ML20151N603

Rev 2 to Procedures Generation Package for Hope Creek Generating Station

ML20151N603
Person / Time
Site:	Hope Creek
Issue date:	12/23/1985
From:	Public Service Enterprise Group
To:
Shared Package
ML20151N601	List: ML20151N596 ML20151N603
References
PROC-851223, NUDOCS 8601030026
Download: ML20151N603 (20)

Text

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PROCEDURES GENERATION PACKAGE FOR THE HOPE CREEK GENERATING STATION PUBT.IC SERVICE ELECTRIC AND GAS COMPANY December 23, 1985 Revision 2

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B601030026 851230 PDR ADOCK 05000354 F , PDR

TABLE OF CONTENTS Page

1.0 INTRODUCTION

.......................................... 3 1.1 Purpose.......................................... 3 1.2 Scope............................................ 3 1.3 B a c kg r o u nd . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 PLANT-SPECIFIC TECHNICAL GUIDELINES................... 5 2.1 General.......................................... 5 2.2 Description of Conversion Methodology. . . . . . . . . . . . 5 2.2.1 BWROG-EPG to P-STG........................ 5 2.2.2 P-STG to EOP.............................. 6 3.0 FLOWCHARTS............................................ 9 3.1 Utilization of Fl o wc h a rp s . . . . . . . . .. . . . . . . . . . . . . . . .

9 3.2 Flowchart Control................................ 10 3.3 Flowchart Execution.............................. 10 4.0 EOPS. WRITER'S GUIDE................................... 11 4.1 General.......................................... 11 4.2 Document Description............................. 11 5.0 EOP VERIFICATION PROGRAM.............................. 12 5.1 General.......................................... 12 5.2 Verification Prog ram Description. . . . . . . . . . . . . . . . . 12 6.0 EOP VALIDATION PROGRAM................................ 13 6.1. General.......................................... 13 6.2 Val id a t ion P rog ram Des c r 1pt ior. . . . . . . . . . . . . . . . . . . . . 13

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l TABLE OF CONTENTS (Continued)

Page 7.0 EOP TRAINING PROGRAM.................................. 15 7.1 General.......................................... 15

'7.2 Tra ining P rog ram Dev elopmen t . . . . . . . . . . . . . . . . . . . . . 15

-7.3 Tra ining Prog ram Obj ec t iv es . . . . . . . . . . . . . . . . . . . . . . 15 7.4 EO P Tr a i n i ng M e t hod s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 8.0 SYSTEM FUNCTION AND TASK ANALYSIS..................... 19 APPENDIX A EMERGENCY OPERATING PROCEDURES WRITER'S GUIDE APPENDIX B WORK PLAN FOR EOP VERIFICATION AND VALIDATION .

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1.0 INTRODUCTION

1.1 Purpose This document identifies the elements to be used by Public Service Electric and Gas Company's (PSE&G) Hope Creek Generating Station to develop its Emergency Operating Procedures (EOPs). The EOP's will provide the operator with directions to mitigate the consequences of a broad range of accidents and multiple equipment failures.

This document is based upon the NRC Guidelines for Preparation of Emergency Operating Procedures, NUREG-0899, Aug us t , 1982.

1.2 Scope This document was developed in response to supplement 1 to NUREG-0737, Item 7.2b. The guidance provided in this document applies only to the Hope Creek EOPs and not to other procedures.

1.3 Backg round Shortly after the accident at TMI, the NRC formed the Bulletins and Orders Task Force (B&OTP). within the Of fice of Nuclear Reactor Regulation. The Task Force was responsible for reviewing and directing the NRC activities associated with the Three Mile Island-type accident for all operating plants, to assure their continued safe operation.

On the basis of the NRC's review, it was concluded that

- the General Electric (GE) designed boiling water reactor (BWR) plants were quite capable of coping with small break LOCA's and feedwater transients, with or without stuck open relief valves.

O t-The NRC d id , however, identify improvements in the systems, procedures and analysis which will make the GE designed BWRs less susceptible to core damage during 1 accidents and transients, coupled with system f ailures or operator errors. One of the recommendations from the B&OTF was to restructure and reformat the current EOPs from an event basis to a symptom basis. The symptom-based Emergency Operating Procedures would be categorized according to general plant symptoms, such as loss of coolant inv e ntory , as opposed to several separate existing associated procedures , i.e., LOCA Inside Containment, LOCA Outside Containment and: Loss of Normal Feedwater.

Shortly after.the TMI accident, the Owner's Groups were formed to study and resolve problems associated with the operation of their plants. The GE Owner's Group concurred with the NRC and recommend ed that the Emergency Operating Procedures for nuclear plants be restructured and reformatted to a symptom basis, as opposed to the more event-specific basis.

The BWR Owners' Group developed Emergency Procedure Guidelines (EPGs) to be used by the utilities to develop Symptom-Based or Function-Oriented Emergency Operating Procedures. The Emergency Procedure Guidelines, Rev ision 2, NEDO-24934, June, 1982 were reviewed by the Of fice of Nuclear Reactor Regulation.

An ~ SER was ~ issued and the EPGs were issued to all licensees on February 8, 1983'(Generic Letter 83-05).

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2.0 PLANT-SPECIFIC TECHNICAL GUIDELINES 2.1 General The BWROG-EPGs will be used as a basis for the Hope Creek Plant-Specific Technical Guidelines (P-STG). The format and arrang ement of the Hope Creek Guidelines closely parallels the BWROG-EPGs and contains plant-specific information for. Hope Creek.

Since the Hope Creek P-STG is based upon the BWROG-EPGs, which has been validated by the Owners' Group and evaluated by the NRC, there is no requirement to validate the Hope Creek P-STG.

2.2 Description of Conversion Methodology The methodology for the conversion of the BWROG-EPGs to the Hope Creek P-STG is described in paragraph 3.2.1.

The Hope Creek P-STG will be developed f rom Rev ision 3 of the EPGs with deviations documented on Fiqures 1 and

2. The methodology for conversion of the Hope Creek P-STG to the EOPs is described in paragraph 3.2.2.

, 2.2.1 BWROG-EPG to P-STG BWROG-EPG backg round information will be used to determine the intent of the Guidelines and their applicability to Hope Creek. Where applicability is verified, the generic Guidelines will be converted to a plant-specific 4 guideline .that meets the intent of the source Guidel ine . This will help ensure that the prescribed operational sequence results in the desired plant condition endpoint. Where inapplicability of a Guideline is verified ,

technical justification of adaptation or omission will be provided.

The EOP writers will reference a variety of source documents for p.lant specific information. These source documents include (but are not limited to) the following :

BWROG-EPGs FSAR Draft Technical Specifications System Descriptions Currently Approved Procedures Log ic Diag rams System Flow Diagrams

As each step of the BWROG-EPGs is converted into the Hope Creek P-STG, the information on Figure 1 will be completed by the writer. The justification section will be used to provide plant-specific technical information or explain dev ia tions from Revision 3 of the BWROG-EPGs.

Each step of the Hope Creek P-STG_that presents a safety-significant deviation from the BWROG-EPGs'Rev. 3 will have an Eng ineering Evaluation attached to the Figure 1. The eng ineering evaluation will validate any safety-significant deviations by ensuring they are technically correct.

2.2.2 P-STG to EOP The writers will convert the P-STG steps into a

" l og ic ' type flowchart format thru direct incorporation where possible. In all cases, the intent of the P-STG step will be included. The format and style of this conversion will be governed by Appendix A.

As each step of the Hope Creek P-STG is '

conv erted to an EOP, step, the information on Figure 2 will be completed by the writer. Where direct incorporation of a step cannot be accomplished, the justification section will be used to briefly describe EOP step equivalency.

The information of Figure 2 will also be completed for EOP steps which incorporate plant specific directives.

o BWROG-EPG Rev.

H.C. P-STG Rev.

Pag e of

', GUIDELINE CONVERSION DOCUMENTATION BWROG STEP:

H.C. P-STG STEP:

t JUSTIFICATION:-

1 Prepared By:

Date:

Figure 1

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BWROG-EPG Rev .

OP-EO.ZZ- Rev.

Pag e of PROCEDURAL STEP CONVERSION-DOCUMENTATION H.C. P-STG STEP:

OP-EO.ZZ STEP:

- JUSTIFICATION:

h Prepared By:

Date:

Figure 2 1

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3.0 FLOWCHARTS 3.1 Utilization of Flowcharts Flowcharts.are utilized for the Operator Action Steps of the Hope Creek.EOPs. These flowcharts provide the operator with visible guidance, which will help the operators place the plant into a safe condition quickly and consistently.

The major deficiencies of event-type EOP's are (1) they required the operator to diagnose the specific event in order to mitigate the consequences of that ev ent ar.d ,

(2) they did not address multiple failures or i unavailability of various equipment.

The Hope Creek EOPs will be designed to minimize these deficiencies. This will be accomplished by selecting entry conditions to the EOP which are indications of potential emergency cenditions or conditions which, if not corrected, could uegrade into an emergency. This gets the operator into the EOP quickly. Once the EOP is entered, the order of priority is ~ established by the values and trends of the monitored parameters as the operator executes the procedures.

There is no need for the operator to attempt to memorize the Operator Action Steps because they are visible on the flowcharts which are to be placed in the Control Room.

If an entry condition occurs the operator enters and executes the EOP(s), the operator may exit the EOP(s) by clearing all the entry conditions for that procedure, or by a step within the EOP directing the operator to another procedure.

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3.2 Flowchart Control The 8 1/ 2" X 11" portion of the EOPs (Sections 1 thru

4) and the EOP support procedures (300 series) shall be located in the procedure binders, along with the rest of the Control Rcom operating procedures. The flowchart location, due to their size nnd use, requires additional control. Although relocaticn of the flowcharts due to revision or administrative controls is allosed within the Control Room, the following guidelines shall be followed reg ard ing the location and control of the flowcharts:

o The flowcharts can either be stored or displayed.

In either case, they shall remain together as a set. Examples of acceptable storage locations are a flowchart box or drafting table with a storage rack underneath the table; display examples include the top-back of the Control Console (10C651) or Operators Console (10C649). All of the flowcharts need not be displayed, those not displayed can be stored in a rack at the end of either panel. Strip magnets can aid in the stability of displayed procedures. In no case shall the location of the flowcharts obstruct any displays or controls during their storage or use.

o The flowchart location shall provide for easy access when required . Although the title block provides a quick and easy method of identifying the procedure by title and by number, add itional iden tification methods may be used. Sequentially numbered s torag e slots or numbered tabs are examples of acceptable methods of identification.

3.3 Flowchart Execution When the need arises to enter and execute the EOPs, a Senior Reactor Operator licensed ind iv idual , normally the Nuclear Shif t Supervisor, will use the flowcharts to direct the operation of the licensed Reactor Operators in the Control Room, and non-licensed support personnel and field operators. System operations should be in accordance with approved System Operating Procedures or EOP support procedures.

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4.0 EOP WRITER'S GUIDE 4.1 General The EOP Writer's Guide is a document that provides specific, detailed instructions to personnel writing or revising EOPs. In add ition to establishing sound writing principles, the guide promotes consistency of format, usage, and technical presentation among all EOPs and rev isions , independent of number of dif ferent EOP writers. The Writer's Guide will be rev ised as necessary to reflect valid feedback resul ting from procedure validation, training, and operator experience.

The Hope Creek EOP Writer's Guide is based upon the requirements of NUREG-0899, " Guidelines for the Preparation of Emergency Operating Procedures", August, 1982, and the industry's Emergency Operating Procedures Writing Guideline, INPO-82-017, July 1982.

4.2 Document Description The Writer's Guide contains detailed information on the following major topics:

o EOP Designation and Numbering - This section contains instructions for procedure numbering and revision numbering .

o Procedure Format - This section contains instructions for page format, procedure org anization , and instructional step numbering .

Additionally this section contains instructions for flowchart content, symbol cod ing , functional flow and branching .

o Flowchart Guidelines - This section contains instructions on step leng th, step content, use of log ic terms, component identification, level of detail, and step numbering .

o Mechanics of Style - This section contains instructions for spelling , hyphenation, punctuation / nomenclature, vocabulary, numerical values, etc.

A complete copy of the Hope Creek EOP Writer's guide is included as Appendix A.

5.0 EOP VERIFICATION PROGRAM 5.1 General Verification of the Emergency Operating Procedures will confirm that .-static . aspects of the procedures, such as component designations, setpoints, and format, are correct in accordance with the EOP source documents, the generic guidelines, and the Hope Creek Writer's Guide. The verification plan is modeled af ter INPO Guideline 83-004, " Emergency Operating Procedures Verification Guideline."

5.2 Verification Program Description The Hope Creek verification prog ram for EOPs will address the following objectives :

o EOPs are technically correct, i.e., they accurately reflect the Plant-Specific Technical Guidelines and other EOP source documents.

o EOPs are' written correctly, i.e., they accurately reflect the Plant-Specific Writer's Guide.

o The information presented in the E0Ps will be consistent with the qualifications, training, and experience of the. operating staff.

The verification includes the following :

o Verification of the correctness and completeness of

-the. plant-specific information merged with the generic guidelines.

o The application of human factors principles to the

'EOPs as delineated in the Hope Creek Writer's Guide.

o verification of the compliance of the resultant. EOPs with the generic guidelines f rom which they were e developed.

! o Verification of the compliance. of the EOPs with applicable operating , system, and administrative procedures.

A complete copy of the Work Plan for EOP Verification and Validation at Hope Creek Generating ' Station is included as Appendix B.

1 6.0 EOP VALIDATION PROGRAM 6.1 General Validation of the Emergency Operating Procedures will confirm the dynamic usability of the procedures by the operator and the operability of the equipment. The validation plan is modeled af ter INPO Guideline 83-006,

" Emergency Operating Procedures Validation Guideline."

6.2 Validation Program Description The Hope Creek validation program for EOPs will address the following obj ectives:

o The EOPs are usable, i.e., they can be understood and followed with a minimum of confusion, delays, and errors.

o The instruc' ions presented in the EOPs will be consistent with the shift manpower, qualification, training, and experience of the operating staff.

o Assurance that the procedures will work, i.e., that the procedures guide the operator in mitigating transients and accidents.

The validation plan includes the following :

o Comparison of the level of information presented in the EOPs with the minimum crew staf fing required by the Technical Specifications, qualification, training, and experience of the operating shift.

o Determination that the EOPs can be understood and followed without confusion, errors, and delays.

o Determination that there is a high level of assurance that the EOPs will be ef fective in providing operator guidance towards the mitigation of transients and accidents.

o Simulator exercises and control room walk-throughs will be used for EOP Validation.

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o Scenarios will be developed to ensure all EOPs possible will be exercised on the simulator. These scenarios will include multiple failures, both simultaneous and sequential.

o Control Room walk-throug hs will be performed on all EOPs not exercised on the simulator to ensure the steps which cannot be performed on the simulator are covered.

A complete copy of the Work Plan For EOP Verification and Validation at Hope Creek Generating Station is included as Appendix B.

7.0 EOP TRAINING PROGRAM 7.1 General EOP training will be a vital element in the overall operator training prog ram at Hope Creek. A unified effort on the part of the training department and the EOP writers will result in operators who are knowledg eable in both the use and the intent of these procedures.

7.2 Training Prog ram Development When developing training in the area of EOP's, the following major items will be considered:

o What type of operator training should be provided (initial, requalification).

o What method of operator training should be followed (classroom and/or simulator, etc.).

o What operator knowledge and skill level is requ ired .

o What training material is needed to support EOP training requirements.

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l o What current operator licensing requirements or l guidelines exist.

l 7.3 Training Prog ram Objectives The objectives of this training prog ram will include:

7.3.1 Review of the requirements for the EOP's from:

o NUREG-0737 TMI II Task Action Plan o Supplement 1 to NUREG-0737-Emergency Planning Requirements r

P o NUREG-0899 - Guidelines for the preparation of l

Emergency Operating Procedures 7.3.2 Discussion and review of the philosophy of the BWR Owners' Group Emergency Procedure Guidelines (EPG's) includ ing o BWR Owners' Group Generic Guidelines 15 - i

O o Need for symptom oriented procedures as opposed to event oriented procedures o Entry conditions and exit criteria o Use of flowcharts for operator actions 7.3.3 Discussion of EOP flowchart development from the BWR Guidelines through the use of the Plant Specific Technical Guidelines.

7.3.4 Understanding of the content and use of each EOP. This will include careful review and walk-through of procedure steps to ensure operator knowledge of technical bases, location of instrumentation, and use of the procedures.

7.3.5 Successful performance of a series of dynamic, practical exercises using the Hope Creek Generating Station's plant-referenced simulator to satisfactorily exercise each appropriate EOP.

7.4 Training Methods and Ev alua tion Prior to implementation of the EOP's, operator training will be conducted using classroom discussion and/or simulator exercises. -

7.4.1 Classroom discussions will be utilized to prov ide all licensed operators with instruction on the full complement of EOP's. The discussions will include a careful review and walk-through of procedure steps to ensure operator knowledge of:

o Technical basis for the procedural steps o Location of instrumentation o Procedural use and philosophy behind the procedures o Procedural interrelationships o Flowchart use o Procedures which cannot be exercised on the simulator u____.

o l Upon completion of classroom training , the  ;

operator's knowledge of the procedures will be I evaluated via written examination.

7.4.2 Simulator exercises will be used to reinforce classroom training and to provide all licensed operators with practical experience in utilizing and executing appropriate procedures as a shift (crew). This training will also serve to ,

I develop the operator's understanding of their responsibilities (roles) during an event and to develop their ability to work together as a team. A wide variety of scenarios will be used, including multiple (simultaneous and sequential) failures.

After training, the operator's knowledge of and performance using the EOP's will be evaluated.

Included in this evaluation will be an assessment of the operator's knowledge of their responsibilites (roles) during an event and their ability to ef fectively work together as a team.

7.4.3 Requalification Training All licensed operators will participate in control room walk-throughs using the EOP's during requalification training . The i

walk-throughs will be conducted in the control i

room or using the plant-specific simulator.

The training and operations staf fs will participate in presenting requalification training. Participants in the requalification training prog ram will critique the EOP's exercised during the training prog ram. Any additional training needs will be determined from this critique and formal feedback discussed in 7.4.5.

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o 7.4.4 Training on Revisions Training on minor procedure revisions will be conducted through a program of preshif t I briefings or lectures in the requalification prog ram. Training on major revisions will be conducted by the use of classroom instruction j and walk-throug hs in the control room or on the '

plant-specific simulator. If operational considerations do not allow control room wal k-throug hs , and the plant-specific simulator is not available, training on major revisions will be conducted during classroom instruction.

7.4.5 Operator Feedback Operator feedback res31 ting from EOP training will be solicited and docunie .t:J . This information will be collected following initial training and each requalification segment as specified by the Nuclear Training Center Instructor Development Manual. Additional training needs will be determined from this evaluation.

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o 8.0 SYSTEM FUNCTION AND TASK ANALYSIS A system function and task analysis was performed during the Control Room Design Review (CRDR) and is described in the Hope Creek Generating Station CRDR sun. nary report. The objective of the system function and task analysis was to determine the information and control requirements associated with control room operator emergency response tasks in order to allow a systematic analysis of the completeness and adequacy of the control room equipment to Support emergency response. The data from the CRDR task analysis is being used in the preparation of the EOPs. The task analysis will be updated on the completed EOPs. This will be done as part of the CRDR. The task analysis provides integration between the EOPs and CRDR.

Additional information regarding the System Function and Task Analysis is contained in a documented titled " Control Room Design Review Summary Report ," dated August 6, 1984.

This document has been submitted to the NRC. The results of the updated task analysis on the Control Room instrumentation information will be provided in a supplemental report to the CRDR.

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