Text

Rev 2 to Station Operating Procedure ADM-0022, Conduct of Operations
	ML20129E953
Person / Time
Site:	River Bend
Issue date:	06/06/1985
From:	; GULF STATES UTILITIES CO.
To:	;
Shared Package
ML20129E940	List: ML20129E953; ML20129E959; ML20129G075; RBG-21-510, Forwards Revs to Station Operating Procedures,Including ADM-0022, Conduct of Operations, AOP-0001, Reactor Scram & GOP-0007, Scram Recovery, in Response to Re Generic Ltr 83-28;
References
	ADM-0022, ADM-22, NUDOCS 8507170127
	Download: ML20129E953 (37)
	v • d • e

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RIVER BEND STATION APPREVAL SHEET STATION OPERATINC PROCEDURES go, ADM-0022 CONDUCT OF OPERATIONS TITLE YES ]

SAFETY RELATED NO NO]

TECHNICAL REVIEW REQUIRED YES X

REV.

PACES INDEP.

TECH.

NO.

ISSUED REVIEW REVIEW APPROVED BY EFFECT SIGNATURE /DATE SIGNATURE /DATE SIGNATURE /DATE DATE M

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I I

l CONDUCT OF OPERATIONS

.l 7N I

l l

TABLE OF CONTENTS l

l 1

-l.

SECTION PAGE NO.

l l

1 l

1.0 PURPOSE 3

l l

2.0 REFERENCES

3 l

l l

l 3.0 ORGANIZATION AND RESPONSIBILITY 4

l

.I A

l 4.0.

I OPERATIONS SHIFT COMPLEMENT, FUNCTIONS AND RESPONSIBLITIES l

l 4.1 Shift, Staffing 11 l

l 4.2 Operations Group Responsibilities 12 l

l 4.3 Notification of Absences 14 l

l 4.4 Personnel Recall 14 l

l 4.5,0ver, time 14 l

l 5

l l

5.0 SHIFT OPERATIONS l

r

.,,,,.f l 5.1 Shift Schedule 15 l

l 5.2 Shift Re!Lef 15 l

'l 5.3 Notificar.on 15 l

l 5.4 Training 16 l

l 5.5 Reactor Scram 16 l

/

5.6 Generator Load Changes 19 l

O, 5.7 Instrumentation and Control 19 l

l 5.8 Operation During Abnormal or Emergency Conditions 19 l

l 5.9 Control Room References 19 l

l 5.10 Housekeeping 20 l

l 5.11 Bypass of Safety Functions and Jumper Control 20 l

l 5.12 Safety Clearance and Tagging 20 l

l 5.13 Control Room Conduct 20 l

l 5.14 Shift / Evolution Briefings 21 l

l 5.15 Fire Brigade 22

'l l

5.16 Key Control 22 l

l 5.17 Component Labeling and Posted Signs 23 l

l 5.18 Radiological Controls 23 l

l~

5.19 Equipment Removal / Return to Service 23 l

l 5.20 Equipment Rotation 24 l

l l

l 6.0 PLANT OPERATING PROCEDURES l

l 6.1 Procedure Compliances 24 l

l 6.2 Procedure Implementation 25 l

~

l 6.3 Procedure Sign-Off List 25 l

l 6.4 System Check Lists 26 l

l 6.5 Periodic Review of Operating Procedures 26 l

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PAGE 1 0F 36 l i

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CONDUCT OF OPERATIONS (Continued)

Ol

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l TABLE OF CONTENTS l

l.

I

'l SECTION PAGE NO.

l 1

1

[.

7.0 SHIFT RECORDS AND LOGS l

~l 7.1 Night Order Book 27 l

.l.

7.2 Standing Orders 27 l

"l:

.7.3 Limiting Conditions for Operation 28 l

1 l

l 8.0 SURVEILLANCE TESTING l

7> l 8.1 Operations Surveillance Tests 29 l

-l

.8.2 Conditional or Off-Normal Surveillance 29 l

1 I

l FIGURES l

l l

l Figure 1 - Operations Section Organization 30 l

- l Figure 2 - Control Room and At-The-Controls Area 31 l

l I

l ENCLOSURES l

.l l

l - Post-Trip Review Check List 32 l

l l - Scram Report 34

~

l.

l - LCO Status Sheet 36 1

g

- vl NOTE l

1 l

l This procedure is intended to provide guidance during normal l

l operation. During the constructio*n and pre-operational phase, l

l those sections that are based on the legal requirements of the l

l-Station Operating License need not be implemented until the l

l issuance of the Station Operating License.

l.

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l

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l 1.0 PURPOSE I

I I

l, The purpose of this procedure is to provide instructions to ensure l'

l that the plant operations are conducted in an safe and effective, I

l consistent manner in accordance with the operating license, plant l

l procedures, and applicable regulatory requirements.

I l

l l

1.1 This procedure establishes the organiz.;tional and individual l

l responsibilities of the Operaticas Section and provides e

I l

.idministrative instructions necoscary for the daily conduct of l

I l

plant operations.

I I

l 1.2 Prior to initial fuel load, the following sections of this I

l procedure will not be applicable and need not be strictly adhered I i

l to:

s

.? :

I

' 8'D' l

l 1

l 1.2.1 5.3, Notification

[

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l 1.2.2 5.5, Reactor Scram l

l l

l 1.2.3 5.6, Generator Load Changes l

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l 1.2.4 5.8, Operation During Abnormal or Emergency Conditions l

l

'I

" * ~

l 1.2.5 5.19. Equipment Return to Service

.I l

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1.2.6 7.3 Limiting Conditions for Operation l

l I

-l 1.2.7 8.0, Surveillance Testing l

s (V) l I

l

2.0 REFERENCES

l I

I i

l 2.1 ADM-0007, Selection, Training,- Qualifica: Lon and Evaluation of l

j l

Plant Staff Personnel.

I l

l l

l 2.2 Gulf States Utilities Operations Quality Assurance Mtnaual l

1 l

(OQAM).

I l

l.

l 2.3 Reg. Guide 1.114 (Rev. 1, 11/76) Guidance on Being Operator At-l i.

l the-Controls of a Nuclear Power Plant.

l l

2.4 NUREG-1000, Vol.1, April 1983.

I I

I l

2.5 RBS FSAR Chapter 13, Conduct of Operations.

l I

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2.6 ADM-0019, Condition Reporting.

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2.7 10CRF55 Operator License.

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2.8 10CFR50, Section 50.54, Conditions of License..

l i

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2.9 Gulf States Utilities Accident Control Manual.

l l

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2.10 G.E. BWR Standard Technical Specifications.

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2.11 INPO Good Practice OP-204 Conduct of Operations.

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l 2.12 OSP-0009, Author's Guide / Control and L'se of E=ergency Operating l g%7-s l

l Procedures.

1 I

l 2.13 RBS General Operatins Procedure GOP-0007, Scram Recovery.

l 1

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2.14 RBS Abnormal Operating Procedure A0P-0001, Reactor Scram.

l l

2.15 AD.'!-0006, Control of Plant Records.

l 1

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'2.16 INPO SOER 82-04.

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2.17 AD21-0031, Temporary Alterations.

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2.18 AD?t-0027, Protective Tagging.

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2.19 ADt!-0037, Equipment Identification and Labeling.

[

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l 2.20 ADt!-0028,?!aintenance Work Requests.

l l

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2.21 AD?l-0003, Development, Control and Use of Procedures.

l l

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2.22 OSP-0002, Shift Relief and Turnover.

l 1

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2.23 OSP-0003, Logs and Records.

I l I

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,l 2.24 IEIN 84-51, Independent Verification.

l($e.

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l 2.25 ADt!-0001, Station Staff Organization, Responsibilities and.

l

[

Authority.

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2.26 0CR-?!-85-009, Operation Respon'se to ANI/:!AELU Inspection.

l 1

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2.27 Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.

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2.28 IEIN 83-27,~ Deliberate Acts Directed Against Plant Equipment.

l

'l I'

7,. _ -

l 2.29 ANSI N18.7-1976, Administrative Controls and Quality Assurance l

for the Operational Phase of Nuclear Power Plants.

l l

3.0 ORGANIZATION AND RESPONSIBILITY l

I l

l 3.1 The Operat. ions Group is comprised of personnel in the following l

l classifications:

l 1

I l

General Operations Supervisor l

l 1

l Assistant Operations Supervisor l

1 l

l Shift Supervisor l

1 1

l Control Operating Foreman l

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l l-l l

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REV - 2 1

PAGE 4 0F 36 l

s l

1 ll l

l l

r 3

n I

l Nuclear Control Oparstars I

l l

,3 g

Nuclear Equipment Operators 1

g IV) l l

l l

Shift Clerkt.

[

l l

The Operations Section is organized as shown in Figure 1.

l 1

l 3.2 Operations Section Position Responsibilities l

l l

1 3.2.1 General Operations Supervisor (GOS) l 1

I l

1.

Plan the overall activities and work of the operating l

l group in cooperation with the other section heads in j

g order to develop an integrated plant operations l

,p g

program; the primary objective being to generate unit j

safety, reliability, and availability.

j g

1 I

l 2.

Provide guidance and direction to supervisors to l

g ensure that the approved operating procedures and l

g practices are followed.

l l

Participate in development of training and retraining, I l

3.

l l

programs for all operating personnel in o:i:r to l

g provide a highly qualified and efficient aperating j

l force and to ensure that qualified replacement l

l personnel are available when vacancies occur.

l l

I p) g 4.

Develop performance standards for personnel under his

[*

i y

supervision as a means of evaluating individual l

l performance. Keep the Assistant Plant Manager j

l Operations informed on the qualifications and

[

g performance of empidyees, and make appropriate l

l recommendations concerning employees showing l

l outstanding or substandard performance.

[

l I

g S.

Promote safe working conditions for employees under l

g his supervision by proper instruction and,the l

g maintenance of tools, equipment, and work areas.

l g

Ensure that employees receive che requird l

l instructions concerning industrie! 34rety.

l 1

I l

6.

Promote good housekeeping.

l l

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7.

Ensure that personnel under hir supervision receive l

l training in appropriate radiokgical protection l

g practices, procedures and ALARA crinciples.

l 1

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8.

Develop and prepare operating orders, grocedures and l

g instructions to ensure safe and reliable operation of l

l equipment.

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9.

Establish and regularly review the required operating l

l logs and records. Supervise the praparation of l-

. l operating records to ensure that they are complete, l.'

l accurate and timely.

l

'p l

l l

10. Insist on-strict adherence to the company and plant l

j.

security provisions and procedures.

l I

I l

11. Coordinate development and implementation of progr..ms l

l and policies that ensure that plant operations ara l

l carried out in a safe and reliable manner.

l l

1 l

12. ?!aintain familiarity with the requirements of all l

l regulatory agencies with regard to plant operations.

l

_ l Prepare, supervise or assure the initiation and l

l preparation of the necessary reports and notifications l l

for these agencies as directed.

l l

13. ?!aintain familiarity with the company-union agreements l' l

and keep current on interpretations. Ensure that they l l-are' administered properly.

l l

'l l

14. Ensure all required operational surveillance testing

,l l

is performed in a timely and proper manner.

l l

1 l

15. Perform such other duties as may be assigned by the.

l l

Plant !!anager.

l l

I

^l

16. Serve as an active member of the Facility Review l$

I l_

Committee (FRC) and Joint Tes: Group (JTG).

1 I

l

17. Implement plant goal.s and objectives. Establish l

l departmental goals and objecttves.

l 1-l l

18. Ensure the plant is operated in accordance with the l

l operating license requirements.

l l

19. Authorize restart following post trip review.

l i

I r

l 3.2.2 Assistant Operations Supervisor (AOS) l 1

I l

1.

Administration of operations section surveillance l

l program.

l l

2.

Initiate changes to operating procedures (per l

l Reference 2.21) which are required due to procedural l

l deficiencies or plant modifications.

l 1

I l

3.

Develop shift schedules to meet manpower and license l

l requirements of the Technical Specifications and I

j.

expected operational activities.

1 I

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N/A ll ADM-0022 REV - 2 l

PAGE 6 0F 36 1

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4.

Review the operations section shift records l

g l

periodically, at least weekly for abnormalities and l

l completeness (Reference 2.26).

l l

k 5.

Assist with coordinatica of fuel handling activities g

with other plant sections.

l l

l 6.

Schedule, coordinate and document on-shift operations l l

g group training as specified in TPP-0007 " Training l

l Program Occutentation".

l I

I i

7.

Initista reports as directed by the 003.

l l

l I

g Initiata notification to operations group and licensed l 8.

l personnel of plant modifications, procedure changes, l

gj g.

and Techncial Specifications revisions that have l

l-operational or safety significance.

[

?

1 I

9.

Review of Operations Section Procedures.

l g

l I

g

10. Assume the responsibilities of the GOS in his absence. l l

l l

NOTE

l While the responsibilities of the AOS are l

l delineated in some detail above, it should l l g

be clearly understood that the list is not l>

'g exhaustive nor does it preclude delegation l

g of functions.

l 1

I 3.2.3 Shift Supervisor (SS) l l

1 I

l 1.

In direct charge of unit operations during startup, l

g power operation and shutdown.

Normally~ acts as th.e

[

l Plant Management representative on site during

[

g backshifts, weekends, and holidays.

l l

1 l

2.

Supervise the Control Operating Foreman to ensure

['

g proper performance of his assigned duties.

l

.o.

l l

l 3.

Ensure shift operations are conducted in accordance j

g with plant procedures an'd operating licenses.

l 1

I g.

4.. Coordinate the activies of Operations, Chemistry, l

l Radiation Protection, Maintenance, Instrument and l

l Control (I&C), Radwaste, and Security groups to l

l accomplish the operating objectives for his shift.

l l

1 l

5.

Notify higher management authority as required by l

g plant reporting and notification requirements.

l l

l 1

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N/A ll ADM-0022 l

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6.

Supervise the on-site operations group functions

[

l required by the Emergency Plan, Radiation Protection l

l Plan, the Security Plan and their respective l

l implementing procedures.

l g..

I I

l 7.

Act as Emergency Director until relieved by higher l

l management authority.

l l

8.

Authorize the removal of equipment and systems from l

l service for maintenance, testing, or cperational l

l activities.

l l

9.

Authorize the return to service of equipment and l

l systems from service for maintenance, testing of l

l operational activities.

l-1 I

l

10. Act as custodian of plant keys assigned to the l

l operations group.

1 I

I l

11. Review shift records for accuracy an'd completeness.

l l

1 l

12. Ensure shift operating crews review changes to l

l operating procedures, plant modifications, and

.'l l

revisions to the Technical Specifications.

l l

1 l

13. Ensure that on-shif t training of personnel is

l l

conducted as scheduled, including required reading.'

l

'l l

l

14. Ensure his shift is properly aanned. Request or

[ (@.

}

initiate callout of personnel as required.

l W;;

l I

l

15. Initiate reports of reactor trips and abnormal l

l activities and rep 6rtable events.

l l

16. Supervise implementation of radioactive waste l

l management program with respect to shift operations.

l l

17. Ensure completion of all surveillance / shift routines l'

l assigned to his shift.

l-equipment and l

1

[

18. Authorize safety tagging of plant l

systems.

l l

1

-l

19. Authorize temporary alteratic:u, jumpers, and lifted

[

l leads.

l l

l-l

20. ?!onitor qualification, mental and physical conditions l

l of operating shif t personnel.

I I

I l

21. Complete Post-Trip Review and Scram Report per

[,

l and 2 for any unplanned Reactor Scrams.

l l

22. Authorizes access in accordance with Plant Security' l

l Procedures.

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N/A ll AD?!-0022 l

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23. Rssponsiblo for maintaining and complying with the l

requirements of the NRC Senior Reactor Operator l

l l

License.

l^

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V

[

24. Insuring a fully manned fire brigade' is present on l

l each shift.

[

l I

l

'3.2.4 Control Operating Foreman (C0F) l l

1 l

1.

Supervise activities assigned by the SS in accordance 1

l with the operating licenses and plant procedaros.

l l

I l

2.

Coordinate the operation of plant equipment and l

l systems.

l.

I I

l 3.

Coordinate safety tagging operations.

l l

l s

l-4.

Coordinate surveillance testing.

l l

I l-5.

Supervise the Nuclear Equipment Operators in the l

l performance of their duties.

l l

1 l

6.

Coordinate the activities of the Nuclear Control l

l Operators with other operations and plant personnel t

[

achieve safe reliable and efficient unit operation.

l l

7.

Review of shift records for compliance with Reference l

l 2.23.

l i

I (mi l

8.

Responsible for maintaining and complying with the l

l requirements of the NRC Senior Reactor Operator l

l License.

I y

1 1

l 9.

Perform the duties of the SS in his absence.

l l

I l

3.2.5 Nuclear Control Operator (NCO) l 1

I l

1.

Responsible to the SS or C0F for operation of all 1-l equipment controlled from the !!ain Control Area.

l l

Operation is interpreted to mean:

l l

I l

a.

Acutal controls manipulation.

l 1

1

-l

,b.

?!onitoring equipment and system parameters.

l 1

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l c.

Documentation of evolutions and significant events l l

related to those systems and/or components l

l controlled from the ?!ain Control Room.

l l

1

-l d.

Initiation or performance of operation actions l

l required by normal operating procedures, Emergency l l

Operating Procedures, Abnormal Operating l

l Procedures, and Alarm Response Procedures l

l applicable to the ?!ain Control Board area.

l A

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N/A ll ADri-0022 l

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ma

o.

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1 l

2.

Recording of Control Room Log readings l

l l-l 3.

Initiate power reductions if plant parameters indic that such actions are required to sustain safe g

l l

+

l operation or prevent equipment damage.

l l

4.

The NCO has the authority and responsibility to shut l

l the reactor down when he determines that reactor l

l safety is in jeopardy or when operating parameters l

l

'(scram settings) are exceeded and automatic. shutdown l

l does not occur (Reference 2.26).

l l

5.

Initiate Emergency Safety System actuation if l

l indications exceed automatic actuation setpoints and l

l actuation has not occurred.

[

l I

l 6.

Initiate holds during plant evolutions that are l

g required to ensure that the evolution does not l

l threaten the stability of the plant, result in l

j equipment damage or violate administrative controls l

l such as System Operating Procedures, Technical l

l Specifications, etc.

[

l l

7.

Responsible for maintaining, and complying with the l

l requirements of NRC Reactor Operators License.

[

l

.' l l

8.

Initiate and Complete Page 1 of Scram Report l

l (Enclosure 2), for any unplanned Reactor Scram.

l

'l j (ih l'

l 9.

Act as Fire Brigade leader p

I I

l NOTE l

l l

l The At-The-Controls Operator shall not under l

g any circumstances leave the "at-the-controls l

l area" (Figure 2) for any reason without l

l obtaining a qualified relief operator.

Prior l

l to assuming responsibility, the Relief l'

l Operator will be informed of any evelutions l

l in progress that might affect the overall l

l status of the plant.

l 1

I l

3.2.6 Nuclear Equipment Operator (NEO) i l

l l

1.

Responsible for performance of assignments associated

[

l with shift operations and fuel handling as directed by l l

the SS.

l l

I l

2.

Duties are normally associated with operation of l

l auxiliary systems and equipment outside the main l

l control room and will include routine checks, data l

l acquisition, and local operation of equipment.

l l

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PAGE 10 0F 36 [

L I

II l

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l'.

l l

l 3.

?!aintain satisfactory progress toward qualification as l

2 Neo.

l l

l

.- (]-

l 3.2.7 Shift Clerk l

l

(_/

l l

g This individual will be required to t(ork.1 rotating shift l

j, schedule with duties as follows:

l l

1 l

1.

Trained to be the communicator for the Eaergency Plan l

l in the control rcom.

l l

I l

2.

Assist the SS in calling out personnal to maintain l

l shift staffing.

l l

3.

!!aintain the Main and Auxiliary Control Room records, l

prints and station manuals.

l l'j' l

l

~"

l l

4.

Maintain overtime list, vacation and sick leave logs.

l

~

j i

g 5.

Transmit shift records to the PPF.

l l

I l

6.

Maintain inventory of chart paper, logs and control l

l roem supplies.

,l l

,I w.

.g 7.

Process and track Maintenance Work Requests.

l 1

1 l

8.

Process and track Technical Specification Surveillanc.e l

~

l Procedures.

l (X

l 1

)

d l-9.

Aid the SS in the maintenance and audit of the Safety l

l Tag Log and Jumper Log.

I l

l OPERATIONS SHIFT C0!!PLEMENT, FUNCTIGNS, AND r.SPONSIBILITIES I

4.0 l

l l

4.1 Shift Staffing l

1 l

l 1 Shift Supervisor (SRO) l l

l M-l 1 Control Operating Foreman (SRO) l

.u-l l

1 l

3 Nuclear Control Operators (RO) l l

l g

i.

l 4 Nuclear Equipment Operators I

l l

I l

4.1.1 A SS with a Senior Reactor Operator license, who is also a l l

member of the station supervisory staff, shall be on site l

l at all times when fuel is in the reactor.

l l

I l

4.1.2 A C0F with a Senior Reactor Operator license shall be in l

l the control room at all times, except when the unit is in l

l a cold shutdown condition. The SS may, from time to time, l l

act as relief for the COF assigned to the control room.

l l

1 l

I D

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ay s

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4.1. 3 A licenssd reactor operator shall bs in the at-the-

' g l

t g

controls area (Figure 2) of the control room at all times l when fuel is in the reactor.

l l

l 1.

Additional licensed operators, the Unit Operator, may l be used for data taking and other "back panel" work.

l 4.1.4 (Non-licensed) operators shall be properly qualified to 4

y support the the activities to which assigned.

l l

I 4.1.5 Periods of core alterations shall include a licensed SRO g

This licensed ll g

to directly supervise the core alterations.

g SRO operator shall have no other concurrent operational l

duties.

g l

,,,]

4.1.6 Deviations in shif t compliment may be approved by the GOS so long as the minimum manning and license requirements of l g

l Technical Specifications are met.

l l

l 4.1.7 g

Additional Operations Section personnel may be. required on l l

shift because of. unusual plant conditions or operational l

needs.

The SS shall obtain the additional personnel as g

Activities requiring additional personnel will l g

necessary.

g not be undertaken until the required personnel are

'll available.

g

,l l

-l i

4.1.8 Personnel who are relieving the shift should review all' l

g.

pertinent operating data back to the time that they had

[

previously been on watch (Referenca 2.26).

1.

Narrative Log Books l

g l

l 2.

Standing Orders l

l l

3.

Tagging Order Log I

g l

l I

4.

Temporary Alteration Log

-l g

l 1-5.

Night Orders l

l l-I 4.2 Operations Group Responsibilities g

l

- l l

4.2.1 The following responsibilities are delineated for l

g l

Operations Section personnel:

.l l

I 1.

The responsibility of the SS shall be to maintain a l

g g

broad perspective of operational conditions affecting l

g the safety of the plant as a matter of highest l

l priority at all times.

l 1

I I

I

- l 1

- l I

I I

ll 1

l I

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PAGE 12 0F 36 l l

l ll l

l l

4 e

-5.-

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..,-r

s e

l 1

l 2.

The SS should not become involved in any single l

l operation that would prevent him from being' fully

(,

l aware of the overall plant status. This applies to l

m (V) l both normal and emergency conditions.

l g

l l

3.

During events that require implementation of Emergency l l

Plan Procedures, the SS is designated Emergency l

l Director until properly relieved.

l l

I l

4.

During accident situations, the COF is in charge of l

l the control room, and shall remain in the control room l l

unless properly relieved. His responsibilities are j

outlined in Reference 2.12.

l l

I l

S.

The SS, C0F, and Plant Operators on shift must be l-

,g l

aware of and responsibile for the plant status at all l

l times.

l 1

I l

6.

All Operations personnel must be alert and remain l

l within their immediate areas of responsibility until l

l properly relieved and be responsible for monitoring l

l the instrumentation and controls located within their l

l areas.

They are responsible for taking timely and l

l-proper actions to ensure safe operation of the l

~

l facility (i.e., actions or activities, including l

l

' failure to take action, related to the facility that. l l l

could have an adverse effect on the health and safety l

l of the public, plant workers, or other individuals).

l

,n l

I t].

l_

7.

Only Licensed Operators or trainees, under the direct l

y l

supervision of Licensed Operators, are permitted to l

l manipulate the controls that directly affect the l

l reactivity or power

1evel of the reactor.

l l

8.

Personnel who have the classification of NCO or NEO l

l shall be considered as qualified personnel to perform l

l independent verification (see Reference 2.24).

l i.

l l*

l 9.

Operations personnel are responsible for the proper l

l exchange of important information and for manning l

l their stations until properly relieved. Shift l

l turnover shall be conducted in accordance with l

l Reference 2.22.

l l

10. Operation of mechanisms and apparatus controls that l

l may directly or indirectly affect the power level or l

l reactivity of the reactor shall only be accomplished l

l with the knowledge and consent of a licensed operator l

l or SS.

l I

I I

I l

I I

I A

l l

V l

l l

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1

-11 1

I I

11. The use of valva parsuadars will be restricted to manually operated valves only. They shall not be used l to manually position motor operated valves (Reference l

2.16).

l

-l 1

4.3 Notification of Absences g

l 4.3.1 Personnel expecting to be late or unable to report for shift duty at the scheduled time shall, at the earliest l

possible time, inform the COF of the situation. The C0F

[

g shall make necessary arrangements for obtaining a replacement.

j l

l 1

4.4 Personnel Recall g

l 1

I 4.4.1 y

The SS has the authority to call out all required l

g personnel, regardless of discipline.

l 1

I 4.5 Overtime g

l l

1 4.5.1 g

Overtime shall not be routinely scheduled to meet the j

g shift crew staffing requirements stated in Section 4.1.

l In the event that overtime must be used, the following l

g g

overtime restrictions apply:

,((

1.

An individual should not be permitted to work more

{

g than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight (excluding shift turnover l

l time).

l 2.

There should be at least a S-hour break between all I

g work periods (shift turnover time is included in this.

g break).

l l

l I

3.

An individual should not be permitted to work more g

j than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24-hour period, nor more than 24 g

hours in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in ll g

l any seven day period (all excluding shift turnover l

g time).

l.

I I

4.

Except during extended shutdown periods, the use of g

l g

overt.ime should be considered on an individual basis l

g and not for the entire staff en a shift.

l l

I l

5.

When circumstances arise that require deviation from l

g[

the above, such deviations may be authorized by the

[

g Plant Manager or his designee. Authorized deviations l

g shall be recorded in the shift supervisor's log.

l 1

I 4.5.2 g

If a Reactor Operator or Senior Reactor Operator has been l

g working more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during periods of extended

.l l

shutdown (i.e., at duties away from the main control j

g board), he shall not be assigned licensed duties without l

least a 12-hour break preceding such an assignments.

at l

l L

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i l

l 5.0 SHIFT OPERATIONS l

l l-l 5.1L. Shift Schedule l

l I

. d l.

5.1.1 The shift schedule shall be devised to provide twenty-four l l

hour coverage of operational activities. The schedule l

l must provide for vacation, sickness and training.

l 1

l l

5.2 Shift Relief l

l I

g 5.2.1 Shift cperating personnel on duty are to remain at their l

l assigned station with full responsibility for their l

l station, until properly relieved. Shift relief shall be a l l

formal evolution with documentation in accordance with l

l Reference 2.22.

l l

I l

5.2.2 As soon as practical after shift turnover the on coming SS l l-will.cour the plant and make contact with each watch l

2-l stander. During this contact, the SS will verify that all l l

watch standers appear to be physically and mentally able l

l to carry out their duties.

l l

I l

5.3 Notification

- l l

l

.l.

5.3.1 Some plant conditions and operating situations are of suc kl l

a nature that it is necessary or prudent to advise the GOB l L

l or designee of the circumstances. The SS must utilize ftis l Judgement and experience in assessing the need for such l

ll notification. The following situations require verbal l'

1 l

notification:

l i.

l l

l 1.

Reactor Scram l

l I

l 2.

?!ajor equipment failure or malfunction l

l-l l

3.

Unexplained reactivity-changes l

I l

l 4.

Loss of off-site power l.

l I

l 5.

Any circumstances requiring unit outage or which l

l affect the ability to meet unit operations schedules.

l 1

'l 6.

Inadvertent Radioactive Liquid or Gaseous Release.

l l

7.

?!ajor personnel injury or radiation overexposure.

l l

l 8.

Accidents occurring on plant property (except minor l

l injury).

l l

1 l

9.

All reportable events.

l l

10. Events requiring immediate (red phone) NRC l

t l

notification.

l l

I O

i l

l 1

ll 1

1 I

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-l PAGE 15 0F 36 l 1

I II I

I I

s

,-ev---

,,----.,,-,,,--~ep.w--a,--m..,,,~-m---

m

-,wemw-,-w.-

,.v.,,r--..-n

.,--,-----r--,

,,-,--r-

I I

l

11. Violations of local, state, or federal pollution l

l (SPDES) regulations.

[

I h#

I l

12. Turbine trip.

l 1

I l

13. Load restrictions or inability to meet load l

l dispatchers requiremants.

l l

5.3.2 The SS shall document in his log when he notifies the GOS, l l

or person on call.

If the GOS or his designee can not be l l

contacted, the on-call Emergency Director should be l

l notified. When cotification is required by Emergency Plan l l

Implementing Procedures, the above requirements are l

l superseded.

l 1

I l

5.4 Training l

1 I

l

?.4.1 It is important that operating personnel be informed in a l l

timely manner of plant modifications, procedure revisions, l license changes that have operational or safety l

l and l

significance. Training will normally be accomplished by l

l one of threc methods:

l l

I l

1.

On-shift formal instruction by Plant Instructors or l

l supervisory personnel.

l l

2.

Covered as part of regularly scheduled license l

retraining.

l 3.

Placed in the required reading file.

l l

I l

5.5 Reactor Scram l

l I

l 5.5.1 When a reactor scram occurs, the SS or C0F will take the l

l following actions:

-l l

I l

1.

Ensure that the plant is placed in a safe condition by l -

l directing that the necessary operations are performed l

l in accordance with Reference 2.14.

I I

I l

5.5.2 Post Trip Review l

1 I

l The following information will be utilized to determine l

l thE direct and indirect causes for the trip:

l l

l 1.

Computer, printout of Sequence of Events (provide l

j details of log) (Process and ERIS).

I l

2.

Computer princout of alarms (observe "first out").

l I

I l

3.

Other NSS Computer printout such as P-1, 00-3, and OD-l l

7.

l 4.' Status lights and annunciator windows.

l l

11 1

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PAGE 16 0F 36 l 1

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I l

~.

l

?

..f~

l The operators are directed not to reset any l

l a.

-l annunciators or status lights until they are l.

l noted.

[

l I

.l 5.

Recorder charts l

I I

The operators are directed to time and date each l

l a.

~

j' chart once per shift and as soon as practical l

l after a trip event.

l 1

l l-5.5.3 The SS is responsible for compiling all information and

[

l making the initial determination of the causa(s) for tha l

.l trip.

l l

1 l

1.

Determine if trip was spurious or.from an parameter l

2,tk

ll.

deviation actual by comparing trip signals to other l

P.'

available instrumentation.

1 I

I l

a.

Complete Post-Trip Review Checklist (Enclosure 1). l 1

I l

2.

If trip was from actual parameter deviation, then l

l -~

determine the reason for the parameter deviation.

l l

a.

Review FSAR Chapter 15 events.

l yv l

l b.

Review / complete applicable AOP's and ARP's.

l l

c.

Consult with Reactor Engineering and maintenance l

l personnel.

l i

I s

l 3.

If_ trip was spurious, than determine what caused the l

l spurious trip and if the tripped channel has been l

l restored to a stabre state.

l l

I l

a.

Operator / Technician error l

l l

"2 l

b.

Power supply problems l

l 1*

' ' y,i.,2 l

c.

Radio interferrence l

9 l-l

[>

l d.

Relay / solid state device failure l

l

~

I

~'

-l 4.

Initiate repairs of the failed component (s) if l

l

.necessary.

l l

1 l

S.

Complete Scram Recovery prerequisites and Scram Report l j'

(Enclosure 2).

I I

I l.

6.

Report all the above to the GOS.

l 1

I l

5.5.4 The.GOS will review all compiled information (either over

(

-l-the phone or in person) and determine if restart is l

l authorized.

l

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A l

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i i

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I I

e

i

=

l l

l 1.

For straight forward causes such as operator error or [

g.

spurious trips he can make the authorization over the [

. phone with no other consultation and be recorded in l g l

the shift supervisors log.

l wp i

I l

2.

For more. complex situations such as actual FSAR

{

l Chapter 15 events the GOS should consult the

]

l following:

l 1

l l

a.

Reactor Engineering Supervisor 1

I I

l b.

Assistant Plant ?!anager-?!aintenance' l

1 I

Appropriate Technical Staff Supervisor l

l c.

l l

l and obtain concurrence from the Plant flanager and the i

g Assistant Plant Ifanager-Operations.

l 1

I l

3.

For complex situations, the GOS, or designee, should

[

g come to the plant to personally review the compiled

[

l information and interview personnel before authorizing l l

re-start.

l

[

.1 l

5.5.5 For any trip that the cause cannot be determined or l[

l corrected, the FRC shall convene to review the data befora l [

l recdemending restart.

1 l

I l

1.

Rostart shall be authorized by the Plant ?!anager, or

[

designee.

[

'l 2.

Plant !!anager should obtain eencurrence from the VP-l l

RBSG.

{

l 1

l 5.5.6 For all events, the Scram Report (Enclosure 2) and Post-

{

l Trip Review Checklist (Enclosure 1) shall be completely

[

g filled out and copies all supporting documentation shall l

l be attached (Recorder Charts, computer printouts, logs).

l I

I,.

l 1.

The Scram Report shall be assigned a sequential number l l

(83-01, etc).

l l

2.

A copy of the scram report shall be retained in the l

l Control Room for 1 year.

l l

3.

The original pai:kage shall be retained as a permanent l

g plant record per reference 2.13 after routing to Tech l

l Staff.

l

.l l

l 4.' Restart is performed in accordance with Reference l

l 2.13.

[

l 1

I I

1 l

l l 43 l

1 QP l

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PAGE 18 0F 36 l l

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l

'l l

5.6 Generator Load Changes l

5.6.1 Generator load changes will normally be requested by the

(...

l System Load Dispatcher. When requested to change load the [

l NCO shall obtain concurrence from the SS and C0F and l

l comply with the Dispatcher's request.

The NCO shall l

l inform the JS when all load changes are complete. The l

l Load Dispatcher shall be notified by the NCO when tite

[

l l

requested load change is completed. Whenever plant l

l conditions dictate a load reduction, the Load Dispatcher l

l will be notified as soon as possible.

l l-I l

5.7 Instrumentation and Control l

1 i

l 5.7.1 Personnel shall not adjust or operate any set points, etc. l q,;.

l inside the control panels or on meter faces unless such l

l action is specifically called for in an approved l

q,'

l-procedure.

l l

5.8 Operation During Abnormal or Emergency Conditions l

l l

5.8.1 When operations are not a's expected, return to a known l

l safe condition.

If conditions warrant, reduce power level l l

as required until the cause of the condition haa been

' l l

determined and the status of the core is known to be in a ; i l

safe condition. Guidelines for equipment use during l

l emergencies is contained in Reference 2.12.

l I

I

_ (e.

l 5.9 Control Room References

[

l 1

l 5.9.1 To assist operations personnel in the conduct of their l

l duties, reference information reitted to plant operation.

l l

safety and administration is perniitted in the control l

l room.

Only controlled, approved documents are to be used l

l to conduct operations. The GOS is responsible for l

l ensuring that the controlled reference information is l

l maintained current. To meet these needs, the controlled l

l reference information listed below will be available in l*

.g l

the control room area.

l l

1.

Plant Operating Procedures l

l

~C I

l 2.

Final Safety Analysis Report l

l I

l 3.

Technical Specifications l

1 l

l 4.

Selected Technical Manuals I

I l

S.

Selected Prints l

- l 1

l 6.

Emergency Plan l

l I

l-7.

Setpoints Document l

l l

O i

~

i l

I il l

I I

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N/A ll ADM-0022 l

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'l PAGE 19 0F 36 l 1'

I ll I

I I

1 m,

-r

.4 y

l I

l 8.

Selected Tables and Curves l

l 1

,h l

9.

Radiation Protection Plan l

g j

l "i@

l 5.10 Housekeeping l

l I

l 5.10.1 The control room will be maintained in a clean and orderly l l

condition in the interest of safe and efficient l

l operations. The responsibility for keeping the control l

l room in this condition is that of all shif t operating l

l personnel. All dusting and cleaning of control consoles, l

l instrument panels, computer consoles, kitchen area, and l

l the orderly storage of books, drawings and records will be l l

performed by shift operating personnel.

It is sometimes l

l advisable not to clean or dust in some areas of the l

l control room during plant power operations because of the l

l hazard of bumping or otherwise moving critical controls.

l l

1-l 5.10.2 The NEOs are responsible for maintaining their watch l

l stations in a neat and orderly fashion.

l l

I l

5.11 Bypass of Safety Functions and Jumper Control l

l 1

[

5.11.1 All activitics involving lifted leads and jumpers will be [ [

' l conducted in accordance with Reference 2.17 with the

, l l

exception of jumpers, mechanical blocks or other comporar)l l

devices specified for us'e by the E0Ps or AOPs during l

l_

performance of these procedures shall be identified,

.l

'l maintained and controlled as follows:

l' 1

I l

1.

Premade and labeled for its incended function.

l I

I l

2.

Retained in locked storage in the control rcom when l

l not in use.

l 1

I l

3.

Controlled by S/S.

l l

l

}

4.

Not used except for its intended function.

l*

l l

l 5.12 Safety Clearance and Tagging i

i I

l 5.12.1 All safety clearance and tagging activities will be l

l conducted in accordance with Reference 2.18.

l I

I l

S.13 Control Room Conduct l

l I

l 5.13.1 Potentially distracting activities in the control room and l l

other watch stations are prohibited (for example: radios, l

l TV, alcohol or drug use, games, horseplay, hobbies and l

l reading that is not job related).

I i

i I

(

.l 5.13.2 Control room access must be limited to those persons on l

l the official access list.

l l

l@

l 1

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PAGE 20 0F 36 l 1

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i

,vi

l l

l 5.13.3 All necessary plant-related technical / administrative l

l control room business must be conducted at a location and l.

l in such a manner that neither licensed control room l

l operator attentiveness nor the professional atmosphere l

l will be comprised.

l l

5.13.4 No unauthorized, uncontrolled notes, pictures, graphs, l

l prints, etc. shall be used as operator aids for the l

l performance of Safety related activities.

l 1

I l

5.13.5 The "At-The-Controls area" will be identified for l

l restricted access, and casual access for non-work related l l

reasons will be prohibited (see Figure 2).

l l

5.13.6 Permission to enter the "At-The-Controls area" for l

g l

personnel other than the shift complement must be obtained 1 l

from the At-The-Controls Operator,-Unit Operator, COF or l

4 l

the SS.

During periods of abnormal-or emergency l

l operations, permission shall be obtained from the SS.

l l

1 l

5.13.7 The SS and the C0F have the authority to restrict access l

l to or remove personnel from the control room during l

l routine and emergency operation.

,l l

1 l

5.13.8 The shift personnel must react / respond to instrument

,l l

Indications and annunciators in accordance with approved,

, l l

procedures unless they have been verified incorrect by l

l other instrumentation and data (Reference 2.26).

I j

5.14 Shift / Evolution Briefings l

l l

l 5.14.1 Briefings shall be conducted for individuals involved in l

l an evolution that is b4ing performed. The detail of the l

l briefing is dependent on the degree of complexity, l

l routineness, logistics, or number of people invcived.

l l

5.14.2 The individual who is to perform the activity is l

l responsible to adequately review the procedure, to fully l'

l understand what he is doing, and to be cognizant of all l

l the limitations, precautions, and requirements.

l l

5.14.3 Because some evolutions may be very complex, occur over an l l

estended period of time, or not be covered by approved l

l pro.cedures, the SS may supply written instructions or l

l checklists.

l l

1 l

l l

I l

l l

I I

I C'

l l

EJ l-1 I

I It I

l I

l N/A l

N/A ll ADM-0022

[

REV - 2 l-PAGE 21 0F 36 l l

l ll l

1 I

e-

.. s l

1 l'

3.14.4 Evolutions involving many individuals, especially from two l l

or more departments or disciplines, may require large l '

l formal briefings or preplanning sessions.

If the 1 56 l

evolution is complex and involves close coordination, the l l

briefing session should include:

I I

I l

1.

A review of the appropriate section of the procedure I

l by key parties.

l l

1 l

2.

Examination of each individual's specific involvement l l

and responsibility.

I I

I l

3.

Discussion of expected results or performance; review l l

of limitations, hold points, emergency action to be I

g l

taken if contingencies arise.

I I

I l

4.

Ensure that everyone understands the interface and l

l communications required.

I I

I l

5.15 Fire Brigade l

I I

l 5.13.1 A brigade of at least 5 members shall be maintained on l

l site at all times. The members of the fire brigade shalli l l

be designated each shift on the control room status board,I l

The fire brigade shall not include those personnel

! lI l

required in the control room nor those personnel required!

l for a safe sliutdown of the plan.

l 5.16 Key Control h

l I

l 5.16.1 A list identifying each key-contcolled item and area l

l should be maintained in the SS's affice. Keys shall be l

l maintained in a locked cabinet, under the control of the l

l SS.

Permission to obtain a controlled key shall only be l

l given by either the SS or COF.

l I

I l

5.16.2 Controlled keys are issued to certain "0N DUTY" operating ~ l l.

l classifications.

Possession of such keys will be l

necessary to perform normal and emergency duties within an l l

area of responsibility. The controlled keys remain on the l l

operator's person during assigned hours of duty and are l

l not permitted to be used by unauthorized individuals.

I I

I

[

5.16.3 A key control log shall be maintained.

Entries shall show l l

the purpose for which a controlled key was required, l

l personnel using it, their badge number,'and time it was l

l removed and returned to the key cabinet.

l I

I l

5.16.4 A physical inventory should be conducted at least semi-l l-annually for locks and keys used for operations (Reference l l

2.26).

I I

I l

I I

I i

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PAGE 22 0F 36 l l

l ll l

I I

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l

-(

l l

5.17 Comoonent Labeling, and Posted Signs l

l 1-fm l

5.17.1 Labeling of components or systems and posting of signs l

(v) l will be performed in accordance with Reference 2.19.

l g

l 5.18 Radiological Controls l

l l

l 5.18.1 All personnel must be continuously alert to the l

l radiological aspects of the work / evolution they are l

l involved in and take appropriate actions to minimize man-l l

rem exposure and to control the generation and spread of l

l radioactive contamination.

l 1

I l

5.18.2 Very high radiation areas shall be locked and prior to l

l entry into these areas Radiation Protection personnel l

P l

shall be contacted. This shall apply except in an l

g, emergency condition.

l 1

I l

5.19 Eguipment Removal / Return to Service l

l l

l 5.19.1 Prior to remcval of equipment from service, the Operations l l

Section will verify the equipment may be removed.

Before~ [

l authorizing the removal for maintenance, testing, or

,l l

operational activities the following will be performed:

l 1

. Verify the equipment or system can be removed from I

l 1.

.l service.

l

[

.l 1

2.

Determine how long it may be removed from service.

l 3.

In the case of a component or system that is required l

l by Technical Speci(ications, attention shall be given l

l to the potentially degraded degree of protection when l

l one subsystem of a redundant safety system has been.

l l

removed from service.

l I

I l

4.

Documencing the removal from service per Reference

[,

l 2.20.

[

l I

l 5.19.2 Following maintenance on or modification to a l

l system / component, the Operations Section is responsible l

l for verifying the operable condition of the l

l system / component to comply with Tech Spec's.

Verification l l

may be accomplished by either special testing or by l

l adherence to surveillance testing.

In the case of the l

l component / system that is not covered by Technical l

l Specifications, a special return to service inspection l

l shall be performed.

Requirements on tests performed shall l l

be logged on the Maintenance Work Reques't per Reference l

l 2.20.

l l

1.

Mechanical coupling

'l l

I l

2.

Blinding flanges installed / removed l

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3.

Electrically connected l

.l 1-g 4.

Area cleanliness

[

g l

W g

5.

Valve alignment l

1 I

l 6.

Proper lubrication l

1 I

g 7.

System integrity l

1 I

l 8.

Hand torquing of remotely operated valves

[

l l

l 9.

System filled and vented

{

l I

l 5.19.3 Components of the Reactor Trip System and other safety l

l related components must (as a minimum) be demonstrated

[

g operable by performance of the applicable Surveillance

[

g

, Test Procedure (s).

l 1

I l

5.20 Equipment Rotation l

1 I

g 5.20.1 The SS or C0F should ensure major plant equipment is l

l rotated monthly when continued plant operation is not

,[

g jeopardized to maintain equipment run times near equal.

l l l

Equipment run times are maintained in the Equipment Run

ll g

Time Log as described in Reference 2.23.

l l

6.0 PLANT OPERATING PROCEDURES

'g lh l

I l

6.1 Procedure Compliance l

1 I

l 6.1.1 Plant equipment shall b,e operated in accordance with l

g written approved procedures.

l 1

I l

6.1.2 If the individual actually performing the activity cannot

[

g or believes he should not follow the procedure governing

[

g that activity as written, he shall place the l

g system / component into a stable and safe condition and l,

l inform the responsible supervisor. The supervisor shall

[

g resolve the discrepancy in the procedure by either:

l I

I g

1.

Determining the methods by which the activity can be.

l l

performed using the procedure as. written and conveying l l

. this to be the individual performing the activity, or I

I I

l 2.

Submitting a procedure change, either temporary or l

l permanent depending on the actual situation.

(No

(

g Further procedural steps shall be accomplished until l

1 l

the procedure change is approved in accordance with l

l Reference 2.21.

(

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~*

l 6.1.3 In the event of an emergency not covered by an approved l

l procedure, operators shall take action so as to minimize l

(q l

personnel injury, damage to the facility, and to protect l

'y l

the health and safety of the public.

l l

6.1.4 It is the policy of the Operations Group that no interlock l l

will be bypassed or defeated from performing its function l

[

unicss it is accomplished in accordance with an approved l

l procedura or work request.

l I

I l

6.2 Procedure Imolementation l

l 1

l 6.2.1 Procedures that control operations where reliance on l

l memory cannot be trusted and where operations must be l

l performed in a specified sequence shall be followed step-l i;$c l

by-step with the procedure in hand. Many procedures will l

l also require signoffs, while others may need to be l

l referred to only occasionally. Routine procedural actions [

l that are frequently performed may not necessitate the use l

l of a procedure.

If there is any doubt as to the l

l procedural action by the individual performing the job, l

l the procedure must be in hand. Entry conditions of

[

l cmergency procedures shall be committed to memory by

, l l

licensed personnel.

l l

l 6.2.2 If an evolution is suspe,nded for an extended period of l.

l l

l time, reverification of the initial, conditions is required [

as determined by the SS.

l

}l l-V l

6.2.3 Controlled copies of appropricte system operating l

l procedures and temporary proceduras shall be available to l

l all Operations Section, personnel for in-plant use at l

l important local / manual stations.

l l

6.3 Procedure Sign-Off List l

l 1

l 6.3.1 Procedure sign-off lists are used as an aid in confirming l,

l the completion of steps in proper sequence as,, required.

l l

In addition, it provides formal documentation of the

[

l completion of critical steps in the procedure and thus l

l aids in any subsequent determination of equipment or l

l system status.

Sign-off lists are executed when specified l l

by the associated procedure or when included as an l

l Intogral part of the procedure. After the completion of l

l each item on the sign-off list, the operator completing l

l the sten initials the item. The operator completing the l

l final item of the sign-off list signs the list to signify l

l its completion'. The sign-off list is then reviewed by the l l

, SS and placed in the control room status file. The l

l previous n-off list is removed from the file and l

l forwarde( o the GOS for distribution per reference 2.15.

l l

1 1

I I

I

("'i l

l O

l l

ll l

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PAGE 25 0F 36 l 1

l ll l

l l

s l

l l

6.4 System Check Lists l

l 1

l 6.4.1 System check lists are used for establishing and l.g, l

confirming the status of equipment and systems. Systems l %1 l

check lists are performed as a prerequisites for system l

l operation and periodically for equipment status l

l verification.

l 1

l l

6.4.2 The _ operator will be instructed to note the position of l

l all components with any discrepancies to be resolved at a l

l later time, OR he will be instructed to reposition l

l components that are found not to be positioned in l

l accordance with the check list.

l l

1 l

6.4.3 When checking a manual valve's position, it must always be l l

operated in the close direction. NEVER CHECK A VALVE BY l

l MOVING IT IN THE OPEN DIRECTION.

l 1

I l

6.4.4 When all check list items are completed, the operator who l

l ccmpletes the final item signs and dates the check list l

l signifying completion. For safety-related and other l

l important systems an independent position verification l

l will then be performed by a second qualified individual.

l l

Each completed check list l

completion and to determine exceptions or unusualis reviewed by the

[ {l l

conditions. The completed check list is inserted in the l l l

control room system status file. The superseded check -

l

'll list is forwarded to the GOS for distribution per l

.h references 2.15.

I l

1 l

6.4.5 Selected valves will be sealed in position to prevent l

l undetected tampering (I,EIN 83-27).

l 1

I l

6.4.6 Independent verification is intended to mean a second l

l check of the position or status of a component or system.

l l

The independent verification will be performed separately l

l without visual or audible contact with the first performer l,

l (Reference 2.24).

{

l l

l 6.5 Periodic Review of Operating Procedures l

l I

l 6.5.1 The following procedure categories are defined as l

l operating procedures:

l l

1.

General Operating Procedures l

1 I

l 2.

System Operating Procedures l

1 I

l 3.

Alarm Response Procedures l

l 1

l 4.

Emergency Operating Procedures l

l 1

l S.

Fuel Handling Procedures l

l l

1 h"-

l l

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I ll l

1 I

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1 4

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6.

Surveillance Test Procedures (Operations Group) l l

I'

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l 7.

Abnor:nal Operating Procedures l

v l

l l

6.5.2 The GOS is responsible for conducting a periodic review of I l

operating procedures per Reference 2.21 with the exception l l

of AOPs and E0Ps, which will be reviewed annually.

l l

Appropriate documentation of this review will be made.

I l

Applicable procedures will be reviewed folicwing an l

l unusual incident such as an accident, an unexpected l

l transient, significant operator error, or major equipment l

l valfunction where inadequate procedural controls l

l ccstributed to the incident. Applicable procedures will l

l be reviewed following modification to a plant syste.

I g

l When procedures are determined to be inadequate through l

W*

l reviev or during use, the procedure will be revised.

l l-I l

6.5.3 Review of Night Orders, Standing Orders and Special Orders l l

shall be done by the GOS or designee on a periodic basis l

l not be exceed 90 days (Reference 2.26).

I I

I l

7.0 -SHIFT RECORDS AND LOGS I

^

l

' I l

Shift records and logs will be maintained and reviewed in accordance i l l

with Reference 2.23.

l l l

l 7.1 Night Order Book

. t I l

s

-1~

I

[\\

~

- l SS will be responsible for impl eenting these orders. The l

_ l 7.1.1 The GOS will from time to time iu.:e night orders, and the I i

l Night Orders Book will ncrmally ba kept in the SS's l

l o f fic.e. All night orders vill be signed and dated by the l

l individual issuing them. Orerators on shift will read and l l

initial night orders c. the shifts following their being l

l written.

l I

I l

7.2 Standing Orders l.

I I

l 7.2.1 A Standing Order will be used as a vehicle for-l l.

disseminating information or non-procedural information, l-l relative to the conduct of operations,. of an intermediate l

l to long-term nature. These memorandums will be serialized l l

for a period of one year (i.e., 83-01, 63-02, etc.).

l l

Ackhowledgement of receipt and understanding will be l

l accomplished via a signature sheet for each Standing l

[

Order.

l l

'l I

l I

I I

l l

1 l

l

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l l

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I I

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REV - 2

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7.3 Limiting Conditions for Operation l

-7.3.1 The COF will initiate a LCO Status Sheet (Enclosure 3) for 1 x

l any LCO which becomes-effective during his shift. This l

l will be. accomplished by filling out Section I of the LCO l

l Status-Sheet with the following information:

I I

I l

1.

Date and time LCO became effective l

1 I

l 2.

Condition initiating LCO l

l 1

l 3.

Reference to applicable section of Technical l

l Specifications for the particular LCO.

l I

I l

4.

Required time for completion of restoration (maximum I

l time allowed by Technical Specifications to continue l

l operatioris in present mode with LCO in effect).

l I

I l

5.

Required action if time exceeded (action required by I

l Technical Specifications if restoration is not made by l

.l time specified in "4" above).

I l-l l

6.

Testing or other actions required by Technical l

l Specifications while LCO in effect (any limitations or I

l plant operation or special surveillance testing).

I I

I l

7.

C0F's signature.

l 7.3.2 Section I of the status sheet will then be reviewed and l

l signed by the SS and filed in the LCO Status Binder under l

l the applicable Operational Condition. The pink copy will l

l be forwarded to the designated individual of the Technical l l

Staff for reporting purposes at the time the LCO is l

l initiated.

Subsequently, for as 'long as the LCO-is in l

l effect, the C0F will insure that the required time for l

l completion of restoration will not be exceeded during his l

l shift. The COF will initial Section II indicating that I-

~

l any testing or actions (specified in Section I) required l

l by Technical Specifications have been completed as l

l applicable to his shift.

l I

I l

7.3.3 When the LCO is no longer in effect, the C0F will complete l l

Section III of the status sheet and forward it to the,SS l

l.,

GOS.

If cummulative inoperative restrictions apply to the l for review. The SS will forward :he status sheet to the l

l l

LCO, the COF will have a copy made for the control room l

l files prior tio forwarding the status sheet to the GOS.

l I

I I

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REV - 2

l PAGE 28 0F 35 l

I I

II I

I I

q *;- p l

l 8.0 S!!RVEILLANCE TESTING g

l l

l-The GOS is responsible for overall performance contro.1 and e

(

coordination of the operations surveillance testing program.

l l

-l l

~8.1 Operations Surveillance Tests l

l

-1 The Operations Section is responsible for the performance,.l1 8.1.1 g

g documentation and initial review of operations j

surveillance tests.

l l

I 8.1.2 The SS/C0F approval will be obtained prior to the l

g l

commencement of any surveillance testing. The performer l

g of the test will record the information required by the l

g

est procedure in the appropriate space and initial each j

ze g

step as it is completed. The performer will sign and date l l

the procedure upon completion of the test.

All items will j be written in ink.

If a step is not completed for any l

l reason, the reason must be recorded on the procedure.

l g

When a test is performed and does not meet the specified l

g acceptance _ criteria, the SS will be notified and

[

g corrective action initiated.

l l

l 8.1.3 The SS/C0F will review all surveillance tests performed o l

.l g

his shif t.for completeness and accuracy and shall so l

g indicate by signing and dating the procedure (s) in the I

l appropriate space.

In addition, he will ensure that an,

l l

'g entry is made on the control room surveillance test l

(Q

=

schedule to document the completion of operations section l

/

g test.

l l

l 8.2 Conditional or Off-Normal Surveillance Requirements g

l l

l 8.2.1 The SS/C0F is responsible for establishing the schedule.of l g

g surveillance testing to comply with Technical

[

_g Specification requirements in ccnditional or off-normal l

l situations.

l, I

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REV - 2

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I I

l FIGURE - 1 l

OPERATIONS GROUP ORGANIZATION 1

I 4

l ef I

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GENERAL I

OPERATIONS I

l-SUPERVISOR l

AsstsTANT g

g OPERATIONS l

St'PERVISOR I

i l

SECRETARY I

l CLERx l

I l

l l

l sutri l

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SUPERVISOR l

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SaIrT l

CLERK i

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CONTROL l

OPERATING l

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I NUCLEAR l

l CONTROL l

OPERATORS I

I I

NectEAR I

l EQUIPMENT l

OPERATORS I

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I l

l 11 I

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' FIGURE - 1 I

PAGE 1 0F 1 ll ADM-0022 l

REV - 2 l

PAGE 30 0F 36 l l

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FIGURE - 2 l

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l FIGURE - 2 l

PAGE 1 0F 1 ll ADBI-0022 l-REV - 2 l

PAGE 31 0F 36 l l

l 11 I

l l

o e -o l-1 I-1 I

I l

ENCLOSURE - 1 l

POST TRIP REVIEW CHECKLIST J

l l

(dQ l

V l tit!E/DATE/# OF SCRA!!

l l

I l _ Review Computer Trip Logs and Sequence-of-Events Logs to determine " Initial Scram l

l Signal".

l l

(Initial Scram Signal) l l

1 l _ Review computer alarm printout and annunciator " hits" to confirm " Initial Scram l

l Signal" l

.l l

.l Review Computer Trip Logs, P-1, OD-3, and OD-7 printouts to determine that all l'

l required automatic Safety-Related actions occurred.

l I

I l

Review Control Room Logbook and Shift Supervisors Logbook to determine if any work l

l was going on that could have generated the condition that generated the scram.

l l

l l _ Review the following recorders.to determine what additional conditions have contri-l l

buted to the scram and if Safety-Related Automatic Action occurred as required.

l l

Reactor Water Level (wide range) (P680) l Reactor Recirc Loop A/B Flw (P680) l APRtf/IRt! (P680) l l

Rx Level / Press A/B (P601) l Standby Service Water Flow (P870) l, l'

l Drywell Pressure (P808)

[

l l

.Contmt Atmos Temp I/II (P808) l Drywell Atmos Temp I/II (P808) h l

Suppression Pool Temp I/II (P808) l Contmt/Drywell Analyzer I/II (P808) l l

ADS SRV Temp ?!onitoring (P614) l l

Off-Gas System After Filter Disch Flow (P845) l l

1 l

l l

Interview Shift Operations personnel before the end of the affected shift, 7.0 l

l determine the cause of the scram, what automatic actions occurred, and what manual l

l actions were taken.

.l 1

l l

Review recorders, control room logs, computer sequence-of-events printout, and

,l l

computer alarm printout for the following parameters to determine if any safety l

]~

systems function was supposed to actuate. Check any that exceeded a trip / actuation l

l setpoint:

l l

RPV Water Level t!ain Condenser Vacuum l

l RPV Pressure Drywell Pressure l

l

!!ain Steam Line Pressure t!ain Steam Line Flow l

l Flain Steam Line Radiation CRD Disch Vol Water Level l

l Steam Pipe Tunnel Temp 1R!i Power Level l

l' APRt! Power Level SRt! Flux l

l Flode Switch Position

?!SIV Position l

l Turbine Control Valve Position.

Turbine Stop Valve Position l

l Reactor Protection Sys Trip Logic 4.16KV Bus Voltage l

l Suppression Pool Level Drywell Sump Flow Rates l

1 I

I I

il I

l l

ENCLOSURE - 1 l

PAGE 1 0F 2 ll AD!i-0022 l

REV - 2 l

PAGE 32 0F 36 1 I

I ll l

l l

m i.

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l i

I I

. I I

' I ENCLOSURE - 1 l

POST TRIP REVIEW CHECKLIST (Continued)

'l

[

l 1

. N. A l

I Log any safety systems functions that were. supposed to actuate, but did not I

1 I

I i

I I

I Shift Supervisor I

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ENCLOSURE - 1 I

PAGE 2 0F 2 ll ADM-0022 I

REV - 2 I

PAGE 33 0F 36 l' l-1 II I

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ENCLOSURE - 2 l

SCRAM REPORT I

I e

I l Date:

Time:

_ Number:

l l

l MODE SWITCH l

REACTOR l

FLOW CONTROL I

l CAUSE l

POSITION l

STATUS l

l l

l l _ Operator Error l

Run l

Critical l

Loop ?!anual j

i l

i I

I l

Testing Error l

Startup l

MWT l Flux Manual l

l l

1 1

I l

Equipment Failure l Refuel l

Subcritical l

Master ?!anual l

l i

I I

I l

Other l

l l

Master Auto l

l l

l 1

l l

l SCRAM TIMES l

l l

STATION STATUS l

(For Monitored CRDS's) l STATION CONDITIONS l

1 I

I I

l Starting-Up l

None Available l Core Flow Lb/Hr l l

l l

Shutting Down l Average Seconds l Reactor Pressure Psig l l

l 1

I l

Changing Power l Fastest Rod l Steam Flow Lb/Hr l l

1 1

I l

Steady State l Time Seconds l Vessel Level I5ches l l

l 1

I l

Surveillance l Slowest Rod l Feedwater Flow Lb/Hgg l

Testing l

l

'y l

Other l Time Seconds l Radwaste Building Vent l

l l

Activity Mr/Hr l l

1 I

I l

l l Plant Exhaust Stack l

l l

l Activity Mr/Hr I I

I i

1 l

l l Fuel Building Vent l

l l

l Activity Mr/Hr'l l

l 1

I l

l l_ Generator Output MWE "__Of f l l

l l Brief Description of Scram:

l l

l l Contributing Conditions:

I l

l l

I l

l l Suspected Cause of Scram:

[

l l

I I

i 1

l Operator At-The-Controls [.

l ENCLOSURE - 2 l

PAGE'l 0F 2 ll ADM-0022 l

REV - 2 1

PAGE 34 0F 36 I I

I II I

I

. g a r,

+

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l e-r l-I

.I

(,.J.s l ENCLOSURE - 2 l

SCRAM REPORT (Continued) l 1

1 I

Vl l

l 1.' Requirements of A0P-0001 " Reactor Scram" have been completed:

l l

I I

I l 2. Determination of the cause of the scram / bases *:

l l

1 I

I

c 1 1

I I

I.

I

..r JS;" l 1.

7, l

Shift Supervisor l

Wl I

"[ l 3. Determination that the cause of the scram has been corrected / bases *:

l l

l

.I

-l 1.

'l I

..I l

1 I

,[

Shift Supervisor l

l l

l 4. Classification of scram:

Spurous Actual Para:ceter Deviation l

ml l

I i

1

'l Shift Supervisor l

l

.I

-l S. Personnel Contacted:

l 1

I I

I l

General Operations Supervisor l l

l

,~

j

.l I

I gi: _l 6' FRC Review required:

Yes No l

-l I

I I

l 7. Authorization to Restart / Concurrence:

l l

I 1

l l~ General Operations FRC Chairman Plant Manager VP-RBNG l

l Supervisor l

I l

l

Attach supporting documentation (copies of records, charts, logs, etc.), use additional l l pages as necessary.

I l

l l

I I

>m I

(J l

11 I

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I l REQUIRED ACTION WHILE LCO IN EFFECT:

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CONTROL OPERATING FOREMAN SHIFT SUPERVISOR GENERAL OPERATIONS

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2.0 REFERENCES

2.0 REFERENCES

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