ML20112D501

Forwards marked-up Pages to FSAR Addressing SER Open Item 12 Re Training Programs.Description of Emergency Dose Assessment Computer Model Also Encl in Response to SER Open Item 13.Info Will Be Included in Amend 9 to FSAR

ML20112D501
Person / Time
Site:	Hope Creek
Issue date:	01/07/1985
From:	Mittl R Public Service Enterprise Group
To:	Schwencer A Office of Nuclear Reactor Regulation
References
TASK-1.A.2.1, TASK-1.A.3.1, TASK-2.B.4, TASK-TM NUDOCS 8501140325
Download: ML20112D501 (41)

Text

-

O PSEGEEx 80 Park Plaza, Newark, NJ 07101/ 201430-8217 MAILING ADDRESS / P.O. Box 570, Newark, NJ 07101 Robert L Mitti General Manager Nuc' ear Assurance and Regulation January 7, 1985 Director of Nuclear Reactor Regulation U.S.

Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 Attention:

Mr. Albert Schwencer, Chief Licensing Branch 2 Division of Licensing Gentlemen:

HOPE CREEK GENERATING STATION DOCKET NO. 50-354 TRAINING PROGRAMS AND EMERGENCY DOSE ASSESSMENT COMPUTER MODEL Pursuant to the Hope Creek Generating Station Safety Evaluation Report (SER) Open Items identified below, Public Service Electric and Gas Company (PSE&G) hereby submits the enclosed information for NRC staff review. addresses the following SER open items pertaining to Hope Creek Generating Station (HCGS) training programs:

Open Item 12 (a) - Initial Training Program Open Item 12 (c) - Replacement Training Program Open Item 12 (d) - TMI Issues I.A.2.1, I.A.3.1 and II.B.4.

Open Item 12 (e) - Nonlicensed Training Programs The information in Enclosure 1 is provided in the form of marked up pages of the HCGS Final Safety Analysis Report (FSAR).

This information will be formally included in the HCGS FSAR via Amendment No. 9.

Open Item 12 ( b), pertaining to the HCGS Requalification Training Program, was addressed in a letter from R. L.

Mittl, PSE&G, to A. Schwencer, NRC, dated December 28, 1984. addresses SER Open Item 13, which requires a description of the emergency dose assessment computer model.

The description provided in Enclosure 2 will be included in a future amendment to the HCGS Emergency Plan.

g sum) M ObOOO34 b

The Energy P PDR y, phipop4 M86 nnu m,vn

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2 1/7/85 Based on the above information and on the enclosures provided herein, PSE&G considers HCGS SER open items 12 and 13 to be fully closed unless notified otherwise.

Should you have any questions in this regard, please contact us.

Very truly yours,

,/

///

Attachment C

D. H. Wagner U.S. NRC Licensing Project Manager A.

R.

Blough U.S. NRC Senior Resident Inspector NE 2 1/2a

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6 e

ENCLOSURE 1 L

i f'

HCGS FSAR 10/84 l

l 13.2

26. LENS

~

l 13.2.1 PLANT PERSONNEL TRAINING PROGRAM l

l The training program for Hope Creek Generating Station (HCGS) is l

formulated to develop and maintain an organisation qualified to j

assume the responsibility for preoperational testing, operation, maintenance, and technical considerations for-the facility.

Achievement of this goal is based on a philosophy of providing training developed from a systematic analysis of job requirements and using job and task analysis where available.

This philosophy i

is consistent with both Nuclear Regulatory Commission requirements and Institute of Nuclear r Operations (INPO)

A recommendations necessary for accred of training programs.

,4-The timetable for achieving accredit shall be consistent with INPO recommendations.

To accomplish these objectives and to provide the necessary control of the overall plant, the following three general training programs will be implemented:

a.

Initial Plant Staff Training Programs - These programs are designed to provide competent, trained personnel in all disciplines and at all levels of plant organization.

The programs are designed to allow personnel to be placed at various points, according to their training, experience and intended position.

The training procedures are detailed in thevNuclear Department Training Manual.

APPropWate.

R ualification Training Program - A requalification

,,1;essed par ogr as required by 10 CFR 50.54 (i-1),will be develope,d to provide continuous training and upgrading of plant personnel and will meet the requirements of 10 CFR 55, Appendix A and NUREG 0737 Enclosure 1.

Use will be made of the Hope Creek specific simulator.

A-::h:duled t; b; d;1iv :;d t; th: f;;ility in the ;6;;;;

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q::lifi ;tien pre;;;;

3-eill not be eveilable until 1:te !?!d.

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nd 9 ::t:blich;;;t ;f ap;;;t;; ;hif t ;;t; tion, th; li:::::i jgpg;etegL.{.ggggj.{pggtjgg_pgggggg,y{jj_y.jppjgyg..gep,gg-

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The requalification program will run on an annual basis with all program requirements completed during the two l

year requalification cycle.

The requalification program will consist of three areas; pre-planned lectures, on-the-job training and requalification examinations.

i 13.2-1 Amendment 8

~

u j

f

l 10/84 HCGS FSAR The pre-planne'd lectures will cover fundamental review Fundamental review d

fluid and operational proficiency.

training will be in those areas of heat transfer, flow, thermodynamics, mitigation of accidents involving d in a degraded core and these subject areas delineateOpera i

il will involve lectures that will focus on essent 10CFR55, Appendix A.

l i nces l

in the nuclear industry.

d The on-the-job training will ensure that each license lls and operator maintains an acceptable level of ski d

familiarity associated with plant systems, controls an l

This will be acc g lished I

l d

operational procedures.through reactivity manipulations, plant operational reviews.

i Requalification examinations will be given to determ ne l

the licensed operator's knowledge of the materia covered, areas where additional training may be These y

required and operational proficiency. examinations wil examination and an oral examination.

Personnel demonstrating a significant deficiency in a l

d given area of knowledge and proficiency may be p ace This program into an accelerated training program.

ld will be specifically structured to upgrade know e ge Successful and skills identified as deficiencies.

l be completion of the accelerated training program wil evaluated by a written and/or oral examination.

Procedures describing the content and conduct of the ll be requalification program will be developed a frr: -

opprop risk-Manual.

Replacement training - These programs are designed t provide qualified personnel for the station The General Manager - Hope Creek c.

i Operations, or the designated representative, may wa v organization.

l based portions of the training program for individua Training procedures are detailed in thegNuclearapprog,;,xh Department Training Manual.

Amendment 8 13.2-2

HCGS FSAR 10/84 l

anager - Nuclear Training is responsible foraimplementation The its programs. Prior toitsplementation, each course,

~

ofscheduled starting date, and its duration shall be approved by the General Manager - Hope Creek Operations 4r We des;yee.

The Manager - Nuclear Training will ensure that all individuals providing instruction are technically qualified to present the material and that they have demonstrated a knowledge of i

3.1-1981, instructional techniques as required by ANS/ ANSI Individuals providing instruction to license operator 4.4.7.2.

candidates will have received all appropriate training and hold i

or have held an SRO license or certification as required by the 1980, Enclosure 1, and H.R. Denton letter of March 28,There individ.;1e aill te%e en j

e_

ANS/ ANSI 3.1-1981, 4.4.7.2.

lic;;;; ;;;;eiw6.hiii sseininv y.wv6 Upon

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i

" crtic; ; rt i-th:

completion of the cold license training program and establishment i

individuals providing of the operator requalification program, 3.1-1981, specific license training outlined in ANS/ ANSI 4.4.7.2.c will participate in the requalification program as l

specified in ANS/ ANSI 3.1-1981, 5.5.1.5.

1 Figure 13.2-1 shows the present schedule for the various initial l

plant training programs. If significant differences or changes l

occur in those courses not yet conducted, the appropriate course i

l outlines and descriptions will be revised by Amendment.

l 13.2.1.1 ODeratina Department Trainino Procrass These programs are designed for individuals who will assuse the responsibility for both licensed and nonlicensed plant operating functions, as outJined in job specifications.

m; nim is proWdel4e l

1. The pf?gf*" 10 dividwd iniv ins foilowing uswee!

l Non-licensed Operator training a.

i l

b.

Reactor Operator training l

Senior Reactor Operator training c.

l d.

Shift Technical Advisor training

~

l Licensed Cp;reter Rese:1!!i::tien tisininy l

4t a l

13.2-2a Amendment 8 1

1

- ~ ---- -...- -

HCGS FSAR 10/84 I

13.2 1.1.1 Cold License Training Program 1

This program is designed for NRC reactor operator (RO) and senior i

reactor operator (SRO) cold license candidates of varying backgrounds and experience.

Candidates will be factored into the program at various points, depending on their previous experience l

i and training.

Testing and screening will be an intimate part of t

the overall training program.

All license candidates who are

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?--!=in;Techicaj p,y g g supervisors will attend the PSEEG 4 rci;;r; Still:

! ga fik Program and will meet the supervisory training requirements of l

ANSI /ANS-3.1-1981, Section 5.2.1.8 prior to core load.

l s

L To assure the experience criteria of ANS 3.1 (1981) is set, as well as the general guidelines of NUREG-0094, additional esperience will be provided by a structured observation program I

for all licensed operator candidates.

A detailed description of this observation training is shown in Appendis 13K.

13.2.1.1.1.1 Senior Reactor Operator Training Program The senior reactor operator (SRO) candidates will attend a training program consisting of, but not limited to, the following areas of instructions i

Nuclear Reactor Fundamentals a.

i b.

Reactor Startup Esperience c.

Advanced technical training j

d.

Pre-Certification system training BWR Cold certification training e.

l f.

In-plant training g.

Hope Creek Systems training h.

Pre-license examination testing and training l

l 13.2-3 Amendment 8

l.

1 HCGS FSAR 10/84 j

~

Detailed course descriptions and outlines are shown in Appendices,1,3A, 133, 13C, 13D, 13E, 13F, 13G, 13I and 13J.

l l

The Advanced Technical training will consist of two separate

)

programs, Advanced Technical Training as outlined in Appendix 13C and SS-N Training as outlined in Appendia 13F.

The Advanced Technical training program was designed for those individuals who are to be senior shift supervisors or shift technical advisors.

The SS-N training program was designed for those individual who are to be shift supervisors.

ll SRO 8-It is Mntended that through this training program a

'i candidates will obtain at least thirty (30) semester hours of f'

equivalent college level education.

With the exception of Hope Creek Systems Training the General Hanager - Hope Creek may waive any of these programs as recommended by the Manager - Nuclear Training for selected individuals based on previous emperience, training and/or licensing.

I:

Previously licensed PWR operators who do not attend a simulator certification program, shall attend a BWR operational review training program at an appropriate BWR simulator or the Hope Creek simulator when it becomes operational.

Following the Hope Creek systems training the SRO candidates will be assigned to a shift where they will participate in the cold license operator in-plant training program described in Appendis 13I.

13.2.1.1.1.2 Reactor Operator (RO) Training Program i

i The RO candidates will attend a training program consisting of, l

but not limited to, the following:

Nuclear Reactor Fundamentals a.

b.

Reactor Startup Esperience Pre-Certification system training c.

13.2-4 Amendment 8

. - ~.

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

f HCGS FSAR 10/84 i

d.

BWR Co.ld Certification training

~

e.

Hope Creek system training l

l f.

In-plant training l

g.

Pre-license examination tes*:ing and training.

l Detailed course descriptions and outlines are shown in Appendices 13A, 133, 13D, 13E, 13G, 13I, and 13J.

l

)

With the exception of Hope Creek Systems Training the General Manager - Hope Creek may waive any of these programs as recommended by the Manager - Nuclear Training for selected individuals based on previous experience, training and/or licensing.

t j

Previously licensed PWR operators who do not attend a simulator certification program, shall attend a BWR operational review training program at an appropriate BWR simulator or the Hope Creek simulator when it becomes operational.

i i

Following the Hope Creek systems training the RO candidates will be assigned to a shift where they will participate in the cold license operator in-plant training pecgram described in j

Appendia 13I.

l 13.2.1.1.1.3 Shift Technical Advisor Training I

Shift technical advisor (STA) training will meet the requirements outlined in ANSI /ANS-3.1-1981.

Training programs will consist of l

those areas where their prior education did not meet those requirements and will include plant specific ~ thermodynamics, i

l fluid flow, reactor physics, system engineering, transient and accident analysis, nuclear instrumentation, process computer, i

plant response, and duties and responsibilities.

l The STA training program will consist of, but is not limited to, 1

the following areas of instruction:

13.2-4a Amendment 8

i HCGS FSAR 10/84 Nuclear reactor fundmentals a.

b.

Ree. ace startup experience c.

Advanced technical training 4

d.

Pre-certification srstem training BWR cold certification training e.

1 f.

Hope Creek systems training I

g.

In-plant training.

-l Detailed course descriptions and outlines are shown in Appendices 13A, 135, 13C, 13D, 13E, 13G, and 13I.

I I

l l

I

'l I

13.2-4b Amendment 8 9

10/84' HCGS FSAR With the exception of Hope Creek Systems Training the General Manager --Hope Creek may waive any of these programs asre individuals based on previous esperience, training and/or l

licensing.

Previously licensed PWR operators who do not attend a simulator certification program, shall attend a BWR operational review training program at an appropriate BWR simulator or the Hope Creek simulator when it becomes operational.

All STA candidates will be assigned to NCGS staff where they will participate in the cold license operator in-plant trainingSTA candidates will attend program as described in Appendix 13I.It is not intended at this j

training with the SRO candidates.

j' J._ time to test in lieu of training as stated inVANEiufWl5"13sDeg+

,,pj

'1-

E%m'malion Teshnj ANATnioni6j

.E 13.2.1.1.1.4 BWR Prelicense "?'

09.;; W ;i...r.;

i Because of the long lead time required for cold license training, This course a Prelicensing Refresher Course will be conducted.

will be approximately 12 weeks in duration and will be scheduled An to end about 3 to 6 months prior to initial fuel loading.

NRC-type audit examination will be given during the refresherF by the audit examination.

Appendix 1.1J provides a detailed training.

description of this program.

Amendment 8 13.2-5

+ -

HCGS FSAR 10/84 13.2.1.1.2 Nonlicensed Operator Training Program J

This program is designed to make equipment operators knowledgeable of HCGS systems, operations, and procedures.

The Ope. rations-h program will cover, but is not limited to, the followingpg dgyg g

materials Tr*5 ram baseel on an l

OdeQan.divid@ previous k IB

• *wer-Mucwhro I

a.

Mathematics Refresher ence arc a l

i,,ig.

l b.

Physics and Basic Heat Transfer and Fluid Flow (HTFF)

Refresher l

Basic Power Plant Equipment (valves, pumps, etc,),

c.

Lubrication, and Job Duties d.

NSSS l

Electrical Systems lll l

e.

I f.

Auxiliary Systems g.

Health Physics Firefighting (idem 4;$icahon,nMidon M iwedid @k h.

i.

Heating Boiler j.

Procedures (as applicable) k.

Administrative Functions, Equipment Tagging, and Log Keeping 1.

Technical Specifications (as applicable).

It is anticipated that the classroom program, Appendix 13H, will last 12 to 14 weeks and will be followed by a period of in-plant l

training where the equipment operators will complete required checklists.

13.2-6 Amendment 8 l

i n

l HCGS FSAR 10/84 l

l 13.2.1.1.3 Maintenance Department Training Program

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~

Maintenance supervisors, electricians, machinists, and boiler repair personnel will generally be selected from other operating j

PSE&G facilities (fossil and nuclear) or be direct hire, i

j i

journeyman level qualified.

As such, they will alrea have l

received training appropriate for their particular ski 1 area.

l Through their previous esperience and selection / testing l

procedures these personnel will exhibit a high degree of manual desterity and the capability to learn and apply basic job skills in performing maintenance activities.

j l

l Maintenance personnel will receive on-the-job training during the preoperational test program by performing maintenance activities, Selected personnel will receive specialised vendor training on j

specific equipment or skills.

Personnel promoted to the journeyman or supervisory level will be required to i

satisfactorily complete the PSE6G Advanced r *r;rr=irer, C Training Program associated with their particular skill area.Flermonne.{,

l Pmmoiad to %e. super @ory W. vel shan umpete. %. ?nsrs raMoni.%queg.9cna Mope,.

" iffiti;;;1 Training for e ? M S p.esonn.1 will includ. a swr Technology Course, appropriate quality assurance training, l

training on plant specific maintenance procedures, and radiation worker and general employee training, as well as other programs A deemed necessary.

Procedures for these training programs rill ire are j

available in thevNuclear Department Training Manual.

OPPaPN Personnel below the supervisory and journeyman level, as a minimum, will complete the various required apprentice level training programs as their career progresses.

These programs

> "iH also h detailed in theyNuclear Department Training Manual.

i Gre.

oppropricde i

Training will be conducted by PSE&G and qualified vendor personnel.

13.2.1.1.4 Technical Department Training Program The objective of the Technical Department Training Program is to j

provide highly skilled personnel to effectively support the j

preoperational testing program and plant power operations.

)

i l

1 k

13.2-7 Amendment 8

,-,---_.-c.-n,,w_n____

1 HCGS FSAR 8/83 ave.

JL-Procedures fo'r these training programs r!!! 5e available in the gehr. Nuclear Department Training Manual.

13.2.1.1.4.1 Chemistry Section Training l

Supervisor and technician level personnel will be selected only after meeting applicable esperience requirements.

As such, they will generally have completed the appropriate training program associated with their respective job position.

Procedures for conducting these programs h available in thetNuclear o?Profed Department Training Manual.

Experienced personnel who fit that description will, as a minimum, undergo training in the following general subject areas:

a.

BWR Technology b.

Chemistry Practices and Procedures c.

Chemistry Equipment and Use g

d.

Applicable Administrative Procedures e.

Special Courses presented by the Nuclear Training Center and/or vendors, as appropriate.

f.

QA Program g.

General Employee and Radiation Worker Training.

Personnel promoted to the er;::ci;;;y ;; technic'ian level will be av required to complete the PSE6G Chemistry Technician Advanced

-c Course.ee Mr:1::: Esp;; vise; cv....,

...vigopriate so so.-

cr

ti.- jv-vveitionr h sonnel yometec: +o-He, supervisory level shai c.oqWe h ? SUS Tah; cot sp<p%,7 switte Boya.

Personnel below the supervisory and technician level, as a minimum, will complete the various required apprentice level training programs as their career progresses.

13.2-8 Amendment 1

HCGS FSAR 8/83 Chemistry personnel will receive on-the-job training during the preoperational testing program by performing their job associated tasks in, support of that testing.

Training will be conducted by qualified PSE&G and vendor personnel.

13.2.1.1.4.2 Instrumentation and Controls Section Training l

kiced er fr 'ned to mest ANSllAM 3.1-14CI, 2-Supervisory and technician level personnel will bqd;: lect:d nly d-e't:: ;;; tin; sp;1acESTE ;;p;;;;nce r quire e.tc.

As such, they will generally have completed the appropriate training program associated with their respective job position.

Procedures f er a-*- conducting these programs " A*-Se available in the/NucleaP OPProPriak Department Training Manual.

Experienced personnel who fit that description will, as a minimum, undergo training in the following general subject areas:

a.

BWR Technology b.

Instrumentation and Controls Practices and Procedures c.

Instrumentation and Controls Equipment d.

Applicable Administrative Procedures e.

Special Courses presented by the Nuclear Training Center and/or vendors, as appropriate.

l f.

QA Program g.

General Employee and Radiation Worker _ Training.

reasona ble terrco'of h Qn a

st Personnel promoted to the :;;;csisecy vc technician level will be required to complete the PSE&G Instrumentation and Controls (I&C) 4-Technician Advanced Course er Mu:1::c "wyecrisec Cwu6.e, es s W repri:te to the reep:cti;; jet, pesitien.

TenanneA protacted to 44,tuffvitory le.ve.1 Shah comph h PSEIG Tec.hnical Suptvig Sk:us?rgra

/

13.2-9 Amendment 1 9

j 8/83 HCGS FSAR Personnel below the supervisory and technician level, as a 5

minimum,,will complete the various required apprentice level training progcams as their career progresses.

IEC personnel will receive on-the-job training during the preoperational testing program by performing their job associated i

tasks in support of that testing.

l Tra.ning will be conducted by qualified PSE&G and vendor i

personnel.

2 6

l S" 13.2.1.1.4h4H Reactor Engineering Training Program l

il Prior to core load, selected reactor engineering personnel will have attended a vendor-offered course typically entitled " Station Nuclear Engineer".

Typical subject matter will include reactor i.$

behavior, control rods, shutdown margins, technical

j$ $

i specifications and Fuel Warranty Operation Provisions, core flow and thermal limit calculations, fuel failure and Preconditioning

' '4 Interim Operating Management Recommendation and water chemistry.

4 j

d l

Radiation. Protection Department Training Program 13.2.1.1.5 Supervisory and technician level personnel will be selected only As such, they afte'r meeting applicable experience requirements.

will generally have completed the appropriate training program Procedures for associated with their respective job position.

conducting these programs will be available in the NuclearExperienced Department Training Manual. description will, as necessary, undergo train j

general subject areas BWR Technology a.

Radiation Protection Practices and Procedures b.

Radiation Protection Equipment and Use i

c.

Applicable Administrative Procedures d.

i i

1 Amendment 1 l

13.2-10

_,. ~ _

HCGS FSAR 8/83 e.

Special Courses presented by the Nuclear Training Center and/or vendors, as appropriate f.

QA Program g.

General Employee and Radiation Worker Training.

~

'- Personnel promoted to the ru;rr"ircry er technician level will be required to complete the PSE&G Radiation Protection Technician 4 - Course.es "urlerr 0;;;rcicer Crur:0, rr apprcpr!:t: t: th; Slen co@ %e.beiti;n. Personnel peoM % hyusory le.W

1. :;;p.ci1 e jeL GTMI byerms:ky Skilla,Mmm.

Personnel below the supervisory and technician level, as a minimum, will complete the various, programs as their career progresses.

Radiation Protection personnel will receive on-the-job training l

during the pre-operational testing program by performing their job associated tasks in support of that testing.

Training will be conducted by qualified PSE&G and vendor personnel.

i 7

dE-13.2.1.tsk General Employee Indoctrination l

All persons regularly employed at HCGS, including temporary maintenance and service personnel, who are permitted unescorted access shall be given General Employee Indoctrination.

This training covers the following areas a.

Site Description b.

Emergency Plan c.

Security System d.

Quality Assurance Program 13.2-11 Amendment I

HCGS FSAR 8/83

~

?

e.

Radiological Health.

Personnel will be tested in the above areas to determine the effectiveness of General Employee Indoctrination.

Personnel who will routinely work in radiation and/or contaminated areas will also complete a Radiation Worker Training Program of approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Cowknuin Er'rerbr_g Trainino for Nonlicensed Plant Personnel 4-13.2.1.2 AA o ram will be provided ":: :11 c..c.:1 to ensure

,s.

that h romain proficient in their particular jobs.

, _. -. :e l

den 4tmly tvoiwinj

' 5:tr in_ ; in specific areas is provided to the extent necessary

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for personnel to safely and efficiently carry out their assigned responsibilities in accordance with established policies and procedures.

This includes operating experiences, design changes, revisions to procedures, and new procedure indoctrination.

)

f Such training may consist of vendor presentations, technical training sessions, on-the-job work experience or programmed l

instruction.

Personnel are evaluated on an annual basis where l

individual needs for retraining will-be identified.

13.2.1.3 General Employee Indoctrination Reaualification All persons regularly employed at HCGS, including temporary maintenance and service personnel who are permitted unescorted access, shall requalify in General Employee Indoctrination annually.

This is accomplished by attending the requalification class and obtaining a satisfactory score on an examination JL covering the areas mentioned in Section 13.2.1.1,4/7.

l Personnel trained in the Radiation Worker Training Program will requalify annually by attending the Radiation Worker Review Program of approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Satisfactory completion of that program also meets General Employee Indoctrination Requalification requirements.

13.2-12 Amendment 1

J HCGS FSAR 8/84

~

i 13.2.1.4 Roolacement Trainina for Nonlicensed Plant Personnel Replacement training is designed to supply qualified personnel at all levels and job positions within the plant organization.

Training is carried on at all job levels to qualify that d

particular individual to effectively perform the required job l

functions.

Qualified personnel who are promoted to the next job level are placed, as rapidly as possible, into the appropriate training program.

It is the general policy of PSE&G to promote from within.

In this manner, as an individual progresses, he/she is immediately trained for the new position and capable of l

supporting and training personnel in the lower classifications.

Personnel who are directly hired into job positions above the entry level will meet or exceed the applicable requirements of I

that position.

Training programs will be developed for these personnel to familiarize them with appropriate HCGS-specific material.

j t

Training will be conducted by qualified PSE&G and vendor personnel.

The training programs will be described in the Nuclear Department Training Manual.

f 13.2.1.5 Replacement Trainino for NRC IAcensed Plant Personnel l

%\\\\owin3 iwow.e. 04 4M. PM CP""+'"3 '"*"589 "P9'*" for

[

A-t~ raining h RC licensed replacement personnel will, as a minimum, meet the existing NRC requirements as outlined in 10 CFR 55.21,

.22,.23, appropriate NUREGs, and the H. Denton f

.A letter of March 28, 1980 and all applic ble training (requirements

.A of ANS/ ANSI 3.1-1981 3 These programs described in the opeopvde i

d as regulations

. g k Nuclear pepartment Training Manual and ese rev se and job requirements change.

13.2.2 FIRE BRIGADE TRAINING PROGRAM l

Fire protection training will be conducted in accordance with the guidelines of the SRP (NUREG 0800) Section 13.2.2.II.6, 10CFR50 Appendix R and Branch Technical Position CMEB 9.5.1 Section C.3.d.

This training will include classroom instruction, hands-on fire extinguishing and plant drills.

13.2-13 Amendment 7 i

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10/84 HCGS FSAR SIh We. Say2= -hg h_mm 13.2 2.1 J -TheIIIre Brigade Trainintirogram is designed to ensure that the employees assigned to th(=U re brigade are capable of providing adequate manual fire fighting strategies to control fires that The program might occur at the Hope Creek Generating Station.

will cover, but is not limited to the following:

Indoctrination of the plant fire fighting plan.

l a.

l Identification of fire hazards.

b.

l The properties of the product of combustion.

c.

Identification and use of all fire fighting equipment.

l d.

The proper use of communication, lighting, ventilation, '

e.

and emergency breathing equipment.

i including

{

Familization with the layout of the plant, f*

l access and egress routes to each area.

l Correct method of fighting fires, including fires in energized electrical equipment, fires in cable and g.

cable trays, hydrogen fires, fires involving flammable and combustible liquids or hazardous process chemicals, fires resulting from construction or modifications (welding) and record file fires.

The direction and coordination of the fire fighting h.

activities (fire brigade leaders only).

I 56 Detailed review of fire fighting strategies and i.

l procedures.

Review of the latest plant modifications and j.

corresponding changes in fire fighting plans.

1 l

Amendment 8 13.2-14

HCGS FSAR 10/84 The classroom instruction will include the following course saterial a.

Fire Fighting Plan l

1.

Response to alarms l

i 2.

Responsibility of members l

l 3.

Reason for fire brigade l

l b.

Identification of Fire Hazards l

1.

Concept of fire l

2.

Properties of flammable and combustible liquids l

3.

Hazardous chemical properties l

l 4.

Boiling liquid, expanding vapor explosion l

c.

Products of Combustion l

1.

Products of burning plastics l

2.

Products of smoke l

3.

Properties of carbon monoxide 1.

4.

Properties of contaminated smoke l

l 5.

Effects of heat 6.

Ventilation 13.2-15 Amendment 8

HCGS FSAR 10/84 d,.

Fire Fighting Equipment l

1.

Fire detection l

l l

2.

Fire suppression l

e.

Types of Fires l

~

l 1

f.

Auxiliary Equipment l

l l

g.

Plant Modifications Actual hands-on fire extinguishing will be conducted to provide brigade members with actual fire extinguishing and the use of emergency breathing apparatus under strenuous conditions.

These practice sessions will be held at least once per year for each s k fire brigade member, j;en:. K..I1: ri11 1. :..;p iw y..i :hift t{ _=11 y

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Each drill will include the simulated use of fire-fighting equipment required to cope with the situation and type of fire selected for the dril?,

The area and type of fire chosen for the drill will differ from those used in the previous drill so that brigade members are trained in fighting iires in various plant Th's situation selected will simulate the size and areas.

arrangement of a fire that could reasonably occur in the area.

selected, allowing for fire development due to the time required to respond, to obtain equipment, and organize for the fire, assuming the loss of automatic suppression capability.

At least one drill per year will be performed on a back shift for each shift fire brigade.

/

d W e. s a c.

13.2-16 Amendment 8 n

INSERT Al HOPE CREEK FSAR SECTION 13.2.2 Plant drills will be held at specified intervals, not to exceed three months, for each shift to allow Site Fire Brigade members the opportunity to practice as a team and to ensure adequate l

l procedures and readiness.

Each Site Fire Brigade member must l

participate in at least two drills per year.

Fach drill will be preplanned to establish training objectives and will be critiqued to determine how well the training objec-I tives have been met.

Performance deficiencies noted will be remedied by additional training.

Records regarding drill attend-ance, deficiencies and follow-up training requirements will be maintained by the Nuclear Training Center.

Fire drills, as a minimum, will assess the fire alarm's effec-l tiveness, time to assemble the Site Fire Brigade, use of the fire-fighting equipment, fire-fighting strategies and the effec-tiveness of the Prigade Leader.

l l

l l

l l

I I

j s

..-a.

- ~ - - - -

't.

HCGS FSAR 10/84 a(k s;A At.least one drill for each shiftafire brigade per year will be.,

unannounced to determine the fire fighting readiness of the +1;.yg l

fire brigade, brigade leader, and fire protection systems and l

drillwillensurethattheresponding_g{izinganunannounced equipment.

Personnelplanningandautg

-__t fire brigade members are not aware that a drill is being planned until it is begun.

l Unannounced drills will not be scheduled closer than four weeks.

Unannounced drills will be planned and critiqued by members of the management staff responsible for plant safety and fire 3,. y y,;g Performance deficiencies of affire brigade or protection. Tire brigade members will be remedied by scheduling individual %

additional training for the brigade or members.

Unsatisfactory drill performance will be followed by a repeat drill within thirty days.

l At three-year intervals, a randomly selected unannounced drill will be critiqued by qualified individuals independent of the licensee's staff.

A copy of the written report from such individuals shall be available for NRC review.

Regularly planned meetings will be held every three months for allymembers to review changes to the program.

Whs 9nt br;$ade Periodic refresher training will repeat classroom instruction over a two-year period.

These sessions may be concurrent with planned meetings.

TrainingofthepNa$bfirebrigadewillbecoordinatedwiththe local fire department so that responsibilities and duties are delineated in advance.

This coordination will be part of the l

training course and will be included in the training of the local l

fire department staff.

• Local fire departments will be provided training in operational precautions'when fighting fires on nuclear power plant sites and will be made aware of the need for radiological protection of personnel and the special hazards associated with a nuclear power plant site.

Instruction will be provided by qualified individuals who are knowledgeable, experienced and suitably trained in fighting types of fires that could occur in the plant and using types of equipment availabic in nuclear power plants.

13.2-17 Amendment 8

HCGS FSAR 10/84 i

Instructionwiilbeprovidedforallemployeesonceperyear.

It will'be reposted,on an annual basis. Jhe instruction will be Y given on (a) the fire protection plar)K, (b) the evacuation routes, and (c) the pror:edure for reporting a fire.

Instruction will be provided for security personnel that addresses (a) entry procedures for outside fire departments, (b) crowd control for people exiting the station, and (c) procedures for reporting potential fire hazards observed when touring the facility.

Instruction will be provided to appropriate shift personnel that complements that given to members of thevfire brigade.

Si+C-l Instruction will be provided to temporary employees so that they are familiar with (a) evacuation signals, (b) evacuation routes,.

and (c) the procedure for reporting fires.

Station personnel will participate in an annual accountability and evacuation drill.

l l5 7 2.LFire Protection Staff Training for the fire protection staff members shall include courses in:

Design and maintenance of fire detection, suppression a.

and extinguishing systems.

b.

Fire prevention techniques and procedures.

l Training and manual fire-fighting techniques and c.

procedures for plant personnel and the fire brigade.

y Sife-13.2-18 Amendment 8 y

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HCGS FSAR 10/84 l

APPENDIX 13J PRE-LICENSE EXAMINATION TESTING AND TRAINING Presented by: PSEsG or selected contractor personnel.

Objectives: To determine individual candidate's ability to operate the plant in a safe and competent manner and to identify areas of weakness that may be corrected prior to administration of the NRC license examinations.

==

Description:==

The pre-license examination testing and training period will consist of an intensive period of instruction and testing prior to the NRC license examinations.

The instructional phase of this program will consist of the the following:

a.Ne.(&on %Jt;plicsHo*t Y l -

a.

Classroom presentations on 4 weeks) 3mc '

• 4 ]%.as / t F.fydue/ priseur 1.

Reactor theory review,p

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2.

Heat transfer review l

a. sau +. - +. e.a von s " w C.11& %,

3.

du N mechanics review l

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- pr w ake eIeses 4.

Thermo8ynamics review l

a Cwcle diep c>4a.etys/5, b.WW.'ere y 5.

Health phy a review +5 l

a.%t o\\

cN

(. *u' nr.4e@-

+eV'6%i NfI 6.

Technical specification and administrative procedures review 7.

Related industry events relevant to operation, b.

Simulator Operation / Classroom preparation (*50/50) (7 weeks) 13J-1 Amendment 8 l

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HCGS FSAR 10/84 3

APPENDIX 13K PLANT OBSERVATION / EXPERIENCE TRAINING Objective:

To provide each cold license candidate (RO/SRO) with extensive operating experience of an operating nuclear facility.

==

Description:==

Demonstration of extensive operating experience of each cold license candidate is essential to ensura a safe and timely initial reactor and plant startup.

This program is j

designed to augment the operator training described in Appendices l

13A, 138, 13C, 13D, 13E, 13F, 13G, 13I, and 13J to ensure l

adequate operating experience of a comparable reactor facility.

The following sections describe the observation / experience training requirements for each area of training, reactor operator and senior reactor operator.

Specific segments of each section may be waived by the General Manager-Hope Creek Operations for select individuals based on previous training and experience.

I.

Reactor Operator (RO) l A.

Complete simulator certification training program at either the Susquehanna simulator or the Hope Creek simulator as described in Appendix 13E.

This program gives each operator hands on experience related to plant operating characteristics of a large (1100 MWe) BWR under normal, abnormal and emergency conditions.

B.-

Participate on shift for two weeks at the Salem Generating Station (1000 MWe PWR)

'/

1.

This program will introduce the operator to PSE&G corporate policies regarding'the operation of the nuclear facility and administrative procedures covering shift conduct, safety tagging, emergency response and surveillance procedures.

The format and bases for many of these procedures will be very similar to those used at the HCGS.

This therefore, provides early training for the operator on the conduct of operations at HCGS.

L l

13K-1 Amendment 9

~

HCGS FSAR 10/84 2.

This program will introduce the operator to the Bailey controls system and their operator interface requirements as these will'be identical to those utilized in the HCGS control room.

l l

l 3.

This program will introduce each operator to the

(

size and complexity of a commercial nuclear l

facility including the radiological precautions N)

'C and health physics procedures.

G T) g.

Complete operator in-plant training requirements described in Appendix 13I.

l 6 W.

Complete the pre-license examination and testing l

program described in Appendix 13J including simulator training on the HCGS plant referenced simulator or a simulator of a similar type plant.

II.

Senior Reactor Operator (SRO)

Non-Previously Licensed A.

Complete simulator certification training program at the Susquehanna training simular as described l

in Appendix 13E.

B.

Participate on shift for two (2) weeks at the Salem Generating Station (1000 MWe PWR)

C.

Complete operator in-plant training requirements

/ described in Appendix 13I.

D.

Participate on shift for a minimum of'six (6) weeks at a large commercial operating BWR facility to meet the experience requirements for ANSI 3.1-1981 Section 4.3.1.2(b) 1.

This participation allows for the involvement in the day-to-day operation of the facility as a member of the operating shift.

This participation includes review of procedures i

13K-2 Amendment 8

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HCGS FSAR 10/84 s

and technial specifications, observation of surveillance testing and control tr manipulations.

This participation gives the supervisor first hand experience in the operation of a large commercial BWR facility.

E.

Complete the pre-license examination and testing program described in Appendix 13J including simulator training on the HCGS plant referenced simulator or a simulator of a similar type plant.

Previously Licensed-PWR e

A.

Complete a two (2) week simulator training program at the Susquehanna training simulator or similar type plant to familiarize the individual with the controls and respopse. characteristics of a large BWR.

B.

Participate on shift for two (2) weeks at the Salem Generating Station C.

Complete operator in-plant training requirements described in Appendix 13I.

D.

Participate on shift for a minimum of six (6) weeks at a large commercial operating BWR facility to meet the experience requirements of 4JC 2.1-y W Gi, Cictic.^. 4.3.'

?( N Nf.c Gew.'c L e t/e< gy.jg E.

Complete the pre-license examination and testing

,/ program described in Appendix 13J including simular training on the HCGS plant referenced simulator or a simulator of a similar type plant.

Previously Licensed - BWR

?..

7;rticipet wu shiic for two tai.cck; ;t ti.e fil;; C r.cratir.g Statier-

-4dri$. Complete operator in-plant traininn requirements described in Appendix 13I.

13K-3 Amendment 8

HCGS FSAR 10/84 sker 8. Complete the pre-license examination and testing program described in Appendix 13J including simulator training on the HCGS plant referenced

-simulator or a simulator of a similar type plant.

In addition to those requirements stated in II above, those SRO license candidates who are scheduled to be senior shift supervisors will participate in a six (6) month program at the Susquehanna Steam Electric Station designed to meet the experience requirements set forth in Generic Letter 84-16 dated i

June 27, 1984.

This program incorporates both participation as a l

member of the shift of an operating power reactor and during the initial fuel loading and power ascension testing of a large BWR.

Summary: Through this program, each cold license candidate will obtain an extensive working knowledge of large commercial BWR nuclear facilities and, combined with previous training and operating experience make safe and reliable operators.

References:

ANSI 3.1-1981, Section 4.3.1.1 4.3.1.2 4.5.1.2 10 CFR 55.25(b)

/

Generic Letter 84-10 dated 4/26/84 Generic Letter 84-16 dated 6/27/84.

/

13K-4 Amendment 8

HCGS FSAR 10/84 OUESTION 630.4 (SECTION 13.2)

With regard to training in the use of plant systems to control or mitigate an accident in which the core is severely damaged, please provide the training programs and schedule fort a.

Licensed operators and senior operators b.

Other plant personnel (Ref. H. R. Denton letter of March 28, 1980 and II.B.4 of NUREG-0737)

RESPONSE

Licensed Operators and Operations Personnel NUREG 0737,Section II.B.4 requires that training of plant personnel be conducted to teach the use of installed equipment and systems to control or mitigate accidents in which the core is severely damaged. to the H. R. Denton letter dated 3/28/80 identifies the topics that should be included in the

~

training program.

In addition this training will stress HCGS system information as it relates heat transfer, fluid flow and thermodynamics consideration to mitigation of core damage.

The HCGS operator training for mitigating core damage is under development. "!t ;;11 interperate 511

identi';ed 17. $6 enclosure 3 of the 3/28/80 letter as it.;,..

applicable to a BWR:

A.

Incore Instrumentation 1.

Use of fixed or movable incore detectors to determine the extent of core damage and geometry changes, I

i 2.

Methods of determining peak temperatures, extended range readings and direct readings at terminal junction.

3.

Methods of calling up incore data from plant process computer.

B.

Vital Instrumentation 1.

Instrumentation response in an accident environment; failure sequence & indication reliability.

2.

Alternate methods for measuring flows, pressures, levels and temperature.

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MM,d,a Opercrhcas chMrs-h Y.c Ucemied OFe**. sw$t b 3 l

630.4-1 Amendment 8 i

l.__,_

. _ __.....,_.~ ______ _

HCGS FSAR 10/84 C.

Chemistry l

1, Expected. chemistry results from severe core, damage.

2.

Expected isotopic breakdown for core damage (clad damage) 3.

Corrosion effects and time to failure.

D.

Radiation Monitoring 1.

Response of process and area radiation monitors to severe damage; behavior when saturated; alternate methods of obtaining radiation readings from detectors, use of detectors to determine core damage.

2.

Methods of determining dose rates E.

Gas Generation 1.

Methods of H, generation during an accident; other sources of gases (Xe, Kr); techniques for venting and i

disposal of non-condensibles.

2.

H, flammability and explosive limit; containment inertion and sources of O, in containment.

l l

3.

Methods for removal or reduction in H,,

0, concentrations.

This is to be a continuing process of the license operator training program where all of the areas identified will be covered.

This training will include class room presentations, simulator performance and evaluation and in-plant demonstrations and will take place during the followings o

Simulator Cold Certification o

Hope Creek Systems training o

Shift Cycle continuing training

'o Pre-Operational testi~ng o

Hope Creek simulator training Normal, Abnormal and Emergency Operating Procedure o

training o

Pre-license examinations, audits and review.

l 630.4-2 Amendment 8 L

o

HCGS FSAR 10/84 T

The Hope Creek simulator is to play a vital role in the training of operations personnel in determining the extent and mitigating core damage.

- t. i; ::p ;t;d te to deli.e ed ;.d eccepted in th:

fell rf

'?"t.

Plant operating procedures and emergency operating procedures also play a vital role in adequate training on core damage mitigation.W T;.eee e e exp;;t d i.v oe avaii ol. i.,y Joiu. y

!aat. thar-ferr full ispi.ae..tetien f =iti; tir; cere di r;:

trei..ing is expe Led t J;n; r; 1000.

1 Other Plant Personnel NUREG 0737 Section II.B.4 requires that managers and technicians in the Instrumentation and Control, health physics and chemistry I

departments receive training in the use of installed instruments and systems to control and mitigate accidents involving a degraded core commensurate with their duties and responsibilities. to the H. R. Denton letter dated 3/28/80 and INPO document STG-01, Rev. I dated 1/15/81 identify those topics that should be included in these training programs.

Plant operating and emergency procedures play a vital role in the, training of core damage mitigation.

These procedures are expected to be available by January 1985.

Training to recognize and mitigate the consequences of core damage for the I&C, I

chemistry and health physics managers and technicians will be l

incorporated into the respective technician training programs by j

January 1985.

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630.4-3 Amendment 8 i

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4 9

9 9

ENCLOSURE 2 I

l l

I l

ACCIDENT ASSESSMENT Accident Assessment Instrumentation i

There are several monitoring systems used to support emergency I

planning activities for the Hope Creek Generating Station.

The plant computer systems and their functions are described in FSAR Section 7.5.1.3.3.

Specifically, the primary systems utilized to support emergency planning activities are:

Control Room Integrated Display Systems (CRIDS)

(PSAR Section 7.5.1.3)

Radiation Monitoring System (RMS) (FSAR Section 11.5 &

12.3.4)

Meteorological Monitoring System (MMS) (FSAR Section 2.3.3)

Post-Accident Sampling System (PASS) (FSAR Section 9.3.2)

The CRIDS system is primarily an operator tool and will be used to provide operator information on plant status.

All instrumentation for plant systems assessment is included in Table 7.5-1 of the FSAR.

This table provides a cross reference to Regulatory Guide 1.97, Revision 2, requirements.

The primary systems which support dose assessment activities are the RMS, MMS, PASS.

Accident assessment modeling capabilities for Hope Creek are provided by the radiation monitoring system and the use of time-shared facilities from Pickard, Lowe and Garrick (PLG) which include the use of MIDAS (Meteorological Information and Dose Assessment System) software.

The RMS is a computerized digital radiation monitoring system consisting of a Central Radiation Processor (CRP) (two VAX ll/750's), and a network of Local Radiation Processors (LRP) provided throughout the plant to monitor process systems, ventilation effluent, and local area radiation monitors.

The LRPs have sufficient " intelligence" to support themselves and to function as a stand alone system should the CRP be unavailable for communication with the LRPs.

LRPs have local displays which provide for local input, output, and data acquisition.

The radiation monitoring system will be used to provide emergency response personnel information nece:sary for dose assessment.

The Meteorological Monitoring System is a computerized digital data acquisition system which provides information from the Artificial Isignd meteorological monitoring tower.

The meteorological monitoring system conisists of one communication computer (DEC 11/23) and a primary and back-up data acquisition system (DAS).

Information from the meteorological monitoring system is available independently in the Hope Creek EOF and through dial-up wherever access is necessary.

The meteorological information is relayed through data link to the Hope Creek radiation monitoring system computer (CRP) and is available for any location where the radiation monitoring system display keyboard printers (DKPs) are available.

The locations include the Hope Creek Radiation Protection Control Point, Hope Creek TSC, Hope Creek Control Room, and Hope Creek EOF.

Also, meteorological information is relayed through the CRP to the CRIDS computer.

The Post-Accident Sampling System is a standard General Electric design.

All NUREG 0737 requirements for analysis of containment atmosphere and reactor coolant system samples are supplied.

i In addition to the systems described above, a list of portable sampling and survey instrumentation will be provided by July 1985 as per the commitment in the Hope Creek FSAR.

Multi-channel analyzers for isotopic analysis are also available within the Hope Creek Station with back-up support available from Salem Station.

l Radiolocical Assessment Reactor Coolant Sampling Analysis of Reactor Coolant samples provide the EDO with i

information on the status of the reactor core.

These samples can be used to provide confirmation of a loss of one of the fission product barriers.

Dose Assessment from Plant Radiation Monitoring System The radiation monitoring system computer provides early indication of abnormal radiological conditions from both process and area monitors.

The radiation monitoring system provide monitoring capability for the radiological parameters identified in Regulatory Guide 1.97 (this includes high range monitoring capability for effluent l

release paths.)

l The Hope Creek CRP provides release rate calculation, dose l

rate calculations and dose integration.

Most calculations l

are provided using a modified puff advection model which includes a straight line gaussian modification for the initial release calculation.

Dose conversion factors are values taken from Regulatory Guide 1.109.

The system provides for data storage and Regulatory Guide 1.21 reporting.

i l

MIDAS software provided by PLG will be installed on the VAX to provide additional emergency dose assessment modeling capability.

This software is intended to be installed prior to the end of 1985.

Until the MIDAS software is provided on the VAX hardware, time share arrangements have been made with PLG using dedicated telephone lines to supplement the dose l

assessment capability of the Hope Creek CRP.

i The MIDAS system has two plume dispersion models available.

One that utilizes the straightline gaussian technique and a second that estimates plume trajectory utilizing a segmented approach.

A Tektronix 4115 19" Color graphics terminal with hard copy devices (color and grey scale) is provided at the EOF.

In addition a Tektronix 4107 13" Color terminal and a grey scale i

copier will be provided in the Hope Creek Control Room and TSC.

All terminals will be connected by dedicated phone lines or back-up dial-up phones.

i Results of real time atmospheric dispersion and dose calculations for accidents are available in tabular and l

graphical form.

Software is available for the models referred j

to in NUREG-0654, Appendix 2 as Class A and/or enhanced Class A.

I The Class A model used for real time assessment of dispersion is the standard Gaussian model.

The graphical isopleth

output, representing a straightline Gaussian shaped plume was designed to supplement the plastic overlays (for maps of the same scale) currently found in the emergency kits in response facilties.

A basemat map of the site is plotted along with the isopleths so that both appear on the same plot.

I As per NUREG-0654, Appendix 2, the enhanced Class A model will be used for estimating diffusion and exposures out to 50 miles.

The model currently planned for use at Hope Creek is a plume segment model based on a program developed by PLG called CRACIT (for Calculation of Reactor Accident Consequences Including Trajectory) which is similar in concept to that of the CRAC program which was written for the Reactor Safety Study (WASH-1400).

The basic functions of the plume segment model as the calculation of meteorological dispersion of the released radioactive material as it travels down wind and the estimation of the resulting doses from this material.

The meteorological 1

dispersio,n is modeled assuming Gaussian diffusion and variabletrajectory transport.

Several choices are available to the user for the source term.

If a Design Basis Accident is assumed, but the release rate is unknown, preset release parameters can be used for up to ten accident scenarios.

Otherwise, real time data from effluent monitors can be used.

e o

The dose calculations in both models provide information based on Protective Action Guides (PAGs), that is used in making protection action decisions.

Projected integrated organ doses for the whole body and thyroid organs are computed as a function of distance downwind and for a given short term (usually 15 minute) release.

These pathways are used in the plume segment model including plume shine, inhalation and ground shine.

The plume model includes both finite and semi-infinite cloud assessment.

The whole body dose consists of the sum of the plume shine dose due to the plume passage overhead, inhalation dose due to inhaling airborne radioactive material and ground shine dose from particulates deposited on the ground.

The thyroid inhalation dose is reported separately for use in comparison with PAGs, although the plume shine and ground shine components are available in tables.

The average dose rate (mrem / hour) is also estimated from the three pathway components.

The Class A model does not consider particulates (other than iodine) or ground shine.

Either model can be run in a predictive mode using the most recent meteorological data.

Thus, persistance of meteor-ological conditions is used for all dose projections.

Calculation routines are also provided for making longer term dose estimates (for more than one 15 minute release).

Versions are available for either the straight line or the plume segment models.

Releases are simulated as several short term releases, each having a separate plume according to the meteorological conditions for that time.

The dose over all releases for each of up to four requested projection time periods can be displayed graphically as isopleths on the CRT.

Procedures will be developed to monitor potential release pathways and perform dose assessment.

Techniques will be utilized to re-late dose rates inside containment to the dose at the exclusion area boundary for the protective action levels of 1 and 5 rem for different meteorological conditions.

These techniques will allow for emergency action levels to be identified as a function of actual meteorological conditions.

L