications systems.

9.1.2.2 Technical Su ort Center The Technical Support Center is located in the north east corner of the Administration Building elevation 248 to be equa11y accessible to both the Unit 1 and the Unit 2 control rooms.

9.1.2.3 0 erations Su ort Center The Operations Support Center is a facility from which personnel and equipment necessary for the support of emergency operations can be dispatched. The Lunch Room areas in the Administration Building at elevation 261 and 277 feet, which have sufficient space to assemble station personnel, aze designated as the OSC. There same areas are also designated as the primary assembly area so that after personnel assemble and are accounted for, they are immediately available for assignment.

The Operations Support Center elevation 261 has communications equipment, with which to control OSC related activities, either installed or readily available. Personnel dispatching from the elev.

277 center shall be controlled from the elevation 261 location. The First Aid Room and Emergency Cabinets with supplies and equipment for various teams are near the 261 foot elevation Lunch Room.

AP-4. 0 -15 January 1986

9.1.2.4 Emer enc 0 erations Facilit (EOF)

The Nuclear Training Facility is designated as the Near Site Emergency Operations Facility. This facility is used for continued evaluation and coordination of all activities related to an emergency having potential environmental consequences. Space is provided so that Federal, State and local response agencies can manage their activities from this location. Space will be provided for a limited number of the news media at appropriate times, such as media briefings. Recovery operations will also be handled at this facility. Appropriate Communications and and Emergency Operations kit with necessary maps and clerical supplies are provided to aid the EOF while it performs its function.

The EOF will be fully staffed by appropriate members of the Emergency Response/Recovery Staff as detailed in Section 9 of the NMPNS Site Emergency Plan.

9.1.2.5 Alternate (Offsite) Emer enc 0 erations Facilit 4

The Niagara Mohawk Service Center on Howard Rd in the Town of Volney, which is nozmally an electrical maintenance service dispatch center, is designated as the Alternate Emergency Operations Facility. This facility is located 12 miles from the site and generally is in the upwind direction. In the event that the TSC and/or the near site EOF is deemed to be inappropriate for occupancy, the" offsite facility will be activated. The alternate EOF serves the same function as the EOF and has essentially the same emergency equipment and communication systems.

9.2 Procedure 9.2.1 Events Re uiri De artuze from Normal 0 erations Five classes of events are described in the Site Emergency Plan and Procedures which require a departure from normal station operations.

They aze:

Operational event Unusual Event Alert Site Area Emergency General Emergency The first class of events is not categorized as an emergency but should be subject to management review. The others require notification and response according to the Site Emergency Plan and its implementing procedures.

AP-4. 0 -16 January 1986

9,2.2 Announcements and Notifications I

9.2.2.1 Operational Event This emergency class may or may not result in the sounding of the station or fire alarm depending upon the requirements for response as determined by the Station Shift Supervisor. Once a station alarm or PA, announcement is made, the only persons who may enter the control room without specific summons are personnel who have specific duties in the control room, the members of SORC, or the emergency response personnel identified in the Site Emergency Procedure No. 13.

9.2.2.2 Unusual Event Announcements and notifications for these events are provided in Site Emergency Action Procedure No. 1. The initial response and staffing of the Emergency Facilities is described in Site Emergency Implementing Procedure No. 13. Personnel accountability and evacuation procedures are covered in Site Emergency Implementing Procedure No. 5 and No. 19.

9.2.3 Personnel Reassi ents During station and site emergencies station management personnel and technical support personnel from off site are assigned special duties. These individuals, with their designated titles, are described in detail in Site Emergency Implementing Procedure No. 13 and summarized in Figure '1. These position titles are used throughout the Emergency Plan and Procedures when assigning appropriate responsibilities during an emergency.

9.2.4 Conduct of 0 erations 9.2.4.1 The nine sections of the Emergency Plans and the 26 Emergency Plan Implementing Procedures (EPP) describe the conduct of emergency operations.

9.2.4. 2 Initially the Station Shift Supervisor assumes the role of the NHPNS Emergency Director, and continues in that capacity until relieved by the General Superintendent Nuclear Generation or his designated alternate.

9.2.4.3 The NMPNS Emergency Director performs assessment actions relative to the situation in accordance with Section 6.0 of the Site Emergency Plan and- appropriate Emergency Plan ,Implementing Procedures. This assessment and concurrent classification of the emergency are based on available information such as the initial verbal communication, Control Room instrumentation readings, dose pro )ection data, follow-up monitoring data and other supportive information. The assessment is updated as new information becomes available, with appropriate changes in the emergency classification being made, if necessary.

AP-4.0 -17 January 1986

0 G

9.2.4.4 Director ensures that both onsite and offsite emergency The Emergency pex'sonnel, organizations, and response centers are alerted and, if necessary, activated. (See Figures 1 and 2 for Emergency Response Organizations.) Offsite notification methods for various emergency conditions are discussed in Section 6.0 of the Site Emergency Plan and are summarized as follows:

a. Requests fox'ssistance, such as fire fighting and medical transportation, from local offsite support groups may be made by telephone or radio directly to the individual group(s).

b. Notification to offsite authorities of an emergency is made primarily to assure that those agencies are cognizant of the details of events which may arouse public concern. Thus, the authorities will be informed on a timely basis. These notifications will be made to the OCOEP, NYDOH and NRC.

C~ Notification to the above listed offsite authorities will commence immediately upon the declaration of an Unusual Event, an Alert, a Site Area Emergency or a General Emergency. Section 4.0 of the Site Plan describes the time limitations between the first indication of an event and declaration of the applicable emergency condition.

9.2.4.5 Onsite corrective actions may proceed concurrently with assessment, and are described in detail for situations within each emergency classification in the Emergency Plan Implementing Proceduxes and in applicable Special Operating Procedures.

9.2.4.6 Onsite protective actions, including cx'iteria and methods, are described in Section 6.0 of the Site Emergency Plan, The primary protective action is evacuation of nonessential personnel and the use of protective equipment and clothing for those personnel who are required to perform emergency activities. Provision is made for evacuating increasingly larger areas commensurate with existing conditions, summarized as follows:

a. A Station Evacuation may be implemented by the Emergency Director if the affected area is or may be the area within the NMPNS Unit 1 security fence.

b. A Site Evacuation may be implemented by the Emergency Director if the affected security fence.

area is or may be beyond the NMPNS Unit 1 AP-4. 0 -18 January 1986

9.2.4.7 Offsite protective actions are addressed in Section 6.6.2 of the Site Emergency Plan, Such actions are primarily the responsibility of State and local emergency organizations, but may be based on recommendations made by the Emergency Diector. These offsite organizations may invoke any emergency actions which they deem appropriate based on their assessment of the situation, with respect to the level of radioactivity released and the projected offsite dose. The key element which ensures compatibility of this Plan and offsite emergency plans is the provision for initial notification and continuing status reports to the State and local agencies, and for conveying current release and dose projection information.

description of the communications systems 'which assure the capability for prompt notification and continuing transmittal of vital information is contained in Section 7.2 of the Site Emergency Plan.

9.3 Termination of Zmer enc The Corporate Emergency Director/Recovery Manager will determine when the emergency phase has ended. Some of the criteria for making this determination are discussed in Section 9.1.3 of the Site Emergency Plan. The determination will result from )oint evaluations made by the Corporate Emergency Director/Recovery Manager, the Emergency Director, the State and County emergency response agencies and other involved agencies.

9.4 Recovere Provisions for establishing a Recovery Organization which with the scope and magnitude of the emergency condition is'ommensurate are discussed in Section 9 of the Site Zmergency Plan.

This organization is comprised of two major groups: Functional and Support. The Functional Group is essentially comprised of the normal station organization and would be responsible for the development and implementation of plans and procedures necessary to support long-term emergency response and recovery operations. The Support Group is comprised essentially of corporate support personnel and would provide necessary administration and engineering support.

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AP-4. 0 -19 January 1986