ML18086A889
| ML18086A889 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/18/1981 |
| From: | Schneider F Public Service Enterprise Group |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML18086A888 | List: |
| References | |
| NUDOCS 8108250220 | |
| Download: ML18086A889 (12) | |
Text
Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430- 7373 Production June 18, 1981 Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission Off ice of Inspectibn and Enforcement Region I 631 Park Avenue King of Prussia, PA 19406
Dear Mr. Grier:
RESPONSE TO EMERGENCY PREPAREDNESS APPRAISAL (APPENDIX A AND B)
MARCH 23 -
APRIL 2, 1981 SALEM GENERATING STATION DOCKET NOS.
50~272 AND 50-311 We have reviewed the results of your Appraisal which was conducted on March 23 - April 2, 1981, and transmitted with your letter of May 19, 1981.
Our *response to the Appendix A and B items is attached as Enclosures 1 and 2 respectively.
The response and implementation of the Appendix A items were reviewed and found to be responsive by Mr. Dale Donaldson of your staff.
A revised Salem Emergency Plan and Procedures which reflects our overall response to the Appraisal was submitted to the U.S. Nuclear Regulatory Commission on May 26, 1981.
We feel that our Emergency Preparedness Program including the commitments and programs described in Enclosure 1 provides for an adequate state of on-site emergency preparedness as required by 10 CFR 5 0. 4 7 (a) ( 2 ).
If you have any further questions concerning thi$ matter, please feel free to contact me.
Sincerely, Enclosures
,,--------------- -- ----~
8108250220 810819 -
~DR ADOCK 05000272 PDR
ENCLOSURE 1 RESPONSE TO EMERGENCY PREPAREDNESS APPRAISAL APPENDIX A Item 1 Item 2 Item 3 Item 4 Item 5 The Manager -
Emergency Preparedness has been given the direct working level responsibility and authority over all aspects of the development and maintenance of the Emergency Preparedness Program.
A description of this authority and responsibility is given in Section 18 of the Emergency Plan (Revision 0).
Section 3 of the Emergency Plan has been revised to reflect functional areas of the emergency activity, reporting chains and interrelationships for functional areas down to the working level.
New functional descriptions, job descriptions arid organization charts have been added.
A cross reference to Table B-1 of NUREG-0654 has also been provided.
The Assistant to Manager -
Salem Generating Station has been charged with the responsibility of maintaining a list of qualified individuals who perform emergency planning activities.
Addendum 1 currently lists those individuals who are assigned specific on-site emergency response functions.
Update training was completed on May 15, 1981 and as a result a revision to Addendum 1 will be made.
Figures 3~1, 3-2 and 3-3 of Section 3 of the Emergency Plan show how the Radiation Management Corporation and the Salem Memorial Hospital report into the Emergency Response *organization.
Other support organizations will be di~ected to report to the Site Support Manager (shown in Figure 3~3)' for reassignment to other in-dividuals within the Emergency Response Organization.
These assignments will be made on a case by case basis and in ac6ordance with the services to be provided.
section 4 of th~ plan identifies off-site support organizations.
Th~ various administrative off-site support groups are listed in EP II-6.
Section 3 of the Emergency Plan contains a functional description of each position noted on the Organization Charts.
The* candidates to fulfill those positions are noted as a part of the functional descriptions.
EP lI-4 contains a list of those corporate individuals whO a,re qualified to perform emergency response functions.
Item 6 Item 7 rtern 8 Item 9 Item 10 L A new Emergency Preparedness Training Program is presently under development and will be completed by September 1, 1981.
This training program will contain lesson plans, training objectives, and means for verifying attendee performance and the means to train the emergency organization in changes of assignment or responsibilities.
Short term training has been provided to individuals assigned Emergency Preparedness duties and records of this training are available at Salem Generating Station for NRC inspection.
This training fell into three categories, initial emergency preparedness training of approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration, emergency preparedness changes training of approximately 1 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> duration and Operations Support Center training of approximately 1-1/2 hours duration.
Training in accordance with the training program being developed under Item 6 noted above will be completed by January 1, 1982.
The conceptual use and staffing of the TSC has been reviewed in light of the organization described in Section 3 of the Emergency Plan.
Section 3 describes the transfer of the various emergency planning functions from the normal on-shift organization (Control Room) to the Technical Support Center and then to the Emergency Operations Facility.
Section 9 of the Emergency Plan
. gives a description of the facilities available at the TSC.
The Operations Support Center has been reevaluated in 1,ight of the organizational changes and the location in the aisleway between the two Control Rooms has been found to be ~dequate. If increased staffing is required, the function of the Operations Support Center will be transferred to the Machine Shop in the Clean Facilities Buil,ding CB Building).
An OSC coordinator, described tn Section 3 of the Plan, will direct the operations of the. OSC.
EP I-19 details the activation of this facility.
The. Emergency Operations Facility and its conceptual use and staffing has been reviewed in light of the organizational ch~nges. Section 3 of the Emergency Plan de~cribes this functional use and staffing and Section 9 de~cribe~ the facility itself.
This new organization reflects the overall coordination of response ~onsistent with NUREG-0654.
Item 11 Item 12 Item 13 Item 14 Item 15 Item 16
- EP V-2 describes the procedures for obtaining plant vent samples.
Demonstrating that plant vent samples collected with the Interim High Level Sample System emergency conditions will be representative was provided via Porter Consultants analysis dated April 22, 1981 (entitled "Sample Line Plateout Factors for Particulate
& Halogens In the Interim High Level Sample System").
Implementation of this plateout information will be via a revision to EP V-2.
Assembly/Reassembly areas for individuals who may be evacuated from Hope Creek and Salem and/or recalled to augment the on-site response organization have been reevaluated.
The new areas are the Salem or Hope Creek parking lots or Quinton Township School.
Provision for supplies and equipment for decontainating persons and vehicles evacuated from Salem and Hope Creek are described in Emergency Procedure EP I-12.
As a result of the reevaluation of the Operations Support Center, it has been determined that no additional equipment is needed in the OSC to support repair and corrective action teams.
These teams will obtain the necessary equipment for performing their functions from their normal duty stations.
If radiation protection and/or habitability equipment is needed for these teams, it is available at the control point in sufficient quantity.
The Salem Generating Station Emergency Instructions have been appropriately revised to direct the operators to reference the new Accident Classification Guide in EP I-0.
This Accident Classification Guide then directs the ~perator to take emergency actions under Emergency Procedures EP I-1 through EP I-4.
The Accident Classification Guide is contained in Section 5 of the Emergency Plan.
Appropriate on the spot changes to specific Emergency Instructions have been made.
The emergency action levels have been reviewed and a new Accident Classification Guide in EP I-0 has been developed which provides clear, readily observable, site spedif ic indications that EALs have been reached or e:x:ceeded.
Direction to proceed to the Accident Classification Guide is given in the Salem Generating
$ta.ti.on Emergency Instructions.
Item 17 Item 18 Item 19 Item 20 Item 21 Item 22 Emergency procedures have been developed for the Emergency Response Manager EP II-1, Site Support Manager EP II-2 and the Radiological Emergency Manager EP II-3 which are the three primary functions associated with making recommendations for protective actions to off-site authorities from the Emergency Operations Facility.
These procedures describe how functions are transferred from the Technical Support Center to the Emergency Operations Facility.
Procedure EP II-4 has been implemented for calling in all corporate licensee personnel having emergency duties associated with the Emergency Operations Facility.
Call in procedures for station personnel are contained in EP I-1 through 4.
The call in list is contained in Addendum 1.
Protective Action Guides have been developed that correlate certain plant conditions directly with EALs.
This procedure, EP I-4, Attachment 5, gives actual distance and sector protective action recommendations based upon plant conditions and wind direction.
Procedures for containment air sampling under accident condition using interim equipment have been developed and are EP IV~l21 for Unit 1 and EP IV-122 for Unit 2.
A new Evacuation Procedure for personnel at the Salem and Hope Creek sites has been implemented.
This new procedure EP I-12 (Table V) takes into account the single access road and provides the option for evacuating personnel to other areas on Artificial Island based upon meteorology and projected dose.
Personnel and vehicles evacuated from the Salem/Hope Creek sites requiring monitoring and decontamination will be accommodated at a decontamination facility run by the State ~f New Jersey in Quinton.
Procedures for the operation of this facility are provided as a part of the New Jersey Radiological Emergency Response Plan.
Salem Emergency Procedures are available for backup to the ~tate procedures if needed.
Evacuation will be in accordance with EP I-12 and any decontamination conducted by Sale~ pe~sonnel will be in accordance with EP IV-119 a,nd E:P IV-120.
A. new section of the Emergency Plan Procedures with 5 procedure~ has been provided to account for the actions of the Security Force under emergency conditions.
The~e procedures cover activati6n of the TSC and EOF, station accountability, site evacuation and communication equipment and are referenced in EP I-21.
Item 23 Item 24 Item 25 Item 26 Jtem 27
- Procedure EP I-17 has been developed and incorporated into Emergency Plan Procedures and governs emergency actions of the repair and corrective action teams.
This group is described functionally in Section 3 of the Plan.
Procedure EP VI-1 has been developed and incorporated into the Emergency Plan Procedures for reviewing, approving, and distributing the revisions to the documents comprising the Emergency Preparedness Program and its implementation.
This procedure insures proper review of all revisions in accordance with the Facility Technical Specifications.
Maintenance and scheduled review of the Emergency Preparedness Program documents is accomplished in accordance with Section 18 of the Plan.
The Salem Emergency Plan and Emergency Plan Procedures have.been reviewed by the Station Operations Review Committee and Manager -
Subsequent to this review it was determined that the Manager -Salem Generating Station had not reviewed and signed approval of the SORC meeting recommendation due to an administrative oversight.
This deficiency was immediately corrected.
In the future, the Manager -
Salem Generating Station will sign each Procedure and Plan Section prior to implementation.
EP VI-1 will be revised to insure proper approval signatures prior to implementation.
The interface between the NRC (Director of Site Operations) and the PSE&G Emergency Organization is shown on the Emergency Organization Charts in Section 3 of the Emergency Plan.
The Emergency Response Manager who is located in the EOF has responsibility for overall direction and control.
All NRC interaction will be coordinated at this level.
- J
- :nforma.tion regarding actions to be taken by individuals within the* Emergency Planning Zone during a radiological e~ergency h~s been distribu~ed to individuals within th~ Pltime EPZ in the State of New Jersey.
Similar information tailored to the State of Delaware will be
. given to the State for distribution.
ENCLOSURE 2 RESPONSE TO EMERGENCY PREPAREDNESS APPRAISAL APPENDIX B Item 1 Item 2 Item 3 Item 4 Item 5 It is not intended at this time to develop or implement a selection and qualification criteria specifically for individuals performing emergency preparedness activities.
- personnel as*signed to perform these activities meet the corporate *selection criteria for employment with the Company.
It is not intended at this time to devel0p a specific structured program for t:r;-aining individuals who ar-e assigned emergency-planning re~ponstbilitie~.
As training programs, seminars* or other meetings which. pertain to emergency preparednes:s become ava.+/-lable,* Company pe;r:'sonnel wh_o are as:s*.tgned emergency prepa,redness developmental and,fior i'mplemeritation functions* may be given the opportunity to atterid.
Attendance at such programs or meetings will be ba.s-ed upon the.tndi:vidual' s specific function and relevance to the material being pres'.erited, the ava.ila.bility of the individual's* time and the cost as*socia,ted with the program.
Training will be documen.ted by use of a training matrix.
This matri:x wi~ll indi_ca,te what training ea.ch_ Functional Title will be given:.
In addition, the.Assistant to the Ma,na,ger will develop and maintain records that will list each,Function and the names* of those individuals qualified to perform the Function as well as the training they have received.
This item will be initiated by September 1, 1981.
We will continue to use individuals who are 'familiar with the Emergency Plan and :Procedures a,s instructors.
we do not anticipa,te developing specific criteria, for qualification of emergency p:r'eparedness* instructors.
The ha.bitability and accousti:cs of the interim. TSC loca,ted on the thir:d floor of the Clea;n :Facilities Building are considered a,ccepta,ble :until th~e i*nterim TSC ;i::s* moved to a, new location on the *second floor of the Clea;n ;B'a,cili ties Building.
Thi~s-change in loca.tion i*s necess*ary to permit construction of the: ultimate *Tse.in the *location where the interim TSC (third floor of ciean *Fa,cillties Building) now* exists.
The *location of the new inte.ri:m TSC on the* * -
second floor of the Clean Fa,ciliti:e.s Building should affo:r;-d somewhat better a,ccoustics beca,use i~t conta,ins an a,ccoustica,l tile ~eiling.
Item 6 Item 7 Item 8 Item 9 2 -
A specific area designated "NRC" will be provided in the TSC.
The ENS, HPN, and two dedicated commercial telephones will be located in this area.
This modification will be accomplished as part of our TSC upgrade program.
The present computer displays are part of the interim TSC.
ThJs data.system will be used until it is replaced by an emergency response facility data system. Cons*ideration will be given to providing units* for plant parameters in our proposed data syste.m.
The present computer d+/-s*pla,ys* are pa,rt of the interim TSC.
This da,ta, sy,sten:i wi.11 be used until it is replaced by a.n errierge:ricy~ response facility da,ta system.
Consid-el:;'ati.on w+/-.il be given: to providing an independent TSC dis*:pla,y* ca,pa,bil+/-tY' in our proposed data system.
Existing procedu:i::es* wi'll be revised to provide for stafftng the* Technical Document Room with appropriately gua,li::fied personnel.
These *revisions will be included in :Revi:s*ion 1 to the Emerge:ricY: Pla,n Procedures'.
The procedural i'm.proveme:rits 6~ ':Revision O of the Emergency
- i?la,n :Procedures* and the proposed improvements to* J?lant data tr ans*miss'1on outlined in ;I:terris 7 and 8 above should provide improved da,ta tr;ansmi:ssion.
Item 10 A sys.tern to provide mul ttple high_ radiation liquid and gas* sa:mples duJ;i:ng normal ~nd wost accident' conditions ha.s :Oee*:n: selected and sha:ll be installed by Ja,nua,ry 1, 1982.
Item 11 The necess*a,ry* post acc.:Lde:rit rea:ctor coolant sa,mple analyti.ca.l supplies~ are now-stored ;i..n a des;i..gna,ted area ;i.._n the chemi:stry, la,b.. The s-upplies sh:a:11 be peri:odi:ca,lly t.nventori:ed.
Th:e inventory* will be ;r;'eques:ted by an inspection o;i:-der ca;r-d as* described in Station Administrative Procedure A,P-10.
Item 12 The equi:pmen't for obtaining the rerriote 'plant vent and conta.fnme:rit sample has heen assembled.
- r.t is stored i'.n th_e erriergen'cy' locke;r-at the' control poi,nt. - '*
- r:tem 13 Th_e representativeness* of post accident containment air samples ha.s* been determined erripir;i..cally* f;t;"om a,ct:-Ual a,i*r samples~.
An insuffi.ci:erit lodi.ne 'source term wa,s present in the containment a,t the t;L:me of the sa,mple and a correction factor for Iodines w.fll be determined when the source *term i's* adequate.
U~til a specific value is obtained the particulate correcti:on fa.ctor will be used for J:odi:ne~.
- 3 -
Item 14 The location of the Operations Support Center in the hallway between the two Control Rooms has been found acceptable in light of the new organization described in Section 3.0 of the Emergency Plan.
If -additional space is required to a.ssemble support personnel, provisions have been made to use the Ma.chine Shop in the Clean 'Faci:li ties: Building.
Item 15 PSE&G ha.s received sepa,;t:'ate correspondence :from the u. s.
Nuclear Regula,tory Cornmi*ssion da,ted Ma,y 5, 19.81 which requests* that we a,ddress* the *"bay, breeze" ques:tion.
Our response to th.is* Ma.y* 5, 19.81 letter will be provided by Jruly 1, 1981.
Item 16
- [nforma,tion on severe wea;the*r wa.rnings or wa,tch.es,is a,nnounced via the* Na,ti:.ona.1 wa.rning System (NA,WA,S t. This system is *moni:tored in the* *senior Shift Supervisor's off ice.
Item 17 Procedures EP I-1, EP r-2; EP I-3 and EP I-4 a.re being reviewed to determine *wne*re it may be necessary to include refe*rences: to a.ppropriate 'procedures:,.be more specific on who is :r'espons..tbl'e :for implementing the* procedures and identify which res:ponsj::bilities: ca,n or cannot be delegated by the person performing the dut.i;es of. the Emergency
- Coord.i;n,3,tor.
These cha;nges: will rre ma.de in Re*vision l to the Emer:gency* '.Plan 'Procedures*.
Item 18 Procedures have been reviewed and, where neces:sa,;r;y, telephone numbers will be. referenced op included.' Th.ese cha.nges will be -ina,de in *R.evisi:on l to the* Eme:rigency Plan
- procedures*.
Item 19 EP I-1, EP I-3 a,nd EJ;> r-4 will be* revised to provide for notifica,ti:on of the: N*RC Resi.dent ;J;:ns;pector.
These cha,ngep" will be -ina,de. in *:Revision 1 to the Eme.Jigency :Pla,n procedures.
Item 20 It is not necessary to provide for an automa,tic activa,tion o;E the. TSC ;i:n res:ponse to a, R.a,dia,tion A,lert Alarm.
The Emergency* ;E>la,n procedures EP I-2 thru 4 require an a,nnouncerrierit over the publlc *addres:s. system of "Ra,dia,ti:_on J?rotec"ti:on personnel re;Port to your enie:i;-gency duty sta,ti:ons."
a,n~ a. proceeding ste:i? in th.e *procedure reguires the Senior Sh.rft Supervisor;1EDO to ver*t*fy a,ctiva,ti:on of the TSC by the Shift Tech.rii*ci:an -
Nuclea;r.
Item 21 The Health. Physi*cist *a,nd Ra,dia,t;ion ll?rotecti'on :E;ngineer w;Lll
- review ex.tst.tng procedures, and ;i;ncorpora,te addit+/-onal discussions,.where necessa,;ry*, to provide for i:ntegration a.nd I?r.to;i;itiza;tion o;E assessment data,.
Th.ts' ;review* will he completed pri*or to 'Rev.ts*ion l to th.e Emergency Pla,n Procedures.
4 -
Item 22 The existing dose assessment procedures were reviewed and the timeliness for manual dose assement improved in Revision O to the Emergency Plan Procedures.
Item 23 Procedure PD 15.12.315 has been incorporated into the station emergency, procedures* and is now referred to as EP IV-110.
The *dose data ta,bles~ were corrected and included i:n R,ev.tsion 0 to EP IV-110.
Item 24 P:rocedure EP IV-110 (J?reyiously PD 15.12. 315 r has been reviewed wi.th. "the~ following res'.ults:
a,.
Radiation p,;i;otection guidance provided in *R,evision 0
.t.s conside;i::ed a,dequate."
- b.
The flow of info:t;"ma,tion between the TSC a,nd the survey, tea:ms' by radio is now' dis*cusse.d in the p;t:'ocedu;r-e. Documenta,ti:on of survey results is a,chi:eved through: *the use of an emergency survey log which. *is included as an attachment to the procedure.
The procedur*e wi.11 be revised in Revision 1 to
.include retu:r:ning the: sa,mples* to the* counting room, for loggi-ng and storage.
- c.
The new, ons*i.te survey, points' were included in Rev.ts.ton O to the procedure.
Item 25 The procedures~ governing routine surveys. Cdose rate, con-tamination and" air sampling): were reviewed and will be re.vised i:n 1;R,evi§*ion 1 to the Hmergency-Plan Procedures.
Item 26 The seemingly long time required to aquire the primary coola,nt sample *wh.i:ch *wa.s* observed was because the available *radi:a.ti:on pr:otecti*on personnel were a,ssigned to highe:ri pri'ority-actfviti'es~ whi*le *the* plant was brought to a safe cohditi:on. ;rt i's fe.lt that the "sample was conducted in a.ccorda.nce with_ the prio;t:'ity, ass*igned to i:t a,t the time.
Item 27 We ha:ve not pr-e*vi::ously, noted problems* COil).IUl'J.nicating with.
Control Room personnel during sampling drills.
- However, we will revi.ew, communicati*ons, rec;tuirements* during prima;i;y sampling and install equipment or* pevise procedure~ i"f necessary by*.::ra,nuary 1, 1981.
- Item 28 Procedure EP v-.1 II Inteii'm Post A,ccldent Primary Coolant
~a;mpl;tng" CR.ev. 01 requires* verification tha,t th.e following a.re obta::Ined o:r;- a,chfeved p!'ior to.initiating the sa,mpling '
p;i:ocess':
11 a.va.ilability of the proper survey meters'.
2 )_ use.of ppotect;i:ve clothing, 3I" appropriate respira,tory device'.3 L dosimetry* a,nd 4 r worker b!'i:efings.
The detaj:.ls on specif'i::c p:r:otect:tve :rrtea,"sures:* and b~i:ef+/-ngs a,re iden.tifj:ed i~n EP IV-106 "Alara,. Ta,sk...,Review" (:Rev. or.**
Item 29 Item 30 Item 31 Item 32 Item 33 Item 34 Item 35 Item 36 5 -
An alternate counting facility is located in the radiation protection office area beyond the Control Point.
This item is addressed in the procedure for primary coolant sampling (PD-3.8.032) and will be included in the next revision to the procedure for sample analysis (PD-3. 5. 0 71 I.
The dissemina.tion of the containment air sample analytical results* i?* provided in Emergency Plan Procedure EP IV-118 "High Activity Sample Analysis" (_Rev. O) which_ requires~ th_at the person performing the analysis notify- :Ooth the 'indivi.dua,l reques:ting the analysis a.nd the A,la:r::a/Dose A,s*ses~smerit Supervisor of the results.
The necessity* to verify* containment vent flow pate will he ;r:eyiewed further to determine 'the: neces.s;tty* ;for ;flow
- r:a.te -veri*fica_tion.
The transportation of post accident plant vent sa,mples w:;L.11 Be reviewed and equipment provided where required by January 1,.1~82.
Procedure EP V-2 "Emei<Jency: sa.mpling p;i:-ocedure for the plant vent" ('R,ev. OI, cur;Lently includes a preca,ution statement identifying the ha,za:rds-of high contamination and high_ dose rates:~ *Additionally, procedure EP rV-106 "Alar a Task :Review" is* lis-ted as a preretjuisite.
Radiation Protection precautions for high_ a,ctivity post accident plant vent sample analysis is.provided in Emergency Plan Procedure EP IV-118 "High 'Activity Sample Analys-is-" (Rev. 01.
An organiza:tion for receipt* and
- distributi_on of analytical results and the* admi:_nistration of original data sh:e.ets has been agreed u.pon and will be included i:n Revi*s*ion 1 to the. *Emergency: :Plan J?rocedures.
Upon review of the 'data by a Cherrii:stry Supervisor, the da.ta wi:ll :Oe p:r;esented to* the *Radiation :Protection EngineeJ:'.'(
Des.+/-gnee.
Ori:gina,l da,ta, sheets will be :r::etained Cduring the: 'eitjergency1 by the *chemistry g]'.'oup.
Copie$ of the plant ven*t ana,lyti:cal res:u1 ts will *be transmitted to the Ra,diological Emer'gen*cy: Ma,hager for his use du.ring an emergency:. ' *_ cherrii':-stry* procedures-will be :revised to' show th:L$*. :t7outi'ng ;tn Revi:sion 1 tq th:e *Emergency :Pia,n Procedupe$
Section IV.
A,n EA,L will be provided which will interface post a,cci_dent pla,nt vent sample *analytical results. *This-EAL will be provided i'n :Revision 1 *to the* Emergency: Pla,n :Procedures.
An interface hetween the post accl.dent analytical results and protective *acti'on recoinmenda,ti:ons* is currently p;r;ovided j:*n Emergency Plan l;';rfocedure EP l'-12 l'.Rev. *of.
6 -
Item 37 Precautions and prere~usites for analysis for high activity liquid effluent samples was provided in Revision 3 to the sample analysis procedure CPD-3. 5. 071I.
Item 38 Emergency ;I?la,n fauplerrientation training is provided for all personnel badged for access to the station.
This training program and the individual departmental training programs p;r;ovide direction on evacuation of the site.
This program coupled with_ direct guidance fl:'om radiation protection pers-onnel in the Cont;r;"olled Area,s of the station is consider:ed adequa,te to direct pers*onnel from these a,rea:s in the event of a,n evacuation.
Item 39
- Procedures~ wi:ll be revised to address a,ccident class deesca,la,ti'on a,nd event teimi.nation.
The criteria which will be used to determine 'if deescalation is appropriate will be the plant obseiva,bles of the Accident Classi-f;i:ca ti;on Guide.
Iterri 40 The "kitchen ca.rd" which_ has been prov;Lded for the Sta.tes~ of Dela,wa.re and New 0'ersey* has* been placed in the press* k:i::ts.
Th~ese '"kitche*n cards" con ta.in the i:nfo;Lmati;on on protective actions to be taken by the Public.