ML20077L642

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Procedure Generation Package for Emergency Operating Procedures
ML20077L642
Person / Time
Site: Oyster Creek
Issue date: 07/29/1983
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20077L630 List:
References
RTR-NUREG-0737, RTR-NUREG-737 PROC-830729, NUDOCS 8308090501
Download: ML20077L642 (77)
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l OYSTER CREEK NUCLEAR GENERATING STATION PROCEDURE GENERATION PACKAGE

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B300090501 830729 ,

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0YSTER CREEK -

l VERIFICATION AND

' VALIDATION PROGRAM FOR E0P's t

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,_, 0YSTER CREEK NUCLEAR GENERATING STATION VERIFICATION PROCEDURE FOR EMERGENCY OPERATING PROCEDURES t-PURPOSE The purpose of this procedure is to identify the phases of the verification process, how they will be performed and by whom, and what source ducuments will be used. This procedure shall be utilized for initial EOF approval and for any revisions made in the future. .

t DEFINITIONS Emeraency Operating Procedurus (HOPS) - Plant procuduru's directing operatur actions necessary to mitigate the consequences of transients und acciduuts that cause plant parameters to exceed reactor protection system setpoints, engineered safety features s&tpoints, or other appropriate technical limits.

Emeraency Operatina Procedure Guidelines (EPCs) - Guidelines that providu sound technical bases for the development of EOPs.

E0P Source Documents - Fundamental documents or records upon which EDPs are based.

ROP Technical Accuracy -

Proper incorporation of generic und/or plant-specific technical information from E0P source documents and plant hardware into the EOPs..

IOP Verification - The evaluation performed to confirm the written cor-rectness of the E0Ps and to ensure that the generic and/or plant specific e technical aspects have been properly incorporated.

EOP Writtah Correctness - Proper incorporation uf information from thu l Horison writers guide for E0Ps and other appropriate administrative policies into the E0Ps.

Symptoms - Displayed plant characteristics which directly or indiruccly j indicate plant status. ,

r E0P SOURCE DOCUMENTS The designated E0P Source Documents to be used in completing the Verifica-tion Checklist for Written Correctness (Attachment 1) and the Verification Checklist for Technical Accuracy (Attachment 2) are:

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Page 2 Verification Checklist for Written Correctness s.

1. Writer's Guide For Emergency Operating Procedures (INPO)
2. Oyster Creek Nuclear Station Emergency Operating Procedure Writer's Guide Verification Checklist for Technical Accuracy
3. Oyster Creek Nuclear Station Symptom Based Emergancy Operating Procedure Technical Guidelines
4. Oyster Creek Nuclear Generating Station Technical Specifications
5. Memo, OC Emergency Operating Procedures: Plant Unique Action Points and Limit Curves, SAPC 043, March 7, 1983

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The source document and section used should be referenced on the Discrepancy Sheet (Attachment 3).

RESPONSIBILITIES The following personnel are responsible for some portion of the EOP Verifi-cation Process:

Oyster Creek Director of Operations J

  • Final approval of all E0P's and revisions.

Systems Enaineerinz

  • Overall responsibility of the E0P Verification Process.
  • Determine when EOF verification is needed and its scope.
  • Manage the technical accuracy evaluation portion of the process,
  • Approve the technical content of all E0P's and revisions.

Special Engineerina Projects

  • Determine when E0P verification is needed and its scope.
  • Approve the verification resolutions.

Human Factors

  • Manage the written correctness evaluation portion of the process.

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, [ EOF VERIFICATION PROCESS After personnel have been selected to perform the evaluation and the appro-priate E0P Source Documents have been gathered, the process can be divided into three phases: verification, resolution, and documentation.

  • During the verification phase, tha evaluators identify discrepancies using the Verification Checklist for Written Correctness and the Verification Checklist for Technical Accuracy. The Discrepancy Sheet is used for this purpose. This is accomplished by comparison of the E0P's to their source documents. Justifying remarks by the EOP writer shall be provided for the discrepancies noted by the evaluator. Concurrently, operators who have been trained on the new E0P's, participate in the verification phase by com-pleting Operator Feedback Sheets (Attachment 4). Their comments ard used by the evaluators in filling out Discrepancy Sheets.

After the EOP writer has provided justifying remarks, potential resolutions should be developed, the choices reviewed, and one of them selected, ap-proved, and incorporated. The resolution phase requires input from super-visory personnel who have the responsibility of final approval of the EOP.

They will review the evalustor's comments and resolve any conflicts between the writer's and evaluator's comments. Resolutions will then be forwarded to the Oyster Creek Director of Operations for review and approval. EOP's and/or source documents will be modified to reflect the approved resolutions under the direction of the Oyster Creek Director of Operations.

The identification of discrepa'acies and the resolution for each discrepancy should be documented fully, using the Discrepancy Sheet provided for this purpose. This documentation will aid in identifying future discrepancies, resolutions thereof, and incorporating the appropriate changes in the E0P's and/or EOP Source Document.

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Page 4 rx EOP VALIDATION PROCESS t-To determine if the operator can effectively use the E0P's during emergency conditions, the table-top, walkthrough, and simulator validation methods will be used. Walkthroughs at the Oyster Creek Control Room Mockup will be conducted. Scenarios will be devised to challenge the Symptom-ori3nted procedures. Walkthroughs of the new Oyster Creek E0P's will include assessment of whether:

(1) The required controls and indications are available to the operator and can be interpreted as called for in the E0P's.

(2) The symptoms described and the guidance provided are sufficient to allow the operator to respond to the spectrum of plant upsets which might confront him.

(3) There are any evolutions spelled out for which time may be a control-ling factor - is it reasonable to expect the operator (s) to act in the time required.

(4) There are any evolutions for which being.in more than one procedure at a time may be a controlling factor - is it reasonable to expect the

. operator (s) to be in more than one ti rocedure at a time.

( [ The new E0P's will also be exercised at the simulator by each group of operators that pass through the training program. A checklist will be employed for the walkthrough portion (Attachment 5) and for the simulator portion (Attachment 6).

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. ATTACHMENT 1 will be provided at a later date specified by the cover letter.

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ATTACHMENT 2 Page 1 0

-- VERIFICATION CHECKLIST a.

For Technical Accuracy The following four areas will be evaluated using the Oyster Creek Nuclear Station Symptom Based Emergency Operating Procedure Technical Guidelines:

- Entry Conditions or Symptoms Information

- Instruction Step, Caution or Note Information

- Quantitative Information .

- Plant Hardware Information Goal of Evaluation: To determine if the entry conditions or symptoms used for identifying when to use the E0P are correct and not excessive.

ENTRY CONDITIONS OR SYMPTOMS INFORMATION

- Are the entry conditions listed correct in s11 cases?

l ,_, - Are they unique entry conditions?

l L-g Goal of Evaluation: To determine if the content and arrangement of EOP instructional steps, cautions, and notes are supported by information from the Oyster Creek Technical Guidelines.

INSTRUCTION STEP, CAUTION OR NOTE INFORMATION

- Do EOP steps, cautions and notes reflect the intent of the Technical Guidelines?

- By content?

- By order?

- Are any differences documented and explained?

- Are limits used supported by Technical Guidelines?

- Are correct plant-specific systems, instrumentation, controls and indications called out in the E0Ps?

l - Do any licensing commitments have to be modified? (Please document l including discrepancy and when and how it will be addressed.)

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ATTACIDENT 2 Page 2 Goal of Evaluation: To determine if calculated or translated quantitative a. .

1 values used in the EOPs are correct. l QUANTITATIVE INFORMATION Do the quantitative values, including limits, used in the E0Ps comply with '

the Technical Guidelines?

Where values used are not prescribed in the Technical Guidelines, are they computed accurately?

Where values are given in the Technical Guidelines but not utilized in the E0Ps, is it documented and explained?

When the EOP requires the operator to perform a calculation, is sufficient information provided for the operator to perform the calculation easily and is adequate space provided?

Goal of Evaluation: To determine if the hardware specified in the EOP is available for operator use.

PLANT HARDWARE INFORMATION 5 -

Is the plant hardware specified in the EOP available for operator use, incliiding all equipment, controls, indication and instrumentation?

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ATTACIOtENT 3 Discrepancy Sheet Number a.

1 Verification Checklist:

Procedure and Step Number:

Discrepancy:

Evaluator:

Date:

Resolution:

Approved: Yes No (circle one)

Supervisor:

Date:

Operations Supervisor:

Date:

Resolution Incorporated by:

Date:

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OERATOR FEED 8AO< SMETS - Page i t-l

1. Are entry conditions unique and indicative of when the precedure should l be useo? l e

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OPERATOR FEEDBACK SifETS - Page 2

3. Is the numbering -scheme used easy to understand and follow't I

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Are if necessary? operator actions accurately and specifically stated? And to what, i

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6. Are limits and alarm setpoints stated?

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Are cautions placed before the steps to which they upply? -

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Are cautions brief and clear?

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OPERATOR FEED 8ACK SifETS - Page 5 I O 9. Are notes placed before the steps to which they apply? .~

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10. Are notes brief and clear?

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OPERATOR FEEDSACX SFEETS - Page 6 11.

Is information presented in charts, tables, graphs, und figured bu~sytu understand?

Does it aid in properly carrying out the precedure?

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Are conditional statements used where appropriate?

Is it clear from the boxed apply?

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OPERATOR FEED 8ACK SFEETS - Page 7 O 13. Are the conditional statements clear, concise, and consistent witl8b'e rest of the procedure?

14 When more than one procedure or parts of a procedure should be followed at the same time, is this easy to do? How?

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OPERATOR FEEDBACK SHi.ETS - Page 8 15.

Is it clear procedure? if and when the operator should return to the first b  !

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Is there any way understandable, or the easier procedures to follow? can be improved to be more, accu 1

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A ATTACBMENT 5

() NALKTHROUGH CHECKLIST EMERGENCY OPERATING PROCEDURES ENTRY 0. Are the conditions for entering the CONDITIONS procedures clearly and unambiguously displayed?

i NOMENCLATURE 1. Is the nomenclature -- names or

, abbreviations-clear, consistent and unambiguous?

DISPLAY 2. Are the displays which should be IDCNTIFICATION used to read a refer.enced variable obvious? If there are disagree-ments, is it obvious what course the operator should follow?

DISPLAY 3. Can the variable be read on the O UNITS reference display with the required precision? In the same units as in the procedure? With reference to the same point?

DISPLAY 4. Is long term trend required of the TREND display? If so, is the display capable of providing it?

CONTROL 5. Is the control action required of ACTIONS the operator clearly spelled out?

l Is the control or controls to be used in taking this action obvious? .

Is the consequence of the control action obvious?

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ATTACHMENT 5 (continued)

WALKTHROUGH CHECKLIST EMERGENCY OPERATING PROCEDURES EXIT 6. Exit Conditions: Are the CONDITIONS conditions which take the operator back to normal procedures clear?

COMPLICATIONS 7. Simultaneous abnormal occurrences:

Are these effectively treated, assuming EOPs come first?

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( SIMULATOR TRAINING EXERCISE CHECKLIST, EMERGENCY OPERATING PROCEDURES

1. What -- instruments

-- controls are operators using to respond to scenario? Are these present at suitable locations for timely response at OysterCreek?

2. Are there -- instruments controls that the operator ,needs which are missing from the simulator? Are they missing at Oyster Creek?
3. In the scenarios exercised, would a division of responsibility along these lines works (a) level / inventory fm. (b) pressure / power (c) backup CRO-power (if no scram),

otherwise responsibility containment control and ex-control room (d) SRO - Supervision of Oyster Creek operators --

imposition of interactive conditions on CRO's --

backup to CROs.

! (e) STA, -- backup to SRO in keeping track of where they are.

4.

What the scenarios?was the most time-constrained control action (s) in Was it effectively handled?

5. Was the SRO (exercise leader) able to keep track of where the team was in eact procedure? Was each oper-ator able to keep track of where he was? How effec-tively were " hooks" imposed?

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.l OYSTER CREEK TRAINING PROGRAM ,

FOR SYMPTOM BASED 5

EMERGENCY OPERATING PROCEDURE O

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O Course 418.5 Symptom Based Emergency Operating Procedures Course

Title:

Symptom Based Emergency Operating Procedures Course Number: 418.5 I

Training Criteria:

This course, a part of the 1983 License Requal and STA Requal Programs, is designed to ensure that each Licensed Operator, Senior Operator, and Shift Technical Advisor is cognizant of the new Symptom Based Emergency Operating Procedures (EOP) including when entry or exit to each is required and how to utilize them effectively.

Behavioral Learning Objectives: At the completion of this training, the Licensed Operator or STA shall be able to:

1 (1) Given simulated plant parameters (alarms and indications},

correctly determine when the EOP's should be entered and which procedure (s) to follow.

(2) Given any EOP precaution, state the basis and briefly explain the intent of that caution.

(3) Given any of the EOP parameter limit curves or graphs and stated parametric conditions, correctly determine whether a limit has been exceeded and the potential consequences if correct action is not taken.

(4) On a Non-Specific Plant Simulator, demonstrate the ability to maintain adequate core cooling, shut down the reactor, -

and cool down the RPV to cold shutdown as a member of a Control Room Team.

(5) On a Non-Specific Plant Simulator, demonstrate the ability to maintain primary containment integrity during analyzed plant accident conditions as a member of a Control Room Team.

(6) On a Non-Specific Plant Simulator, demonstrate the ability to restore and maintain control of reactor core reactivity 1during analyzed plant accident conditions as a member of a

( _.) Control Room Team.

() Note: Measurement of Behavioral Learning Objectives (4), (5),

-and (6) may be performed on a Non-Specific Plant Simulator.

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j Evaluation Criteria:

(1) Satisfactory achievement of Behavioral Learning Objectives 4

(1) , .(2) , and (3) shall be demonstrated by obtaining a score of at least 80% on a written examination.

(2) Satisfactory achievement of Behavioral Learning Objectives (4), (5), and (6) shall be demonstrated by each Control Room Team member by correct performance in real' times with no operator errors that prevent (in and of themselves) meeting the objectives.

Prerequisites:

(1). Course participants are enrolled in (and are actively participating in) their respective Requalification Programs of which this course is but a..part.

(2) A complete set of Symptom Ba' sed Emergency Operating Procedures are available.

(3) Full scope BNR Simulator is available including a qualified Simulator Instructor with demonstrated proficiency on Oyster Creek Symptom Based Emergency~

Operating Procedures.

1 Note: BWR Simulator need not be plant specific but must be

approved for Oyster Creek Operator Training.

Instructor Qualifications:  :

(1) Demonstrated expertise in Symptom Based Emergency Operating Procedures.

(2) SRO Licensed or Certified (or SRO Licensed individual present during presentations).

(3) Instructor certified by GPUN training.

Training Methods:

i l (1) Formal classroom instruction.

(2) Directed self study and required reading.

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c (3) Procedural walkthroughs in Control Room Mockup and Oyster Creek Facility.

(4) Non-Plant Specific Full Scope Simulator, demonstrations and performance evaluations (team and individual).

Schedule for Course' Completion: -

(1) Formal classroom training is scheduled to begin on March 21, 1983 following initial verification and validation of the Oyster Creek Procedures.

(2) . Simulator Training (including performance evaluations) is scheduled to begin on May 30, 1983 to be completed by October 2, 1983.

Audience (Required Course Participants):

i s (1) All Oyster' Creek Licensed Operators.

(2) All' Oyster Creek Shift Technical Advisors (Qualified). ,

References:

i (1) Oyster Creek Training Program Manual, Section 303,

" Licensed Operator Requalification Program," and Section 306, "STA Requalification Program."

(2) Oyster Creek NGS Symptom Based Emergency Operating l Procedures Technical Guidelines (Draf t) .

(3) Memo, EPIC Committee Meeting Minutes (82-01), 9/16/82, A. Rone.

i' (4) Memo, Symptom Based Emergency Operating Procedure Operator Training, 10/15/82, A. Rone.

. Instructional Materials and Proposed Topics:

i The course will be broken down into several units of instruc-tion, each covered by an individual Instructor Guide (Lesson Guide). Each Instructor Guide will detail the specific topic to be covered, method (s) of instruction appropriate to that topic, the topical behavioral learning objectives that relate

(- directly to the overall course behavioral learning objectives, and the method of evaluation (including standards of per-formance) appropriate to that topic.

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The following outline is a proposal of the topics to be covered I i

and approximate instructional hours devoted to that topic.

Topics Approximate Hours I. Symptom Based Emergency Operating Procedures Overview -

4 II. RPV Control Procedure,, -

17 III. Containment Control Procedure -

17 IV. Contingency Procedures -

18 V. BWR Simulator, Evaluation of Course Objectives -

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Instructor Guides will be reviewed and approved in accordance with Oyster Creek Training Department Procedures.

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  • Continued Evaluation and Follow-On Training:

O Continued Evaluation of trainee proficiency on the job will be in accordance.with their respective Requalification Program Requirements..

l Follow-On Training -

The objectives. of this course will be met in subsequent initial training and STA's. An appropriate course of review of these topics is programs for Licensed Operators a part of the subsequent Requalification Program for Licensed Operators and will be made a part of the Requalification Program for STA's in accordance with Reference 1.

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1 OYSTER CREEK PLANT SPECIFIC EMERGENCY PROCEDURE GUIDELINES From Revisions 2 & 3 of BWROG

! Generic Guidelines July 12, 1983 i'

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INTRODUCTION O The following symptomatic Emergency Procedure Technical Guide- ,

lines have been developed for Oyster Creek from the generic BWR l Revision 2 Guidelines and enhanced with steps from the generic Revision 3 Guidelines:

' RPV Control Guideline  !

  • Primary Containment Control Guideline The RPV Control Guideline maintains adequate core cooling, shuts down the reactor, and cools down the RPV to cold shutdown '

conditions. This guideline is entered whenever a low RPV water  !

level, high RPV pressure, high drywell pressure, or an isola-tion has occurred or a condition which requires reactor scram exists and reactor power is above 2% or cannot be determined.

i The Primary Containment Control Guideline controls. primary

'N containment temperatures, pressure, and level whenever suppres-

, sion pool temperature, drywell temperature, containment tem-perature, drywell pressure, or suppression pool water level is above its normal operating limit or suppression pool water 3

level is below its normal operating limit.

4 Table 1 is a list of abbreviations used in the guidelines.

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l At various points throughout these guidelines, precautions are I

noted by the symbol- # . The number'within the box' refers to

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a numbered " Caution" co'n'tained in the Operator Precautions section. These " Cautions" are brief and succinct red flags for the operator.

The differences b'etween the Oyster Creek plant' specific EPGs and the generic Revision 2 EPGs are summarized in Table 2.

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Page 1 of 50

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l TABLE 1 ABBREVIATIONS ADS -

Automatic Depressurization System i APRM - Average Power Range Monitor CRD -

Control Rod Drive ECCS -

Emergency Core Cooling System HCU -

Hydraulic Control Unit IC -

Isolation Condenser .

LCO -

Limiting Condition for Operation .

LOCA -

Loss of Coolant Accident LPCS -

' Low Pressure Core Spray MSIV -

Main Steamline Isolation Valves NDTT -

Nil-Ductility Transition Temperature NPSR -

Net Positive Suction Head RPS -

Reactor Protection System RPV -

Reactor Pressure Vessel

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RSCS -

Rod Sequence Contrcl System C( RWCU -

Reactor Water Cleanup SBGT - Standby Gas Treatment SLC -

Standby Liquid Control SORV -

Stuck Open Relief Valve EMRV -

Electromatic Relief Valve SDC -

Shutdown Cooling i

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Y TABLE 2

() DIFFERENCES BETWEEN OC EPGS AND REV. 2 GENERIC EPGS

. Th'e OC EPGs have an entry condition into the RPV Control guideline based on high' RPV pressure which is not in-cluded in the Rev. 2. generic guidelines. This entry condition was added to the OC EPGs from Rev. 3 of the generic EPGs.

. The OC EPGs have an entry condition into the RPV Control ,

guideline based on operator judgment which is not in-cluded in the Rev. 2 or Rev. 3 generic EPGs. This entry condition was added to give the operator the flexibility of entering the EPGs prior to satisfying an entry con-dition if he needed to conserve inventory or limit a radioactive release. ,

. The generic EPGs include a conditional statement prior to step RC/L-2 which instructs the operator to go to Contingency #7 to better control the effects of an ATWS if boron injection is required. The OC EPGs do not include this step since the Contingency 97 guideline is not being implemented at this' time.

. In step RC/L-2, the OC EPGs set a lower limit for con-trolling level at.LO-LO-LO level. Both the generic Rev. 2 and Rev. 3 EPGs specify this limit at TAF. If the level cannot be maintained above this limit, the operator is instructed to abandon RC/L and go to Con-tingency #1. From our simulator experience, the lower limit for level control was raised from TAF to LO-LO-LO level. This higher limit'gives the operator more time l to recover level with steps in. Contingency #1.

,a. -

Page 3 of 50

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y-.-v. -

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TABLE 2 (Cont'd)

D

. Caution #18 was added to the OC EPGs at step RC/Q-5.1.1 to assure that the RPS subchannel test switches can be placed in the trip position. This caution is Oyster Creek specific and is not contained in the generic Revision 2 or Revision 3 EPGs.

. The OC EPGs instruct the operator to put the mode switch in REFUEL to manually drive in individual rods in step RC/Q-5.2. This instruction is not included in either Rev. 2 or Rev. 3 of the generic EPGs since it is an 4 Oyster Creek specific step.

. Step RC/Q-5.6.2 in the DC EPGs loops the operator back to the start of the RC/Q guideline to give him an exit path from the Power Control guideline or to allow him.to try the steps again to insert control rods. This step is not present in Rev. 2 or Rev. 3 of the generic EPGs O' but is correctly placed in the OC EPGs.

. Caution #19 was added to the OC EPGs at step SP/T-1 to make the operator aware that removing the right com-bination of control power fuses defeats ADS for all of t the valves. This caution is Oyster Creek specific and l

is not contained in the generic Revision 2 or Revision 3 EPGs.

. Caution #20 was added to the OC EPGs at step SP/T-2 to guard against overloading the diesel generator if it is necessary to use this power source for operating the containment spray system. This caution is Oyster Creek plant specific.

l l

(f Page 4 of 50 l

l

~ ' ~

.-. , _ - = - .-

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

- =~ - n2-.. , = : :- - - -

TABLE 2 (Cont'd)

O . - Caution #21 was also added at step SP/T-2 to assure that excessive' differential pressure is not imposed on the containment spray heat exchanger, baffle plate. This caution is Oyster Creek plant specific.

! . The OC EPGs include a step prior to step DM/T-2 which instructs the operator to execute steps DW/T-2 and DM/T-3 concurrently. This assures that the ,drywell temperature is maintained below the qualification tem-perature of the drywell liner and that reference legs of the RPV level instruments are monitored to determine if they flash. This step is not included in Rev. 2 of the generic EPGs but waE added from the Rev. 3 EPGs.

. In step DW/T-3, the generic Rev. 2 and Rev. 3 EPGs make use of.a limit curve as a criterion for initiating dry-well sprays at a reduced flowrate. This limit curve O guards against rapid depressurization in the drywell caused by condensation or evaporation cooling when the drywell sprays are initiated at the wrong time. The curve is a function of temperature in the torus vapor space and torus pressure. Oyster Creek has no tem-perature measurement capability in the torus vapor space and has no way to throttle drywell sprayflow rate.

. Thus, this curve is not included in the OC EPGs.

The OC EPGs will instruct the operator to initiate dry-well sprays at full flow if the temperature in the dry-well exceeds the design temperature of the liner. This step appears again in step PC/P-3 and the above argument applies in that case also.

(R.

  • O v

Page 5 of 50

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i 1

TABLE 2 (Cont'd)

. Step PC/P-5 in the OC EPGs instructs the operator to enter the RPV Control guideline if RPV flooding is required. This step is included to assure that the RPV level and pressure control is transferred to Contingency

  1. 6. In addition, it assures that the reacto'r is shut down prior to flooding the RPV. This branch to RPV control is not included in Rev. 2 or Rev. 3 of the' generic EPGs. .

. Step SP/L-3 in the OC EPGs instructs the operator to execute steps SP/L-3.1 and SP/L-3.2 concurrently to lower torus level and to give him some criteria for terminating external water injection sources from adding water to the RPV which may be raising the level in the to.rus. This step is not present in the Rev. 2 EPGs but was taken from the Rev. 3 generic EPGs.

_- . In the OC EPGs, steps SP/L-3.1 through SP/L-3.2 are taken from Rev. 3 of the generic EPGs. These steps were incorporated to give the operator greater flexibility in controlling torus level. ,

! . The conditional statement prior to step Cl-4 in both l

l sets of generic EPGs directs the operator to inhibit I

automatic ADS actuaticn whenever level is less than l LO-LO-LO level. In the OC EPGs, automatic ADS actuation

(

will be overridden only when level is below LO-LO-LO level and steam cooling is being used to remove the core heat.

i f

f c

(v.

O Page 6 of 50 i

-- n. . . -- .

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TABLE 2 (Cont'd)

LJ . In the OC EPGs, step C6-2.2 returns the operator to steps RC/P-4 and RC/L if the RPV level can be determined and all of the control rods are not inserted. The generic Rev. 2 guidelines direct the operator to Con-tingency #7 and step RC/P-4 under the same conditions.

However, since Contingency 97 has been omitted from the OC EPGs at this time, the best guidance available is to direct the operator back to RPV control at steps RC/L ,

and RC/P-4.

. The ATWS mitigation steps in Contingency 47 of the generic EPGs have been omitted from the OC EPGs due to

- technical questions about the guidance given in Con-tingency #7. The implementation of ATWS mitigation guidelines in the OC EPGs are contingent upon analysis work currently underway which evaluates Contingency 97 and alternate ATWS mitigation methods.

E l

t l .('

O Page 7 of 50 ,

l

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- OPERATOR PRECAUTIONS O GENERAL This section lists " Cautions" which are generally applicable at all times.

CAUTION #1 Monitor the general state of the plant. If an entry con- ,

dition for either EMG-3200.01 "RPV Control" or EMG-3200.02

" Containment Control" occurs, enter that procedure. When it is determined that an emergency no longer exists,' enter normal operating procedure.

CAUTION $2 Monitor RPV water level and pressure and primary con-tainment temperatures and pressure from multiple indi-Cations.

O CAUTION #3 If a safety function initiates automatically, assume a true initiating event has occurred unless otherwise confirmed by at least two independent indications.

CAUTION #4 Suppression pool temperature is determined by (procedure for determining bulk suppression pool water temperature].

Drywell temperature is determined by [ procedure for determining drywell atmosphere average temperature].

w.

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_ _ m . . -o .

+

CAUTION #5 Whenever [ temperature near the instrument reference leg

(} vertical runs 1 exceeds the temperature in the table and the instrument reads below the indicated level in the table, the actual RPV water level may be anywhere below the elevation of the lower instrument tap.

Indicated Temperature

  • Level- Instrument 107'F -

107 in. Wide Range Level '

i~

(90 to 490 in.)

310*F 19 in. GEMAC Narrow Range Level (90 to 180 in.)

545'F 168 in. YARNAY Narrow Range Level (85 to 185 in.)

NOTE: The values in the above table are not plant specific and are presented for illustrative purposes only.

( CAUTION #6 YARNAY indicated levels are not reliable during rapid RPV depressurization below 500 psig. For these conditions, utilize GEMAC and fuel zone level instruments to monitor RPV water level.

q t)

Page 9 of 50 w-w w .-y--w*, -p uyw---w- -- r - e e w w - vv eew-wv - qv gr3++r4-*e n g-we#w-w M o w-a ze- e--we-yPawr-, w-W* e w ve r-w er w-=rw-=w-r- wt--w- m s - w- -trer-=P w 7N w-w rws' mes r-e- u -$r-w-W W--oww-Ww--r

l CAUTION #7 -

Observe NPSH requirements for pumps taking suction from the suppression pool.

240- -

10 psig q: . .

ao

" 5 psig EE 220 -

5 .

EE gg - - O psig

&!  % rmunem s paAt

"" 200 -

4MR NPSH Limit 2 4 6 8 10 RHR Pump Flow (X1000 gpm) 240 - -

I0 psig ,

[

m. -

N 5 psig

= 220 O psig

?5 CoRESPRAT 200--

NPSH Limit l 2 4 6

~

LPCS Pump Flow (X1000 gpm).

  • Suppression chamber pressure Suppression pool at normal water level NOTE: The above curves are not plant specific.

l (

Page 10 of 50

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SPECIFIC

~

() This section lists " Cautions" which are applicable at one or more specific points within the guidelines. Where a

" Caution" is applicable, it is identified with the symbol CAUTION 58 Do not secure or place an ECCS in MANUAL mode unless, by at least two independent indications, (1) misoperation in AUTOMATIC mode is confirmed, or (2) adequate core cooling is assured or (3) manual operation of-ECCS is required by

, EOPS. If an ECCS is placed in MANUAL mode, it will not initiate automatically. Make frequent checks of the ini-

, tiating or controlling parameter. When manual operation is no longer required, restore the system to AUTOMATIC mode if possible.

CAUTION 49 If a high drywell pressure ECCS initiation signal 2.0 psig (drywell, pressure which initiates ECCS) occurs or exists while depressurizing, prevent injection from those LPCS pumps not required to assure adequate core cooling prior to reaching their maximum injection pressures. When the high drywell pressure ECCS initiation signal clears, restore i LPCS to AUTOMATIC mode.

CAUTION 410 Cooldown rates above 100*F/hr (RPV cooldown rate LCO) may j be required to accomplish this step.

.1 g-Page 11 of 50

- . . 2 ..-..- .-.. ...- ::L - -.::D. L. -.  :~_X  :::: - ..::: _ _ ...

l CAUTION #11

' Open EMRVS in the following sequence if possible: EMRV opening sequence: A, C , D, B, E CAUTION #12 Bypassing MSIV isolation interlocks may be required to accomplish this step.

CAUTION #13 Cooldown rates above 100'F/hr (RPV cooldown rate LCO) may be. required to conserve RPV water inventory, protect pri-mary containment integrity, or limit radioactive release to the environment. .

CAUTION #14 Confirm automatic trip or manually trip SLC pumps at 0%

(low level trip) in the SLC tank.

t CAUTION #15 Defeating isolation interlocks may be required to ac-complish-this step.

CAUTION #16 A rapid increase in injection'into the RPV may induce a large power excursion and result in substantial core damage.

' CAUTION #17 Large reactor power oscillations may be observed while executing this step.

Page 12 of 50

~ : : -__ _. ~ , _

Tra .- _ _;;;n_-. . :::- . _ - __ _ _ n_._ _ _. __ _____ ar~.za . ._ _ ___ . .. ._ _.. J

. CAUTION 918 Do not place the isolation subchannel test switches to the trip position.

CAUTION #19

. Removing the control power fuses from both NR108A and NR108B defeats ADS for all valves. _

CAUTION #20 Do not exceed a diesel genera, tor load of 2750 kW when placing the containment spray system into service.

CAUTION #21 Limit containment spray heat exchanger baffle plate dif-ferential pressure to less than 10 psi.

i

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1 l

l Page 13 of 50

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EMG-3200.01 "RPV CONTROL" PURPOSE The purpose of this guideline is to:

  • Restore and maintain RPV water level within a satisfactory range to assure adequate core cooling,
  • Shut down-the reactor, and
  • Control RPV pressure and/or cool down the RPV to cold shut-

- down conditions (100*F ( RPV water temperature < 212*F (cold shutdown conditions)).

ENTRY CONDITIONS The entry conditions for this guideline are any of the fol-() lowing:

RPV water level below +138.in. (low level scr,am setpoint) , or

  • Drywell pressure above 2.0 psig (high drywell pressure scram setpoint), or

RPV pressure above 1060 psig (high Rx pressure scram set-point)

A condition which requir.es reactor scram, and reactor power above 2% (APRM downscale trip) or cannot be determined.

l.

6 Page 14 of 50

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. -. . =.. . .

f Condition which requires a scram in the judgment of the A

( ,) operator to conserve inventory or limit radioactive. releases to the environment.

OPERATOR ACTIONS RC-1 If reactor scram has not been identified, initiate reactor scram.

Irrespective of the entry condition, execute , Steps RC/L, RC/P, and RC/Q concurrently.

RC/L Monitor and control RPV water level.

J RC/L-1 Confirm initiation of any of the following:

, Reactor Isolation IC Isolation RWCU Isolation

(

  • SDC Isolation LPCS Start If while executing the following step:

RPV water level cannot be determined, RPV FLOODING IS l REQUIRED; enter Procedure EMG-3200.08 "RPV Flooding."

RPV Flooding is required for reasons other than level j cannot be determined, enter Procedure EMG-3200.08 "RPV Flooding."

i c.

O .

Page 15 of 50 i

_.:" '~~T 11; .__. _ 1_ li_ ._. ___. ___ . .. _ __ _ Z.T_1 _ i _ _ _ _ _ ___ _ _ _ _ _

RC/L-2 Restore and maintain RPV water level be-() tween +138 in. (low level scram setpoint) and +176 in. (high level trip setpoint)

  1. 8 with one or more of the following systems: 69 Condensate /feedwater system 1500 - O psig

, (RPV pressure range for system operation)

CRD system 1500 - O psig (RPV pressure range for system operation) ,

LPCS system 285 - O psig (RPV pr' essure range

! for system operation)

, If RPV water level cannot be restored and main-tained above 138 in. (low level scram setpoint),

maintain RPV water level above (61 in TAF LO-LO-LO Level).

O If RPV water level cannot be maintained above 61 in TAF LO-LO-LO Level, enter Procedure

~

l EMG-3200.03 " Level Restoration."

If Alternate Shutdown Cooling is required, enter Procedure EMG-3200.07 " Alternate Shutdown Cooling."

RC/L-3 Process to cold shutdown in accordance with (procedure for cooldown to cold shutdown con-ditionsl.

4 Page 16 of 50-

.. ~:H::::- . :::.L:7.: _ ,.L~X,L.-.- -

.---. LL L.-_-._-_.

RC/P Monitor and control RPV pressure.

If while executing the following steps:

  • Emergency RPV Depressurization or RPV Flooding is required and less than 3 (number of EMRVs required for ,

Emergency Depressurization) EMRVs are open, enter Procedure EMG-3200.04 " Emergency RPV Depressurization."

4

  • RPV Flooding is required and at least 3 (number of EMRVs required for emergency dedicated depressuriza-tion) EMRVs are open, enter Procedure EMG-3200.08 "RPV Flooding." -

() RC/P-1 If any EMRV is cycling, initiate IC and manually open EMRVs until RPV pressure drops to 920 psig or any open turbine bypass valve begins to close.

If while executing the following steps:

Suppressi'on pool temperature cannot be 57 maintained below the Heat Capacity #10 Temperature Limit, maintain RPV below the Limit.

s l'

~

O Page 17 of 50 1

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== me == == == == uma RPV PassauRS.Pstrq .

Suppression pool water level cannot #10

. be maintained below the Suppression Load Limit, maintain RPV pressure

,O below the Limit.

b

. . .i a 20 "

tan emise

=

o

. mms y

e .

en 8W

s 1 . .

a O

i A e ToAu.s .-

o Lcad Limit

.e E .

. ./ i a.

m.

/

=

a 12.5 0 -

400 1200 RPV Pressure (psig) ...

NOTE: The above curve is not plant specific.

! k 1

Page 18 of 50

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

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. .c .-. - ,

  • Steam Cooling is required, enter Procedure

() EMG-3200.05 " Steam Cooling."

If while executing the following steps:

Boron Injection is required, and

. The main condenser is available, and There has been no indication of gross fuel

' failure or steam line break, open MSIVs to re-establish the main #12 condenser as a heat sink irrespective of the differential pressure across the valves.

RC/P-2 Control RPV pressure below 1060 psig (lowest EMRV lif ting pressure) with the main turbi'ne bypass valves.

RPV pressure control may be augmented by one or more of the following systems:

, k IC

  • EMRVs if torus level is greater than ill 4 ft. 9 inches (EMRV quencher height).

RWCU (recirculation mode) if no boron has been injected into the RPV.

Main steam line drains.

O Page 19 of 50

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.. . ; , t : . :. L

4 .

If while executing the following steps the

() '

reactor is not shutdown, return to Step RC/P-2.

RC/P-3 When RPV water level is stabilized and either:

l 7 All control rods are# inserted to at least position 02 (maximum subcritical banked with-drawal position) , or 273 pounds (Cold Shutdown Boron Weight) of boron have been injected into the RPV, or The reactor is shutdown and no boron has been injected into the RPV, Depressurize the RPV and maintain #13 cooldown-rate below 100*F/hr (RPV cooldown rate LCO)s O RC/P-4 When the shutdown cooling interlocks clear, initiate shutdown cooling.

If the shutdown cooling cannot be established and further cooldown is required, continue to cool down using one or more of the systems used for i depressurization.

If RPV cooldown is required but cannot be ac-complished and all control rods are inserted to i at least position 02 (maximum subcritical banked withdrawal position) , ALTERNATE SHUTDOWN COOLING IS REQUIRED; enter Procedure EMG-3200.07

" Alternate Shutdown Cooling."

Q

Page 20 of 50

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,- ~. .. - . .

RC/P-5 Proceed to cold shutdown in accordance with

() [ procedure for cooldown to cold shutdown con-ditions).

RC/Q Monitor and control reactor power.

If while executing the following steps:

All control rods are inserted to at least position 02 (maximum subcritical banked withdrawal pos,ition),

terminate boron injection and enter [ scram procedure].

The reactor is shutdown and no boron has been injected into the RPV, enter [ scram procedure].

RC/Q-1 Confirm the reactor mode switch in SHUTDOWN.

RC/Q-2 If the main turbine-generator is on-line, confirm or initiate recirculation flow runback to mini-

)

mum. When recirculation flow is at minimum, trip the recirculation pumps.

RC/Q-3 If reactor power is ab'ove 2% (APRM downscale

~

trip) or cannot be determined, trip the recir-culation pumps.

Execute Steps RC/Q-4 and RC/Q-5 concurrently.l l RC/Q-4 If the reactor cannot be shutdown before #14 I

l suppression pool temperature reaches 110'F

{ (Boron Injection Initiation Temperature), BORON INJECTION IS REQUIRED; inject boron into the RPV with SLC and prevent automatic initiation of' ADS.

!6 i

Page 21 of 50 v- . - - - - + - - - , - - - . - , . - - - - - . _ . , - - - , , - - - ,- ..v,..n._ . . , , . , , m- -ve. , - - , - - - , , , , , .- - - - , , . , ,,

RC/Q-4.1 If boron cannot'be injected with SLC, inject

() boron into the RPV by one or more of the following alternate methods:

RWCU Feedwater RC/Q-4.2 If boron is not being injected into the RPV by RWCU, confirm automatic isolation of RWCU.

RC/Q-4.3 Continue to inject boron until 273 pounds (Cold Shutdown Boron Weight) of boron have been injected into the RPV.

RC/Q-4.4 Enter [ scram procedure].

RC/Q-5 Insert control rods as follows:

RC/Q-5.1 If any scram valve is not open and MSIVs are O '; - ,

closed:

Open both 100 amp RPS breakers. Continue at RC/Q-5.1.2.

RC/Q-5.1.1 If any scram valve is not open and #18 main condenser is being use as heat sink, place RPS channel I and II subchannel test switches IA, IB, IIA and IIB to trip position.

RC/Q-5.1.2 Close V-6-175 (scram air header supply) and open V-6-409 (scram air header vent) .

Page 22 of 50 -

T ,- i,~ 11 - 1 ; - - ----- - --

RC/Q-5.1.3 When control rods are not moving inward:

Close any breakers opened in Step RC/Q-5.1 or close any switches tripped in Step RC/Q-5.1.1.

RC/Q-5.1.4 Close V-6-409 (scram air header vent) and open V-6-175 (scram air header supply) .

RC/Q-5.2 Reset the reactor scram. ,

If the reactor scram cannot be reset:

1. Start all CRD pumps.

If no CRD pump can be started, continue in this procedure at Step RC/Q-5.6.1.

( y 2. Close V-15-52 (CRD charging water supply

, valve).

2.5 Place mode switch in REFUEL.

.3. Rapidly insert control rods #20 manually until the reactor scram can be reset.

4. Reset the reactor scram.
5. Open V-15-52 (CRD charging water supply j valve) .

l l

O Page 23 of 50

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RC/Q-5.3 If' the scram discharge volume vent and drain O( ,j valves are open, initiate a manual reactor scram after the SDV headers have drained.

1. If control rods moved inward, return to Step RC/Q-5.2.
2. Otherwise reset the reactor scram.

If the reactor scram cannot ,be reset, continue in this procedure at Step RC/Q-5.5.1.

3. Open the scram discharge vent and drain valves.

RC/Q-5.4 Individually open the scram test switches for control rods not inserted to at least posi-(~')

tion 02 (maximum subcritical banked with-drawal position).

NOTE: Control rods of highest reactivity should be' selected first.

When a control rod is not moving inward, close its scram test switch.

RC/Q-5.5 Reset the reactor scram.

RC/Q-5.5.1 If the reactor' scram cannot be reset, start available CRD pumps and close V-15-52 (CRD charging water supply valve) .

i:<

-- l Page 24 of 50 j l

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

l L

1 RC/Q-5.5.2 If no CRD pump can be started, continue (f in this procedure at Step RC/Q-5.6.1.

RC/Q-5.6 Place the mode switch in REFUEL and rapidly  ;

. insert control rods manually until all con-trol rods are inserted to at least position 02 (maximum subcritical banked withdrawal

-position).

RC/Q-5.6.1 If any control rod cannot be inserted to at least position 02 (maximu'm sub-critical banked withdrawal position):

1. Individually direct the effluent from CRD withdraw line vent to a contained radwaste drain and open CRD withdraw line vent for each control rod not insert 9d to at least position 02 (maximum subcritical

) banked withdrawal position).

2. When a control rod is not moving inward, close its withdraw line vent.

RC/Q-5.6.2 Continue in this procedure at step RC/Q.

l , , -

O Page 25 of 50

! a .~ . . z. . . .:.....  :  :: . =, . . . - . ..

. . -- ...:====== . : . . . === .: ,. z : ::= z: :- -.. . -

EMG-3200.02 " CONTAINMENT CONTROL" PURPOSE The purpose.of.this guideline is to control primary containment temperatures, pressure, and level.

ENTRY CONDITIONS The entry conditions for-this guideline are any of ,the fol-lowing:

Suppression pool temperature above 90*F (most limiting suppression pool temperature LCO)

Drywell. temperature above 135'F (maximum normal operating t.emperature) ,

Drywell pressure above 2.0 psig (high drywell pressure scram setpoint)

  • Suppression pool water level above 10.9 inches (maximum suppression pool water level LCO)

. Suppression pool water level below [-1.9 inches (minimum suppression pool water level LCO)]

.A.

Page 26 of 50 1

. - - . . .- l:~-- . . -.- - . - :- . . - .. - . - .--, .L -. _- _- . - ..- .. _ - :.:::; . . . .-.: :. .- . -- -, . . -- .

OPERATOR ACTIONS Irrespective of the. entry condition, execute Steps SP/T, DW/T, PC/P, and SP/L concurrently.

SP/T Monitor and control suppression pool temperature SP/T-1 Close any SORV. ,

(19 If any SORV cannot be closed, scram the reactor.

SP/T-2 If pool temperature exceeds 90*F, start b one loop of containment spray in dynamic 021 test. If pool temperature exceeds 95'F, start other loop of containment spray in dynamic test.

SP/T-3 Before suppression pool temperature reaches 110*F (Boron Injection Initiation Temperature), scram the reactor.

SP/T-4 If suppression pool temperature cannot be 57 maintained below the Heat Capacity B10 0- Temperature Limit, maintain RPV pressure below the Limit.

l 1

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Page 27 of 50

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If suppression pool temperature and RPV pressure cannot be restored and maintained below the Heat Capacity Temperature Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter Procedure EMG-3200.01 "RPV Control" at Step RC-1 and execute it concurrently with this procedure.

(Ntv

' k, Page 28 of 50

f DW/T Monitor and control drywell temperature.

DW/T-1 Operate'available drywell cooling when #5 drywell temperature exceeds 135'F (maximum normal operating temperature) l Execute steps DW/T-2 and DW/T-3 concurrently.

DW/T-2 If drywell temperature near the cold reference leg instrument vertical runs reaches ,the RPV Saturation Temperature, RPV FLOODING IS REQUIRED; enter Procedure EMG-3200.01 "RPV Control" at Step RC-1 and execute it concurrently with this pro--

cedure.

550 - NN cn7 *

  • i' Ie%

=.u o .RPV Saturation 36 >

\ -

Temporature i 22e N -

ist s

  • f' ,

6.5 .

212 ,

0 RPV Pressure (psig) 1000 c, . .

Page 29 of 50

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~ ~ _ .__ .. _ ___ _ _ ; _ ___ -. E: ,,_...._ _ _ _ .. _ i : 1.

DW/T-3 Before drywell average temperature reaches 281*F (maximum drywell design temperature) , shut down recirculation pumps and drywell cooling fans and initiate drywell sprays.

DW/T-4 If drywell temperature cannot be maintained below 281*F (maximum drywell design temperature) ,

EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter Procedure EMG-3200.01 "RPV Control" at. Step RC-1 l

and execute it concurrently with this, procedure.

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I PC/P ~ Monitor and control primary containment pressure.

1 O PC/P-1 Operate the following systems, as required:

SBGT and drywell purge, only when the tem-  ;

perature in the space being evacuated is below j 212*F (Maximum Noncondensible Evacuation Temperature) . Use [SBGT and drywell purge  ;

t operating procedures).  !

T PC/P-2 If suppression chamber. pressure exce s 18.6 psig  !

! (Suppression Chamber Spray' Initiation Ptwssure),  !

shut down recirculation pum'ps and drywell cooling fans and initiate drywell sprays.

  • PC/P-3 If suppression chamber pressure cannot be main-tained below the Pressure Suppression Pressure

. Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. Enter Procedure EMG-3200.01 "RPV Control'" at Step RC-1'and execute it concurrently s, with this procedure.

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  • Page 31 of 50 i

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PC/P-4 If suppression chamber pressure cannot be main-O tained below the Primary Containment Design Pressure Limit, RPV FLOODING IS REQUIRED. Enter Procedure EMG-3200.01 "RPV Control" at Step RC-1 and execute it concurrently with this procedure.

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g ' Pressure Suppression G Pressure m

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0 12.2 17 34.5 Primary Containment Water Level (f t.)

NOTE: The above curve is not plant specific.

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l Page 32 of 50

PC/P-5 If suppression chamber pressure cannot be main- ,

tained below the Primary Containment Pressure Limit, then irrespective of whether adequate core cooling is ascured; trip the recirculation pumps and drywell cooling fans and initiate containment spray.

To

}.

/ -

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e 46.5 - -

t Pritn.Ary Couca Ltunetit

.c U Design Pressure O E t.

IO -

0 12.5 34.5 Primary Containment Water Level (ft.)

NOTE: The above curve is not plant specific.

o .Page 33 of 50

CJ Containment Pressure Limit, restore cooling to the core.

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.2 0 N Primary Containmenc

$ Pressure Limit

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k0 O 12.5 34.5 Primary Containment Water Level (ft.)

NOTE: The above curve is not plant specific.

PC/P-6 If suppression chamber pressure exceeds the #15 Primary Containment Pressure Limit, vant the primary containment in accordance with [ procedure for containment venting] to reduce and maintain pressure below the Primary Containment Pressure Limit.

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l Page 34 of 50

, _ .~--..__.._,_.s - , , _ - , . = . , - . . . . _ . . . - . , _ . . _. .~.m.._ _e.,,,. _ . , . . = .

N SP/L Monitor and control suppression pool water level.

I SP/L-1 Maintain suppression pool water level 97 between 10.9 inches (maximum suppression ~

pool water level LCO) and 1.9 inches (minimum suppression pool water level LCO). If level cannot be maintained above -1.9 inches, execute step SP/L-2. If level cannot be maintained below 10.9 inches, execute step SP/L-3.

SP/L-2 Maintain water level above the Heat dapacity Level Limit using core spray system. If sup-pression pool water level cannot be maintai.ned above the Heat Capacity Level Limit, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED; enter Procedure EMC-3200.01 "RPV Control" at Step RC-1 and ex-ecute it concurrently with this procedure.

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4 SP/L-3 lExecute steps SP/L-3.1 and SP/L-3.2 concurrently.}

SP/L-3.1 Maintain level below the Suppression Pool Load Limit SP/L-3.1.1 If suppression pool water level #10 '

cannot be maintained below the Suppression Pool Load Limit, maintain RPV pressure below the Limit.

SP/L-3.1.2 If level and RPV pressure cannot be maintained below the Suppression Pool

. Load Limit and adequate core cooling is assured, terminate injection into the RPV from sources external to the

primary containment except Boron injection and CRD.

O

}= to "

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Suppresssion Pool -

o L oad Limit i U /' <

3 12.5 l 1500 l

. 0 400  ;

I RPV Pressure (psig)  ;

l NOTE: The above curve is not plant specific.

Page 36 of 50

, =r=-- .

. .--=.. : ::=- :- z =.=: z. =_ -_. = _ . . =: . =::= == == . = == -

SP/L-3.1.3 If suppression pool water level and 4

s_/ RPV pressure cannot be restored and maintained below the Suppression Pool Load Limit, EMERGENCY RPV DEPRES-SURIZATION IS REQUIRED; enter Pro-cedure EMG-3200.01."RPV Control" at Step RC-1 and execute it concurrently with this procedure.

SP/L-3.2 Before primary containmen,t water level reaches [104 ft. (maximum primary containment water level limit)], and only if adequate core cooling is assured, terminate in-jection to the RPV from sources external to the primary containment except for Boron injection and CRD.

() If primary containment water level reaches [104 ft. (Maximum Primary Containment Water Level Limit)],

terminate injection into the RPV from sources external to the primary con-tainment irrespective of whether adequate core cooling is assured.

O Page 37 of 50 i

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

EMG-3200.03 " LEVEL RESTORATION" If while executing the following steps: .

RPV water level cannot be determined, RPV FLOODING IS REQUIRED; enter Procedure EMG-3200.08 "RPV Flooding."

RPV Flooding is required, enter Procedure EMG-3200.08 "RPV Flooding."

l Cl-1 Initiate IC. i f

Cl-2 Line up for injection and start pumps in two or more of the following injection subsystems-l l

4 Condensate ,

LPCS-I

()

  • LPCS-II If less than two of the injection subsystems can be lined up, commence lining up as many of the following alternate injection subsystems as possibl'e:
  • Fire system

, ECCS keep-full systems SLC (test tank)

SLC (boron tank) i l

10 Page 38 of 50

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

I l Cl-3 Monitor RPV pressure and water level. Continue in this

( procedure at the step indicated in the following table, t . RPV PRESSURE REGION l

[285 psigi l

, RPV Level High Low Increasing Cl-4 Cl-6 Decreasing Cl-7 Cl_-8 i

(RPV pressure at which LPCS shutoff head is reached) i

. If while executing the following steps:

The RPV water level trend reverses or RPV pressure changes region, return to Step Cl-3.

(f RPV water level drops below 61 inches TAF (ADS initiation setpoint) and Steam Cooling is required, prevent automatic initiation of ADS.

Cl-4 RPV WATER LEVEL INCREASING, RPV PRESSURE HIGH -

Enter Procedure EMG-3200.01 "RPV Control" at Step RC/L.

Cl-6 RPV WATER LEVEL INCREASING, RPV PRESSURE LOW l

l If RPV pressure is increasing, EMERGENCY RPV DEPRES-SURIZATION IS REQUIRED. Enter Piocedure EMG-3200.04

" Emergency RPV Depressurization."

, (d '

Page 39 of 50

. x =-- -

-=--=:.. =; .-- z = . =. a . .. ... -. .. . - .. _ .- = : ::,= =.

Otherwise, enter Procedure EMG-3200.01 "RPV Control" at

,O Step RC/L.

Cl-7 RPV WATER LEVEL DECREASING, RPV PRESSURE HIGH If no injection subsystem is lined up for injection with at least one pump running, start pumps in alternate in-jection subsystems which are lined up for injection.

l When RPV water level drops to 0 inches (top o,f active fuel):

If no system, injection subsystem or alternate in-jection subsystem is lined up with at least one pump running, STEAM COOLING IS REQUIRED. Enter Procedure EMG-3200.05 " Steam Cooling." When any system, in-jection subsystem or alternate injection subsystem is lined up with at least one pump running, EMERGENCY RPV

() DEPRESSURIZATION IS REQUIRED.

EMG-3200.04 " Emergency RPV Depressurization."

Enter Procedure When RPV water level is increasing or RPV pressure drops below 285 psig, return to Step Cl-3.

Cl-8 RPV WATER LEVEL DECREASING, RPV PRESSURE LOW If no LPCS subsystem is operating, start pumps in al-ternate injection subsystems which are lined up for injection.

If RPV pressure is increasing, EMERGENCY RPV DEPRESSURIZATION IS REQUIRED. Enter Procedure EMG-3200.04 " Emergency RPV Depressurization."

Lo Page 40 of 50

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- - - =.. ..

P R

When RPV water level drops to 0 in. (top of active fuel),

SPRAY COOLING IS REQUIRED; enter Procedure EMG-3200.06

" Spray. Cooling."

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l Page 41 of 50

-_ __. ._ __. e wevw>?g- -p.-.,-- *- - c,w~.,,,eny.g--%,, ., ya p-eaw,ge - +=.wwwwn**-mg w-r--4.g-w,yw.,=p,.eewg y-,w-%.m--,-,-y.9 ,- ne eu-e^-evv w ww e ew w--w-w ar w ew m we-w

C2-1 EMERGENCY RPV Initiato IC.

C2-2 DEPRESSURIZATI ON" If suppr (eleva tion ofession pool wate

) EMRVs. top of r leve l is abov EMRV \

C2-3 e4 If discharge devie ft. 9 in.

c ),

Requiredless than 3 (Mi open all open for Em and RPV nimum Number ergency Depr of EMRV EMRVs r

pressure opening Prpressure is at essu ization) of e a es sure) abov least 50 EMRVs #15 are the followingr , r pidly dep e suppr psig (Minimum minimize the systemsressuri,ze the RP ession radioactiv (us chamber e e e in orderV usidg one s

r leas or Main more er e to the ewhich will Main condens nviro nm IC ent):

C2-4 If tube steam side vent line dr a s in RPV "RPV Flooding is Flooding. " e C2-5 r quired, enter Pro

(, Enter Pro cedur cedur e EMG-3200 08 e E'MG-3200.01 V "RP Control" at Step RC/P-4 .

  1. 9* 42 og 50

- N) ,

. ~ _ _ __

'w.,_

w

EMG-3200.05 " STEAM COOLING" C3-1 -Confirm initiation of IC.

If while executing the following steps Emergency RPV Depressurization is required or any system,. injection subsystem, or alternate injection subsystem is lined up for injection with at least one pump running, enter Procedure EMG-3200.04 " Emergency RPV Depressurization."

If IC cannot be initiated:

When RPV water level drops to -65 in. (Minimum Zero-Injection RPV Water Level) or if RPV water level cannot be determined, open one EMRV.

When RPV pressure drops below 700 psig (Minimum Single EMRV Steam Cooling Pressure), enter Procedure EMG-3200.04 " Emergency RPV Depressurization."

(}

.-.s m.

Page 43 of 50

. 2 . . -. : : - - . . . -. :: =: 2 . -- T . .::----_. - . 2::: 2 . - - - : . - - . . -. -, - - . - _ - ..- .

EMG-3200.06 " SPRAY COOLING" l

C4-1 Open all EMRVS I6 10 I

C4-2 Operate LPCS subsystems with suction from the sup-pression pool.

When at least one core spray subsystem is operating and RPV pressure is below 285 psig (RPV pressure for rated LPCS - flow) , terminate injection into the RPV, from sources external to the primary containment except for Boron injection and CRD.

C4-3 When RPV water level is restored to 0 in. (top of active

~

fuel), enter Procedure EMG-3200.01 "RPV Control" at Step RC/L.

O l

i l

l Page 44 of 50 l

. = , _ _ _ = = :::: . _ _ _ . .:. --:==-.___--

EMG-3200.07 " ALTERNATE SHUTDOWN COOLING" l C5-1 Initiate suppression pool cooling.

C5-2 Close the MSIVs, main steam line drain valves, and IC isolation valves.

C5-3 Place the control switch for one (Minimum Number of EMRVs Required for Alternate Shutdown Cooling) EMRV in the OPEN position. ,

C5-4 Slowly raise the RPV water level to establish a flow path through the open EMRV back to the suppression pool.

CS-6 Slowly open LPCS injection valve into the RPV until it is full open.

C5-6.1 Maintain RPV pressure between 130 psig and 273 psig above torus pressure as follows: If RPV (f

pressure does not stabilize at least 130 psig (Minimum Alternate Shutdown Cooling RPV Pres-sure) above suppression chamber pressure, start

' another LPCS pump.

If RPV pressure does not stabilize below 237 psig (Maximum Alternate Shutdown Cooling RPV Pressure), open another EMRV.

C5-6.2 If the cooldown rate exceeds 100*F/hr (maximum RPV cooldown rate LCO), reduce LPCS injection into the RPV until the cooldown rate decreases below 100*F/hr (maximum RPV cooldown rate LCO)

O Page 45 of 50

,-.,,1__*,. , ** , ^

,,,,,I* _y .1_ ,*_ "_ my.,

5_,y_,_ y jg,y y . , _ _ , .m.., '[

or RPV pressure decreases-.to within 50 psig (Minimum EMRV Re-opening Pressure) of sup-pression chamber pressure, whichever occurs first. )

l C5-7 Control suppression pool temperature to maintain RPV water temperature above 185'F (RPV NDTT or head tensioning limit). l C5-8 Proceed to cold shutdown in accordance with ,[ procedure for cooldown to cold shutdown conditions).

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l Page 46 of 50 w -,,-.,,--,..--,,.,..,,w__ .-.....$..---- -.,*-,..-.-e-, ,,r.., d ., --

EMG-3200.08 "RPV FLOODING" C6-1 If at least 3 (Minimum Number of EMRVs Required for Emergency Depressurization) EMRVs can be opened or if feedwater pumps are available for injection, close the MSIVs, main steam line drain valves, IC, isolation valves.

C6-2 If any control rod is not inserted beyond position 02 (maximum subcritical banked withdrawal posit, ion):

C6-2.1 Terminate and prevent all injection into the RPV except from boron injection systems and CRD.

If while executing the following steps, RPV water level can be de'termined and RPV flooding is not required, enter Procedure EMG-3200.01 "RPV Control."

C6-2.2 When RPV pressure is below the Minimum f #16 Alternate RPV Flooding Pressure, commence and slowly increase injection into the RPV with the following systems to maintain RPV pressure above the Minimum Alternate RPV Flooding Pressure:

Minimum Alternate RPV

. Number of Open SRVS Flooding Pressure (psig) 5 285 4 340 3 425 2 600 il Page 47 of 50 l

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

l l

  • Condensate pumps CRD pumps If RPV pressure cannot be maintained above the Minimum Alternate RPV Flooding Pressure, com-mence and slowly increase injection into the RPV with the following systems to maintain RPV pres-  ;

I sure above the Minimum Alternate RPV Flooding Pressure ,

LPCS

  • Fire System ECCS keep-full systems Poison test tank

! Poison system C6-2.3 When:

All control rods are inserted to at least position 02 (maximum subcritical banked with-drawal position), or The reactor is shut down and no boron has been injected into the RPV, continue in this procedure. ,

C6-3 If'RPV water level cannot be determined:

l C6-3.1 Continue injecting into the RPV with the systems initiated in Step C6-2 and maintain at least 3

. ("%.

2 i

Page 48 of 50

-. _ _. - - - , . . . _ . _ - . - , . . _ . _ _ - ...___. . . - , - - , . _ ; =- ,m=. . . _ , . - - . . _

(Minimum Number of EMRVs Required for Emergency Depressurization) EMRVs are_open and RPV pres-i sure is at least 77 psig (Minimum RPV Flooding Pressure) above suppression chamber pressure. ,

C6-4 If RPV water level can be determined, continue injecting into the RPV until RPV water level is increasing.

C6-5 If RPV water level cannot be determined:

C6-5.1 Fill all RPV level instrumentation reference columns.

C6-5.2 Continue injecting water into the RPV until temperature near the cold' reference leg instru-ment vertical runs is below 212*F and RPV water level instrumentation is available.

If while executing the following steps, RPV water level can be determined, continue in this procedure at Step C6-6.

C6-5.3 If it can be determined that the RPV is filled or if RPV pressure is at least 77 psig (Minimum RPV Flooding Pressure) above suppression chamber pressure, terminate all injection into the RPV and reduce RPV water level.

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C6-5.4 If RPV water level indication is not restored s Y

  • within the Maximum Core Uncovery Time Limit after terminating injection into the RPV, return I

to Step C6-3.  %

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r zm. o vt.n. nue. von. m .v = = mza C6-6 When suppression chamber pressure can be maintained below the Primary Containment Pressure Limit, enter a Procedure EMG-3200.01 "RPV Control" at Steps RC/L and

,,,,, RC/P-4 and execute these steps concurrently.

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  • 5. NOTE: This curve is not plant specific.

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0 12.5 34.5 Primary Containment Water Level (ft.)

Page 50 of 50

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