ML20078J847
| ML20078J847 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/30/1983 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20078J543 | List: |
| References | |
| SAP-1, NUDOCS 8310170659 | |
| Download: ML20078J847 (213) | |
Text
{{#Wiki_filter:t NewYorkFbwer I 4 Authority JAMES A. FITZPATRICK ! NUCLEAR POWER PLANT l O < EMERGENCY RESPONSE PLAN EXERCISE MANUAL OCTOBER 12,1983 O lSAi?88 Pols 8s8'gg
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DRAFT #1/PAGE 1 1 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT SMALL SCALE EXERCISE OBJECTIVES OCTOBER 12, 1983 0; 1 l
D?. AFT #1/PAGE 2 i
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p 1983 Nuclear Regulatory Commission Observed Exercise James A. FitzPatrick Nuclear Power Plant Objectives A. PURPOSES This document provides guidance for the conduct of the 1983 Nuclear Regulatory Co= mission (HRC) observed small scale radiological emergency exercise at the James A. FitzPatrick Nuclear Power Plant (JAFNPP). The scope of this exercise, with some exceptions, will en-deavor to demonstrate by actual performance a number of primary emergency preparedness functions. At no time will the exercise be permitted to interfere with the safe oper-ation of JAFNPP and the plant management may, at their discretion, suspend the exercise for any period of time nec-l essary to ensure this goal. l This exercise will include the appropriate notification to the Nine Mile Point Nuclear Station (RIPNS). Active partic-ipation by the IRGNS crganizations is not expected. This exercise will include the appropriate notifications to p Oswego County and New York State. Limited participation by
\d these organizations shall be included.
B. EXERCISE OBJECTIVES
- 1. Radiological Emergency Preoaredness Plans
- a. Evaluate the adequacy and capability of implemen-tation of the James A. FitzPatrick radiological emergency plans.
- b. Demonstrate the emergency response capabilities of JAFNPP and New York Power Authority (NYPA).
- c. Demonstrate the capability of JAFNPP to implement their radiological emergency preparedness plans in a manner satisfying NRC acceptance criteria.
- 2. Notification Procedures
- a. Demonstrate the ability of JAFNPP staff to elassi-i fy actual or potential emergencies in accordance l with JAFNPP Emergency Plan Implementation Proce-1 dures as to:
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DRAFT fl/PAGE 3
. Notification of Unusual Event (optional)
Of . Alert E=ergency
. Site Area Emergency
. General Emergency
- b. Demonstrate the capability of JAFNPP to notify the state, local and federal levels of government in accordance with federal guidance and established protecols,
- c. Demonstrate the capability to communicate tachni-cal information among JAFNPP, New York State and Oswego County, JAFNPP will also demonstrate com-municating technical information with the NRC via the NRC Hot Line.
- d. Demonstrate the capability of the JAFNPP to notify and activate emergency response personnel.
- e. Demonstrate as appropriate the notification and request for assistance to federal agencies such as radiological assistance from the Department of 7
Energy. l
- 3. Emergency Com=unications
- a. Demonstrate the JAFNPP communications capabilities i
among the Control Room, Technical Support Center
- ('iSC ) , Emergency Operations Facility (EOF), and <
the Operations Support Center (OSC), and the abil-ity to maintain communications with the federal government.
- b. Demonstrate emergency com=unications cability among Oswego County, New York State and JAFNPP in-cluding the Radiological Emergency Communications System (RECS - Hot Line).
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- c. Demonstrate the adequacy of JAFNPP emergency com-
- munications to
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4 i 1) Transmit instructions to activate essential staff. 4 4
- 2) Disseminate essential information to assist-ing agencies.
- d. Demonstrate the ability of JAFUPP to coordinate, control and deploy radiological monitoring teams
- via the respective field communications system.
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DRAFT #1/PAGE 4
- 4. Emergency Resconse Facilities
- a. Demonstrate the adequacy of the staffing and set-ting-up as appropriate of emergency response fa-cilities as well as demonstrating the adequacy of space and habitability for management of radiolog-ical emergency at:
. JAFNPP Control Room (CR)
. JAFNPP Technical Support Center (TSC)
. JAFNPP Operational Support Center (OSC)
. JAFNPP Emergency Operations Facility (EOF)
- b. Evaluate the adequacy of access control and secu-rity for emergency response facilities.
- 5. Direction and Control Demonstrate the ability of key emergency personnel at JAFNPP to initiate and coordinate timely and effective decisions with respect to a radiological emergency and clearly demonstrate "who is in charge".
( 6. Accident Assessment and Evaluation
- a. Demonstrate the activation, operations and re-porting procedures of JAFNPP field monitoring teams. JAFNPP teams will be dispatched within and beyond the site boundary. Field monitoring teams will be provided with simulated data at assigned times and specific locations consistent with the simulated release from the plant.
- b. Demonstrate the ability of JAFNPP and Oswego County to receive and assess radiological data from licensee field teams in accordance with the radiological emergency. plans.
- c. Demonstrate the ability of JAFNPP and Oswego County to calculate dose projections, compare pro-jections and determine appropriate protective ac-tions with regards to the Protective Action. Guides (PAGs).
- 7. Protective Resoonse
- a. Demonstrate the capability of JAFNPP emergency response organizations to make recommendations concerning appropriate protective action response
. options.
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DRAFT #1/PAGE 5
- b. Demonstrate JAFNPP employee accountability fol-
,^ lowing the requirements of their Emergency Plan (,) I=plecenting Procedures.
- 8. Radiolocical Excosure Control
- a. Demonstrate the decision process for limiting ex-posure of emergency workers.
- b. Demonstrate methods and resources for distribution of dosimetry to emergency workers at JAFUPP.
- c. Demonstrate the capabilitf of personnel for keep-ing records of individual radiation exposures at JAFNPP.
- 9. Medical Support The initial treatment of an injured worker with contam-ination at JAFUPP, transport to and subsequent treat-ment at a hospital will be demonstrated at a medical drill in association with Oswego Hospital.
- 10. Reentry and Recovery
- a. Demonstrate the capability of emergency personnel to identify requirements, assess and implement pq 4
procedures for reentry. \ /
- b. De=onstrate the capability of emergency personnel to identify requirements, programs and policies governing damage assessment and recovery.
C. INTENT OF THE FITZPATRICK EXERCISE SCENARIO The licensee (New York Power Authority), New York State and Oswego County plan a coordinated small scale exercise of their respective emergency plans for the JAFNPP site October 12, 1983. In order to minimize the i= pact on scheduling and agendas, -ae exercise scenario will be completed in a time frame of approximately a routine working da7 The exercise is intended to demonstrate many, but not neces-sarily all, of the JAFNPP capabilities to respond to a wide range of emergency conditions. This scenario is designed to activate the JAFNPP Emergency Plan through its various ac-tion levels. Although this scenario attempts to accurately simulate operating events, it is not intended to assess all of the o,arator's diagnostic capabilities, but rather pro-vides sequences which ultimately demonstrate the operator's ability to respond to events and which results of exercising onsite emergency plans and procedures. Free play is en-couraged and the controllers will interfere only if opera-i ) v
DPAFT #1/PAGE 6 tor / player action prematurely terminates the exercise or (N excessively deviates from the drill schedule. D. CCiCEPT OF OPEPATIOiS AND C0!iTROL OF THE EXERCISE The licensee shall supply official controllers for locations where an emergency response is being demonstrered for the exercise. Prior to the exercise, the controllers will be provided with the appropriate locations, maps, time periods, guidelines, and an observer evaluation checklist. for their exercise assign =ents (as appropriate). The exercise initiating events will be controlled by a lead controller at the JAFNPP. Simulated initiating events will consist of two types of information: l 1. Infomation and data provided to control room personnel by the control room referee.
- 2. Onsite and offsite dose rate data (simulated gam =a and iodine dose rate measurements) provided to the site monitoring teams by controllers.
The lead controller (onsite) will have the responsibility to control and coordinate the time sequency of initiating events to ensure an orderly flow of exercise events. As the initiating events are provided to the JAFNPP staff, 4 h they will determne the nature of the emergency and i=ple-ment appropriate plant emergency response procedures. These procedures include a determination of the emergency classi-fication in accordance with the JAFNPP Emergency Plan. Af-ter the emergency classification has been detemined , the ! appropriate federal, state and local authorities will be notified in accordance with the JAFNPP emergency response procedures. The simulated accident will continue to develop based on data and infomation provided to the control room personnel by the control room referee. As the situation develops, infomation will be forwarded to New York State and Oswego County. Certain inconsistencies (such as plume width, release dura-tion, technical reason for the simulated release, etc.) may be intentional and required due to the nature of si=ulating an accident that has never occurred and the requirement to provide an exercise basis which tests the site to the maxi-mum extent feasible in a limited time frame. If an incon-sistency is known or decemined to be intentional, then the accident assessment group will note the inconsistency and ignore it. The lead controller shall have the authority to resolve or explain any inconsistencies or problems that may occur during the exercise. v
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. DRAFT fl/PAGE 7 E. PUBLIC INFORMATION AND AUARENESS Agencies should make every effort to prevent the public from being misinformed about the nature of the exercise. There-fore, it is important to inform members of the public that an exercise is in progress and that their involvement is not required, whenever public contact occurs in the field.
F. MAINTAINING EMERGENCY READINESS During the performance of an exercise the aoility to recog-nice a real emergency, terminate the exercise, and respond to the new situation must be maintained. Therefore, the exercise scenario and actions of participants shall not in-clude any actions which degrade the condition of systems, equipment or supplies, or affect the detection, assessment , or response capability to radiological or other emergencies.
- Actions taken by the participants shall also avoid actually i reducing plant or public safety. The potential for creating real radiological or other emergencies shall be specifically avoided. All messages about real events shall be clearly identified as such. For example, precede a real message with "This is NOT, repeat, NOT an exercise message."
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JA>ES A. FITEPATRICK NUCLEAR POWER PLA:iT 53 ESERGE: ICY PLAN IMPLESE:iTI;iG PRCCEDURE ESERGE; ICY PLAN VOLCE II i PROCEDURE NO.: SAP-1 i TITLE: MAINTAINING EMERGENCY PREPAREDNESS
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Approved By: ltw9 %V Restcen: Manager Approved By: , hw
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Cervices Superintenden: . 1 l O' . w PAGE N0. 1, 2 3 4 5 6 7 8 9 10 11 REV. NO. 1 1 1 1 1 1 1 1 1 1~ s l PAGE No. 12 13 la 15 16 17 13 19 20 21 22 REV. NO. 1 1 1 1 1 1 ' 1 1 1 1 - Rev. No. 1 Date: 04/83
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t a C.O N". . T C .C. n 1.0 PURPOSE This procedure details the actions to be taken to =ain:ain e=ergency preparedness at the JAF"PP site. The proc 2 dure establishes a =ethod for the condue: and evaluation of a drill or er.ercise a: the JA.="PP. This procedure also ou:- lines the =anage=ent controls used to ensure that cor- l rective actions are i=plemented. , 2.0 REFERE'!CES
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4.0 PROCEDUP2 3( 4.1 General - E=ergency preparedness - at JA?;i?? is =ain-ta:.ne c through an integrated' progra= of training, drills, exercises, plan and procedure =ain:enance, and audits. 4.1.1 Training - Plant staff and outside support agen-cies are given for=al classroo= training in ac-cordance with ITP-12 - TRAINING. For=al trainingEMERGENCY cons:.s:s PREFARED' c: c:.assroo= JESS instruction tions. and wri::en quinces and examina-Drills and exercises are u:ili:ad to evaluate e=ergency preparedness, and the results of these are input to subsequent training. 4.1.2 Drills - A drill is a hands on, supervised in-struction period aimed at testing, developing and tion.
=aintaining skills in a particular opera-Drills at JAFMPP are conduc:ed in accor-dance with the schedule and guidelines of sec-tion 4.3 of this procedure.
4.1.3 Exercises - As defined in NUREG-0654, an exer-cise is an event :ha: tests :he integra ed capa-bility and a major portien of the basic elements existing tions. within emergencf plans and organica-Exercises at JAF.;i?? are condu::ed in acccrdance wi:h :.ne senecu e anc guicesines c:- section 4.4 of this procedure. 4 .1. .'- Plan and Procedure Maintenance - Mainten nce of the JAFMPP E=ergency Plan and Implementing pro-cedures consists of docu=ent control activities including distribution con:rol, change control, procedure review, and cross reference review. Plan and procedure =aintenance is in accordance with A?-6.2 - PROCEDURE FOR COiTROL A' D DISTRI3UTION OF IliE EMERGEsiCY PLEi IMPLEEiTI.;G PROCEDURE 3 AilD 4.1.5 Audi:s - The JAFU??' e,=ergency preparedness pro-gra= (in accordance with reference 2.12) is au-diced a: least once every 12 con:hs in accord-ance with Quality Assurance Manual Procedure 13.1 - QUALITY ASSURANCE AUDIT PROGRAM - PLA:iT . Findings anc corrective action recorcs snata oe main ained by the QA department in accordance wi:h their procedures. Rev. No. 1 Date 04/83 Page 2 of 22 of SAP-1
a. D v- 4.1.6 Drill /Enercise Doc =encation - Doc =entation for dri,ls and exercises sna3:, be maintainec. .o v, Training Superintendent. Docu=entation shall :.ne be deve_,oped .,n accordance witn. s e ct:..cn
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4.1.7 Drill / Exercise Conduct, Observation, Criticues and De.ficiencies - A fo=alized method for eval-uating a drill or exercise has been established. SAP DRILL / EXERCISE CONDUCT details the =eth-od for concucting :ne Dr:11/ Exercise Observation Progran, Criticue, and Deficiency ac:icn. 4.2 Traininz - The respcnsibility for training is shared by tne Iraining Coordinator and the E=ergency Plann-ing Coordinator. 4.2.1 Training Coordinator - The Training Coordinator is responsible for the fo=.al classroca : raining or- o n - s ;_ : e and orr-sl:e inciv:. duals wno uave u duties in the emergency organization. The Trainin,g specia.. :ec C.oordinator. is al.so respc.nsible for tra.,ning services suen as rire -. fighting and emergency medical services. The Training Coordinator is responsible brigade drills, for fire k - 4.2.2 E=ergency Planning Coordinator - The E=er Planning Coordinator is responsible for cen=gency uni-ca icns, =edical energency (cenracinated injury), radiclogical =cni:oring and radiation prc ection drills. 4.2.3 Inicial training and periodic retraining shall be condue:ed in accordance wi:h ITP-1, and T."'D _1_9 ITP-3, 4.2.4 Fo=al training shall be documented using a Training Report (For.. SAP-1.1).. 4.2.5 The Training Cecrdinator shall be responsible for =aintaining a).1 E=ergency Plan records. training
=al : raining This shall include sessions, drills and records of all for-exercises.
4.3 Drills - Responsibili:7 for the conduct of drills is civicedand between the E=ergency Planning Coordinator the Fire Protection (EPC) Supervisor (FPS). There are five drill areas: A. Co : unication Drills - E=ergency Planning Coor-s cinator.
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\/ Rev. No. 1 _ Date 04/83 P-= 9 - -- --
[ f- , Cc=unica icns wi:h Sta:e and local gover=ents (A within the plume exposure pathway E=ergency Planning Zone shall be tested con hly. Co uni-cations with Federal emergency response o=rgani-cations and Sta:es within the ingestion pathway shall be tested quarterly. Co =unications be-i tween the nuclear facility, Scace and local emergency operations centers, and field assess-ment teams shall be tested annually. Co=unica-tion drills shall also include the aspec: of understanding the content of messages via the observer evaluation. Documentation for co=u-nication drills shall be in accordance with pro-cedure SAP.3.- EMERGENCY COMMUNICATIONS TESTINC. Co=unication drills saati ce consicerec super-vised instruction upon review of~the Cc=unica-tions checklists by the E=argency Planning Coordinator.
- 3. Fire Drills - Fire Protection Supervisor.
Fire drills shall be conducted in accordance with the plant technical specifica icns and Fire Protec:icn Procedures. Resconse to an actual fire may be counced as a dr'ill. Documen ation of Fire Drills shall be done by cc=oletine Fo= (Q'7 V SAP 1.2 " Drill Report" and prov'iding'a cc=pleted copy to the Training Superintendent. C. Medical E=ertencv Drills - E=er;ency Planning Cccrcinacc , iire Pro;ection Supervisor. A cedical energency drill invciving a simulated contacinated individual which con:ains provi-siens for participation by the local support services agencies (i.e., Oswego Hospital, Upsta:e Medical Center, and .he Oswego Fire Depart =en: A=bulance) shall be conducted annu-ally. The o ff-s ite' portions of the medical drill =ay be perforced as part of the required annual exercise. Res to an actual medical e=ergency =ay be counponse ed as a drill. Documenta-tien of Medical E=ergency Drills shall be done by cc=pleting For: SAP 1. 2 " Drill Report" and a drill scenario and providing a completed copy to the Training Superin endent. D. Radiolacical Moni:crinz Drills - Emergency Plann ng Georcinaccr. S.
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annually. and analysis Theseof alldrills sa ple shall include collec:icn media (e.g., water, vegeta ion, soil and air), and previsions for cc==unications and record keeping. This drill -
=ay be condue:ed as par: cf the JAFNPP Annual Exercise. Documentation for Radiological Moni-toring Drills shall be done by cercleting For:
SAP 1.2 " Drill Repor " and a drill s' cenario and providing a . cc=pleted copy to the Training Su-per:.ntencent . E. Radiation Protection Drills - Energency Planning Coorcinator. ~ (1) Radiation Protection drillsinvolve shall be con-due:ed seni-annually which response :c, and analysis of, siculated elevated airborne and lic carec radia:icn =casureme.uid n:: in sacolcs and the envi-o.
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(2) Analysis of inplan: licuid samples with ac-cual or simulatec elevated radiarien levels ( including use of the post-acciden: sa= ling syste: shall be included in Radia: ion' Pre-teC icn drills. This drill may be CCnduC:- ec as par: c: the JA75PP Annual Enercise. Do cumen:".2:icn. of
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l 1.2 " Drill Reper:" and drill scenario and providing a cc= l Superin:encer.:. pleted Resconse copy to the Training to an incident involving elevated ' airborne or licuid activity or elevated radiation levels '=ay be counted as a drill. 4.3.1 Drill Scheduling - The E=ergency Planning Coor-dina:cr shall 'oe responsible for the scheduling , o: which all drills is the with res the excection of Fire Drills, tion Supervisor. ponsibility' To the grectest of the.extent Fire Prctec-possi-ble drills should be scheduled in conjunctica wi:h plant each operating otherschedules. to =ini= ice inter #erence with
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=e c:. c a.3 anc cc=unications aspects of theo e=ergency plan in conj unction with the JAFMPP
- Annual Exercise.)
4 1. i %/ t Rev. No. 1 Date 04/33 Page _ 5 of ?? me em $ I
4.4 .
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An e=ergency response exercise is an event tha: tests the in egrated capability of a major porcion of the basic elecents contained in the JAFMPP E=ergency Plan. An exercise can be cc= prised of nu=erous drills conducted simultaneously. The purpose of the annual exercise, as described in NUREG-0654 is to test a full scale response capabil - ities of the plant, State, Local and Federal agen- ' cies. The Plant is directly involved and is evalu-ated on its response to the siculated emergency situation. .- As it now exists, the JAFMPP is required to conduct an exercise annually. The exercise shall either be a full scale exercise which will include full partici-pacion by Sca:e and Local. agencies or a small scale exercise that shall include only limited participa-tion of State and Local agencies. The decision as cc the above exercise choice is dependen: en sca:e and local resource availabili:7 ' 4.4.1 All persennel at JAFN!? tay participate in an io f energency exercise. (Note: Only Fire 3rigade LA personnel =ay participate in a fire drill.) 4.4.2 An exercise shall be developed c include the Sice Area or General Energency. 1 4.4.3 The scenario should be varied free year to year - such that all =aj or elecents of the plans and preparedness organica:icns are tested within a five year period. Once every six years an exer-i cise shall s:ar: between the hours of 1800 and 2400 hours and one shall start between 2400.and 0600 ed. hcurs. Scre exercises should be unannounc-4.4.4 Offsi:e support agencies should be contacted and I included in the development of a JAFU?? Exercise, and requested to supply observers. 4.4.5 Exercises of e=ergency preparedness should si=ulate an e=ergency that results in offsite radiological releases which would require responses by offsite authorities. 4.4.6 Exercises should be conducted under varicus wea:her conditions. To facilitate this, since O t v# Rev. No. 1 Date 06/33 Page 6 of 22 of sap _1
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( ( ably schedule drills in advance to coincide with acverse wea:n.er. :: . . . . s acvisac3e no: ec cance.7 or enci.es cos :unles :ene drills s cencinua:icn based en unexrected incle - would c' onstitute un-due risk to the carticic.an:s or to the c.lant. . 4.4.7 The annu.al exercises shall be planned in advance via a :or=al scenario incorporating simulated . plant, enviren= ental, and related events (input by controllers) personnel to guide the ac-tien and allow for free c.la.v. , 4.4.8 Depending en the nature of the exercise, i: :ay be desirable to brief the exercise as to their duties. In sc=e cases , participants such as an unannounced p, 4 a* e. -
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ea ... e... . -e.vs ., ec,.. es. i 4.5.1.2 The Fire Protec:icn Superviser shall assist the Energency Plannin c 4- 3. , e ....u-a .o 4. e a. c .a~. e.g< Coordinator c,. e in preparing 4.5.1.3 The Superintendent of Operations shall provide assistance to the Energency Planning Coordinator in preparing drill / exercise scenarios. 4.5.1.4 The Superintenden: of Radiological and Environ-cental Services shall provide assistance to the ency Planning Cocrdinator in preparing Enerj;/enerc:.se dr.11 scenar:,.cs , gs Rev. No. 1 Date 04/33 Page 7 of 22 of SAP-1
.,) 4.5.1.5 The Superin:enden: of Power shall crevide assis-V {s cance to the Iner,ency Planning Coordi- acor in preparing drill / exercise scenarios.
a 4.5.1,6 The Viceassistance provide President to of Public Relations shall the ? ergency Planning Coordinator in pr2 paring the drill / exercise scenarios. 4.5.1.7 A represencative the reactor of PORC with a senior operator's license shall review 4 i' drill / exercise scenarios. 4.5.2 Drill Scenario Developnent and Documentation - As a cinicu=, a drill scenario shall be organic-ed to include the following (See for: SAP 1.5): (1) Drill
Title:
(e.g., Refueling accident, ; loss or Coolant accident, etc.). 1Ao , , Cu.Se ----.s=w , -n,. m. n m= .,.n c... =. G=.vC.Re fe to CO.D,. r i TIO:iS for in:ormation. (2) Obiectives: The basic objective cr:.2 . of :he ( ( ,- (3) Score: Da:e, time, duration, location, and y V - - - - : - - - : . s- n.. . ., 4- e
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(5) Time Schedule: A time schedule ins::a:Ing events of including expected or siculated plant alar:s, indications, energency classifications. or (6) S" arv-1 A narrative surn:ary describing ene ccacuo: things as siculated of'the events to include such casualties, offsite departmen: assisrance, rescue of personnel, evacuation recuired, use of protective clothing, deploy =en: of radiological coni:oring aC 4. 2 -t.-- os. teams, and public information i (7) Data: Data related to drill in question. G't Rev. :To . 1 Date 04/33 Page R of 22 of SAP-1
eW (%jr- (8) Drill Recort: (With arrangements for cual-
- . :.ec caservers.) This report describes infor ation pertinent to the understanding of the drill intent. A sign-off sheet for PORC representative, and a list of observ-ers and controllers.
1 4.5.3 Exercise Scenario Development and Documenta-tion - An exercise scenario shall be organized to include (See Forni SAP 1.5): (1) Exercise
Title:
(e.g., Refueling accident, loss o coolant accident, etc.) Refer to IAP-2, CLASSIFICATION OF EMERGENCY CONDI-TIONS for in:or=at:.on. (2) Obiectives: State basic objec:ives of the proposec exercise and which portions of :.t,e . E=ergency Plan will be tested. (3) Scoce: Date, time, duration, location, and i participating onsite and offsite organica-tions. Also to include, date, :ime, and loca:icn of observer briefings and Critique. f A (L) Safe v Precautions: Safe:v Precau ions to oe :=- =uec. (5) Ccncent of Oaeration and Centrol: Disduss concuc: anc respcns:.: .; .ci'es . Describe the method to be used in controlling flow of exercise even:s. (6) Overview
- a. xerc.se - .= e Se.nac",= .
- , ov:. . ..ce a l
concensec c:.=e senecule of raal and sicula:ed ' events . Provide a time schedule of emergency classifications,
- b. Narrative Su==arv -
'A narrative smary cescr:.0:.ng the conduct of the events to include such things as simula:ed
=en assistance, rescue of personnel, casualties, offsite depar:-
evacuations recuired, use of protec-tive clothing, deployment of radiolog-ical =cnitoring teams, and public in-for=ation activities. cG (O. Rev. No. 1 Date 04/83 page 9 of 79 ne can 1 _ _ _ - _ . _ _ . ~ . _ _ _ . . _ . _ _ . . _ . . _ _ _ . _ . . . _ . _ _ . . _ _ . - _ - _ _ _ _
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. 5: ace curing s:.=ulatec exercise. .
- orevents initia:Ing . to and con: rolling e=ergency actions.
(7) Criticue: State :he time, location, and i at:encees participating in the exercise / drill critique. (8) Plant Data: Include co=pleted sheets for use in ne exercise detai,ing ac: .vieles, events, ti=e, and sequence. The Controller Sheet (Form SAP 1.3), the Message Sheet (For= SAP 1.4), and the Plan Data Sheet (Forn EAP 1.7). (9) Radiolacical Data: Include cc=pleted data sneers 2o: use in the exercise detailing activities, even:s, time and secuence. This snou.d incluc.e a p.,u=e .=ap, l c:: site si=u.,ated data, .. . . . anc ractological ca:a,
=eteorology.
(10) Arrance=ents -cr Qualified O'eser.*ers: Incluce a i; sting or ocservers to ce usec q t to evaluate the e:.:e: cis e , the standard co LM. waren evalust cn snal- ce = ace, anc a lis: or ooserver supper: cocu=enza::.cn.
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9C.CRs: C. . I IISTACCTCR: t.CCAT!Ci: O. CEEC?.!ET:C:8 CF TRA!'lI:iC:
- i C::aleta reverse side of this retort 1%'er attaen
, :: er cata necessary f:r s :: :le a :escr;;u:n i of :he traini..o ;erf:r eo.
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i J a 1 t ? I 'e .~ k-J l< T y F. RE11E'iED: G. OcC";fE.'iTAT:C:1 CCtPLETE erannsng c: r:nnsc:r or Aecresentatsve
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4 y Rev. No. 1 Date 04/83 i Page __ 11 of 22
!- of sap.;
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) i a CESCRipi?C?t CF TR:.:?ti?:G TRAI*t!?;G CNECTI'lE: (What was the training to have at:: cIls.9ed in terms of i perf:r ance?) f - 4 REFERE::CIS At:0 AICS: (What .aterials were used by tte person (s) providing t.9e iristructten?) ? i 3 e 1 4 i [ CEIC.t!?ifC?l CF TRAI.*:!.':G. (%:. !: was th;n: and w - F w was *"1= i NA. :rs:.1ic; evaiuate:?)~ -as it tau;nt? ' 4 J i i i i I i. t
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1-(Attaen resA ts of qui:. examina: ten or ot?er evalua tien. ) i 4 ?2go 2 . ~ t, t j Rev. 30, 1 Date 04/83 pne. 19 e aa -
1 i -l r
- g. FOR'4 SAP 1. 2 Page 1 of i T* **
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~.~3 DRILL REPORT f
Drill / Exercise
Title:
Drill / Exercise Date: Reviewed Sy- . rO.Brgency Planning CCOrCinator/ Date Fire Protection Supervisor I
.se Vi a%*e d .,3 7 :
A - PORG Represents:1ve Date Copies to:
- 1. JA?;!?? EMERGE';CY PLA;i'!I;;G CCORDI.!ATOR
\f 2. JAF:I?? TRAI'.!I;!G SU?ERI iTE;iDE'.;T
- 3. JA.;,.Len. ;
. t.O r cr..o . . .C . ~ 0.'I .<"u._:..V7..C O R .
( 7. ~.2. D.o n..' S O'I'cY) . Rev. No. 1 Date 04/81 0,~- 'a - -- _ . , . _ _ . . _ . . . _ . ~ . . . . . _ _ . _ . . - - _ . . _ _ _ . _ _ , _ _ . , _ _ . . . _ _ _ _ _ . - .
1
- 7. 0.0.'3 S.a._' .' . .' . Pacem ' o# '
/
s- ! D =.m~ r_r_ o. ._= =_. 0 s .
- 1. Time Frame
- a. Drill / Exercise date b.
Date of last similar drill / exercise
- c. Real ti=e span of drill hours, days ,
i
- d. Drill / Exercise time frame hours, days
- e. Season (circle one) -- -
Winter Spring Su==er Fall f. Period of the week (circle one) Weekday Weekend Holiday
- g. What shif shall the drill begin on?
8 <. . . - 5 o.. o' :.-.
- - .. 2.. 43' . . .< .d.
d 6 a. m
.3.'. .. .
s . 2. Mani=u I ar liexercise level of e errencr (cnece ene). classificacion durinz the
%A Notificction of Unusual Even:
e., m .- _- Site Area E ereency o , General E=ergency _ Does not ac. c. iv.
- 3. .
Orzanica :.en Invo.lve:en: (t.irca.e ace 3 .cante) .
- a. PASNY Control Roc = 2:aff Yes / No Technical Support Cen:er (TSC) Yes / No E=ergency Cperations Facility (EOF) Yes / No i
1 I i l O~ r x/ E i Rev. No. 1 Date 04/83 Page lc of 22 of SAP-: l. as y w_9vr4_ . _ _ _ _ _.-.p y my9,. g -q+.,-..,,_..-.-_.,y_,,.,-__-w____ _ q.Sm,_,..,__.%y. .MM-nwWW re*m'"-- 1 +-IC'N-'""""-T--"NhW'TFF*'-""'T '- Y*TW-"*Fr ?-~**--'9"--e' -"W
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, age a, or- /
D.D .TT T, proCO.~.
- 3. Organiza:ica Involvenen: (Circle acclicable) (Continued)
Site Security Yes / No Fire Brigade Yes / No b" nite Plains Office (WPO) Yes / No Joint News Center (JNC) Yes / No Operational Support Center (OSC)
~ '
Yes / No Alternate Operating Support Center (AOSC) Yes / No Alter . ate Emergency Operating Facility (AEOF) Yes / No First Aid ~ean Yes / No
- b. Non PASNY
- !Y State Radiological Energency Preparedness Grcup (Fl?G)
Yes / No
..y
.4. c.,.e p
se,_, - ._ _. e,.,. . o: .:. ., ., ._. . y
.es / .,o ..
NY 5: ace Office of Disaster Preparecness Yes / No NY State Eureau of Radiclog:. cal F.eal:h Yes / No US Nuclear Regula: cry Cc cission Yes / No {_ US Depar: ent of Energy Yes / Nc US Coas Guard
, Yes / No L..
s 4 . e .._< u _1e 2.o_... n L.._e . . .- .-
- v. e s /wuo Oswego County Office of Enargeny Preparedness Yes / No Oswego Ccunty Sheriff Yes / No w
Rev. No. 1 Date 04/83 Pace is as 99 - e - - - -
, , , - - . , - . , - - - . , , - - . - . . , . , , , . - -e,,-y-,-,,,---,-m,y-,. ---%-, - ,__,,m7-- ...,-r, ..-,,-,,-,er.,-.-,%,- - . - -,-
f' FORM SA? 1.2
\ PaSe 4 of 7 DRILL REFORT 3.
t Orzanication Involvenen: (Circle acclicable) (Continued) Oswego Hospital Yes / No Upstate Medical Center Yes / No Oswego Fire Depart =ent Ambulance Yes / No General Electric _ , Yes / No , Other (Scecifv) 4 Cc=unications
- a. Shall the JAFNPP Radio Systen be used for con =unications?
Yes / No
- b. Should a news release be prepared?
Yes / No
c. Ac ivation of Join: News Center?
Yes / No
, d. Activation of Public Notification Systen/E3S?
Yes / No
- 5. Drill /E: ercise Ele ents
- a. Will key e=ergency response positicas be filled by alternate?
Yes / No If so, who?
- b. Is a contaminated cedical,. injury to be involved?
Yes / No ' If yes, (1) Onsite response by First Aid Tean Yes / No (2) Offsite response Yes / No (Circle Agencies Involved) Oswego Hospital Upstate Medical Center Oswego Fire Depart:en: Ambulance b ( Rev. No. __.1 Date 04/83 pa-a 'e - ^^ -
A I ), -
\ / (. : 0.-J, :..: 1. v. age c or. ,
1 Dx __
- ,0-:
a_ s 5. Drill / Exercise Elemente lCcntinued) c. Will Yes /:he No exercise involve a simulated fire? (1) Onsite response Yes / No (2) Offsize response Yes / No (Circle Agencies Involved) Oswego Fire Department Scriba Volunteer Fire Department Volney Volun eer Fire Corporation Alcan Fire Department Minetto Volun:eer Fire Department
- d. Will the Security Force response be tested?
Yes / No (1) Sabocage/3c=b (2) In: ruder Yes / No t% (3) Yes / No (_. k Accoun:abili:7 Yes / No
- 6. Radiclo:ical Release Yes I' No
- a. Me:eorcicgical capabili ies.
(1) Will real-ti=e retecrclogy be used? (2) Will fixed retecrcicgy be used? Yes / No I Yes / No
- b. Dose Assesstent.
(1) Will dose projection be made using cc=puterized =cdel? Yes / No (2) Will dose projec:icn be made using
=anual calcula:c overlay wheel? Yes / No (3) Will field coni:oring : ears be dispatched?
Yes / No (4). Will dose projections warran: protective l I action recentendatiens? Yes / No i
- c. Pos: Acciden: Sa pling.
(1) Are sa=ples c scack iodine / particulate sample recuired? <O
\-sl Yes / No (2) Should a reactor coolant sample be taken? Yes / No t
4 Rev. No. 1 Date 04/83 Paea 17 a' " " -- k
L. FOR'4 S."_? 1. 2 Page 6 of 7
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- 6. Radiciczical Release (Continued) f
- d. Enviorn= ental.
(1) Should enviren= ental radia be collecccd? Yes / No (2) Should sa=pling devices be collected frc= environmental stations? Yes / No
- 7. A : ached is a copy of the scenario used for_:his drill.
ll 8. Drill Controllers /Referencei Name Loca:icn
- 1. Lead Controller Controller Con:rciler
/7
'v( Con: roller f
Centroller Con clier Controller Controller Controller Centroller 4 4 b 4 i Rev. No. 1 Date 04/33 Page _ 18 of 22 ofw o -
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- 9. Obser*zers j Name Organi:2 tion s
Area of Rescensibili v Reference Procedures i A v 3 i 2' s 1 E 1 + s i Rev. ;io . __ 1 Date 04/83 Pa2e to e --
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C.".:C**xT .T C T. (Use this checklist as a handy reference for drill or exercise develeptent. DRILLS
- 1. D 41I -- ~t4.,e-.
l
- 2. Objectives
- 3. Secpe - -
4 Safe:y Precautions
- 5. Time Schedule
- 6. Si- arv.
- 7. Data 4
- 3. 3-::_' .".e , c .
1
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- 2. Obj ec:ives
- 3. Scope i
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- 5. C,..ce,r . c.: O f,e .c--e .. . -.. a-..c Co,.... ,,- .
- 6. Overview .
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- 9. Radiolo-iccl Data O
~
v) Rev. No. 1 Date 04/83 Page _ 22 of 22 1 _ of-SAP-1 i
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J t Initial Conditions t The Reactor has been operating the equivalent of 250 full power days since refueling and is currently at 98% power. The RHR A-LPCI loop inboard injection valve 10-MOV-25A is 1 out of service for repair. The valve is closed and cannot be opened. The Shift Supervisor has declared the A side of LPCI inoperable. This permits seven days of operation to repair per Technical Specifications (7 day LCO). The required surveil-lance tests have been completed satisfactorily.
, The RCIC System is out of service for repair and is not
! e::pected to be available for another 72 hours. The reactor
. coolant chemistry is normal and all other systems important to , safety are operable.
I T i e i
)
4 4 t i I i-4 i ) _l-l l
}
() TIME EXERCISE TIME SCHEDULE KEY EVENTS 0630 Initial conditions 0715 A diffuser on j et pump No. 6 breaks. The resulting debris partially blocks the water circulation in the core plate preventing adequate core cooling flow. Small pieces of the jet pump become clogged in fuel bundles. 0725 The Unusual Event Emergency Action Level is exceeded for air ejector off-gas radiation levels (>100,000 1 uCi/sec increase in 30 min.). Reactor power level has been reduced by de-creasing core coolant flow. 0735 Off-Gas Hi Rad alarm is received. 0745 The Off-Gas Hi/Hi Rad and Off-Gas Timer Initiated alarms are received. Opera-cor action has reduced power level to
- N30%. Nevertheless, air ejector / off-gas and main steam line radiation \-- levels have continued to increase.
Core differential pressure has also increased, even th'o ugh core flow is greatly reduced. One control rod of the cram group jams at notch position 14 and will not move. 0755 Containment isolation (Group I) and' reactor scram occurs on excessive main steam radiation levels. Alert E=ergen-cy Action Level is reached for main 4 steam line radiation (3X normal full power level).. Safety relief valves K and L open to reduce reactor pressure. Several control rods do not fully in-sert due to j amming of jet pumpd'ebris against fuel bundles. This condition
. results in fuel failure. Further at-4-
tempts to insert rods causes additional damage. 4 k e s
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' (3 g ) EXERCISE TIME SCHEDULE TIME KEY EVENTS 0805 Reactor is subcritical as indicated on the SRM's and IRM's. Water level is fluctuating with pressure changes. The HPCI sy' stem starts on Lo-Lo water level (126.5 ) and the recirculation pumps trip. Three control rods did not insert and seventeen rods are partially inserted and/or are inserting slowly.
0815 Eleven of the slow rods have completely inserted. The HP'CI inboard steam iso-lation valves 23-MOV-15 has started leaking from the pressure seal. HPCI has rcscored reactor water to the nor-mal operating range. 0330 Drywell pressure reaches 2.2 psig and the high drywell pressure alarm is re-ceived. Three more control rods.have-been fully inserted. Due to jet pump fs debris clogging in the core, further () ' rod movement causes additional fuel damage. 0345 Drywell radiation levels begin to in- , crease due to the leak in the. pressure seal en HPCI motor operated valve 23-MOV-15 and fuel failures.The con-tainment pressure reaches 2.7 psig causing RHR(LPCI), core spray pumps and emergency diesel generators to start. Ooerators use HPCI to reduce reactor pressure and cool down the reactor at
'600F/hr.
0900 Containment radiation level is 2000
-R/hr and is increasing rapidly due to progressive fuel failures. Drywell temperature is increasing and drywell pressure has increased to 3.0 psig.
Site Area Emergency should be declared. The release rate enrougn Standby Gas Treatment System has increased to 3 curies /sec. NM' 1
, s EXERCISE TIME SCHEDULE TIME KEY EVISTS 0915 One of the remaining si:c stuck control rods is fully inserted. Two rods ra-main froten in their partially inserted position. Three rods are still fully withdrawn. 0930 Containment high range radiation moni-tors indicate s10000 R/hr inside dry-well. Stack gas release increated to 10 Ci/sec. 1000 General Emergency should be declared when the Emergency Director determines that 2 of 3 fission product barriers are lost with potential loss of the third. Stack Gas release rate in-creased to 25 Ci/sec. 1015 Containment radiation levels are indi- . cated at s25000 R/hr. r 4 1030 Most of the reactor building is inac-cessible by this time-due to high radi- [N' ) ation levels (100 to 1000 R/hr) especi-
; ally c: the 326' elevation and the 344' elevation south and all elevations in the SE quadrant. Stack 3as release rate has increased to 60 Ci/sec.
1100 Stack Gas effluent taenitors indicate a stabilited release rate of. radioactive material at s100 Ci/sec. 1200 Operators terminate release by giving an additional close signal to 27-MOV-120. Leakage path was past 27-A0V-ll3 & -114 Drywell purge valve to SGTS (27-MOV-120) was not fully closed although indicator lights indi-cated full closed. 1300 Off-site radiation levels return to background levels. 1330 E=ergency is de-escalated and recovery is initiated. f-~g b ~
F 4' Scenario Overvieu -
\
At 0715, a diffuser on jet pump No. 6 ruptures in many small pieces. 3 cue of these small pieces are carried by the . core flow through c.e core place and fuel support piece and
- eventually lodge between the fuel rods in many of the bundles.
Other pieces of debris become lodged in the bypass region (be-tween fuel channels). Operators note the loss of jet pump No. , 6 flow as well as increases in core place differential pres-l sure, main steam line radiation and air ejector off-gas radia-4 tion levels. By 0725, the Unusual Event Emergency Action Level (EAL) is exceeded for air ejector off-gas radiation level (>100,000 uC1/sec incraase in 30 min.). At 0735, the Off-Gas Hi Rad alarm is received on canel 09-3. Radiation Protection should be contacted and requested to obtain off-gas and reactor coolant camples for-analysis. They should be duly warned of
- the potential for significantly higher than normal radiation
, levels. At 0745, the Off-Gas Hi/Hi Rad and Off-Gas Timer Initiated alarms are received. Operator action in accordance with AOP-3 has reduced power level to 4,30%. Nevertheless, air ejector off-gas and main steam line radiation levels have continued to increase. Core differencial precsure has also increased even though core flow is greatly reduced. One control rod of the cram group has jammed at notch position 14 and does not move with normal drive water pressure. This is a result of debris O.- from the ruptured jet pump No. 6 ja= ming between the control rod and the fuel channel. At 0755, the MSIV's fast close (Group I containment isolation) and a reactor scram is inici-ated as a result of excessive main steam radiation. The Aler: Emergency Action Level (EAL) is reached for main steam line radiation (3X normal full power reading). Safety relief valves K and L lift at 1090 psig to limit reactor pressure. Several control rods do not fully insert due to jamming of the jet pump debris against the' fuel channels. Since 2 or more adjacent rods are not inserted past position 06, contingency A of AOP-1 (Reactor Scram) is utiliced. This indicates the problem is hy-draulic. By 0800, the reactor is subcritical as indicated by the IRM's and the SRM's. Water level has fluctuated on pres-
~
sure changes (SRV's lifting) and HPCI has started on Lo-Lo water level (126.5). A computer print-out of rod positions in-dicates that 3 rods did not insert and 17 are partially in-serted. By 0815 the HPCI system has restored reactor water level to the normal coerating range. Eleven of the 17 partial-Iv inserted rods are f'ullv inserted. Also the HPCI inboard s' team isolation valve (23'-MOV-15) has started to leak from the pressure seal (body-to-bonnet). At 0830 the high drywell pres-sure alarm (2.2 psig) is received. This is a result of the steam leak from 23-MOV-15. Three more of the partially in-serted control rods have been fully inserted. Rod motion with the jet pump debris clogging the core causes additional fuel damage. By 0845, drywell radiation levels have increased sig-
'J nificantly due to the leak cn.23-MOV-15 and the cany fuel fail-(fs)
\'
ures. The containment pressure has reached the 2.7 psig ECCS , initiation and the RiiR and core spray pumps and the emergency diesel generators have started. Stack gas release rate (from SGTS) has increased to s1 Ci/sec. At 0900 containment radia-tion level is s2000 R/hr and increasing rapidly. Drywell pres-sure has increased to 3 psig. The stack gas release rate as indicated by the high range stack effluent monitors is s3 Ci/sec (the normal stack radiation monitors are off-scale high). By 0915 three control rods are still fully withdrawn and two rods remain stuck at a partially inserted position. Containcent radiation level indicated at 6000 R/hr. At 0930 stack gas release rate has increased to 10 Ci/sec. with a con-tainment radiation level of $10,000 R/hr. A General.Ecergency should be declared when the E=erSency Director determines that 2 of 3 fission product barriers are lost with potential loss of the third. By 1000 stack gas re-lease race is 25 Ci/sec. At 1015 centainment radiation levels have essentially stabilitad at s25,000 R/hr. stack gas release rates continue to increasa. Most of the reactor building is unaccessible due to high radiation levels. By 1100 stack gas release rate is stabiliced at s100 Ci/sec. . At 1200 The release is terminated when operators fully close 27-MOV-120. This valre was indicating closed but was ac-cually partially open. In addition, vent and purge isolation gsI s valves 27-AOV-ll3 & 114 failed to close, even though they
indicated closed. These failures were attributed to failed taper pins which attach the valve disc to the shaft. By 1300 off-site radiation levels have returned co background levels.
-At 1330 the emergency cay be de-escalated and recovery initiated.
4 l
. -. . - -.- , . . - - - . . - . ,,, , ,. - , - . . . - - -. , , . - . , . - - . . ~.
%h o #+ b IMAGE EVALUATION [j [*# ,
4 xp,,77 ~\! gff TEST TARGET (MT-3) ff4 #4 44,, <[' $
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- IMAGE EVALUATION ////Y,4 [.ddg#,
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- vN y7xx o '*%a%+#+4
- - -- 5 = - - -- - . ..
As ' i J V * - 1 4 FITZPATRICK SCENARIO I 4 MESSAGE ANTICIPATED RESULTS AND EMERGENCY ! TIME NUMiiER ISSUED TO
SUMMARY
OF MESSAGE C0dTENTS COMMENTS CLASSIFICATION 1
^
- t j
0630 1 Control Sununary of Initial Conditions None None Room
- A LPCI Subsystem is'INOP
( { - RCIC is INOP 4 1 i i t 1 i i 4 [ 4 i I Page la
- g. FOICI SAP 1.4 Page .lb
(' MESSAGE SHEET MESSAGE NO. 1 Exercise Time: 0630 Issued To: Control Room Personnel Issued By: Control Room Controller MESSAGE Initial Conditions The reactor has been operating the equivalent of 250 full power days since refueling and is currently at 98% power. The RHR A-LPCI leep inboard injection valve 10-MOV-25A is out of service for repair. The valve is closed and cannot be opened. The Shift Supervisor has declared the A side of LPCI inoperable. This permits seven days of operation to repair per Technical
, Specifications (7 days LCO). The required surveillance tests have /-~ been completed satisfactority.
The RCIC System is out of service for repair and is not expected to be available for another 72 hours. The reactor coolant chemistry is normal and all other systems important to safety are operable. O
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O. 32:1:s *.0aded/ F--* g ; 1:sse d; it s. ity, ;;3 i Vess.:1 20tte: , O. R= ing '. aied/E= ing C 1:aceioitsna:y, 0.03 Orain Ie:;ers ure ' 35
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i 12 Spent Tuel Area 0 :R/hr Core Spray Pu ;s (71:v ? ate 4625 g;:) 12 ?x. 31dg. 364' Ilv. Zouth - :?/hr j 16 :*ev Fuel Vault i R/hr ? 1.A. :: Servicei Standby; 003 , , 15 Cleanup Precoat ank Area li R/hr I 16 Cleanup Et. Ex. Intrance R/hr i ! 1.3. In Service / 5tandby> C03 17 Tuel Pcci F :ps 23 R/hr
- l I.PCI (b P=;s MO,000 g;d es: )
15 00 tas. Equi;t Storage 23 :R/hr 17 Fx. Cleanup Pump Ars n R/hr l 20 ?x. Sa:ple 3ta Ares A. :: Servi:e/ 2tacity/ M 21 01ose2 C:o1 Water Ex. 1.4
- R/hr
- R/hr '
i
' 22 Cc d. Ce:in Valve Ares 00s R/hr
- 3. *: Servi:e/[Stanity/004 23 ?x. Slig. Access ~
13/hr 2L ?x. 3114. ::? Machines _M 23/hr l C. In Service / Starity/ Q I 03 East CEO HYD Centrol 10 :R/hr 1 i it '.*est CD HY3 Cc tr:1 .: R/hr O. In Service / 2 tan:cy/ CO3 27 Equip. Cr. Sump 227' East :5 =R/hr k 2$ ?x. CED Removal Hate: ' :R/hr e EPCI In Service / Standty/ CO3 23 T1. ~r. Surp 227' West !) R/hr I
- I RCIO *: Servi:e/5tanity/[E33) 1
. , Ci/see .E.s = 10:R/hr m~..:
m ....,rm.
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- = 2ervice Yesh Yes.f[
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O O O FITZPATRICK SCEllAl:IO MESSAGE AdTICIPATED"RESULTS AND EMERGEllCY TIME IlUMBER ISSUED TO
SUMMARY
OF I1ESSAGE CollTENTS COMMENTS CLASSIFICAT10Il 0645 2 Control Steady State Operations None None Itoom Same as Initial Condition 4 i ) l l 4 I l 1 .i l Page 2a
I FORM SAP 1.4 Page 2b MESSAGE SiiEET MESSAGE NO. 2 Exercise Time: 0645 Issued To: Control Room Personnel Issued By: Control Room Controller MESSAGE 4 See Plant parameter data sheet. i ) 4 o 4 v
=
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l l l 1 l FITZPATRICK SCENARIO MESSAGE ANTICIPATED RESULTS AND EMERGEHCY I TIME NUMBER -ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION ! 0700 3 Control Steady State Operations Turnover to Relief. None Room Shift should begin
- Same as initial after turnover of real conditions Plant conditions to j- Day Shift i
1 ) = } }, i i i 1 i ) i i 1 Page la
i 1 r0RM SAP 1.6 Page 3b . i MESSAGE SHEET i MESSAGE ';0. 3 Exercise Time: 0700 Issued To: Control Room Personnel Issued By: Control. Room Controller l' MESSAGE i l See Plant parameter data sheet. 4 4 i 4 l m _. _ _ , _ . _ . _ - _ ~ .
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- ty '! 3 i Reaster vessc Pressrs n. ; sis 3. ?"-- %; 1:adei/h :i s Unu sieiL 5::.n.:tr03 Eea::or ?ressu.re Cre:1 -
O. 2Mring hadei/h: ing 0:Ralei 5:anit7J0:3 , Vessel 3ctt:: ": . h: ing hated /h :1:g Onhaled 'atanity '003
- '
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1151~i Reserve ?:ver Availatie 5 Clea=up Inlet Te:;. 510 o7
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Torus Ave. "ater Te:;. :. 'F Sulin 4 '.'es 2si 1:::1 Ors
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. 037 '.evel 2. :. 1.:ces 3:2:r. Est ::: 1ter .: . J;s**
1, 4 Orfeell Iqui; ent E14: Eange Iffh en: "anit: rs *" j leak Rate 5 g;: Sta:4 '-
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- 3. hService/fstanity/003 23 .'x. 311g. Access ~
- R/hr i
_,,,,,, 2 ?2. 313g. 7'? "accines o =R/hr C. hServi:e/Itacity/[,05] 25 Iast CRD HYO C:ntrol u :R/hr 26 We.st 02D 5YD :n:rol .* =R/hr f O. h Servi:e/ 2:anity 003 27 Eq.1;. Or. S ep 227' Iast a :R/hr i 2? ?x. CRD Renoval Haten :R/hr EPCI h Servi:e/ It antt" 003 29 F1. Or. L :; 227' West i) :R/hr j RCICInservice/ Star.ity/[C03 e . , , , e . - .e -
"'^"~"' c'". ~ ^ ^ ^ ' ' - ' '
, g,g aC*. / s.a. .n. G = .' _-. .= / w..-
A/cr A 3
" K = 0.95 aCi/sec IK3 = 3 CPS h Service Yes Yes
***K = 2 5. 'C'*/ aa i 12000 07'
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L o ( O i FITZPATRICK SCENARIO MESSAGE ANTICIPATED RESULTS AND TIME EMERGEtiCY NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 4 0715 4 Control - Generator output down +30 These symptoms are the-j None j Room MWe and declining rupture of No. 6 jet
-pump.
- Core follow down but core
{ AP up Fuel failures are occuring as a result.
- No flow or AP indication .of debris blocking for jet pump no. 6 cooling flow passages.
l
- Main steam line and off-- Operaccirs should ' carry 4
j gas rad levels increasing out actions of AOP-29 jet pump malfunction. l 3 l i i 1 i Page 4a f
r FOR'4 SAP 1. 4 Page ib MESSAGE SHEET i MESSAGE :!O. A Exercise Time: 0715 i Issued To: Control Room Personnel Issued By: Control Room Controller j MESSAGE
- Generator Output suddenly drops $30 mie and continues to decline
- slowly. Core flow drops from 73 ML3/hr to 62 ML3/hr but core ;P 4
increase from 21 to 25 PSI. Indication is lost for jet pump : o . 6 ! flow (and aP). Main steam line and air ej ector off-gas radiation
- - levels begin to increase.
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i O O O , ! FITZPATRICK SCENARIO i i MESSAGE ANTICIPATED RESULTS AND EMERGENCY l TIME NUMBER ISSUED TO SUl@!ARY OF MESSAGE CONTENTS COMMENTS CLASSIFICATION L 0725 5 Control Recirculation flow reduction UNUSUAL EVENT should be UNUSUAL EVENT Room has reduced power to less be declared when it is than 50*4. Off-Gas (air determined that off-gas , ejector) rad monitor reading radiation level has in-has increased to 900 mR/hr. creased >100,000 pCi/ see in less than 30 min i l i s k 1 1 L 1 i ) a l .
! I i
) !
{< Page Sa 1
I i. i FORM SAP 1.'. Page 3b l MESSAGE SHEET MESSAGE ;io. 5 Exercise Time: 0725 i
- Issued To
- Control Room Personnel Issued By: Control Room Controller j MESSAGE i
i Power has been reduced to less than 507'. by recirculation flow reduction. Off-gas (air ejector) rad monitor reading has 1 increased to 900 MR/hr. I f 1 { l l l l I. I e I
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-FITZPATRICK SCE!1ARIO !
i MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 3, f 0735 6 Control Of f-Gas 111 Rad Alarm was Operator should carry UNUSUAL EVENT l Room received at s0728. Main out ADP-3. Abnormal steam line and off-gas off-gas radiation j radiation levels have ~ level. UNUSUAL EVENT continued to increase must be declared at despite power reduction. this point. i Accident analysis / should be in progress k l i . I t i i I i j Page 6a
1 FORM SAP 1.4 Page 6b MESSAGE SHEET MESSAGE NO. 6 Exercise Time: 0735
- Issued To: Control Room Personnel Issued By: Control Room Controller
. MESSAGE The Off-Gas Hi Rad Alarm was received at s0723. Main steam line and off-gas radiation levels have continued to increase despite the power reduction that. has been performed.
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- E/hr li?; S Zervice/ 2: an d: /, ::2 2 ^, 71. Cr. S zp 227' West ,
R/hr RC : h cert::e/ ::an:ty/l:02
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O O O FITZPATRICK SCENARIO MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0745 7 Control Off-Gas Hi-Ili Rad and Oft-Gas Accident Analysis UNUSUAL EVENT Room Timer initiated alarms re- should be in progress ceived s0743. Off-Gas and Based on this analysis main steam line rad levels the Emergency Classi-still increasing. Power fication maybe upgraded reduced to < 30%. Control to ALERT. If an at-Rod 22 .- 23 januned at posi- tempt is made to scram tion 14 and does not move rod 22 - 23, it will ' with normal drive pressure. move into notch post-Main Steam Line 111 Rad Alarm tion 08 and jam there. 2400 mR/hr. i 6 p I i r P } Page 7a I i
FORM SAP 1.4 Page 7b l MESSAGE SHEET MESSAGE :!O. 7 Exercise Time: 0745 4 Issued To: Control Room Personnel Issued By: Control Room Controller l l MESSAGE i The Off-Gas Hi/Hi Rad and Off-Gas Timer Initiated Alarms are received (at 0743). Power level has been reduced to s307.. Nevertheless, air ejector off-gas and main steam line radiation i levels have continued to increase. Core differential pressure has also increased, even though cote flow is greatly reduced. Control 22 - 23 j aamed at position 14 Main Steam Line Hi Rad Alarm (2400 i mR/hr) is also received. l l
\
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O Cleanu; ::le !e p. :D F F3 12H Yesf:o Mai Stes: Pressure ';2 ? ;sig 54 . '? Yes,'::o Orfeell ?ress ee ".6.2 ;sia Crysell Ave. Ce ;. .i) 'T Fad ':: it:rs Torus Ave. Water Ze:p. : a? Su i n ng '.in: Sai :'.:nitors
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- j above Con:::1 Ece: inlet .:. 0?%
no. a1 Oryvell Fisor leaX ? ate i g; Off-Gas Esd Monitor '.6a0 :R/ar* C37 level ca in:hes Staa lad Monitor _.:- ';s** .I ,j Orfeell Iqui;:en: High Range Offluent :'o it:rs *** i lea 4 Sate 5 3;: Sta:4 1.3 23/hr
- ,---- Turtine Building 0 23/cr
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- R/cr
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. K 0?I C103IO 3 Radvaste C: tr:1 Poe: i R/.u-l L C?I 01 3IO 9 Radv Filt/Yalve C;. Ares e3 :3/hr 1,0 Endv. Or's S* rage Area o :*/hr r_........-- s n--s.m.s. a- sr. .....e . .
- a.4.easte r._..p r , .
5 q/w.r i 12 .' pent Tuel Area 0.7 23/hr Core spray Fu ;s (71ov Ia:e :.625 g;:) 13 F2. nig . 3w nr. scu:h . =8/hr , 1:. ::ev Tael 7aul 9 =d/hr i t 1.A. 3 Servi:s/ Itacity/ C3 15 Clea.up ?ree:at rank Area . :R/hr 16 01eanup Et. Ex. F. tran:e 4 8/hr i 1.3. 2e-vi:e/ Jtacity/ 0^3 17 Tuel ? sol Fu ps :0 =R/hr t 15 C:::as. Iqui;t storage cc 23/hr l 1?C: (. ?m;s %10,000 g;: esch) 19 ?2. Cleanup Pu=p Ara .,
?/hr 5
' 20 ?2. Sas;1e 5ta Area 23/hr A. 32ervi:e/Ita:dby/h:3 21 0;osed Cool Water Ix. ..c 23/hr 22 00:1. Ce:10 Valva Area C05 R/hr i 3. 22erviceil2tacityif003 23 ?2. Slag. Access :2/hr 23/hr 2 ?2. 31dg. !!? Mac ines a C. S Service / Stacity/l0 3 25 East C33 HY3 Centrol la :R/tr r 26 West CFD HYD C0ctr:1 13 :3/hr l 3. In cer 1:e/ 2tanaty/ 003 27 Iquip. Or. Su=p 227' Ias: 2) :R/hr 23 P2. CRD Re= oval Haten =R/hr E?C: != Service / Itandby/ C03 29 F1. Or. Su p 227' 'a'est D :R/hr RCIO 3 Service / Jtand:y/ 003 n- . ," " ~ ' c.^s ..3.,,...,a.-..
~-w u".f3.. " *" _2f"5.
- K = 133 =N ar A 3 f " K = 0.}5 201/see 2K3 = 3 C?$ I:. Service Yesh Yespio
' * "K = 2. 5 4 ~ , ...~~ ! 12^;0 CFM
- J nr 4
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3 O O O i
, FITZPATRICK SCENARIO 1
i
- MESSAGE ANTICIPATED RESULTS AND EMERGEHCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMUNTS CLASSIFICATION 0755 8 Control Group I isolation from high ALERT should be de- ALERT j Room steam line radiation (3x clared for main steam i normal full power level). line radiation level ! Reactor scram from MSIV's 3x normal full power , 10% closed. Several con- level. Operators ! trol rods do not fully in- should carry out ac-i sert. SRV's K and L open tions of AOP-1 in-to regulate presst.re. cluding contingency A ~ i Scram failure will.ap-j pear to be hyraulic (blue scram rights on
- and white RPS lights i out). Actual cause l is the jet pump debris j jammed between fuel bundles. Continued cf-
, forts to insert rods l will allow many addi- , tional rods to insert
- slowly causing addi-l
' tional fuel failures.
- See. rod position t sheets.
J i l l i 1 Page 8a
i F0F01 SAP 1.4 Page 8b MESSAGE SHEET MESSAGE NO. 8 Exercise Time: 0755 Issued To: Control Room Personnel
. Issued By: C_o_n_ trol Room Controller MESSAGE Group I isolation and reactor scram occurs from high steam line radiation (3x normal full power level). Several control rods do not fully insert. SRV's K and L open to regulate reactor pressure. (Control positions given on Sheet 8d).
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_ _ - - , 26 ~4e s: 23 : .iY: Ce a.: rci .R/hr
- 2. : Service /l::innyp ::: 27 Equi;. :r. Se:p 227' Iast -
R/hr 23 ?2. :?O Fe=cval :iate a R/hr
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CC:37 1 A3 T- EA-" -.- /.~ s e g . ;33 .'ihe: 2.-/ r 2g . ; ,,,3f;7 A 3 K = 0.M .C1/sec 3E .
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~
i t l FITZPATRICK SCEllARIO
- MESSAGE ANTICIPATED RESULTS AND EMERGENCY j TIME 11 UMBER ISSUED TO SUI @lARY OF MESSAGE CONTENTS COMMENTS CLASSIFICATION l
1 l 0805 9 Control ' Reactor is suberitical by Operators should con- ALERT i Room SRM & IRM indication. IIPCI tinue to carry out the restored / maintains water actions of AOP-1 con- , level. Recirculation pumps tingency A. Rods have j tripped on Lo-Lo water been inserted as shown ] level (126.5"). Three con- on Rod Position Sheet
- trol rods at 48. Seventeen 9d.
! others partially inserted j or are inserting slowly.
- Off-Gas vent pipe lli Rad j Alarm (105 CPS) '
l 1 J b I I l, 3 l I i 1 i i Page 9a
d j c0RM SAP 1.4 Page 9b i MESSAGE SHEET MESSAGE NO. 9 Exercise Time: 0805 Issu2d To: Control Room Personnel Issued By: Control Room Controller MESSAGE i HPCI is operating to restore / maintain water-level. SRV's K and L have cycled to regulate reactor pressure. The Off-Gas Vent Pipe Hi Rad Alarm (105 CPS) was received. Three control rods still at
- 48. Seventeen others hare partially inserted and/or inserting slowly.
C I 4
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#3 153 Yes/::o
- ain Sten: Pressure "/A ;sig l
ek :"? Yes(*:o "rreell Pressure 16.? Isia . Ir,eell Ave. Ter;. ~.:. ;T Fai Monit:rs Torus Ave. .'ater !e:;. M *T 3 ul.21:6 Vent Rad :'cni: Ors 2.x. m-..i
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Torus Pressure 1. 5 ; sis Refuel F1:cr .a A 0?:'
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- r:.s Water ".evel 1.0 inches Rad-aste .C !?
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- r s1 Oryvell Thor *. eat Rate 3/A g;:
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'urbine 3u1111:4 -: :R/hr Pri:ary Cantat----: Iso. C :;. ' Yesl:*o Raivaste 'uilding ,
- R/hr i
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_OSIN [C103I_ 7 Reac:Or Teed Pu:; Area . - R/hr K c?C c:.'3ID 3 Radvaste Contr:1 Re : 5 R/hr 0?I.:
-- 01:3C 9 Radv. Tilt /Yalve Ce . Area 2? :R/hr 10 Radv. Orm Sterage Area e :R/hr I'* E:II*JIO 317IT.UO3 (:ir:le) 11 Radvaste ?=p Re: 35 R/hr 10 $;en Tuel Area 1.5 mR/hr Care 3; ray ? :;s (71:v Rate b625 g;:) 13 ?x. Slig. 3ka ' 217. South o =R/hr
*:ev Tuel 7ault :R/hr 1+
1] 1.A. h Service / Standby / C05 15 Cleanup Preccat Ta 4 Area e :R/hr 16 01eanup :!t. Ex. Intrance 3 R/hr 1.3. In 3ervices 5ts dby/ 003 17 Tuel ? col ?=;s 150 R/hr 13 Contas. Iqui;t Storage 50 R/hr LP"I (L Pu ;s % ;,000 g;: taen) 19 ?2. Cleanu; Pu:p Ara 20 :R/hr 20 Pa. Sa ;1e Sta Area 1; =R/hr A. In Servi:e/ Itacity/l003 l 21 01: sed Cool Water Ex. 5 :R/hr
, 22 Cona. Cecin Valve Area G35 R/hr
- 3. Inservice /j3:andby/003 23 Rx. 31dg. A::ess 15 :R/hr
, 24 Ex. 3114. !!? Macnines e5 :R/hr C. In Service / Standty/l0OS 25 Eas: ORO H C Centrol c] R/hr 2ti West CR0 HYO Centr:1 9 =R/hr O.
InZervice/[3:anac/f003 27 Iqui;. Or Sump 207' Iast t] =R/hr 28 Rx. C33 Pesoval Haten .. 3 EPCI h Se-vir.e 3tancty/ CCO 29 T1. Or, Su=p 027' West J- =R/hr =R/hr ROIC In Service / Jtanaty/%
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cr./ cr A 3 " s ## {s Q,33 aC1/sec 3 C = 3 C73 In Service Yes No Yes
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. : a 27 C>c 00 /8 co 98 Co / 2, co oo 0o co 00 00 - - 27 23 00 00 oo /1 Co c(, oo co oo oo oo oo co ---23 a ' -
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- l ll - .II -
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O. O' : FITZPATRICK SCENARIO i . MESSAGE ANTICIPATED RESUL.TS AND EMERGENCY ,
- TIME NUMBER ISSUED TO SUt@lARY OF MESSAGE CONTENTS COMMENTS CLASSIFICATION i 0815 10 Control Eleven of the 17 slow / par- The IIPCI inboard steam ALERT i Room tially inserted rods fully isolation valve 23-MOV-inserted. . 15 has started 1. caking
, temperattire.Drywell pressure , and radiation from the pressure seal. i i levels are increasing. This caused the in-Reactor building ARM s are creased drywell pres-- beginning to Alarm. Stack sure, temperature and Gas Rad monitor readings radiation. The results continuing to increase. of the reactor coolant water sample indicate I-131 equivalent con- I centrations of 1000 to 5000 pCi/ml. l i i i 4 5 1 l Page 10a
_. . . . __ _ _ - _ - = .. FORM SAP 1.4 Page 10b O MESSAGE SHEET , , MESSAGE '!0. 10 Exercise Time: 0815 l Issued To: Control Room Personnel Issued By: Control Room Controller MESSAGE 1 , Eleven of the slow / partially inserted rods are fully inserted (see rod position sheet). Drywell pressure, temperature and radiation , level have started to increase. Reactor building ARM's are beginning to alarm (Rx bldg. 344' South - 100 mR/hr). Stack Gas Rad Monitor readings continuing to increase. O V f 4 i f
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\ \ l u o FITZPATRICK SCE!1ARIO MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0830 11 Control Stack gas and drywell rad Analysis of accident ALERT Room levels increasing. Drywell should be well under temperature and pressure way. Attempts should increasing. be made to determine the release path and isolate. Reactor Building 326' eleva-tion has rad levels of 1 to 10 R/hr. Further control rod motion causes addi-tional fuel damage. l Page lla
l 2 FORM SAP.l.4 Page llb MESSAGE SHEET
- MESSAGE NO. 11 Exercise Time
- 0830 Issued To: Control Room Personnel l Issued By: Control Room Controller MESSAGE Off-Gas Vent Pipe (Stack Gas) Hi/Hi Rad Alarm received at s0820.
, Drywell High Pressure Alarm (2.2 psig) received. Drywell pressure, temperature and radiation levels continuing to increase. Stack Gas Rad Monitor readings continuing to increase. Three more rods are fully inserted. i
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FITZPATRICK SCENARIO MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0845 12 Control liigh drywell pressure ECCS Rapid cooldown (de- ALERT Room initiation set-point (2.7 pressurization) is psig) reached. RilR and not recommended due core spray pumps start. to potential for EDG's start and run un- . additional fuel fail-loaded. Drywell radiation ures. Emergency level incresed to 1000 R/hr classification may be normal stack rad monitor increased to SITE - has gone off-scale high AREA EMERGENCY. (> 106 CPS). Stack Gas Release
*1 Ci/sec primarily noble gases.
i 1 Page 12a
7 FO.UI SAP 1.4 Page 12b -
.k FESSAGE SiiEET
>ESSAGE NO. 12 Exercise Time: 0845 Issued To: Control Room Personnel Issued By: Control Room Controller MESSAGE
{ High drywell pressure ECCS initiation set-point (2.7 psig) reached. RHR and Core Spray Pumps start. Emergency diesel generator start and run unloaded. Drywell radiation level has increased to 1000 R/hr. Normal stack radiation monitor has just l gone off-scale high (>106 CPS). i t l l - i l l 1 i
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- O J FlTZPATRICK SCENARIO 4 MESSAGE ANTICIPATED RESULTS AND EMERGEllCY
! TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION i i ! 0900 13 Control Drywell radiation level is Release rate through SITE AREA - Room 2000 R/hr and increasing Standby Gas Treatment EMERGEllCY rapidly. Drywell pressure System (SGTS) has in-and temperature continuing creased to s3 Ci/sec. to increase. Drywell SITE AREA EMERGENCY pressure is 3.0 psig, should be declared.
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RilR should be lined i up for torus cooling. i 4 I I i 1 i l Page 13a
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j FITZPATRICK SCENARIO + ! e ! MESSAGE ANTICIPATED RESULTS AND EMERGENCY ! TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION f } ! 0915 14 Control One of three remaining par- No further rod inser- SITE ARE , j Room tially inserted rods is tion is possible, j fully inserted. Stack Gas Release i , See Plant data sheet. Rate s6 Ci/sec. 4 $ 1 k 4 1 } , i i i } ! t 1 I t ! l 1 - i-2 1 Page 14a
. _ . . - - ~. - . , . - _ _. _ , . . _ .
FORM SAP 1.4 Page 14b MESSAGE SiiEET MESSAGE NO. 14 Exercise Time: 0915 Issued To: Control Room Personnel Issued By: Control Room Controller i MESSAGE One of three remaining, partially inserted, control rods is fully inserted. Stack gas releases and reactor building radiation level ' still increasing. i i O
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[G) FITZPATRICK SCENARIO MESSAGE ANTICIPATED RESULTS AND EMERGEtiCY TIME IlUMBER ISSUED TO
SUMMARY
OF MESSAGE COI1 TENTS COMMEllTS CLASSIFICATION 0930 15 Control Containment high range radi- Escalation to GENERAL SITE AREA Room ation monitors indicates EMERGEt1CY should be EMERGEtiCY s 10000 R/hr inside drywell considered. i Page 15a
FORM SAP 1.4 Page 15b FESSAGE SHEET MESSAGE NO. 15 Exercise Time: 0930 Issued To: Control Room Personnel Issued By: Control Roon Controller FESSAGE Containment High Range Radiation Monitors indicate s10000 R/hr inside the drywell. See Plant data sheet. Most reactor building ARM's are offscale high (>103 mR/hr). O - I O
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i i O ' i 4 FITZPATRICK SCENARIO 1 4 ' MESSAGE . ANTICIPATED RESULTS AND TIME EMERGENCY NUMilER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 0945 l 16 Control Reactor Building Radiation May escalate to SITE AREA Room are s 1 to 10 R/hr. GENERAL EMERGENCY. EMERGENCY ! i I l i b i . : i l ! Page 16a l .-. ~_ _ . . _ . - - - - -
FOMI SAP 1.4 Fage 16b ! ESSAGE SHEET
>ESSAGE NO . 16 Exercise Time: 0945 Issued To: Control Room Personnel Issued By: Control Room Controller FESSAGE I See Plant data sheet. Reactor Bulding radiation levels are s 1 to 10 R/hr.
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l FITZPATRICK SCENARIO i MESSAGE ANTICIPATED RESULTS AND EMERGENCY
; TIME NUMBER ISSUED TO
SUMMARY
OF. MESSAGE CONTENTS COMMENTS CLASSIFICATION i 1
; 1000 17 Control See Plant status data sheet GENERAL EMERGENCY GENERAL l Room abould be declared EMERCNECY j when the Emergency ; Director determines that 2 of 3 fission j product barriers are 4
lost with potential loss of the third. 1 ; .i .i l l i i 4 i l 1 1 i i ) i t Page 17a 1
_ .- . - --. -= . . _ 4 FORM SAP 1.4 Page 17b MESSAGE SHEET MESSAGE NO. 17 l Exercise Time: 1000 Issued To: Control Room Personnel Issued By: Control Room Controller MESSAGE See Plant Status Data Sheet. P i i i I i I i
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- FITZPATRICK SCENARIO 1
1 MESSAGE ANTICIPATED RESULTS AND EMERGENCY
; TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION i 1 1015 18 Control Containment radiation level GENERAL EMERGENCY GENERAL i Room has plateaued at 25000 R/hr should be declared EMERGENCY , ! Off-Site (Stack Gas) release at this time. i i rate continues to increase. I 1
! I i
i i i l 1 l l l l I l 4 l I Page 18a ; j i
i FORM SAP 1.l. Page 18b MESSAGE SHEET MESSAGE NO. 18 Exercise Time: 1015 Issued To: Control Room Personnel i Issued By: Control Room Controller i MESSAGE I j Containment radiation level has plateaued at 25000 R/hr. The stack release rate continues to increase. See Plant Data Status Sheet. t l O
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FITZPATRICK SCENARIO MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME IlUM11ER ISSUED TO
SUMMARY
OF MESSAGE C011 TENTS COMMENTS CLASSIFICATION 1030 19 Control Most of the reactor building GENERAL EMERGENCY GENERAL Room is inaccessible by this time should be declared by EMERGENCY due to high radiation levels this time. - (100 to 1000 R/hr) especial-ly on the 326' elevation and the 344' elevation south and all elevations in the SE quadrant. See Plant data status sheet. Page 19a
l FOMI SAP 1.4 Page 19b ESSAGE SHEET
- MESSAGE NO. 19
; Exercise Time: 1030 Issued To: Control Room Personnel l Issued By: Control Room Controller MESSAGE l Most of the reactor bulding is inaccessible by this time due to high radiation levels (100 to 1000 R/hr) especially on the 326' elevation and the 344' elevation south and all elevations in the SE quadrant. See Plant Data Status Sheet.
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i O O O 1 FITZPATRICK SCENARIO i
-i i MESSAGE ANTICIPATED RESULTS AND EMERGENCY
{ TIME flUMBER ISSUED TO SUMI1ARY OF MESSAGE CONTENTS COMMENTS ' CLASSIFICATION i l 1045 20 Control See Plant. status data sheet. None GENERAL-Room Containment radiation level EMERGENCY stabilized at 25000 R/hr. Condensate booster pumps are now supplying water to i the reactor vessel. l-1 i l' f I 1 I il P i i I 1 j Page 20a
1 FOR'! SAP 1.4 Page 20b MESSAGE SHEET MESSAGE NO. 20 , Exercise Time: 1045 Issued To: Control Room Personnel Issued By: Control Room Controller MESSAGE i See Plant Status Data Sheet. Containment Radiation Level stabilized at s25000 R/hr. The condensate booster pumps are now supplying water to the reactor vessel. HPCI changed over to torus suction. l I a I J , e
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i i' a FITZPATRICK SCENARIO MESSAGE ANTICLPATED RESULTS AND EMERGENCY , TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE C011 TENTS COMMENTS CLASSIFICATION 1 2 i l 1100 21 Control Stack gas release rate sta- None GENERAL ; j Room bilizes at s 100 Ci/sec. EMERGENCY e l
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FORM SAP 1.4 Page 21b MESSAGE SHEET MESSAGE NO. 21 Exercise Time: 1100 Issued To: Control Poem Personnel Issued By: Control Room Controller MESSAGE Stack gas release rate as indicated by the high range effluent monitor has stopped increasing. See Plant Status Data Sheet. i l O Q
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i i FITZPATRICK SCENARIO I MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION ; 1 1115 22 Control Low pressure ECCS (RilR & CS) None GENERAL i ) Room now available to supply EMERGENCY reactor vessel, i See Plant' status data sheet. I l 1 i' i I i i Page 22a
i ( 3 FORM SAP 1.4 Page _22b MESSAGE SHEET MESSAGE '!O. 22 Exercise Time: 1115 Issued To: Control Room Personnel Issued By: Control Room Controller MESSAGE Low pressure ECCS now available to supply reactor vessel. See Plant Status Data Sheet. i j 4 m 1 5 4 i 1 v i
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I i FITZPATRICK SCEIIARIO MESSAGE AllTICIPATED RESULTS AND . EMERGE 14CY TIME NUMBER ISSUED TO
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OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 1130 23 Control See Plant status data sheet None GENERAL Room EMERGENCY' t i I i I 4 I Page 23a
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- F0F'4 SAP 1. L Page 23b i MESSAGE SHEET FESSAGE NO. 23 Exercise Time
- 1130 Issued To: Control Room Personnel l Issued By: Control Room Controller 4
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O O O FITZPATRICK SCENARIO 1 MESSAGE ANTICIPATED RESULTS AND EMERGENCY TIME NUMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 1145 24 Control See Plant status data sheet None GENERAL Room EMERGNECY i
. . j i
i 9 Page 24a
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l FOPlI SAP 1.4 Page 24b FESSAGE SHEET FESSAGE NO. 24 i , Exercise Time: 1145 l Issued To: Control Room Personnel Issued By: Control Room Controller FESSAGE l [ See Plant Status Data Sheet, i ll I 1 h I 1 1 4 I ) .
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r' O- Q' T V \ FITZPATRICK SCEllARIO MESSAGE AtlTICIPATED RESULTS AND EMERGEllCY TIME NUMIiER ISSUED TO
SUMMARY
OF MESSAGE COIITENTS COMMENTS CLASSIFICATION 1200 25 Control Operations and Maintenance 27-MOV-120 was closed GENERAL Room personnel terminate the by cycling the valve EMERGENCY release by full.y closing open and closed several 27-MOV-120. Leakage path times. Efforts to do was past 27-A0V-113 & 114. clis earlier is pre-Drywell purge valve to vented by the referees. SGTS (27-MOV-120) was not fully closed although in-dicator lights indicated full closed. 1 Page 25a
/~N FORM SAP 1.4 U Page 25b MESSAGE SHEET MESSAGE NO. 25 Exercise Time: 1200 Issued To: Control Room Personnel Issued By: Control' Room Controller MESSAGE Operations and Maintenance Personnel terminate the release by fully closing 27-MOV-120. Leakage path was past 27-MOV-ll3 and 114. Drywell purge valve to SGTS (27-MOV-120) was not fully closed although indicator lights indicated fully closed.
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C d O V ['/ C i FITZPATRICK SCENARIO MESSAGE AllTICIPATED RESULTS AND EMERGENCY TIME NUlWER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION 1215 26 Control Stack gas release rate down None GENERAL l Roota significantly. See Plant EMERGENCY
! status data sheet.
i i 1 i 1 1 i ) t i i 4 l i i i l Page 26a
i , i i 'l , FOR:1 SAP 1.4 Page 26b , i: MESSAGE SHEET MESSAGE NO. 26 i Exercise Time: 1215 2 Issued To: Control Room Personnel , i Issued By: Control Room Controller l MESSAGE Stack gas release rate down significantly. See Plant Status Data ) Sheet. l O l
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FITZPATRICK SCEllARIO MESSAGE AllTICIPATED RESULTS AND EMERGENCY TIME NUM13ER ISSUED TO SUl@!ARY OF MESSAGE CONTEllTS COMMENTS CLASSIFICATION 1230 27 Control llPCI tripped (low pressure) EMERGENCY classifica- GE!!ERAL Room See Plant status data sheet tion may be de-esca- EMERGE!!CY lated to SITE AREA EMERGENCY l Page 27a
i_ , 4 i s i l t
! FORM SAP 1.l. Page 27b MESSAGE SHEET i
I MESSAGE ::0. 27 2 Exercise Time: 1230 l j Issued To: Control Room Personnel , t
- Issued By
- Contr51 Room Controller '
i 4 MESSAGE 1 I l HPCI tripped for low pressure. See Plant Status Data Sheet. d .! e i i i d 4 4 t i l l
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%,/ %.,_ s' FITZPATRICK SCEllARIO MESSAGE AllTICIPATED RESULTS A11D EMERGEllCY TIME 11 UMBER ISSUED TO
SUMMARY
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. i l ( FORM SAP 1.4 Page 28b l FESSAGE SHEET MESSAGE NO. 28 Exercise Time: 1245 Issued To: Control Room Personnel Isstied By: Control Room Controller i MESSAGE The reactor is depressurized to <75 psig. Shutdown cooling may now be initiated. Drywell pressure has been reduced to less than the ECCS set point (2.7 psig). See Plant Status Data Sheet. l O i I 1 'l. O
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'%.d' FITZPATRICK SCEllARIO MESSAGE ANTICIPATED RESULTS A!1D E!!ERGEllCY TIME 11 UMBER ISSUED TO SUI @fARY OF MESSAGE COI1TEtlTS COMMEllTS CLASSIFICATION 1300 29 Control Off-site radiation levels Continued de-escalation SITE AREA Room return to background possible EMERGEllCY levels. See Plant status data sheets.
I Page 29a
( i f r I < l I j FORM SAP 1.4 Page 29b ! 4 i IESSAGE SHEET ! i. , ESSAGE : 0. 29 i j Exercise Time: 1300 i Issued To: Control Room Personnel i Issued By: Control Room Controller MESSAGE I ! Off-site radiation levels return to background levels. See Plant Status Data Sheet. l 4 6 k i l i I 1 il 4 I I 1 i I. 1 k i l i e t t
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OF !!ESSAGE COI1 TENTS COMMEIITS CLASSlFICl> TION 1315 30 Control See Plant status data sheet EMERGENCY classifica- SITE AREA P.com tion may be de-esca- EMERGEllCY lated to ALERT level. l Page 30a
i i , FORM SAP 1.4 Page 30b _ MISSAGE SHEET I MESSAGE NO. 30 Exercise Time: 1315 . j Issued To: Control Room Personnel Issued By: Control Room Controller 1
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m-. . _ .~ . . _ . 4 O ( 2 i ) FITZPATRICK SCENARIO ! MESSAGE ANTICIPATED RESULTS AND EMERGENCY j TIME 11 UMBER ISSUED TO
SUMMARY
OF MESSAGE CONTENTS COMMENTS CLASSIFICATION l l 1330 31 Control EMERGENCY de-escalated and De-escalation to ALERT ALERT- ! Room recovery effort initiated, should be complete. l Drill completed. I t ! I l l i I t i Page 31a i
l FOIO! SAP 1.4 Page 31b
>ESSAGE SHEET 4
- MESSAGE NO. 31 i
Exercise Time: 1330 I Issued To: Control Roca Personnel i Issued By: Control Room Controller FESSAGE Emergency is de-escalated and recovery ic initiated. i Drill is completed. 4 ? J l l 9 i i
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