ML20113G988
| ML20113G988 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/19/1992 |
| From: | PENNSYLVANIA POWER & LIGHT CO. |
| To: | |
| References | |
| PROC-920219, NUDOCS 9205140317 | |
| Download: ML20113G988 (344) | |
Text
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FORWAPJ) This exercise package has been dev, eloped to provide the M sis for conduct of the simulated radiological accident at the Susquehanna Steam Electric Station Unit fl located in Luzerne County, the state of Pennsylvania. The exercise will test and evaluate the effectiveness and capabilities of the Emergency Preparedness Response Program for the Pennsylvania Power and Light Company. This package is to be utilized by the exercise referees to initiate, control, and evaluate the activities of the participants in the exercise. The Pennsylvania Power and Light Company approves this document as the standard for conduct in performance of the February, 19, 1992 NRC Graded Exercise. h 6 L
TABLE OF CONTENTS P_M1 SECTION I INTRODUCTION I-1 A. Major Exercise Event Schedule I-3 B. Exercise Development Philosophy I-7 SECTION II OBJECTIVES 11-1 SECTION III GUIDELINES FOR CONDUCT OF EMERGENCY EXERCISE III SECTION IV REFEREE DATA AND INSTRUCTIONS I'!- 1 A. Referee location and Telephone Numbers IV-6 SECTION V TIMELINE V-I A. Sunnary V-2' B. Oe'; ailed Timeline V-12 C. Basis of Timeline Events V-28
- 1. Security Event V-29
- 2. Offgas Explosion V-31
- 3. Turbine Trip / Fuel Damage V-38
- 4. RCIC Steam Line Break V-42 -
SECTION VI INITIAL CONDITIONS VI-l A. NSAG Daily Report VI-2 B. Priority Lists VI-5 C. Operator Turnover Sheets VI-10 9 I
SECTION VII RADIOLOGICAL CONDITIONS A. Offsite Release Data
- 1. Weather and Het Data Log VII-1
- 2. Plume Trajectory and Plume Deposition Data VII-4
- 3. Noble Gas and I-131 Release Rate Data VII-8
- 4. Field Monitoring Team Data VII-ll B. Reactor Water Isotopic VII 16 C. Suppression Pool Water Isotopic VII-19 D. Drywell Air Isotopic VII-22 E. Wetwell Air Isotopic VII-24 F. Vent Monitor (SPING) Data VII-26 G. Reactor Bldg. Area Rad Monitor Readings VII-32 H. Control Structure Area Rad Monitor Readings VII-55 I. In-Plant Dose Survey Haps VII-72 J. PASS Sample Information VII-80 K. CST Berm Water Concentrations VII-83 L. Radwaste Building Offgas Activities VII-85 H. RCIC Room Activities VII-87 SECTION VIII MESSAGE INFORMATION SHEETS VIII-l SECTION IX EXERCISE QUESTIONS IX-1 A. NRC Questions IX-2 B. Questions / Topics of Discussion for HPN Communicator IX-5 SECTION X SIMULATOR INFORMATION X-1 O
O SECTION I INTRODUCTION 9 O 11
INTRODUCTION The Annual NRC Graded Exercise is scheduled to be conducted February 19, 1992. O The exercise is the annual NRC Graded Exercise to satisfy 10CFR50 and NUREG 0654 requirements. The municipalities will not be observed this year by FEMA. The exercise has been developed to test most of the major aspects of the Station's Emergency Preparedness Program (see the Exercise Objectives, Section II). This annual (xercise will have participation by the counties and the appropriate State Agencies. The exercise will be observed and critiqued by the Nuclear Regulatory Commission at the utility level only. The role of the NRC is to evaluate the capabilities of the Licensee to provide the necessary protection for ensuring the health and safety of the public in the event of an accident at the Susquehanna Steam Electric Station. A practice exercise is scheduled for December 17, 1991 and January 14, 1992 in preparation for the NRC Graded Exercise. The practice exercises contain events similar to the NRC Graded Exercise. This is an attempt to ensure the participants are not tested on material never seen before. The two practice exercises combined will provide an opportunity for the participants to sharpen the skills that will oe used during the graded exercise. This package has been developed to guide the referees in the conduct and evaluation of the exercise. This package contains all of the information and data necessary to properly conduct the exercise in an efficient and coordinated manner. EXERCISE PARTICIPANTS WILL NOT HAVE PRIOR KNOWLEDGE OF THE NATURE OF THE SIMULATED INCIDENT OR ANY PARTS SUCH AS: RADIOLOGICAL PLUME RELEASE INFORMATION INCLUDING TIME, CONTENT, SIZE, AND WEATHER PATTERN USED. The exercise should allow individuals and agencies who are assigned responsibilities in an emergency to demonstrate they are adequately trained and capable of responding. ( l I-2 l l l
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SECTION I PART A - HAJOR EXERCISE EVENTJSCHEDULE O l' l e i e O I.3 l l l l I~ r , -- , , - , , , > , ~ . . - -,, --,,.., , e - -- , - e , + -, -e, - e -
ANNUAL FXERCISE DATE AND TIME This exercise has been developed to initiate response actions on December 17 O and January 14 for the practice exercises and February 19, 1992 for the graded exercise. The exercises have been designed to test the response of the station's emergency preparedness program. The duration of the exercises is expec+ed to be about 6 hours. OVERALL SCHEDULE OF EVENTS FOR ANNUAL EXERCISE December 9 TSC Walkthrough Time: 1330-1530 Location: TSC Attendees: All TSC players December 10 E0F Walkthrough Time: 0900-1530 Location: E0F Attendees: All EOF players December 13 Lead Referee Simulator Demo Time: 1000-1200 Lc:ation: Simulator Attendees: All Lead Facility Referee-December 16 Referee Training Time: 0830-1200 g Location: EOF LCR Attendees: All Referees and Observers December 17 First Practice Exercise Time: Day Shift Location: Simulator and all ERFs (M0C from SOP /SE!C/Riverlands) Attendees: All Players, Referees, and Observers December 18 Critique Preparation Time: 0800-1300 Locaticn: E0F LCR Attendees: Lead Facility Referees December 18 Critique Presentation Time: 1400-1600 Location: EOF LCR Attendees: All Manager and Coordinator Players; Lead Referees; others optional . i I-4
December 18 Operations Meeting-(as necessary) Time: 1600-1800 A)- t Location: Attendees: EOF Lead Control Room Referee l l January 10 Lead Referee Training Time: 1000-1200 Location: Simulator Attendees: All Lead facility Referees January 13 Referee iraining Time: 0830-1200 Location: EOF LCR Attendees: All Referees and Observers January 14 Second Practice Exercise Time: Day Shift Location: Simulator and all ERFs (MOC from SOP /SEIC/Riverlands) Attendees: All Players, Referees, and Observers January 15 Critique Preparation Time: 0800-1300 Location: E0F LCR Attendees: Lead Facility Referees January 15 Critique Presentation O Time: 1400 1600 V Location: EOF LCR Attendees: All Manager and Coordinator Players; Lead Referees; others optional January 15 Operations Meeting (as necessary) Time: 1600-1800 Location: E0F LCR Attendees: Lead Control Room Referee February 14 Lead Referee Training
-Time: 1000-1200
, location: Simulator ! Attendees: Lead Facility Referees February 18 Referee Training
- Time: 0830-1200 Location: EOF LCR Attendees: All Referees and Observers February 19 NRC Exercise -
Time: Afternoon Shift Location: Simulator _ and all ERFs (HOC from YMCA) Attendees: All Players, Referees, and Observers 1-S I
February 20 Critique Preparation Time: 0800-1200 Location: EOF LCR ! Attendees: Lead Facility Referees ' February 20 Critique Presentation Time: 1230-1430 Location: EOF LCR Attendees: All Manager and Coordinator Participants; Lead l Referees; others optional February 20 Operation Meeting (as necessary) 1 Time: 1600-1800 l Location: EOF LCR Attendees: Lead Control Room Referee l 1 O t I-6
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I l I l l O l l l Y s f I i SECTION I PART B - EXERCISE DEVELOPMENT PHILOSOPHY t H s I-7
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EXERCISE DEVELOPMENT PHILOSOPHY NUREG N.3 Proper scenario development determines the outcome of the exercise. All operating nuclear power plants, including SSES have already demonstrated their ability to protect the health and safety of the public. SSES has people who are knowledgeable and can respond in an emergency, therefore chances of failing an exercise are remote. SSES can fail an exercise or get a reduced SALP rating because of attitude and that is where scenario development is important. An attitude is generated when an exercise is being conducted and observed; this attitude will affect present and future exercises. The scenario must be detailed enough to test and challenge the participants, and provide information to support expected operator and engineer responses. An answer to a participant's question should be an exact summary of why their solution will or will not mitigate the event. If participants are given that type of answer they will' react as if the situation is more realistic and will work on a solution eagerly. This type of attitude is contagious and this willingness to respond will be transferred to the offsila participants. If an individual asks a question and only gets the reply, "no, that won't work" time after time, they get disgruntled and disgusted with the scenario and won't look further since they expect the same answer. This down attitude will affect how communications flow and how interfaces between the different groups occur. Scenario development is important so that no matter how unrealistic the initiating conditions-appear, after the participants are involved for a period of time, they have forgotten the beginning. They then become active participants in providing input and corrective actions to the other participants. It is important to realize that the scenario is not to test the participants knowledge of the plant. The scenario SHOULD test the response organization's knowledge of the Emergency Plan Implementing Proceduras and other plant procedures, and how the people and the procedu.es interface with each other. Periodic exercises are conducted to evaluate major portions of emergency response capabilities. Sub portions of exercises or separate drills such as fire or medical emergencies develop, maintain, and test key skills. An emergency exercise must involve significant effort in research and I development to ensure that the events depicted are as realistic as possibic. Realism is created through the use of the simulator and additional referee j supplied information. The referee supplied information will come in the f z i of supplied data sheets simulating CRT screens, gage / meter / recorder readings, L area conditions, props (simulated injuries), and simulated reports (daily operating report, service information letters, Nuclear Network messages, etc). Information will be supplied to the Emergency Response facilities directly from the simulator via phone lines to a CRT displaying live plant data, lhe CRT display will not be normal plant display but one used for exercises only. I-8
1 Initiating events for an exercise can be human error-or equipment malfunction. rm No one wants to assume that they will make mistakes, especially of the (") magnitude that can cause significant plant damage. Since the possibility does exist for human error, events may be initiated as a result but are not meant 1 as an indication of staff incompetence, i Equipment malfunction is difficult to incorporate into a scenario to the i extent required to cause plant damage and serious offsite environmental problems. The plant design, equipment reliability and redundancy, construction, and installation of systems preclude such events. The SSES Final Safety Analysis Report analyzes the capabilities of plant systems to maintain control over radioactive material in the plant during all types of abnormal conditions. Therefore to cause a serious event for an exercise some unrealistic assumptions must be made. If the conditions listed in the scenario were probable, an unanswered safety question would exist and actions would be taken to remedy the situation. This must be clear so that the general public doesn't believe that the scenario events are probable. O I-9
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5 1 g i h SECTION II OBJECTIVES I l 1 t b o c. f I" , '.(- 9 I I i Le I 11-1 b k P 4 l ' i
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- ATTACHMENT 1 1992 NRC Graded Exercise Series Objectives BACKGROUND The following 'tist of objectives are a compilation from NUREG 0654 and the Federal Emergency Management Agency (FEMA) Guidance Memorandum EX 3 (GM EX 3).
The CORE OBJECTlvES are taken directly from the FEMA Guidance Memorandum EX-3 (GM EX-3) and are presented in three groups, A,B and C. Grote A are " Core Objectives that are Scenario Independent", to be demonstrated each biennial exercise. Group B are " Scenario Dependent", only impact some organizations but scenarios are to be varied to demonstrate appropriate emergency response at least once every six years. Group C are "Other Objectives: To Be Demonstrated At least Once Every six Years", an example, the irgestion pathway related objectives need to be dereenstrated once e,'ery six years. Each " FEMA" Core Objective is correlated to NUREG 0654 planning standards-The NRC measures the emergency preparedness of PP&L using NUREG 0654, therefore the correlation between the FEMA document and the NUREC. The FEMA Objectives are listed numerically 1 '6. Below each objective arc the NUREG planning standards that are related or directly support the FEMA Objectives. The NUREG 0654 requirements denote which group is responsible for ensuring the exercise demonstrates the organizatiuns preparedness and how the objective will be demonstrated. Approved: RbertGQ Approved: - M Charles A.1ye% Approved: , H. Ge69 Stanle O
GROUP At CORE OBJECTIVES - SCENARIO INDEPENDENT
-41a Demonstrate the organization's ability to recognize operational symptoms and '
{}): parameters indicative of legrading plant conditions and relate such symptoms to pres'sibed Emergency Action Levels (EAL). [ FEMA GM EX-3: (1)] j l
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RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS D '.1 An emergency classification NEP _ x_ The core objective and , and emergency action level supporting NUREG will be 4 scheme as set forth in demonstrated by the i Appendix 1 must be established emergency responder:. l by the licensee. The specific proper use of the SSES instruments, parameters, or EAls. The scenario wil' equipment status shall be use the simulator shown for establishing each Control Room indications ; emergency class, in the in- as initiating plant emergency procedures, conditions. The plan shall identify the parameter values and equipment status for each emergency class. D.2 The initiating conditions NEP x The core objective and shall include the example _supporttug NUREG will be conditions found in Appendix-1 demarstrated by the v &nd all postulated accidents emergency responders in the Final Safety Analysis proper use of the SSES Report (FSAR) for the nuclear EALs. The t e,nario will facility, use the simulator Control Room indications as initiating conditions, / . O
-(la)8-CONT'D RESP. NOT g NUREG_0654 __
GRP . DEMO DEMO COMMENTS T l H5 Each licensee shall identify Plant x and establish onsite monitoring systems that are to be used to initiate emergency measures in accordance with Appendix 1, as well as those to be used for conducting assessment. This equipment shall include: ;
- a. geophysical phen ... ens Het Data will be used monitors (e.g., for dose calculations.
meteorological, hydrologic, Simulator will display seismic); weather parameters,
- b. radiological monitors, Applicable radiation (e.g., process, area, readings will indicate emergency, effluent, wound in the simulator Control and portable monitors and Room on meters and CRT sampling equipment); displays.
- c. process monitors. (e.g.,
reactor coolant pressure Applicable h and temperature, instrumentation will containment pressure and read out in the Control temperature, liquid levels, Room, TSC, General flow rates, status or Office, and EOF on CRT lineup of equipment displays, components); and d, fire and combustion product detectors. Not demonstrated. l l t O
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.(la): CONT'D-eQ RESP NOT V NUREG 0654 GRP DEMO DEMO COMMENTS H.6 'Each licensee shall make NEP x Actual demonstration provision to acquire data from using simulated data or for emergency access to from the met towers, offsite monitoring and simulated ILDs, and analysis equipment including: field monitoring teams receiving simulated data
- a. geophysical phenomena from referees.
monitors,(e.g., meteorological, hydrologic, seismic);
- b. rediological monitors including rate meters and sampling devices.
Dosimetry shall be provided and shall meet, as a minimum, the NRC Radiological Assessment Branch Technical Position for the Environmental. Radiological Monitoring Program; and
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- c. laboratory facilities, fixed or mobile.
I.2 Onsite capability and Plant x _ The simulator Control resources to provide-initial Room accident values and continuing instruments will assessment throughout the indicate for accident course of an accident = shall assessment by responding include post-accident sampling to transients induced capability, radiation and for the exercise. effluent monitors, in-plant iodine instrumentation, and- The PASS located in the
- containment radiation Training Center will be monitoring in accordance with used for sampling.
I NUREG 0578, as elaborated in i the NRC letter to all power reactor licensees dated l' October 30, 1979.
(la): CONT'O NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS O1 !3 Each licensee shall establish Rad & x methods and techniques to be Env used for determining: a, the source term of releases The containment rad of radioactive material monitors will indicate within plant systems. An proper correlation to example is the relationship the radioactive material between the containment released. The values radiation monitor (s) used for the rad reading (s) and radioactive monitors are derived by material available for using a computer ) release from containment. program.
- b. the magnitude of the Data indicating the release of radioactive radiological conditions materials based on plant will be available in the system parameters and Control Room, TSC, E0F, effluent monitors. & OSC.
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(1b): D:monstrate ths organization's ability to properly classify emergency conditions, make initial notifications, and follow up notifications. [FEHA-GM EX-3: (1)] RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS D.1 This NUREG is the same as that used to support Core Objective 1A. D.2 This NUREG is the same as that used to support Core Objective IA. E.2 Each organization shall NEP x Actual demonstration for establish procedures for exercise participants by alerting, notifying, and use of pager system and mobilizing emergency response telephones. personnel. E.3 The licensee in conjunction NEP x Actual demonstration by with State and local Operations disseminating organizations shall establish initial communications the contents of the initial to state and local ('T emergency messages to be sent organizations, m,/ from the plant. 1hese measures shall contain information about the class of emergency, whether a re', ease is taking place, potentially affected population and areas, and whether protective measures may be necessary.
(Ib)8 CONT'D RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E.4 Each licensee shall make NEP x Actual demonstration by provisions for follow up Control Room, TSC, messages from the facility to General Office, and EOF. offsite authorities which shall contain the following information if it is known and appropriate:
- a. location of incident and name and telephone number (or communications channel identification) of caller;
- b. date/ time of incident;
- c. class of emergency;
- d. type of actual or projected release (airborne, waterborne, surface spill),
and estimated duration / impact times;
- e. estimate of quantity of radioactive material released or being released and the points and height of releases;
- f. chemical and- physical form of released material, including estimates of the relative quantities and concentration of noble gases, iodines, and particulates,
- g. meteorological conditions at appropriate levels (w%d speed, direction (to and from), indicator of stability, precipitation, if-anyJ; *
- h. actual or projected dose rates at site boundary; projected integrated dose at site boundary;
- i. projected dose rates and
(2): Demonstrate ability to fully alert, mobilize and activate personnel for both facility and field based emergency functions. [ FEMA-GM-EX-3: (2)] RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E.1 Each organization shall NEP ._X_ Actual demonstration by establish procedures which response organization at describe mutually agreeable each level of emergency. bases for notification of l response organizations consistent with the emergency classification and action level scheme set forth in Appendix 1. These procedures shall include means for verification of messages. The specific details of verification need not be included in the plan. E.2 This NUREG is the same as that used to support Core Objective Ib. Each organization shall All x __ All facilities will (~)$4 q provide for timely activation activate except M0C. and staffing of the facilities activation will be and centers described in the 'ated for the plan. F ce Exercises. The Put Information group will work out of the Susquehanna Energy Information Center and then move to the Berwick YMCA for the Graded Exercise only. l l L)
r (1b): CONT'D NUREG 0654 RESP GRP NOT DEMO DEM0 COMMENTS g-integrated dose at the projected peak and at 2, 5, and 10 miles,. including sector (s) affected;
- j. estimate of any surface radioactive contamination inplant, onsite or offsite; l
- k. licensee c.mergency response actions underway;
- 1. recommended emergency actions, including protective measures;
- m. request for any needed onsite support by offsite organizations; and
- n. prognosis for worsening or termination of event based &
on plant information. W O
(3a): Demonstrato the ability to direct, coordinate, and control emergency activities. [ FEMA GH EX 3: (3)) RESP NOT NUREG 0654 GRP DEMO DEH0 __ COMMENTS A.I.d Each organization shall NEP x Actual demonstration as identity . spacific individual each urganization is by title .00 shall be in activated. c'arge or the emergency
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(3b): Demonstrato the adequacy of the SSES Emergency Plan Implementing Procedures applicable to the scenario. [ FEMA GM EX 3: (3)] RESP NOT NUREG 06S4 GRP DEMO DEMG COMMENTS A.I.d This NUREG is the same as that used to suppe t Core Objective 3A. O 4 0
l l (4): Demonstrate ability to communicate with all appropriate locations, organizations. l and field personnel including 24 hour per day manning of communication links. l (FEMA GH EX-3: (4)] O RESP NOT i NUREG 0654 GRP DEMO DEMO COMMENTS A.I.e Each organization shall All x Demonstration of 24 hour provide for 24 hour per day coverage by filling out emergency response, including a shift manning roster. 24 hour per day manning of communications links. F.1 The comunication plans for NEP 4._ Backup comunications emergencies shall include paths will only be organizational titles and tested if the primary alternates for both ends of sys'.em actually fails the communication links. Each during the drill, organization shall establish Backup communications, reliable primary and back up i.e., radio, to be used means of communication for by TSC for notification licensees, local, and State of offsite agencies. t response organizations. Such systems should be selected to be compatible with one another. Each plan shall include: t a. provision for 24 hour per day notification to and activation of the State / local emergency response network; and at a
;inimum, a telephone link and alternate, including 24 hour per day manning of communica+. tons links that initiate emergency response actions,
- b. provision for continuous comunications with State / local governments within the Emergency Planning Zones;
- c. provision for communications as needed with Federal emergency -
response organizations;
- d. provision for comunications between the p)s nuclear facility and the licensee's near-site
-Emergency Operations Facility, State and local l
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(4): CONT'O RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS emergency operations centers, and radiological monitoring teams;
- e. provision for alerting or activating emergency personne' in each response organization; and
- f. provision for connunication by the licensee with NRC headquarters and NRC Regional Office Emergency Operations Centers and the licensee's near-site Emergency Operations Facility and radiological monitoring team assembly area.
F.2 Each organization shall ensure All x A medical emergency will that a coordinated not be included in the communication link for fixed scenario, and mobile medical support facilities exists. t 9
(5): Demonstrate the adequacy of facilities and displa;*s to support emergency operations. , (FEMA GM EX 3: (5)) RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS C.1 The Federal government NEP x Not demonstrated; no maintains in depth capability simulated or actual to assist licensees, States federal assistance. and local governments through the Federal Radiological Monitoring and Assessment Plan (formerly Radiological Assistance Plan (RAP) and Interagency Radiological Assistance Plan (IRAP)). Each State and licensee shall make provisions for incorporating the Federal response capability into its operation plan, including the following:
- a. specific persons by title authorized to request Federal assistance; see A.1.d. A.2.a.
- b. specific Federal resources p)
( expected, including expected times of arrival at specific nuclear facility sites; and
- c. specific licensee, State and local resources available to support the Federal response, e.g., air ,
fields, command posts, telephone lines, radio frequencies and telecomunications centers. C.2.a Each principal offsite NEP x Will be partially organization may diapatch demonstrated by representatives to the representatives from licensee's near-site Emergency Harrisburg coming to the Operations Facility. (State EOF. i technical analysis - representatives at the nearsite EOF are preferred.) O
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- . _ ,. gg[G 0654 GRP DEMO DEMO COMMENTS c.r.u The licensee shall prepare for NEP x Will be demonstr&ted; an the dispatch of a individual will be representative to principal dispatched to offsite offsite governmental emergency facilities.
operations centers. G.3.b Each licensee shall provide Spec 1 _ _ . . x Not demonstrated. space which may be used for a Office limited number of news media at the nearsite Emergency Operations Facility. H.1 Each licensee shall establish Plant x To be demonstrated when a Technical Support Center and the control room an onsite operations support classifies the emergency center (assembly area) in as an ALERT or when accordance with NUREG 0696, deemed necesary by the Revision 1. ED. H.2 Each licensee shall establish NEP _E_ Actual demonstration. an Emergency Operations The EOF will be fully Facility from which evaluation activated, and coordination of all licensee activities related to an emergency is to be carried out and from which the licensee shall provide information to Federal, State and local authorit.as responding to radiological emergencies in accordance with NUREG 0696, Revision 1. O
(5): CONT'D RESP N01 (G) NUREG 0654 GRP DEMO DEMO COMMENTS H.9 Each licensee shall provide Plant x The OSC will be for an onsite operations activated and required support center (assembly area) emergency equipment will which shall have adequate be used. capacity, and supplies, including, for example, respiratory protection, protective clothing, portable lighting, portable radiation monitoring equipment, cameras and comunications equipment for personnel present in the assembly area. 1.7 Each organization shall Rad & _t field monitoring describe the capability and Env personnel will be resources for field monitoring dispatched from the within the plume exposure plant and the EOF. Emergency Planning Zone which are an intrinsic part of the concept of operations for the O facility. O
(6)8 Demonstrate the ability to continuously monitor and control emergency worker exposure. (FEMA GM EX 3: (6)) RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS i K.3.a Each organization shall make Plant x Dosimetr/ will be used provision for 24 hour per day as determined by the capability to determine the scenario conditions. doses received by emergency personnel involved in any nuclear accident, including volunteers. Each organization shall make provisions for distribution of dosimetcrs, both self-reading and permanent record devices. K.3.b Each organization shall ensure Plant x Dostmetry will be used that dosin;eters are read at as required by scenario appropriate frequencies and conditions and results provide for maintaining dose provided to participants records for emergency workers will be recorded. Any involved in any nuclear readings frnm TL0s will ^ accident, be simulated. O i
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(7a): Demonstrate ability to mobilire and deploy field monitoring teams in a tim 21y fashion. [ FEMA GH EX 3: (7)) RESP NOT NUREG 0654 GRP DEMO DEM0 COMMENTS E.2 This NUREG is the same as that used to support Core Objective Ib. 1.8 Each organization, where Rad & x Actual demonstration for appropriate, shall provide Env airborne release from methods, equipment and the site. expertise to make rapid assessments of the actual or potential magnitude and locations of any radiological hazards through liquid or gaseous release pathways. This shall include activation, notification means, field team composition, transportation, communication, monitoring equipment and estimated deployment times. 9 f% i . . . . n
(7b): Demonstrate appropriate equipment and procedures for determining ambient radiction levels. [ FEMA GM EX-3: (7)) NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS h H.12 Each organization shall Rad & _1_ Actual demonstration by establish a central pnint Env collection of field (preferably associated with samples and return to the licensee's near site the EOF. Emergency Operations facility), for the receipt and analysis of all field hionitoring data and coordination of sample media. 1.8 This NVREG is the same as that used to support Core Objective 7a. O O
(7c): Demonstrate appropriate equipment and procedures for collection, transport, and analysis of samples of sell, vegetation, water, and milk, (FEMA GM EX 3: (7)] O NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS 1.9 This NUREG is the same as that used to support Core Objective 7a. / \ / V
(8)8 Demonstrateappropriateequipmentandprpceduresformeasurementofairborne radioiodine concentrations as low as 10' pCi/cc in the presence of noble gases. [ FEMA GM EX-3: (8)) RESP NOT NVREG 0654 GRP DEMO DEMO COMMENTS 1.7 This NVREG is the same as that used to support Core Objective 5. l.8 This NVREG is the same as that used to support Core Objective 7a. I.9 Each organization shall have a Rad i x Actui demonstration capability to detect and Env using data supplied to measure radioiodine participants after concentrations in air in the demonstrating proper plupeexposureEPZaslowas sample technique. 10' pCi/cc (microcuries per cubic centimeter) under field conditions. Interference from the presence of noble gas and background radiation shall not decrease the stated minimum detectable activity. O
(9): Demonstrate the ability to obtain samples of particulate activity in the airborne plume and promptly perform laboratory analysis. [FEHA GM EX-3: (9)) RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS 1.7 This NUREG is the same as that used to support Core Objective 5. 1.8 This NUREG is the same as that used to support Core Objective 7b. 1.10 Each organization shall Rad & _1_ ___ Dose rates, dose establish means for relating Env projections, and the various measured integrated doses will be parameters (e.g., calculated based on data contamination levels, water indicated on and air activity levels) to instrumentation and dose rates for key isotopes provided from field (i.e., those given in Table 3, teams, page 18) and gross radioactivity measurements. Provisions shall be made for (' estimating integrated dose from the projected and actual dose rates and for comparing these estimates with the protective action guides. The detailed provisions shall be described in separate procedures.
(10a): Demonstrate the ebility, within the plume exposure pathway, to project dosage to the public via plume exposure, based on plafat and field data. [FEHA CM EX 3: (10)) RESP NOT e NUREG 0654 GRP DEMO DEMO COMMENTS 1.4 Each licensee shall establish Rad & x Actual demonstration the relationship between Env using the STREAM system. effluent monitor readings and onsite and offsite exposures and contamination for various meteorological conditions. 1.10 This NUREG is the same as that used to support Core Objective 9. O O
l (106): Demonstrate the methodology for determining the release rate / projected doses if the instrumentation used for assessment is offscale or inoperable. (NUREG ONLY) g U RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS 1.6 Each licensee shall establish Rad & x Partial demonstration. the methodology for Env A portion of the release determining the release from the plant will be rate / projected doses if the unmonitored and instrumentation used for untreated but will need assessment are offscale or to be accounted for. inoperable. l J O
(11): Demonstrate the ability to make appropriate protective action decisions, (recommendations for licensee) based on projected or actual dosage, EPA PAGs, availability of adequate shelter, evacuation time estimates, and other relevant factors. (FEMA GM EX 3: (11)) RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E.7 Each organization shall NEP & .JL, Actual demonstration, provide written messages Speci scenario will require a intended for the public, Office protective action consistent with the licensee's recommendation to be classification scheme. In made, particular, draft messages to the public giving instructions with regard to specific protective actions to be taken by occupants of affected areas shall be prepared and included as part of the State and local plans. Such messages should include the appropriate aspects of sheltering, ad hoc respiratory protection, e.g., handkerchief wer rnouth, thyroid blocking or evacuation. The role of the licensee is to provide supporting information for the g-messages. For ad hoc respiratory protection see
" Respiratory Protective Devices Manual" American Industrial Hygiene Association, 1963 pp. 123-126.
J.10.m The bases for the choice of All .JL Actual demonstration. recommended protective actions from the plume exposure pathway during emergency conditions. This shall include expected local protection afforded 3 in residential units or other shelter for direct and inhalation exposure, as well as evacuation time ' estimates. O
i (12): Demonstrate the ability to initially alert the public within the 10 mile EPZ and begin dissemination of an instructional message within 15 minutes of a deci ion by ! appropriate State and/or local official (s). [ FEMA CH EX 3: (12))- RESP NOT NVREG 0654 GRP OEMO DEMO COMMENTS t E.6 Each orgnization shall All x Protective action j establish administrative and recommendations will physical means, and the time result in discussions required for notifying and with simulated state i providing prompt instructions representatives to the public within the plume initiating public Emergency information messages. Planning Zone.-exposure pathway (See Appendix 3.) It shall be the licensee's responsibility to demonstrate that such means exist, regardless of who ; implements this requirement. ' It shall be the responsibility of the State and local governments to activate such a , system. O [ O
(13): Demonstrate the ability to coordinate the formulation and dissemination of accurate information and instructions to the public in a timely fashion after the initial alert and notification has occurred. (FEMA-GMEX3: (13)) O RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS E.3 This NUREG is the same as that used to support Core Objective Ib. i l E.4 This NUREG is the same as that used to support Core Objective l Ib. ! 1 E.5 State and local government NOT A LICENSEE organizations shall establish RESPONSIBILITY a system for disseminating to the public appropriate information contained in initial and followup messages received froi.1 the licensee including the appropriate notification to appropriate broadcast media, e.g., the Emergency Broadcast System (EBS). G.4.a Each principal organization Speci x Actual demonstration shall designate a spokesperson Office using actors and mock who should have access to all phone calls as necessary necessary information, to initiate public information actions, b Each organization shall establish arrangements for timely exchange of information among designated spokespersons, c Each organization shall establish coordinated arrangements for dealing with rumors. 1 0
-. .. _-__ ..._ _ - _ ..=._.._ _ _ ..~.. _ _ - . _ _ . _ _ _ _ _ . _ _ . . _ _ _
- r, 4
(14): Demonstr2te the ability to brief the media in an accurate, coordinated, and timely manner. [ FEMA.r,M.EX 3: (14)) RESP- NOT
- NUREG 0654 GRP DEMO DEMO - COMMENTS G.3.a Each principal organization Speci x The activation of the shall designate the points of Office MOC at the YMCA in contact and physical locations Berwick will be for use by news media during demonstrated for the an emergency. Graded Exercise. The Information Center will l be used for the Practice J Exercises.
-G.3.b This NUREG is the same as that used to~ support Core Objective '
5. G.4.a This NUREG is the same as the used to support Core Objective
- 13.
G.4.d This it'JREG is the same as that used to support Core Objective O 13. i t O e-- - w.~,w, ar*.-*,---. *,--%-w + e-. m=# ..- ---..-e + =,s u we n te v.e ,.v ., ,-.m.3 ..',.-,.www_,v- e r-gg,r.,.m. me -r--e.e.. v- c.- r- t -w rw-- i h , w- ys.,4gI
(15)s Demonstrate the ability to estabitsh and operate rumor control in a coordinated and timely fashioli.
- FEMA GM.EX.3: (15))
RESP NOT NUREG 0654 .. GRP DEMO DEMO COMMEN15 G.4.c Each organization shall Speci x __ Actual demonstration; establish coon]InatEd Office phone calls will be made arrangements for desling with by various people asking , rumors. questions. 4 9 9 9 9 O I
GROUP B: SCENARIO DEPENDENT (163): Demonstrate the abil'ty to make the decision, based on predetermined criteria, whether to is;ue K1 to emergency workers. (FEMA GH-EX-3: (16)) RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J,10.f NOT A LICENSEE RESPONSIBillTY. O O
1 (16b): Demonstrate the ability to supply and administor KI, once the decision has been made to do so. [ FEMA GM EX 3: (16)) RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS I J.10.e NOT A LICENSEE RESPONSIBILITY. O 5 0
l l l (17): Demonstrate the ability to make the decision, if the State plan so specifies, to ! recomend the use of K! for the general public, based on predetermined criteria, ; as well as to distribute and adainister it once the decision is made, if , necessitated by radioiodine release. [ FEMA GM EX-3: (17)] ' RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.10./ NOT A LICENSEE RESPONSIBILITY. O I l { l r
(18a): Demonstrate ability to project dosage to the public via plume exposure, based on plant and field data, and to determine appropriate protective measures, based on PAGs, available shelter, evacuation time estimates, and all other appropriate factors. [ FEMA-GH EX-3: (18)) g l RESP NOT l NUREG 0654 GRP DEMO DEMO COMMENTS I E.7 This NUREG is the same as that used to support Core Objective i 11. 1.10 This NUREG is the same as that used to support Core Objective 9. J.10.m The NUREG is the same as that used to support Core Objective 11. O O
(18b): D:monstrate the organizational ability and resources n:cessary to manage an orderly evacuation of all or part of the plume EPZ. [ FEMA-GM EX-3: (18))
-- RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.2 Each licensee shall make NEP & x Site evacuation will be provisions for evacuation Sec simulated.
routes and transportation for onsite individuals to some suitable offsite location, including alternatives for inclement weather, high traffic density, and specific radiological conditions. _m (. O
(18c): D:monstrate the organizational abilit, and resources necessary to effect an order'y evacuation of mobility impaired individuals within the plume EPZ, (FEMA GM EX 3: (18)] RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.10.d NOT A LICENSEE RESPONSIBILITY. O O
(19): Demonstrate the abil'.ty and resources necessary to implement appropriate protective actions 19r school children within the plume EPl. [ FEMA GH E' 3: (19)) RESP NOT NUREG 06S4 GRP DEMO DEH0 COMMENTS J.9 NOT A LICENSEE RESPONSIBILITY J.10.g NOT A LICENSEE RESPONSIBILITY. h
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i l (20a): Demonstrate the organizational ability and re,.~ces necessary to control evacuation traffic flow and to control access to evacuated and sheltered areas. 1 (FEMAGMEX3: (2,0)) RESP NOT O-NUREG 0654 GRP DEMO D" ' COMMENTS J.10.k NOT A LICENSEE RESPONSIBILITY O \ O j
(20b): Demonstrate the organizational ability and resources necessary to control access to the evacuated area. [ FEMA-GM EX-3: (20)) h NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS J.10.j NOT A LICENSEE RESPONSIBillTY
(21)g Demonstrate the adequacy of procedures, facilities, equipment and personnel for registration and radiological monitoring of evacuras. [ FEMA-GM EX-3: (21)) RESP NOT NUREG 06S4 GRP DEMO DEMO COMMENTS J.12 NOT A LICENS'E t RESPONSIBILITY O O
(22): Demonstrate the adequacy of facilities for mass care of evacuees. (FEMA GM EX-3: (22)]
<-~ 'O - RESP NOT NUREG 0654 GRP DEH0' OEMO COMMENTS J.10.h NOT A LICENSEE RESPONSIBILITY O
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(23): Demonstrate adequacy of ambulance facilities and reocedures for handling contaminated individuals. (FEMA-GM-EX-3: (23)) RESP NOT NUREG 0654 GRP DEM0 DEMO COMMENTS L.4 NOT A LICENSEE RESPONSIBILITY O O
(24): Demonstrate adequacy of hospital facilities and procedures for handling contaminated individuals. [ FEMA-GM EX-3: (24)) RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS L.1 NOT A LICENSEE RESPONSIBILITY
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(25): Demonstrate adequate equipment and procedures for decontamination of emergency workers, equipment, and vehicles and for waste disposal. [ FEMA-GM EX-3: (25)] RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS K.S.a Each organization, as HP & x Contamination limits appropriate, shall specify Rad & will be excceded and action levels for determining Env appropriate action will the need for decontamination. be required. K.5.b Each organization, as HP & x Scenario does not appropriate, shall establish Rad & include a medical the means for radiological Env emergency. decontamination of emergency personnel wound, supplies, No equipment will be instrLments and equipment, and deconned, for waste disposal. - K.7 Each licensee shall provide HP & x Not demonstrated. the capability for Rad & decontaminating relocated Env onsite personnel, including provisions for extra clothing and decontaminants suitable for the type of contamination expected, witn particular attention given to radiciodine contamination of the skin. O
GROUP C: OTHER OBJECTIVES TO BE DEMONSTRATED AT LEAST ONCE EVERY SIX YEARS 6): Demonstrate ability to identify need for, request, and obtain Federal ( ( - assistance. (FEMA GM-EX-3: (26)] RESP NOT NUREG 0654- GRP DEMO DEMO COMMENTS C.1 The Federal government NEP x Not demonstrated; no maintains in-depth capability simulated or actual to assist licensees, States federal assistance. and local governments through the Federal Radiological Monitoring and Assessment Plan (formerly Radiological Assistance Plan (RAP) and Intertgency Radiological Assistance Plan (IRAP)]. Each State and licensee shall make provisions for incorporating the Federal response capability into its operation plan, Sncluding the following:
- a. spe:ific persons by title authorized to request Federal assistance; see A.1.d, A.2.a.
b, specific Federal resources expected, including expected times of arrival at specific nuclear facility sites; O
(27): Demonstrate appropriate equipment and procedures for collection, transport, and analysis of soil, vegetation, snow, water, and milk. (FEMA GM-EX 3: (27)) O RESP NOT NUREG 0654 GRP DEMO DEM0 COMMENTS I.8 This NUREG is the same as that used to support Core Objective 7b. O t O
(28): Demonstrate the appropriate lab operations and procedures for measuring and analyzing samples of vegetation, food crops, milk, meat, poultry, water,and animal feeds (indigenous to the area and stored). [ FEMA-GM EX-3: (28)] O %) RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS C.3 Each organization shall Rad & x Not demonstrated. identify radiological Env laboratories and their general capabilities and expected availability to provide radiological monitoring and analyses services which can be used in an emergency. O O
(29): Deconstrate the ability to project dosage to the public via ingestion pathway exposure based on field data, and to determine appropriate protective measures, based on PAGs and other relevant factors. [ FEMA-GM-EX-3: (29)] g RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS 1.20 1his NUREG is the same as that used to support Core Objective 9. O l O l l l
(30): Demonstrate ability to implement protective actions for ingestion pathway hazards, [ FEMA GM-EX-3: (30)) RESP N01 NUREG 0654 GRP DEMO DEM0 COMMENTS J,11 NOT A LICENSEE RESPONSIBILITY. ,~ Q,) L)
(31): : Demonstrate ability to estimate total population exposure. (FEMA-GM-EX-3: (31)] RESP NOT NUREG 0654 GRP DEM0 DEM0 COMMENTS M.4 Each plan shall establish a Rad & x Not demonstrated, method for periodically Env estimating total population e.,po s ure . O i i t l 9
.(32): D:monstrate.the ability.to. determine appropriate measures for' controlled
; reentry and: recovery based on-estimated total population exposure, available
-EPA PAGs,1and other relevant factort. [ FEMA-GM-EX-3: (32)]
-y-RESP NOT-
. NUREG 0654- GRP DEMO DEMO COMMENTS
- M.1: 1Each organization,Las Rad & x Not demonstrated.
appropriate, shall develop Env general plans _-and procedures-for reentry and recovery and describe the.means by which decisions to relax protective
.measuresL(e.g., allow: reentry into anfevacuated area) are reached. This process-should consider both existing'and potential conditions.
O 10
(33): Demonstrate ability to implement appropriate measures for controlled recovery and reentry. [ FEMA-GM EX-3: (33)) RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS M.1 This NUREG is the same as that used to support Core Objective 32. O 9
v4-(34)- Demonstrate ability _to fully' staff facilitios and maintain-staffing around the clock._L(FEMA GM-EX-3: (34)]- RESD NOT NUREG 0654 GRP DEMO DEMO COMMENTS A.I.e This NUREG is.the same as that - Lused to support Core Objective
'4.
A.2.a Each organization shall NOT A-LICENSEE specify the functions and RESPONSIBILITY. responsibilities-for major elements and key individuals-by title,-of emergency response.-including the-following: Command and Control, Alerting and-Notification,-Communications, Public Information, Accident Assessment, Piiblic- Health and Sanitationc Social Services, Fire and Rescue,. Traffic Control, Emergency Medical Services, Law Enforcement, -
-Transportation, Protective Response (including authority n~ U to request Federal assistance
_and to initiate'other protective actions), and
-Radiological- Exposure Control.
The description of.these functions shall include a clear and concise summary such as a table of primary and support responsibilities using the agency as_oneiaxis,_and
;the function as the other.-
(SeeSectionB;forlicensee.) lA.4 ~ Each principal organization All' x Actual demonstration by shall be capable of continuous filling out shift
.(24-hour) operations for a rosters.
protracted period. The individual in_the principal organization who will be responsible for. assuring - continuity of resources
-(technicai, administrative, and material) shall be specified by title.
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(34): CONT'D RESP NOT NUREG 0654 GRP DEM0 DEMO COMMENTS E.1 Ihis NUREG is the same as that used to support Core Objective 2. E.2 This NUREG is the same as that used to support Core Objective Ib. F.1 This NUREG is the same as that used to support Core Objective 2. H.4 This NUREG is the same as that used to support Core Objective 2. O O
(35a)- .Each licensee shall. establish the means and. time. required to' warn or' advise
'onsite individuals and individuals who may be.in areas controlled by the operator, including:
O V 1. Employees not having emergency assignments.- 1 2.- Visitors.
- 3. Contractor and construction personnel.
,. 4. Other persons who may be in the public access areas on or passing through the site or within the owner controller area. [ FEMA-GM-EX-3: (35))
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RESP NOT-4 NUREG 0654 GRP- DEMO DEMO COMMENTS J.1 Each licensee shall establish- Ops & _x__ - Actual demonstration the means and time required to Sec initiated by events in
-warn or:advi m onsite' the scenario, individuals and individuals-who may be in areas controlled-
-by the operator,-including:
a .- Employees not having emergency assignments;
- b.--Visitors;
-A: c. Contractor and construction
-V personnel; and'
- d. Other. persons,who may be in the public access areas on or passing through the site or withincthe' owner controlled area. ,
a 0 l
(35b): Each licensee shall make provisions for evacuation routes and transporhtion for onsite individuals to some suitable offsite location, including alternatives for inclement weather, high traffic damity and specific radiological conditions. [ FEMA GM-EX-E: (35)) g RESP NOT NUREG 0654 GRP DEMO DE.J COMMENIS J.2 This NUREG is the same as that used to support Core Objective 18b. O O
(35c):' Each licensee shall provide for radiological monitoring of people evacuated from the site. [ FEMA-GM-EX-3: (35)) ('~) - NUREG 0654 RESP GRP NOT DEMO DEMO COMMENTS _ J3 Each licensee shall provide HP x Not demonstrated. for radiological monitoring of people evacuated from the site. . l l l l
(35d): Denionstrate the ability to effect an orderly evacuation of onsite personnel. [ FEMA-GM-EX-3: (35)) RESP NOT NUREG 0654 GRP DEM0__ DEMO COMENTS J.4 Each licensee shall provide Plant x Net demonstrated. for the evacuation of onsite & Sec non-essential personnel in the , event of a Site or General Emergency and shall provide a decontamination capability at or near the monitoring point specified in J.3. O O ,
1 (35e): Each licensee shall provide for a capability to account for all individuals onsite at the time of the emergency and ascertain the names of missing individuals within 30 minutes of the start of an /^\ emergency and account for all onsite individuals continuously () thereafter. [ FEMA GM-EX-3: (35)] RESP NOT NUREG 0654 GPP DEM0 DEM0 C0ft'iENTS J.5 Each licensee shall provide Plant _1., Actual demonstration. for a capability to account & Sec for all tr"ividuals onsite at the time of the emergency and ascertain the names of missing individuals within 30 minutes of the start of an emergency and account for all onsite individuals continuously thereafter. ,o L.) 1 L)
(35f): Each licensee shall, for individuals remaining or arriving onsite during the emergency, make provisions for:
- 1. Individual respiratory protection g
- 2. Use of protective clothing
- 3. Use of radioprotective drugs (e.g. individual thyroid protection)
(FEMA-GM-EX-3: (35)] RESP NOT NUREG 0654 GRP DEMO DEMO COMMENTS J.6 Each licenseo shall, for HP x _ Actual demonstration for individuals remaining or first individual arriving cnsite during the entering an airborne emergency, make provisions area. for:
- a. Individual respiratory protection;
- b. Use of protective clothing; and
- c. Use of radioprotective drugs,(e.g., individual &
thyroid protection). W t O
(36): Demonstrate the ability to carry out emergency response functions (i.e., activate E0Cs, mobilize staff that report to the E0Cs, establish communications linkages, and complete telephone call down) during an () unannounced off-hours drill or exercise. [ FEMA-CH EX-3: (36)) Q RESP NOT NUREG 0654 GRP DEMO DEM0 COMMENTS N.I.b An exercise shall include Plant x Not demonstrated. mobilization of State and & All local personnel and resources adequate to verify the capability to respond to an accident scenario requiring response. Th, organization shall provide-for a critique of the annual exercise by Federai and State observers / evaluators. The scenario should be varied from year to year such that all major elements of the plans and preparedness organizations are tested within a five-year period. Each organization should make provisions to start an exercise between 6:00 f'"g p.m. and midnight, and~another x_) between midnight and 6:00 a.m. once every six years. Exercises should be conducted under various weather conditions. Some exercises should be unannounced. 9 /~'T . V
GENERAL OBJECTIVES RESP NUREG-0654 GR0'JP COMMENTS N.4 Official observers from NEP Individual debriefs will be Federal, State, or local conducted in conjunction with governments will observe, facility and overall
-evaluate, and critique the critiques, required exercises. A critique shall se scheduled at the conclusion of the exercise to evaluete the ability of organizations to respond as ca? led for in the plan. The critique shall be conducted as soon as practicable after the exercise, and a formal evaluation should result from the critique.
N.5 Each organization shall NEP A formal critique will be establish means for evaluating written with all areas needing observer and participant improvement noted and assigned comments on areas needing to a specific group or improvement, in:luding individual for closeout. emergency plan procedural changes, and for assigning responsibility for implementing corrective actions. Each organization shall establish management control used to ensure that corrective actions are-implemented. O
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I i 1 i i i SECTION Ill , i. GUIDELINES FOR CONDUCT OF EMERGENCY EXERCISE s I .s s I e i 4 h i e i 111-1 1 P l l }. I s. n -o- --v.ww-nw--,-- . .,a e,, ., w- - ,- . - - - . . , -v<rw-ww-r--r- m>~-rm- pr---- ,,-n e ,,m-- .m---
CONDUCT OF EMERGENCY EXERCISES (NUREG 0654 N.3) 'The following guidelines are provided to all players, referees, and observers to describe how exercises and drills are to be carried out to allow free play for decision making and to meet the stated objectives. (NUREG 0654 N.3) SSES EXERCISE MANUAL The exercise will be carried out using the information contained in the SSES EXERCISE MANUAL. This document is safeguarded to insure exercise participants do not have access to it's contents. Distribution is limited to exercise referees and various offsite reviewers such as NRC and FEMA personnel. The exercise manual contains administrative material such as objectives, guidelines for conduct of the exercise, etc. and scenario support material. The scenario support material includes: SCENARIO TIMELINE - Section V EVENT DESCRIPTIONS AND SUPPORT MATERIAL - Section VI PLANf PARAMETER DATA - Section V INITIALS CONDITIONS (DAILY REPORT OF OPERATIONS) - Section VI PLANT RADIOLOGICAL DATA - Section VII ONSITE RADIOLOGICAL DATA - Section Vil 0FFSITE RADIOLOGICAL DATA - Section Vil METEOROLOGICAL DATA Section Vil REFEREE MESSAGES - Section Vill QUESTIONS - Section IX SIMULATOR DATA - Section X How this material is transmitted to the participants is described in the following sections. EXERCISE REFEREES Individuals that have experience in emergency response are selected to be referees. The referees are responsible for exercise initiation per the scenario timeline and evaluation of the area / position assigned. Each emergency response facility has a lead referee who designated by a red T-shirt. Reporting to the lead referee are additional referees assigned to initiate and monitor / evaluate individual and group performance. These referees are identified by yellow T-shirts. A chief referee is assigned the responsibility of coordinating the entire exercise and the lead facility referees report to this individual. Referees should prepare for the training session by reviewing the following sections in the exercise manual. Section V - Part A - Summary Part B - Detailed Timeline Part C - Event Description 111-2
1 Section VIII - Referee Message Sheets hp These message sheets should be read in conjunction with the Detailed Timeline. The referees will transmit information contained in the exercise manual to the participants per the timeline in a manner designated by pre-exercise briefings. For more information concerning referee functions and conduct see the tab labeled Section 4.0 (REFEREE DATA) in the exercise manual. INITIAL CONDITIONS (DAILY REPORT OF OPERATIONS) The day of the exercise i simulated DAILY REPOR1 0F OPERATIONS will be sent to all the key participants Oy the Chief Referee. The DAILY REPORT OF OPERATIONS is a document used during normal operation to provide general information company wide. The information included in tb report is general information that gives status of both units and radwaste. For exercise purposes this simulated report will set up the initial conditions of the station. The report will have pertinent and nonpertinent information to 5.t up the scenario. The exercise participants will not know which information is or is not directly related to the exercise. EXERCISE INITIATION The day of the exercise all the referees will take up their positions for L initiation and monitoring of the exercise. The exercise initiating events will be controlled by the lead controllers. The initiating events will be in the form of supplied data or props as designated by the exercise manual. Example of supplied data: A Health Physics Tech is determining area radiation and the readings that he is seeing on the instrument are supplied by the accompanying referee. OR A phone call is made to the Control Room infc ming them of an injury in the plant. Example of props: An Operator in the plant investigating an alarm received by the control room finds a photograph of the equipment he is investigating. The photograph depicts the drill conditions. OR A maintenance man is provided a mock up in the plant to simulate the actual I v III-3 l 1
o equipruent. mock up is used to demonstrate trouble sho6 ting technique and damage control repairs. HOW TO REPORT INFORMATION TO PARTICIPAP The exercise timeline (Section V) and referee message sheets (Section VIII) will provide the necessary information for the referees so they will be able to report information to '.he participants. The transfer of information is only what the participant would be able to determine in their particular situation. The referees are briefed by the message sheets as to what information is appropriate. An example would be an operator in the plant looking at a local panel with a referee. The operator would not be given any inforeation unless he asked what the indications on the panel were. In another instance where an individual was going into an area affected by fire, the referee would volunteer sensory information such as what smell war in the air, temperature Of the room, any smoke that would be seen. The information given to the participants is indicated on the referee message sheets. Yhe timeline (Section V) indicates referee / participant interface by showing the time and the words REFEREE MESSAGE. The words, REFEREE MESSAGE, indicate that if the participant performs the right actions or asks the proper questions, information is available and will be provided. The far rignt column indicates the number of the information sheet which provides the information. When (Appx) is listed after the time the initiating event is an expected action of the participant and there is normally no information sheet associated. As the initiating events are provided to the plant staff, they w.il determine the nature of the emergency and implement the appriapriate emergency response procedures. These actions will occur through a free-play response. If actions by the participants are other than anticipated and the exercise continuity is jeopardized the lead or chief referee must step in as appropriate and provide the required guidance to keep the scenario on the timeline. This may be done with a prompt called a contingency message and so noted for the critique. Certain inconsistencies (such as technical reason for the simulated release, etc.) may be intentional and required to provide an exercise basis which tests the plant and corporate response capabilities to the maximum extent in a limited time frame. If an inconsistency is known or determined to be intentional, then the emergency response personnel will note the inconsistency and ignore it. The lead referees have the authority to resolve or explain these problems that occur during the exercise in a manner that maintains the integrity of the exercise. The internal operations of the emergency response facilities will be identical , to their intended operation in a real emergency. 1 Ill-4
. SlHULATING EMERGENCY ACTIONS Exercises are intended to demonstrate actual capabilities as realistically as possible, participants should act as they would during a real emergency.
Whertver possible, actions should be carried out. When it is not feasible to perform an action it should be simulated. ANY QUESTION AS TO THE SIMULATION OF ACTIONS SHOULD BE DIRECTED TO A REFEREE FOR APPROVAL.
. SIMULATION - involvts identification and utilization of requirements and procedures short of actual employment.
l ACTUAL - movement of resources and/or physical implementation for the exercise. EAAMPLE - Fire hose would be rolled out but not charged without approval of a referee. g ACTIONS OF PARTICIPANTS SHOULD BE IDENTIFIED TO THE REFEREES 1F NOT OBVIOUS. PARTICIPANT IDENTIFICATION fxercise participants will wear color coded baseball caps which identify their onsition/ function in the exercise. The color designation is as follows: i 1 RED Emergency Director / Recovery Manager / Asst RM g () YElt.0W Emergency Managers and Coordinators (functions identified on balicap) BLUE Emergency Staff (personnel reporting to managers) i GREE'A Operating Crew and On/Offsite Teams I LIGHT BLUE Clerical and Stenographic Staff f WHITE NRC BROWN FEMA, EPA, DOE BLACK INPO
;, MARDON DER /BRP I I GREf PEMA
.g -
I'#AitC1 PANT CONDUCT - Participation in the exercise shall be carried out to the fullest extent pmible in accordance with the Emergency Plan and imp'iementing Procedures as if the exercise were a real emergency. Data should be requested from the 111 5
referees if it is necessary to perform the functions of the response position. Data will be supplied by the referees after the participants have taken the required actions. g If there is a question ask the referee for clarification. The referee will not prompt or coach. The referee will not provide information concerning scenario development or resolution of problem areas encountered. Th rt.sponders are expected to obtain information through their own organizations and exercise their own judgement in determining response actions and resolving problems. The scenario data follows a predetermined course to accomplish objectives for the exercise; this does not mean that the players should limit their attempts at problem solving. Alternate solutions are encouraged and should be brought to the attention of the referee in their arca. The referees will note the alternate solutions but may not allow implementation since it may alter the course oF .he scenario. PARTICIPANT PRECAUTIONS ACTUAL EMERGENCY Should at any time during the course of the exercise, an actual emergency situation arise, all activities and communications related to the exercise will te suspended. All messages concerning actual emergency events shall be preceded with "THIS IS NOT, REPEAT NOT, AN EXERCISE MESSAGE". The lead referee is responsible for terminating or placing on hold the exercise until the actual emergency is handled. EXERC!;E COMMUNICATIONS All exercise communications should begin with, "THIS IS A DRILL". This includes telephone conversations, radio transmissions, plant page announcements, and written documents. The end of the communication should have, "THIS IS A DRILL". It is important that nonparticipating individuals who may overhear exercise communications are not mislea1 into believing that an actual emergency exists. COMPLIANCE WITH LAWS Intentional violation of any laws is not permitted during any exercise. Any motor vehicle response shall observe all normal motor vehicle operating laws which includes: posted speed limits, stop signs / lights, one way streets, etc. AVOID PROPERTY ENDANGERMENT Exercise participants, referees, and observers should avoid endangering property (public or private), members of the general public, or the environment. 111 6
MINIMlZE PUBLIC INCONVENIENCE lt is not the intent to aroese or inconvenience the public during the conduct of an erercise. In order to minimize public inconvenience, the , public should be informed both prior to and during the exercise. Also, all comunications, particularly in the public relations area, should be prefaced with 'This is a drill." RADIOLOGICAL CONTROLS Standing Radiation Work Permits (RWPs) are tot issued for the conduct of exercises. If scenario events direct players to areas that are actually RWP controlled due to high radiation, surface contamination, or airborne radioactivity, players will simulate the activities they would have perfurmed without actually entering the RWP controlled area. NO ONE IS EXEMPT (including company and Federal referees) FROM NORMAL STATION RADIOLOGICAL PRACTICES AND CONTROLS. OBSERVER CONDUCT Individuals must have prior permission from the Supervisor of Nuclear Emergency Planning to observe an exercise. A blue T shirt will designate an Observer. The scenario events and times are confidential and shall be kept confidential during the exercise. While in emergency response facilities, observers must not block the view of status boards, charts, or access to equipment. Observers should not participate in the exercise nor interfere with the actions of participants a;d referees. Any questions should be directed to a referee and not a participant. EXERCISECRITIQUE(NUREG0654N.5) A critique shall be conducted as soon as practicable after the exercise, and a formal evaluation should result from the critique (NUREG 0654 N.4). Three tiers of evaluation are involved in the critique process. FIRST LEVEL: The exercise participants are debriefed after each major portion of the exercise. An example: The PASS SAMPLE TEAM has completed sampling and the assigned referee discusses the evolution with the participants and indicates any weak and/or strong areas. SECOND LEVEL: The area referees get together with the area managers at the conclusion of the exercise and discuss the overali exercise mentioning strong and/or weak areas. 111-7
The area lead referees convene to discuss the overall THIRD LEVEL: exercise results. The lead referees are responsible for publishing the exercise critique.
'g EXERCISE CLOSEOUT (NUREG 0654 N.5)
The areas identified in the critique requiring improvement will be addressed, responsibility for corrective action will be controlled as descrit'ed in NSI 2.2.1 to ensure that corrective actions are implemented. 9 III-8
% illm prgi ii g r-i
O SECTION IV REFEREE DATA AND INSTRUCTIONS O IV-1
REFEREE INS 1 RUCTIONS IKTRODUCTION O Referees are an important aspect of emergency exercises for several reasons. An emergency exercise could not be conducted without them and would be of little value without the critique process at the end. As mentioned in the EXERCl!,E PHILOSOPliY section, the attitude of the participants is directly related to how the referees conduct themselves during the exercise. This point cannot be stressed enough and the following sections will provide guidance 'or referee conduct during the exercise. REFEREE RESPONSIBILITIES Generally referees have the following responsibilities to fulfill before, during, and after an exercise. PRE-EXERCISE
- 1. Review Referee Information Packet
- 2. Attend Scheduled Referee Training Session
- 3. Participate in Referee Walkthrough
- 4. Review Message Sheets which pertain to your responsibility
- 5. Become familiar with Referee Observation Sheets (to be nresented at training session)
EXERCISE
- 1. Assemble at location early
- 2. Log participants on Attendance Sheets (name, signature, employee number, and position code)
- 3. Observe / Evaluate Participant Actions
- 4. Complete Observation Sheets
- 5. Provide Exercise Data As Appropriate
- 6. Debrief participants as soon as possible POST EXERCISE
- 1. Attend / Conduct Debriefing
- 2. Complete Observation Sheets
- 3. Collect Attendance Sheets
- 4. Turn over completed Observation Sheets, Attendance Sheets, and Referee Manuals to Area Lead Referee S. Assure that all participants in your area of responsibility are informed the exercise is over (ie. oil onsite and offsite groups)
- 6. Participate in Critique Presentation I
IV 2
-.- . .- - ._ - ._- .- ~ . _. .
GUIDELINES FOR REFEREES HOW TO DEAL WITH EXERCISE PROBLEMS The referee structure is laid out such that each area has a lead referee and the other referees in that area report to the lead. As an example, the Control Room Lead Referee has the Simulator Instructor, Communications Referee, and the Control Room Data Man reporting to him. Any problems or questions that the referees cannot answer are to be refereed to the lead referee. The area lead referees report te the Chief Referee and refer any problems or aestions they can't answer to him. A complete listing of referees and the telephone number for contact during the exercise is located in this tab. Referees shall not provide information to the participants regarding scenario development or resolution of problem areas encountered. The participants are expected to obtain information through their own organization and exercise their own judgement in determining response actions and resolving problems. In the event of incorrect or incomplete responses, or if the participant indicates lack of knowledge of how to proceed, the referee will prompt the participant with necessary instructions and will note the deficiency on the critique forms. Referees will only guide the actions of the players when it is obvious that unchecked actions will hue a significant impact on the successful completion of the exercise. REFEREE PROMPTS SHOULD BE KEPT TO A MINIMUM AND AVOIDED IF AT ALL POSSIBLE. Each referee has a copy of the exercise manual and the sections necessary to carry out their responsibilities. Each referee is responsible to be knowledgeable in their particular area and of the overall scenario. The referees are selected because of their experience and knowledge. The exercise packape has been designed to allow for various response actions to occur in a natural sequence. The data that has been provided in the exercise package is so the referees can feed information to the participants when they ask for it. The refertes are to play the part of the normally used instruments and gauges that are not available during an exercise. Any portions of the scenario depicting plant system operational transients are simulated events. No Control Room actions, or reactions involving operation of plant systems or affecting generation capability, will be initiated. All exercise messages will he prefixed and suffixed with the words "THIS IS A DRILL." Referees do not have to follow the radiation exposure control practices for the simulated radiation lev 31s from the emergency exercise. The players must follow the radiation protection rules as applicable to the scenario. Both participants and the referees must adhere to all normal station radiation - control practices. l IV-3 i
~ -. - - . . -- -,
As always SAFETY TAKES PRECEDENCE OVER All OTHER EXERCISE REQUIREMENTS. The referees are responsible to insure that all safety rules are followed at all time;. REFEREE REMINDERS
- 1. Stick to the timeline as far as giving out information is concerned. if questions arise contact the lead or chief referee.
- 2. Players are not allowed to introduce items into the exercise.
- 3. Respond to player's questions but provide answers that do not prompt specific actions.
- 4. Make notes on both the good and the weak areas on the observation sheets. l
- 5. Debrief the participants as possible during the exercise to provide immediate feedback. The participants should not be surprised at any of the comments found in the final critique package.
- 6. Be prepared to contribute to the critique at the end of the exercise.
OBSERVATION SHEETS Referee Observation Sheets are an important part of the evaluation process in each exercise. The formal critique is developed around the completed Observation Sheets. To help you complete the Observation Sheets, here are a few helpful suggestions: h
- 1. Complete the upper portion of your sheet including name, location, and date. This is helpful if questions arise later.
- 2. If your Observation Sheet includes a log, complete all parts of it.
This aids in reconstruction of the exercise.
- 3. Observe participant actions.
4 Evaluate participant actions and record on Referee Observation Sheet using the following scale:
- 1. Satisfactory
- 2. Satisfactory with a few problems that may be subject to follow up.
- 3. Deficiency is noted but would not seriously affect our ability to protect the health and safety of the public.
- 4. Deficiency is noted which would affect our ability to protect the health and safety of the public.
IV 4 O
A PAkibN
- 5. Note any action, good or bad, you feel worthy of comment but not covered by the questions on the back of the Observation Sheet.
POST EXERCISE CRITIQUE PROCESS Immediately upon completion of the exercise the lead area referees will conduct & debriefing with the lead participants and the area referees. The purpose of this debrief is to solicit input from the exercise participants on the referee observationt presented. This information will be the backbone of the formal critique package and player input is important for the overall eva'iuation. Upon completion of the :.rea cebriefing the lead referees will gather at the EOF to provitie a general impression of how the overall exercise went. The lead referees will meet the next day at the EOF to put together an exercise timeline and the exercise critique package. The critique package will then b1 presented to the company management at a designated time and location. O
.. . - . - -- _ - . - . - --..-.__ --.---_. _ - -.--._ . .=
0 i ] SECTION IV PART A - REFEREE LOCATION AND TELEPHONE NUMBERS 4 4 IV-6
. . . . . . . , - . - - . , . . 4 , , , . . . - --
- , . ...m. ,_ .. , ..- . - . -. . . . _ ., y . we,-,-. . - - ,
- g. REFEREE LOCATION AND TELEPHONE NUMPER Referet Phone Number A. CONTROL ROOM (Simulator) i.ead Control Room Referee [LL_ Vel sh ext. 3782 Simulator Instructor J. Barke ext. 3782 ~
Communications Referee LE. Homnick ext. 3782 Control Room Referee R.J. Gantz ext. 3782 B. TECHNICAL SUPPORT CENTER Lead TSC Referee T.C. Daloiaz ext. 3530 TSC Comunications Referee (includes data flow) L.S. Sucon ext. 3530 TSC Rad Referee M. Rochester ext. 3530 TSC-Tech Referee M.M. Golden ext. 3530 In plant Team Referee Coordinator F.L. Wurst ext. 3530
-C. OPERATIONS SUPPORT-CENTER Lead OSC Referee- J.R. Tolerico ext. 3907 In Plant Team Referee (Rad) P.J. McGlynn ext. 3907 In-Plant Team Referee Rad) F.e. Jaeaer . ext. 3907 In-Plant Team Referee Rad)- E.J. McIlvaine ext. 3907 In-Plant Team Referee Rad) 0.C. Pfendler ext. 3907 O. In-Plant Team Referee (0ps/NPO) R.W. Brown ext. 3907
- In Plant Team Referee (0ps/NPO) J G. Paisley ext. 3907 In-Plant Team Referee (Maint/l&C) P.A. Herook ext. 3907 In-Plant Team Referee
-(Maint/l&C)- P.L.-McGreoor gxt. 3907 Lead Security Referee R.E. Gaudreau ext. 3115 Security Referee 0.P. McBride ext. 3115 Security Referee -G.E. Gallaaher ext. 3115 3 Reactor Coolant Sample Team Referee L.K. Vnuk ext. 3907 D. F.MERGENCY.0PERATIONS FACILITY Lead EOF Referee
- c. h o p:rc r y -] o "i1 L rt ext. 3605 EOF Rad Referee K.E. Shank ext. 3605 E0F Tech Referee H.P. Seaaer ext. 3605 EOF Communications. Referee E.A. Heckman -ext. 3605 Simulated HPN NRC Team J.S. Fields -ext. 3605 '
Simulated NRC Hotline (ENS) R.T. Jensen ext. 3605
. lh M W %Qg V' 6 (* %
Referee Phone Number E. GENERAL OFFICE GO Tech Referee J.M. Kulick ext. 7550 F. MEDIA OPERATIONS CENTER Lead HOC Referee J.J. Scocelliti ext. 3561 ~ MOC Assistant Referee T.J. Kohler ext. 3561 Person to call in rumors and questions R.R. Beaslev- ext. G. ENVIRONMENTAL HONITORING TEAMS OSCAR Referee E. Wol f f_teld Hear Site Team Referee M.J. Shymanski Field Offsite Monitor Team Referee C.A. Lincenfelter Field Offsite Monitor Team Referee G.L. Croll. 12/17 Field K.H. Staber 1/14.2/19 Field H. CHIEF REFEREES Chief Rad Referee B H. Carson ext. 3601 Chief Referee R.H. Halm gyt. 3530
- 1. N ANT SITE
/
Evacuatio(Group 4th ficod S&A l . IV-8 O
E=- +ca. e 4..., m. _.Aua ham-.. -W-A-.i 22---w A a .J- 4 %& *_uue-4--....A' 4 a4- A-A-d44-4--45---64 4AA - ** w*-O'e-wA0.1-II 6d*h4-a3T-pA44.4n-W hA 4- 4X4.J4- -..m. I i 6 a i t t, I I SECTION V - TIMLLINE PART A--
SUMMARY
L l l I V-1
l FULL SCALE EXERCISE WRITTEN
SUMMARY
The following is an overview describing the events of the detailed timeline and predicted response of the Emergency Organization. SCENARIO OVERVIEW The exercise will be an early afternoon exercise, starting for the operators in the simulator control room with a shift turnover / briefing at 1300 hours. The affected unit will be unit I which is at 100% power and Unit 2, for the exercise, is in cold shutdown. The first event, which will occur at 1330 hours, will be a simulated security event called into the Information Center by an actor portraying an individual predictia an accident at the plant that will cause a radioactive release. The Information Center will pass the information on to Security who will inform operations of the phone call. It is expected that an UNUSUAL EVENT will be declared as a result of the phone call to the Information Center. At 1415 hours the Main Control Room and the Rad Waste Control Room will receive indication of a problem in the Offgas system. Thorough investigation of the offgas system as a result of the alarms will reveal that an offgas explosion has occurred. Tb; explosion in the offgas system is a trigger for an ALERT classification. A plant transient occurs at 1545 which is a trigger for an ALERT classification. A main turbine load reject occurs, a delayed turbine trip with a stuck open stop and control valve resulting in an overspeed condition, slow reactor scram and resultant feel damage on the pressure power transient. Reactor vessel water level drop.s, RCIC manually starts, HPCI starts automatically and breaks the full flow test return line to the CST as a result of water hamer on the start. Break in the test line is not obvious until the Control Room receives a call from the field reporting the leak. If the sump valve line up from the CST berm area is not checked at the time of the leak report, radioactive water will leak to the storm sewer and pose an environmental threat and a situation for the EOF to deal with at a later time when a report from the field to the E0F will be initiated. The RCIC turbine which had been feeding and maintaining the reactor vessel level starts to oscillate at 1630 hours and trips on overspeed and a steam line break occurs as a result. The break of the steam line pressurizes the RCIC room and causes radioactive material to be released out of the room steam vent panel unmonitored and untreated. This event is a trigger for a SITE AREA EMERGENCY classification. The release will be in the direction of the North Gate House (NGH) and parking lot. The portal monitors in the NGH will alarm and there will be contamination in the parking lot and on the vehicles. The plume travel will V-2 h
continue toward_the road north of the plant which is a township road. The E0F , (~) will evaluate the contamination and deposition on the road. QJ The evacuation of non-essential )ersonnel will have to contend with contamination at the North Gate 1ouse and parking lot.. This will be an additional issue for the EOF to deal with. The exercise will be terminated when a plan has been developed to address contamination concerns at the township road, North Gate House parking lot, and the storm sewer discharge (if it becomes an issue), and after all the objectives have been fulfilled; this is expected to occur about 1930. INITIAL CONDITIONS Susquehanna Steam Electric Station Unit I has been at 100% power since the refuel outage with the exception of: e the normal surveillance testing (MSIV and Turbine Valve testing, rod swaps,etc.), e a problem identified with the #2 Main Turbine Control Valve has required additional down powers for investigation and testing, e a series of feedwater heater level control valve problems, g e water and H2 analyzer problems in the Unit 1 offgas recombiner,
'
- fouling of the main condenser with debris requiring drain down and cleaning whenever a down power is scheduled, e ongoing problems with the instrument air compressors tripping and the standby compressor failing to start.
The #2 control valve did not respond properly during weekly turbine valve testing. After the #2 control valve was closed, it failed to reopen. The test switch was taken to closed again and released, but the valve failed to open. As the operators were consulting the off normal procedure, the #2 control valve slowly opened. All turbine valves appeared to operate normally after that. A down power was planned and no abnormalities were found. Main Turbine valve testing has been completed several times since with no problems noted. Power reductions have been conducted as a result of feedwater level control problems. The first problem occurred right af ter turbine valve testing when the 3C feedwater emergency dump valve failed and water level control was lost. The extraction steam supplies for the 3C, 40, and 50 heaters automatically isolated as high water levels developed in those heaters. - Four group 1 CRAM rods were 'i.s,rtei and reactor recirculation pump flow was decreased. Reactor power stabilized at about 78%. Of f normal procedure ON 147-001 was in effect. Power was reduced to 70% and the 'C' feed water V V-3
string isolated. Later power was reduced to 60% with the reactor recirculation Jumps in manual flow centrol. The emergency dump valve has been &l repaired and tie normal 3C feedwater level control valve is being repaired. W ' After the re) airs were made to the 'C' feedwater heater string it was found that the 5B 1 eater drain and dump valves were not operating. A power reduction was taken and the string was isolated again and repairs made to the 58 feedwater heater level control valves. Power was restored when the valve repairs were completed. The 'C' feedwater heater levels have been oscillating 1 and !&C is investigating. The Unit 1 offgas recombiner was found to have some water in it and the H2 analyzer was reading erratically. The Tech Staff engineer is the lead for the water investigation and I&C has been investigating the H2 analyzer. j There appears to be a fair amount of cooling tower fill that is migrating into ! the condenser inlet water boxes reducing flow and reduced generation because of poor vacuum. The recent weather, with high winds, has deposited large amounts of plastic and other material in the cooling tower basin which is causing fouling of the tube sheets. The Tech Staff engineer is investigating the efficiency of the basin screens to determine how the debris is getting to the water boxes. Other problems not requiring power reductions but ongoing are:
- Reactor water cleanup putrp seal failures, which require repair and subsequent chemistry excursions.
- Main Generator field ground currents increasing, o Lube oil intrusion from the Reactor feedpumps, o Pressurization of the 'B' loop of RHR, due to back leakage from the reactor vessel, e Instrument air compressors tripping with the standby failing to start or tripping shortly after starting.
The problems with Reactot Water Clean Up continue and are not expected to be resolved until the new purups are installed. The Main Generator Field ground problem appears to have been resolved by flushing the Stator Cooling Water side. The ground currents dropped after flushing and have been fairly constant since. The Tech Staff engineer is monitoring the situation closely. The Reactnr Feedpump lube oil intrusion problem also appears to be resolved. The source of the lube oil has been determined and the injection has been stopped. Chemistry is continuing to monitor for oil and extra effort is being
- made to get.the oil out of the condensate Demins.
l i V-4
i investigation of the increasing pressure determined that the problem began
/N after the quarterly valve stoking surveillanco.
V Recently the ' A' instrument air comaressor tripped, The 'B' compressor was in standby, but it also tripped. The loss of instrument air procedure was entered. The instrament and service air systems were crosstied. When an operator reset the 'B' compressor trip, botn the 'A' and the 'B' compressors started. Instrument air system pressure dropped to a low of 72 pounds. The System Engineer is investigating. The remainder of the items under investigation are listed on the priority list along with the other scheduled plant work. SHIFT TURNOVER The abova informatton statements will be given to Operations during a turnover process. The Operators will be given a shift turnover by the Control Room Referees. The turnover will discuss the status of the above items as shown on the Station Priority list. (See Initial Conditions Section VI.) SCENARIO SECURITY EVENT - UNUSUAL EVENT c TRIGGER - 1330 ( CLASSIFICATION - 1350 The first event for the exercise is a security threat from a caller at the river intake structure. An actor will actually call from the river intake so that there will be pump noise and plant page noise in the background during the phone converst. tion, it is expected that the person who handles the call at the Information Center will hear the background noise and report that when they talk with security. When security hears the facts from the Information Center they will most likely recognize that the call is coming from onsite and classify the event as very credible. Security will call the control room and inform the shif t supervisor of the phone call to the Information Center and recommend a classification. The Operations shift supervisor will classify the event as an UNUSUAL EVENT. Dur +) emergency training it has been agreed that if a UE type security event is declared, the Shift Supervisor will activate the TSC. The TSC activation is at a UE to support possible walk downs and equipment checks. It is assumed that the exercise will play out in this manner. If the TSC is not manned, it will not be prompted at this time. The classification will be based on the EAL, (16) Security Event, which states: L.) V-5 i
EAL. #16.1 (A or B) A. A report from security of a security threat, attempted entry, or attempthd sabotage of the owner controlled area adjacent to the site, or B. Any attempted act of sabotage which is deemed legitimate in the I judgement of the SS and affects plant operation. ' 0FFpAS EXPLOS!ON ALERT TR14 iR - 1415 Cl. 41FICAT10N - 1430 1 The initial conditions of the plant _provided to the emergency responders provide a basis for almost all of the events that occur during the exercise. The first event in the olant is an offgas explosion that is a result of problems already identified in the initial conditions concerning the recombiner. The water and the H2 analyzer discussed in the initial conditions arc indicators that the system is not working properly. The offgas explosion occurs 45 minutes after the call to the Information Center. Th9 scenario is written such that the explosion in the offgas system is not severe enough to cause a loss of vacuum or major damage to the plant and will require investigation to locate. The responders will have an inclination that there was an explosion in the offgas system but will have to look for it and will most likely tie it to the previous security event, thinking that a bomb caused the explosion. g About 15 ainutes after the offgas indications, another alarm will be received in the control room indicating a release from the Turbine Building Vent, which is offgas being released from the leak in the Rad Waste Building. (The Rad Waste Building ventilation discharges to the Turbine Building stack.) The radioactive release will not be large, less than Tech Spec limits, but enough to cause an alarm in the control room and activation of the TSC if not already activated, and probable classification at the ALERT level. If classification to the ALERT level is not implemented at this time it will not be prompted. Activation of the facilities will be prompted if necessary, but not classification. There is the possibility of two ALERT classifications, one is an explosion on site which affects plant operation (offgas event), the other a security event where there is damage onsite (assumed bomb planted in offgas). The offgas explosion affects operation since 15 minutes after the first offgas indications observed in the control room, there will be an alarm indicating , elevated releases out the Turbine Building Ventilation. V-6
. _ - _ ._ _ _ . _ _ _ _ . . - _ _ - -_ _ - _ _ . _ _ _ ~ ___ _.. _ . . _ _ _ _ _ - - _ lt is expected that even if an ALERT classification is not made at this time O ventilation.the TSC will be manned due to the release from the Turbine Building There are two mechanisms by which the TSC may be manned during the beginning of this exercise. The first is the assumption that the TSC will be activated l 1 be' ore it is required by procedure, during the security event. The early ; activation of the TSC will have no bearing on how the exercise is played out. ! The second chain of events that may occur is the classification at the ALERT during the offgas event. The offgas problem will not manifest itself obviously, much like what would be expected to actually occur. This was planned so that the operators would not iarnediately begin to reduce reactor power and for the Emergency Organization to consider and initiate activation of the EOF and General Office withuut being prompted to do so. A message is being injected from the Vice President of Nuclear to act as a prompt to get the TSC and the EOF / General Office activated. If the ED does not agree with the VP a referee prompt will be initiated a few minutes later. By 1545, the time of the next plant event, the E0F and General Office personnel will be responding to activation of the facilities. The TSC will be activated and the emergency level at the site MAY OR MAY NOT be at the ALERT level. If an Alert is declared, the classification will be. based on the EAL, ONSITE FIRE / EXPLOSION which states: (1 and 2) Explosion damage to facility affecting plant operation, de armined by:
- 1. Direct observation or notification received by control room operator, and
- 2. Shift Supervisor evaluation.
OR The classification will t'e based on the EAL, (16) Security Event, which states: EAL #16.2 (A or B) A. A report from security that a security compromise is at the site but no protection of protected areas has occurred. or . E. Any act of sabotage which results in an actual or potential substantial degradation of the level of safety of the plant as judged by the shift supervisor / emergency director. V7
TURBINE TRIP / FUEL DAMAGE - ALERT g TRIGGER . 1545 CLASSIFICATION - 1600 At 1545 a plant transient starting with a Turbine Generator load reject will be initiated by the simulater instructor. A turbine trip is initiated by the load reject but a problem in the electrical control circuit of the turbine prevents an electrical trip and a mechanical trip is activated as a back up. A turbine stop valve and control valve stick open on the turbine trip. The sequence of events which occur with the turbine cause a large pressure and power transient along with an overspeed condition. The reactor power excursion caues fuel damage and Main Steam Isolation Valve closure on high radiation levels in the steam lines. The transient causes water level to drop, manual or auto start of RCIC, auto start of HPCI, containment isolation and start of SBGTS on low reactor vessel level. The turbine trip will cause the reactor vessel level to shrink. The operators will start RCIC injection to the vessel manually, HPCI will start automatically, a containment isolation and SBGTS start will occur. As stated in the initial conditions, a valve problem exists in the HPCI system which will allow a water hammer event to occur when the HPCI turbine auto starts. The line break causes CST water to leak into the CST berm area and a small portion of the RCIC discharge, while it is running, will leak via the broken HPCI line into the CST berm. h The water from the CST is relatively clean and will not be a major problem, unless tne operators, thinking they have a problem with CST level, swap the RCIC suction to the suppression pool. The activity of the suppression pool water is a factor of 10E3 higher than the CST water and would cause concern if it started leaking into the environment. The responders will be given a success path for this portion of the scenario. IF CST Berm sump drain, valve line up is checked the responders will be advised that the isolation valve to the storm sewer is slightly open. The responders will be allowed to close the valve and no water will leak from the berm to the environment. If the valve line-up is not thought of and not checked, water will leak to the storm sewer and be addressed by the EOF at a later time. The classification will be based on the EAL, (3) FUEL CLADDING DEGRADATION which states: 9 EAL #3.1 (A or B) Core degradation indicated by: V-8
l A. Valid Off-gas Pre-treatment monitor High-High radiation alarm annunciation on panel 0C651 or indication on panel IC600. or B. Reactor Coolant activity greater than 300 pCi/cc of equivalent 1-131, as determined by sample analysis. or C. Valid Main Steam Line High radiation trip annunciation or indication on panel IC651. or D. Valid containment post accident monitor indication on panel 1C601 greater than 200 R/hr. RCIC STEAM LINE BREAX - SITE AREA EMERGENCY TRIGGER - 1630 CLASSIFICATION - 1645 The RCIC system will be in service after the plant trans'.ent to maintain vessel level and remove decay heat. At 1630 the turbine will start to oscillate and then go into an overspeed condition trip and cause a steam line break. The steam line break pressurizes the room, blows out the room blow out panel, and an unmonitored/ untreated release begins. O. V Indication of a steam line break will be received in the control room as a result of multiple alarms and indicators showing the problem. Security will receive an alarm from a tamper switch on the RCIC room blow wt panel indicating a loss of integrity. Security will investigate the tamper switch, ops will investigate the RCIC room. The control room will gather the information from the operators and from security and deduce there is leakage outside the Reactor Building. The organization will monitor the plume direction and determine if protective action recommendations will be required based on the information received from the field and the control room. The classification of the emergency will be based on the EAL, STEAM LINE BREAK, which states:
- 1. Failure of RCIC steam isolation valve HV-F008 and HV-F007 to close, indicated by position indicator on Panel IC601.
AND
- 2. (a OR b OR c OR d OR e OR f)
V-9
- a. RCIC steamline pipe routing area high temperature annunciation on panel IC601, or indication on panel 10614. g, OR ;
1
- b. RCIC equipment area high temperature annunciation on panel l 1C601 or indication on panel IC614.
OR
- c. RCIC steamline high flow annunciation on panel 1C601.
OR
- d. RCIC steamline tunnel ventilation high delta temperature annunciation on panel IC601.
OR
- e. 1CIC turbine exhaust diaphragm high pressure annunciation on panel IC601.
OR
- f. Other indication of steam leakage from the RCIC system.
The radiological portion of the scenario will not be of a magnitude to cause major problems to the general sopulation. The release will be significant enough to have to be dealt wit 1 on a very local level at the site boundary. On site problems will have to be dealt with and action plans developed. The storm sewer may become an issue, the North Gate House (NGH) Parking lot and the vehicles, and the people being evacuated from the site who would normally leave via the NGH. These items will have to be dealt with by the EOF. It is expected that a discussion of whether or not a General Emergency classification needs to be made based on the contamination and dose at the site boundary will take place. The scenario is not designed to go to a General Emergency classification but still be challenging and as real as possible for the participants. WMMARY TI?'" P/ 1330 - r, c' O tt: Security Threat to Info Center, Unusual Event. 1415 - Secona dvent: H2 explosion in offgas system, valve damagcd, offgas . leaking into the Rad Waste building and out Turbine building ventilation. When damage to valve found, classification could be made at the alert level. Y-10
1545 - Third Event: Main Generator load reject, Main Turbine Overspeed, ( pressure / power spike, fuel damage, MSIV closure on high rad, i containment rad levels at the alert level. HPCI auto starts breaks discharge line return to CST with a water hammer event causing CST water to leak into the berm area and into the storm sewer RCIC starts in auto or manual and injects to the Reactor Vessel. 1630 - Last Event: RCIC turbine speed starts to oscillate and goes into an overspeed condition, trips and causes a steam line break in the RCIC room to blow out the RCIC room steam relief panels allowing an unmonitored, untreated release. 1700 - The rad levels in the field provide results thit prompt a discussion on what kind of protective action recommendations may be required due to the type of release and magnitude. 1930 - The Annual NRC exercise is terminated. O 4 l . . -
a m .c k a ,a m Aa .swe -=1-,,mn-&.._-.a day,, r ,saua,_a_masmoa-nn.- e --,---a ,,,_m--a, w a. .may naa.ua e. .. r-o-.-Aua----n O SECTION Y TIMELINE PART B - DETAILED TIMELINE V '. 2
^
f APPROX. TIME - OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS ! i i l- 1300 Referee Message - Shift Briefers to Operations to start the process of shift turnover. The 15-1 i set up initial conditions for the Control Room Referee will review the following with the i
- Control Room Operators. oncoming shift: l
! 1. Previous 24 hour log entries !
- 2. Operations turnover sheets
- 3. Previous and present plant priotity lists !
] 4.. NSAG Daily Report i NOTE: The above material is located in tne INITIAL i CONDITIONS SECTION of the REFEREE MANUAL. 1300 Referee Messaae - Equipment set up, Phone company personnel to perform switching in the IS-2 l initiatc activation of the emergency Service and Administration Building phone room.and hook ! exercise phones, radio, and plant up in the simulator control room. , page for the simulator control room.
,L '
Lead Referee to swap simulator radio and check NRC phone t u activated. ! i j 1300 Referee Messaae - Simulator The initial plant conditions contain the following files: 15-3 l 1 Instructor initialize the. simulator : RH.92NRC - Equipment status and alarms to IC #125. ! ! RH. RAD 1 - Initial radiological conditions for SPDS & j i . containment rad ' RH.PM565 - RX Building ARMS RH.PMS66 - Turbine Building ARMS RH.PMS67 - Miscellaneous ARMS [
.RH.WE3.1 - Initial weather conditions j f
See SECTION IX SIMULATOR INFORMATION for data contained f , in these files. _ l 1300 Referee Message - Plant page Plant page announcement to be made from Control Room 15-4 ! j- ' announcement for start of 1992 NRC indicating the start of the 1992 NRC GRADED EXERCISE. [ j- GRADED EXERCISE. ^
?
l !
. 1
)
.. . .... -._ - . . - - _n _
Al'ROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1330 Referee Message - An actor initiated The Information Center will collect the available 15-5 call will be made to the Information information from the caller and contact the ASCC to Center informing the staff of a report the call. pending threat involving a possible radiation release that will occur ' today. This is the trigger for UNUSUAL EVENT. 1335 The Control Room receives the The Operations Shift Supervisor will review the Emergency information from the Security Shift Plan Classification Matrix. Supervisor concerning the credible threat to the plant and is provided to the Shift Supervisor. [1350 Shift Supervisor to classify the The classification will be based on the EAL, (16)
- situation as an UNUSUAL LVENT. Security Event, which states:
EAL # 16.1 (A or B) A. A report from security of a security threat, attempted er.try, or attempted sabotage of the owner controlled area adjacent to the site. or
- 8. Any attempted act of sabotage which is deemed legitimate in the judgement of the SS and affects plant operation.
The Shift Supervisor will declare an UNUSUAL EVENT appoint a Control Room Conusunicator to announce classification over the plant page, initiate initial notifications, announce to Control Room personnel that he is the Emergency Director, and initiate comununications with the Duty Manager, Recovery Manager, Operations C>ordinator, and Public Information Manager to inform them of the plant status and situation. 9 - 0 0
__ Ak
~ -
APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1355 Duty Manager and Operations Shift Supervisor provides status of security event, Coordinator report to Control Room plant, actions taken, and plans for placing the plant in for briefing of incident. a safe configuration. 1400 The Shift Supervisor in conference The Shift Supervisor will initiate activation of the TSC with'the Duty Manager and Operations by instructing the Control Room Communicator 19 page and Coordinator initiate activation of call out the appropriate people to man the TSC. A page the TSC at this time as a announcement will be made to initiate the TSC staffing. precautionary measure. NOTE: This activation is 4 anticipated to be the consarvative reaction of the participants to the security threat. The TSC, by procedure, is not required to be
< activated at thic time.
L la05 Result of early TSC activation. The OSC begins to set up and muster the people arriving , Responders arrive at the OSC and the for accountability reporting. The OSC Coordinator is TSC and begin turnover process. briefed by the Control Room and in turn briefs the OSC responders. 1405 The Control Room Communicator The communicator has provided all the required , completes notifications to the off- information to the offsite agencies so that they will be ' site agencies. able to take actions as required by their emergency . plans. ! 1<15 Referee Messace - Simulator Control Room Operator will acknowledge the alarm on the 15-6 I initiated alarm (A06FIS) from the main control room panel and investigate the indications Offgas panel indicating high and alarms on the Offgas back panel. temperature, flow and pressure y perturbations. ** This is the trigger for ALERT cla:sification. 1415 Referee Messaae - Simulated Offgas LRW Control Room operator will acknowledge the alarms, IS-7 system alarms received in the Liquid check readings, initiate an investigation, and notify the Rad k'aste Control Room. Control Room.
APPROX. TIME __,OF DAY INITIATING EVENT EIPECTED SEQUENCE OF EVENTS 1415 Referee Messaae - Operator in LRW LRW Control Room operator receives information from 15-8 calls LRW Control Room to ask about caller, initiates an investigation, and reports the the vibration / noise that he information ta the Control Room. felt / heard. 1420 Referee Messaae - The operators will Indications will be checked and investigation of the follow the direction given in the 'arious alarms will be initiated. alarm response procedure. The Control Room will dispatch an Operator to the Offgas 15-9 panel in the Turbine Building to check local indications and report back findings. The LRW Control Room will most likely initiate a walk 15-10 down of the Offgas system in the LRW Cuilding.
< The Shift Supervisor will confer witn the Security Shift 1
Supervisor to initiate a search for an explosive device that may have been set in the Offgas system. 1430 Result of early activation of the The TSC people start to check communicatica links, start ; TSC. up equipment, determine ? ant status in preparation for Responders arrive at the TSC and turnovet. : begin the process of taking over management of the emergency from the ! Control Room. 1430 Referee Messace - Simulator The Control Room Operator will acknowledge the alarm, the 15-11 instructor to initiate File: RH. STA will review the SPING files to determine the validity which initiates a Control Room alarm of the . arm. for the SPING panel indicating a release from the Turbine Building i Vent stack. (A15E04) i o - e - - - - - __--_____ _-_- e
v - - APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1430 Operations Shift Supervisor to The classification will br; when and if the break in the classify emergency as an ALERT when offgas system is located. it is confirmed that there was an explosion in rad vaste. The classification wili be tased on the EAL, ONSITE FIRE / EXPLOSION which states: NOTE: Classification to the ALERT may not be done at this time. Next (1 and 2) plant event at 1530 will be a trigger for ALERT classification by Explosion damage to facility affecting plant operation, the TSC. determined by: kn ALERT classificatina would be 1. Direct observation or notification received by conservative at this co"nt since the control room operator. offgas stream can tc trJosferred to the common without .'"etting plant and e: operation thus not meeting the ' Shift Supervisor evaluation. stated EAL conditices. 2. The Shift Supervisor will declare an ALERT, instruct the Control Rosa Communicatc- to initiate upgrade notifications, initiate activation of the TSC, and accountability. 1430 Results of later activation of the The Shift Supervisor will initiate activation of the TSC of the TSC. by instructing the Control Room Communicator to page and TSC activation initiated as a result call out ti.e appropriate people to man the TSC. A page of the offgas indications and the announcement will be 7ade to initiate the TSC staffing. radioactive release indicated on tne Turbine Building SFING. 1445 The Control Room Communicator The communicator has informed the off-site agencies of completes upgrade notifications to the upgrade of the emergency classification so that the the off-site agencies. agencies may respond as required by their Emergency Plans.
APPR0X. TIME OF "jY ' INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1500 Security reports results of site Security compiles the information required for the accountability to the Operations sccantability and determines the reasons for any Shift Supervisor and takes requuti 19'.epancies that turn up. action for any missing individe.-is. This will occur if the accountability was ordered at 1430 hours. 1500 Referee Prompt - When the The Emergency Director will release everyone from their 15-12 accountability has been completed accountability stations. prompt the Emergency Director to release the people from their accountability stations. 1505 Referae Messaae - Call from Vice The Shift Supervisor or the TSC Emergency Director will 15-13 President Nuclear asking the Shift discuss with the VP the reasons for activating the EOF ? Supervisor or the ISC Emergency and the General Office. Due to the event occurring in 5; Director if the E6F and General the afternoon there already is a lot of public interest Office has been activated. generated and the need to provide site sup;; ort for dealing with the public and government emergency agencies is imperative. 1510 Public Information Manager and The Public Information Manager will have the required Recovery Manager briefed by details for preparation and distribution of information Operations Shift Supervisor or TSC concerning the events at the plant. Emergency Director a* to extent of incident. 1515 Referee Promot - Inform the TSC The TSC Emergency Director will direct the TSC 15-14 Emergency Director to activate the _ communicator to initiate activation of the EOF and the E0F and General Office responders as Teneral Office. a precautionary measure to deal with the influx of news and public To keep the exercise on track the Emergency Director will figures. be told to initiate the activation if he hasn't already done so. The fact that the Emergency Director was prompted will be noted for the critique. O - O O
O v Ov O APPR0X. TlHE OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1515 The Alternate Security rontrol The security officer dispatched to the EOF for access Center will dispatch an officer to control will check the individuals already in the control access to the EOF and building and help the E&S set up crew as requested to initiate call out of EOF personnel. prepare the EOF for responding emergency personnel. 1515 General Office personnel will be The General Office responders begin set up of the called and respond to General facility and data collection for suppe,t of the Office. emergency. 1530 Results of later activation of the The TSC Emergency Director completes briefing the TSC. respective Coordinators, receives updates, and announces TSC takes control of emergency. the TSC has management responsibility of the event. The information that the TSC is in control is passed over the plant page. < 1530 Site based individuals begin The interim EOF responders will contact their i reporting to EOF and start set up of counterparts in the ISC and be updated on the plant
- facility. status, actions in progress, and support required. These individuals will updtte the status boards and will provide updated information to the responding managers when they begin to arrive.
1545 Referee Messe:3 - Simulator The Control Room operators will acknowledge the alarms 15-15 Instructor to initiate file received, review the indications, review the appropriate RH.TUR05, which initiates a turbine procedures, and take the directed actions. trip, fuel damage as a result of a pressure / power spike, MSIV closure The Turbine trip and MSIV closure will cause the reactor on high Rad and an increase in vessel level to shrink. The operators will start RCIC Containment radiation levels. injection to the vessel manually, HPCI will start automatically, a containment isolation and SBGTS start she transient is a trigger for ALERT will occur. classification. As stated in the initial conditions, a valve prcblem exists in the HPCI system which will allow a water hammer event to occur whEn the HPCI turbine aute starts. The line break causes CST water to leak into the CST berm area and a small portion of the RCIC discharge will leak into the CST berm area also.
APPROX. TIME EXPECTED SEQUENCE OF EVENTS OF DAY INITIATING EVENT 15-16 1545 Referee Message - Simulator The control room will monitor the CST level after the low level alarm is received at approximately 50% to determine Instructor to initiate file to where the water is going. indicate a decreasing CST level due to leakage and usage for feed to the vessel. (This file is included in the RH.TUROS file.i The Control Room will dispatch an operator to investigate 15-17 1550 Referee Message - A simulated construction worker calls the the report and determine location, severity, and Control Room from the CST Berm area consequences of the break. to report water shooting out of a The Control Room will instruct the operator dispatched to pipe in the area. investigate the leak to check the valve line up of the CST Berm sump to ensure that no water is leaking into the environment.
?
8 1 l 9 - O O
RPPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1600 TSC to classify the event as an L The classification will be based on the EAL, (3) FUEL- . ALERT if not already classifled to- CLADDING DEGRADATION which states: that . level from the previous event. The ALERT. level classification may 'EAL # 3.1 (A or B) 2 already have been initiated from the _ Core degradation indicated by: previous plant event, offgas explosion. A. Valid Off-gas Pre-treatment monitor High-High radiation alarm annunciation on panel OC651 or - If the Plant is at an ALERT then the indication on panel 10600. TSC should recognize.the events as entry conditions.for a.different or EAL. t . B. Reactor Coolant activity greater than 300 pCi/cc of equivalent I-131, as determined by sample analysis.
< or L
C. Valid Main Steam Line High radiation trip i annunciation or indication on panel 10651. or D. Valid containment post accident monitor indication on panel 1060i greater than 200 R/hr. The TSC Emergency Director will declare an ALERT, instruct the TSC Communicator to initiate upgrade notifications, and accountability if not already accomplished. 1615 Referee Prompt - Have the Emergency To keep the exercise on track the Emergency Director will 15-18 Director. classify the events as an be told to make the classification if he hasn't already ALERT-if not:already done. done so. The fact that the Emergency Director was prompted will be noted for the critique. 1625 The Engineering Support Manager. The Engineering Support Manager contacts the TSC contacts the 15C. Emergency Director for plant status and'what support is needed from Allentown.
APPROX. TIME EXPECTED SEQUENCE OF EVENTS Of DAY ,1NITIATING EVENT The indication in the Control Room will be a high IS-19 1630 Referee Messaae - Simulator instructor to initiate File RH.RCOST temperature alarm indicating high energy leakage into the which simulates a RCIC turbine trip room. There will be a fire protection alarm indicating and on the attempted restart an auto start of the fire pump and a Simplex panel alarm overspeed and steam line break. showing a smoke dctector alarmed. The indication is a fire or a steam leak. The Control Room Operators will check that the RCIC system isolates. The shift supervisor will refer to the l classification matrix and review the steam line break Emergency Action Level. The immediate operator action will be to depressorize the plant. The operators will pay close attention to the RCIC Room Area Radiation Monitors, the vent stack monitors and room temperatures to determine the severity (
< and spread of activity.
g ' The ASCC Controller will inform the Security Shift 15-20 1630 Referee Messaae - A tamper alarm is received in the ASCC fr6m the RCIC Supervisor, pan the Reactor Building with the TV camera steam vent relief panel. and dispatch an officer to check the panel and inform the TSC Security Coordinator. The Control Room will brief the TSC The Control Room infoms the TSC of the events that have 1635 just occurred and make a recommendation for the TSC to on the sequence of events that has The TSC occurred and recommend an upgraded upgrade the emergency to a SITE AREA EMERGENCY. ED will confer with the Operations Cocrdinator for classification. actions to be taken based on the sequence of events. Referee Message - Mobile Patrol The Mobile Patrol Officer reports to the ASCC the 15-21 1635 condition of the RCIC steam preel and on-scene Officer dispatched to assess the RCIC steam panel tamper alarm. assessment. The Access Control Officer in the NGH will investigate 1S-22 1645 Referee Messaae - The portal Monitors at the North Gate House the alaming portal monitors and inform the ASCC (NGH) are simulated in the alarming Controller of the alarms. The ASCC Controller will condition due to plume passage over inform the Security Shift Supervisor, TSC Security the NGH. Coordinator, place the Building ventilation in recirc, and notify Health Physics. 9 - G O
APPROX. TIME OF DAY INITIATING EVENT- EXPECTED SEQUENCE OF EVENTS-
- 1645 The TSC will classify the event as a - The ED will classify the emergency based on the EAL,>
j SITE AREA EMERGENCY. STEAM LINE BREAK, which states:
- 1. . Failure of RCIC steam isolation valve' HV-F008 and i
HV-F007.to close, indicated by position indicator on Panel IC601. AND
- 2. (a.0R b OR c OR d OR e OR f) [
9
- a. RCIC steamline' pipe routing area high-temperature annunciation on panel 10601, or '
4 indication on panel 10614.
<: OR -
4-
- b. RCIC equipment area high temperature '
annunciation on panel 1C601 or indication on . ' panel 1C614. OR ^
- c. RCIC steamline high flow annunciation on panel-IC601.
- OR
- d. RCIC steamline tunnel ventilation high' delta-temperature annunciation on panel 1C601. !
OR
- e. RCIC turbine exhaust diaphragm high pressure annunciation on panel 1C601.
OR i e
- . - ' c - e e w- e u :ivey y
APPR0X. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS
- f. Other indication of steam leakage from the RCIC system.
The ED will initiate upgrade notifications to offsite and internal, initiate evacuation of non-essential personnel, activation of the E0F, and dispatch the OSCAR monitoring team if not already dispatched. Evacuation of the site when ordered will have to be through the South Gate House due to the plume travel over the NGH. 1645 Referee Message - The simulated The individual who called the Information Center at the 15-23 actor that called the Information start of the exercise calls back to report that the Center at the start of the exercise original call was a hoax and hof,es that everything he < calls the Information Center again. hears on the plant page is not a result of his first g call. 1645 Referee Message - Simulator The file provides indication on the various plant IS-24 Instructor to initiate FILE: indicators of the weather conditions. RH.WE3.2 to simulate the meteorological conditions. 1650 Referee Message - Control Room Operator dispatched to investigate RCIC steam line break 15-25 directs operator to RCIC Room to indications, proceeds to the lSC for briefing and then to investigate cause for room alarms. RCIC Room. 1650 Referee Message - Control Room Operator dispatched to check auto start of fire pump from 15-26 directs operator to check out the the steem leak in the RCIC Room. The operator will fire pump auto start. report back to the Control Room that the pump start is valid, that there is flow through the system, and the pumps are operating properly. 1650 Referee Message - The Control Room The Chemistry Coordinator will respond to the sample 15-21 will request Chemistry to obtain a request by initiating set up of the chem lab and a reactor coolant sample. briefing for the chemists for obtaining a coolant sample. O - O O
- g v - -
APPROX. TIME i
-OF DAY INITIATING EVENT EXPECTED SEQUENCE OF-EVENTS 1655 Referee Messaae'- The Offsite The_0ffsite Honitoring Teams will receive direction from '15-28 Monitoring Teams will:be dispatched the Emergency Monitving Team Director on where to go and from the E0F. when and'what to sa W e. .,
1655 The Engineeering Support Manager The Engineering Support Manager initiates an initiates an accountability for- accountability to deterwine.if all the key positions are General Office personnel. filled. , 1655 ' Referee Messagg - Siralator The file provides indication on the various plant 15-29' ' Instructor to initiate FILE: indicators of the weather conditions. RH.WE3.3 to simulate the meteorological conditions. y 1655 Referee Messitgg - A Health Physics The HP will have a survey meter and will determine that 15-30 " Tech responds to the NGH to there are elevated radiation readings at the NGH along
< investigate the alarming portal with contamination on the ground outside the building.
- j. 4, monitors.
1700 Referee Message - Ine Control Room. The operators are dispatched to the RCIC room backdraft 15-31 dispatches an operator to reset the dampers to reset so that SBGT can take a suction from the RCIC room back draft dr.mpers. room. + l 1700 Referee Promot - Have the Emergency If not already declared the classification needs to be 15-32 l Director classify the events as a made to reduce the impact on all the participating i S11E AliEA EMERGENCY. groups. The late classification will be noted in the-critique if this prompt is required 1700 Referee Messaae - The Corporate - The status of the situation and any questions asked will 15-33 ' Crisis Center contacts the General be answered. Office Engineering Support Manager and asks for a status of events at the plant. ' 1700 The TSC Communicator completes The communicator has informed the offsite agencies of the upgrade notifications-to the off- upgrade of the emergency. classification so that the ! site agencies. agencies may respond as required by their Emergency Plans. t l L .
APPROX. TIME OF DAY INITIATING EVENT EXPECTED SEQUENCE OF EVENTS 1710 Referee Messaae - The Contsol Room The Control Room Operators will report the status of the 15-34 receives word from the operators walkdowns to the Shift Supervisor who will in turn inform and/or security in the plant that the rest of the organization. walkdowns of equipment are complete. 1745 E0F takes control of Emergency The Recovery Manager informs the EOF that he has taken Management. over the management of the emergency. 1750 Referee Message - OSCAR to report The TSC Rad Protection Coordinator receives the 15-35 vapor rising from storm sewer. Call information concerning the vapor coming from the storm is to be made only if operations did sewer and informs tne TSC Emergency Director. not check the CST berm valve line up earlier. The TSC ED and the Operations Ccordinator discuss where the water may be coming from and contact the Control Room to have the operators investigate where the source of the < hot water is. E
00 Referee Mssaae - The Offsite Data c;pplied to the monitoring team personnel will be 15-36 Monitoring Teams will report bar.x consistent -ith the actions taken.
the field data. 1800 Referee Mes agg - OSCAR reports the The 15C Rad Protection Coordinator informs the TSC Ef> and 15-37 results of the centamination survey initiates an action plan to deal with the contaminated in the NGH parking lot. vehicles. : 1820 Licensee, State, and NRC to confer The radiological data from the field will be s ilable at concerning the recommended this time. The data from the field will support limiting Protective Action Recommendations to tccess to the township road but not an evacuation. the Governor. 1830 Referee Messaag - Representative The General Office will be contacted by the State with 1S-38 from the State Governor's office several requests for information. The General Office contacts.the General Office for will respond to the questions. information. 1845 Conference call between the Recovery The n.anagers will discuss the sta!.as of the plant and the Manager, Emergency Director, radiological conditions on and ( R site. They will Engineering Support Manager, and discuss their short and long term goals and . strategy. Public Information Manager. O O O
APPROX. TIME OF DAY INITIATING EVENT EXPECTED SE0VENCE OF EVENTS 1845 Referee Messaae - Simulator The file provides indication on the various plant 15-39 Instructor to initiate FILE: indic tors of the weather conditions. Ril.WE3.6 to simulate the meteorological conditions. 1930 Referee Messaoe - The NRC GRADED A page announcement is made in all the facilities by the 15-40 EXERCISE is terminated. Lead Referee that the exercise is terminated. All participants to collect emergency plan records and submit to the facility lead referee. The facility Lead Referee will conduct a debriefing in their area and collect the Referee Observation Sheets. The TSC Lead Referee to contact the phone company q personnel at 3999 to restore the phone and page system to 4 normal. ~ The Control Room Referee to restore the simulator radio system to normal training status. The formal critique will be worked on 02/2P ;2 in the EOF starting.at 0900 and the critique results will be presented 02/20/92 at 12:30 p.m.
O SECTION V - TIHELINE PART C - BASIS OF TIMELINE EVENTS Section I - Security Event f e k e V-28 4
DETAILED DESCRIPTION OF SECURITY EVENT
$)1 The initial classification of the exercise is to be made based on a perceived viable security threat to the plant. The design of the scenario is that the call is a hoax, intended only to cause a mind set for the participants and the initial classification.
The strategy of the scenario is to initiate a classification not based on a plant event so that the plant poser remains at 100% for the later transient that will cause fuel damage. The security threat is from a caller at the river intake structure. An actor will actually call from the river intake so that there will be pump noise and plant page-noise in the background during the pnone conversation. It is expected that the person who handles the call at the Information Center will hear the background noise and report it when they talk with security. The call is being initiated to the Information Center to insert an additional communication step that will be required hefore the correct information to make the classification is received in the Control Room. The intent is to check that information can be communicated properly from one organization to another, The information that the Media Operation; Center uses for news briefings and releases will be monitored closely to insure that privileged information is not released as a result of the initial information flow path. When security hears the facts From the Information Center they will most likely recognize that the call is ccaing from onsite and classify the event as very credible. Security will call the control room and inform the shift supervisor of the phone call to the Information Center and initiate a comparable security condition, The Operations shift supervisor will classify the event as an UNUSUAL EVENT. During emergency training, it has been agreed as a precaution, if a UE type security event is declared, the Shift Supervisor will activate the TSC. The TSC activation at a UE is to support possible walk downs and equipment checks. It is assumed that the exercise will play out in this manner. If the TSC is not manned, it will not be prompted at this time. Note that the information from the River Intake caller to the Information Center does not specifically mention a bomb threat. The caller will talk about a radioactive release occurring, but will not talk about the mechanism. The sketchy information is to require the Operations and Security Shift Supervisors to discuss the situation and come up with a collaborative decision. l The classification will be based on the EAL, (16) Security Event, which . j states: (s V-29 l l
EAL #16.1 (A or B) A. A report from secarity of a security threat, attempted entry, or attempted sabotage of the owner controlled area adjacent to the site, or B. Any attempted act of sabotage which is deemed legitimate in the judgement of the SS and affects plant operation. The Operations Shift Supervisor will key in on the first few words of A.: "A report from security of a security threat" and base the classification on this portion of the EAL. It is expected that because of this security threat, the entire emergency response organization will view all future plant events as security related until proven otherwise. Because of this expectation, a call will be made by the original actor, after the major plant t*ansient, telling the organization that the call was just a hoax. It is anticipated that if the sec rity threat is not cleared to a certain extent shortly after the plant transient, it will be difficult for the referees to control the extent of play and provide the required information/ support that would be expected to come from external agencies. O
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O I s
- i SECTION V - TIMELINE PART C - BASIS OF TIMELINE EVENTS Section 2 - Offgas Explosion e
1 i V-31
. _ - - - . . -, .-- . . . -- ._ ., . _ . .._..- _ , ___ .. -.~-
DETAILED DESCRIPTION OF 0FFGAS EXPLOSION
- The offgas explo'sion has two purposes:
e upgrade the emergency to an ALERT level and, e initiate the EOF and General Office responders WITHOUT changing plant power level. Because of recent industry events and public response in the vicinity of Susquehanna the emergency response organization is very sensitive to declaring an ALERT classification with a Unit continuing to run at 100% power. The initial response to an ALERT event is to begin a plant shutdown if not already started, to place the plant in a safe configuration. This conservative action is contrary to what is desired for this particular scenario. The intent of the scenario is to have a plausible plant transient that causes reasonable fuel damage. For this to occur the plant power level must begin at 100%. In addition, the different emergency levels need to be stepped through for demonstration of the various objectives at er.ch stage of activation. Refer to the attached drawings for exact location in the offgas system and area of the Rad Waste Bailding where the explosion is to be depicted. (Inlet HEPA Filter 1F301 isolation valve HV17102A.) The ignition will be manifested in the Rad Waste and Main Control Room by several alarms coming in which indicate flow and pressure perturbations. In addition a call will be made to the Rad Waste Control Room by an actor in the building indicating that he has heard some kind of abnormal noise. The information passed by the actor will hint of an explosion or water hammer type g event. The offgas explosion is the result of problems already identified in the initial conditions concerning the recombiner. Tho water and the H2 analyzer discussed in the initial conditions are indicators that the system is not working properly. The offgas explosion occurs 45 minutes after the call to the Information Center.- The scenario is written such that the explosion in the offgas system is not severe enough to cause a loss of vacuum or major damage to the plant and will require investigation to locate. The responders will have an inclination that there was an explosion in the offgas system but will have to look for it and will most likely tie it to the previous security event, thinking that a bomb caused the explosion. The scenario intent for this port bn is to make the offgas problem difficult to find. If it is immediately obvious to the operators that an offgas explosion has occurred they will begin shut down of the plant. If and when the location and exact nature of the problem is determined the plant staff should be comfortable with keeping the plant at 100%. It is expected that the organization will increase it's vigilance and activate the V-32
TSC if it has not already been activated along with the EOF and General O Office. V About 15 minutes after ti.e offgas indications, another alarm will be received in the control room indicating a release from the Turbine Building Vent, which is offgas being released from the leak in the Rad Waste Building, (The Rad Waste Building ventilation discharges to the Turbine Building stack.) The radioactive release will not be large, less than Tech Spec limits, but enough to cause an alarm in the control room and another reason for activation of the TSC, EOF, and General Office if not already activated, and probable classification at the ALERT level. If classification to the ALERT level is not implemented at this time it will not be prompted. Activation of the facilities will be ptompted if necessary. A gentle prompt wili be initiated by the Vice President of Nuclear when he calls the Control P.com or TSC E0 and asks if the EOF has been manned. The VP is a quasi referee / controller serving to prompt the emergency organization to activate the EOF and General Office. If the ED does not act as a result of the discussion with the VP, a specific prompt will be issued by a referee. There is the possibility of two ALERT classifications, one is an explosion on site which affects plant operation (offgas event), the other a security event where there is damage onsite (assumed bomb planted in offgas). The c'fgas explosion affects operation since 15 minutes after the first offgas q indications observed in the Control Room, there will be an alarm indicating g elevated releases out the Turbine Building Ventilation, it is expected that even if an ALERT classification is not made at this time the TSC will be manned due to the release from the Turbine Building ventilation. There are two mechanisms Oy which the TSC may be manned during the beginning of this exercise. The first is the assumption that the TSC will be activated before it is required by procedure, during the security event. The early activation of the TSC will have no bearing on how the exercise is played out. The second chain of events that may occur is the classification at the ALERT or arbitrary manning during the offgas event to orovido additional support. If a classification is made it will be based on the EAL, ONSITE FIRE /EXPLUSION which states: (1 and 2) Explosion damage to facility affecting plant operation, determined by:
- 1. Direct observation or notification received by control room operator.
and V-33
- 2. Shift Supervisor evaluation.
OR g The classification will be based on the EAL, (16) Security Event, which statas: EAL #16.2 (A or B) A. A report from security that a security compromise is at the site but no protection of protected areas has occurred, or B. Any act of sabotage which results in an actual or potential substantial degradation of the level of safety of the plant as judged by the shift supervisor / emergency director. By 1645, the time of the next plant event, the E0F and General Office personnel will be responding to activation of the facilities. The TSC will be activated and the declared emergency level MAY OR MAY NOT be at the ALERT level. The next plant event " heals" the offgas release and problem. The plant transient which occurs next causes a closure of the Main Steam Isolation Valves and a loss of condenser vacuum and offgas system isolation stopping the source of the leakage. If the organization has not determined where or what the problem has been with the offgas system by the time of the next event, it will appear that the problem corrected itself, t l l V-34 l l l
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a . - O\ SECTION V - TIMELINE , PART C - BASIS OF TIMELINE EVENTS Section 3 - Turbine Trip / Fuel Damaoe V-38
=
DETAILED DESCRIPTION OF FUEL DAMAGE TRANSIENT Q V The intent of this portion of the scenario is to cause fuel damage to set the stage for the radioactive release from the plant which occurs at 1630. The transient is basis for classification at the Alert level if the station has not yet declared an ALERT. At 1545 the plant transient starts with a Turbine Generator load reject initiated by the simulator instructor. A turbine trip results from the load reject but a preblem in the electrical control circuit-of the turbine prevents an electrical trip and a mechanical trip is activated as a back up. In addition a turbine stop valve and control valve stick open on the turbine trip which allows an overspeed condition. This sequence of events involving the turbine causes a large pressure and power transient along with an overspeed condition. The reactor power excursion causes fuel damage and Main Steam Isolation Valve closure on high radiation levels in the steam lines. The turbine trip will cause the reactor vessel level to shrink. The operators will start RCIC injection to the vessel manually, HPCI will start automatically, a containment isolation and SBGTS start will occur. Stated in the initial conditions, a valve problem exists in the HPCI system which will allow a water hammer event to occur when the HPCI turbine auto starts. The line break causes CST water to leak into the CST berm area and a small portion of the RCIC discharge, while it is running, will leak via the broken HPCI line into the CST bers. n fV) The leakage into the CST berm will not be re Mily observable in the Control Room. Shortly after the break occurs a call will be made to the Control Room
.by a simulated worker in the CST berm area reporting observed leakage from one of the pipes. The operators will dispatch an operator to investigate and learn where and what is broken during the investigation.
Referring to the attached diagram, note that the brr, ken portion of piping is shared by the HPCI and RCIC system and this common pipe enters the CST at the 50% level. The level in the CST will-drop to the 50% level as a result of water flowing out of the break from the CST. Water will also flow out of the break when RCIC is in service due to the test return line isolation valve leaking by at about .5 GPM. Normal operation of the RCIC system in this plant configuration will be a suction from the CST and discharge to the Reactor Vessel for level and decay heat control. The normal valve line for this configuration should not be changed. If_the operators decide to change the suction from the CST to the Suppression pool, the radioactive water from the suppression pool will leak by the closed test return valve into the CST berm area causing a potentially . significant radiological problem to the environment. The activity of the suppression pool water is a factor of 10E3 higher than the
- CST water and would cause concern if it started leaking into the environment.
V-39
The responders will be given a success path for this portion of the scenario. IF CST Bwm sump drain, valve line up, is checked, the responders will be advised that the isolation valve to the storm sewer is slightly open. The responders will be allowed to close the valve and no wt.ter will leak from the berm to the environment. If the valve line-up is not thought of and not checked, water will leak to the storm sewer and be addressed by the EOF at a later time. The classification will be based on the EAL, (3) FUEL CLADDING DEGRADATION which states: EAL #3.1 (A or B) Core degradation indicated by: A. Valid Off-gas Pre-treatment monitor High-High radiation alarm annunciaticn on panel OC651 or indication on panel 10600. or B. Reactor Coolant activity greater than 300 pCi/cc of equivalent I-131, as determined by sample analysi . or C. Valid Main Steam Line High radiation trip annunciation or indication on panel 1C651. or D. Valid containment post accident monitor indication on panei IC601 greater than 200 R/hr. Approximately 30 minutes after this transient takes place the organization should understand the plant status, identify the additional EAL of Fuel Clad Damage, initiate a plant cooldown, complete notifications, .md determine the amount and type of fuel damage. V-40
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e O SECTION V - TIMELINE PART C - BASIS OF TIMELINE EVENTS Section 4 - RCIC Steam Line Break V-42 l
DETAILED DESCRIPTION OF RCIC STEAM LINE BREAK
/ .
'The RCIC system willLbe in service after the plant transient to maintain vessel-level and remove-decay heat. At 1630 the turbine will start to oscillate and then'go into an overspeed condition trip.and cause a steam line break. The steam-line break pressurizes _the room, blows out the room blow out panel, and an unmonitored/ untreated release begins.
Indication of a steam line' break will be received in-the Control Room as a
~
result of multiple alarms and indicators showing the problem. Security will receive an alarm from a tamper switch on the RCIC room blow out panel indicating a loss-of- integrity. Security will investigate the tamper switch, ops will investigate the RCIC ? room. The Control- Room will gather the information from the operators and from security and deduce there is leakage outside the Reactor Building.
.When the Control Room determines that there is leakage out the side of the
- building .they will begin depressurization of the vessel to decrease the motive
. force of the release.
By having an untreated, radioactive release going out of the building, the amount of: leakage and fuel damage recuired to drive the emergency organization becomes very real and no artificial constraints have to be placed on the operators-in the Control Room. The organization will monitor the. plume direction and determine if protective action recommendations.will be required based on the information received from the field and the source term (containment radiation levels). The classification of the emergency will be based on the EAL, STEAM LINE BREAK, which states: l '. Failure of RCIC steam isolation valve HV-F008 and HV-F007 to close, indicated by position indicator on Panel 1C601. AND 2.. (a-0R b OR c OR d OR e OR f)
- a. RCIC steamline' pipe routing area high temperature annunciation on panel IC601, or indication on panel IC614.
OR
- b. RCIC equipment area high temperature annunciation on panel IC601 or indication on panel-1C614. -
OR
- c. RCIC steamline high flow annunciation on panel IC601.
V-43
OR d, RCIC steamline tunnel ventilation high delta temperature annunciation on panel IC601. OR
- e. RCIC turbine exhaust diaphragm high pressure annunciation on panel IC601.
OR
- f. Other indication of steam leakage from the RCIC system.
The radiological portion of the scenario will not be of a magnituse to cause major problems to the general population. The release will be significant enough to have to be dealt with on a very local level at the site boundary. On-site problems will have to be dealt with and action plans deceloped. The storm sewer may become an issue, the North Gate House (NGH) Parking lot and the vehicles, ano the people being evacuated from the site who would normally leave via the NGH will have to be addressed by the E0F. It is expected that a discussion of whether or not a General Emergency classification needs to be made based on the contam.ination and dose at the site boundary will take place. The scenario is not designed to go to a General Emergency classification but still be challenging and as real as possible for the participants. V-44 l i
79 O 4 6 SECTION VI - INITIAL CONDITIONS PART A NSAG DAILY REPORT s VI-l
PP&L NUCLEAR SAFETY ASSESSMENT GROUP SUSQUEHANNA STEAM ELECTRIC STATION DAILY REPORT DATE: 02/19/92 Report period: 0800 hrs 02/18/92 to 0800 hrs 02/19/92 Unit 1 Plant Parameters: Diant Condition 1 Power 100% Megawatts Gross 1092 Total Core Flow 96.4 Million lbs/hr Primary Coolant Conductivity 0.15 umhos/cm HP Condenser Backpressure - 2.2 in. Hga Offgas Pretreatment Rate 81 pCi/sec Flow - 14 scfm Number of Control Room Alarms Lit - 10 Unit 2 Plant Parameters: Plant Condition 5, Refueling Resctor Coolant Temperature 104' F. Reactor Cavity Flooded. Reactor O vity to Fuel Pool Gates Removed. Unit Common Plant Parameters: Number of Control Room Alarms Lit - 5 Major Work in Progress / Completed and Problems Unit 1: O
- 1. lne Unit 1 off gas recombiner has been found to contain water. The current plan is to swap recombiners Wednesday night during down power to support Thursday investigation. (0130 mtg., Unit I log)
- 2. The HPCI quarterly surveillance acceptance criteria for discharge pressure / speed / flow could not be satisfied by a relatively small margin.
With the flow controller at 100*. demand, speed would not increase above 4000 RPM. The system was out of service (LCO entered) for miscellaneous valve work. Investigation following the surveillance identified a null voltage setpoint drift on a regulating valve (EGR). The valve receives a signal from the Electronic Governor Module (EGM) and has a null voltage setpoint of 0.8 volts. The measured setpoint was 2.4 volts. This problem is being worked around the clock until the LC0 ir cleared. (S00R l 92-032 & S log)
- 3. Reactor Power was reduced to 98% at 2003 hours Saturday night. Main Turbine valve testing was performed. Special 1&C and GETARS testing was performed to troubleshoot the sticking bypass and #2 Control valve. 1&C to investigate EHC Wed night and chcage nut two cards.
(Unit I log, 0730 mtg) VI-2
- 4. E&S to pull the cooling tower screens to check integrity Wed night when 1&C investigating EHC. (0730 mig.)
- 5. At about 1000 Tuesday morning, the A instrument air compressor tripped.
The B compressor was in standby, but it also tripped. The loss of instrument air procedure was entered, lhe instrument cnd service air systems were crosstied. When an operator reset the B compressor trip, both the A and B compressors started. Instrument air system pressure dropped to a low of 72 psig. The system engineer was contacted. (S00R l 92-029 Unit I log)
- 6. 1&C continues to investigate level oscillations in the 'C' feedwater heater string. (0730 mtg, Unit I log)
- 7. Main Generator field grsund current is increasing slightly. This mornings reading was 2.8 milliamps. (0730 mtg., tour)
- 8. The 'B' RHR loop quarterly flow surveillance was completed. The 'B' LPCI injection valve is leaking back into the RHR system causing the system to 1ressurize. (Unit I log, 0730)
- 9. The 'B' containment instrument gas compressor is out of service for preventive and corrective maintenance. (0730 mig.)
Major Work in Progress / Con.pleted and Problems Unit 2:
, 1. Core Cooling Status Boara (0740 02/18/91)
( Electrical - All AC available.
- All DC available.
ECCS - Core Spray 'A' and 'B' L,0ps. RHR -
'A' RHR pump.
Alt. - Ul " system. OPDRV None Notes Reactor cavity flooded / fuel pool to cavity gates removed. Fuel pools crossticd via the cask storage pit.
- 2. Fuel loading was completed at 2241 hours last night. Core verification has also been completed. (Unit 2 log, 0730 mtg.)
- 3. Logic system functional testing of RHR Division !! per SE 249 002 was completed. Division 11 will be declared operable and placed la shutdown cooling. (0730 mtg.)
- 4. A small fire occurred in the drywell at about 1830 hours last night. A small bag of rags was ignited due to welding in the area. The workers stomped out the fire and moved the smoldering rags to the decon room where they were wetted down. The fire caused no damage and no fire suppression systems were activated. (500R 2-91-200)
VI-3 l
i
!, . Five of the eight main steam relief valves tested at Wylie Laboratories failed to meet the + or 1% tolerance. Three valves lifted below their &.
setpoint and two lifted above their setpoint. (S00R 2 91-198) W
- 6. The problem with the RHR F024B full flow test valve not closing fully is l not resolved. (Unit 2 log)
Major Work in Progress / Completed and Problems Unit: Comon
- 1. The 'C' chlorine evaporator work was completed. (0730 mtg.)
- 2. Radwaste chiller and Zone 111 chiller restorations are in progress.
(0730 mtg.) Short Term Schedule - Unit . Repair feedwater heater level control valves. Power reducti?n scheduled W6u. night. Short Term Schedule - Unit 2: Continue outage work, hSAG Management Attention: None Richard Henry Mdre Dominauez Written By Reviewed by 0 l l l VI-4 l
i i O l l i 4 l l l I SECTION VI - INITIAL CONDITIONS O PART B - PRIORITY LISTS 1 l l l l l l l l 1 i e l l l 0 VI-5
-. - . . ~ . ..-- - -. _ _ _ - _ _ - _ - . .
4)AANN4 b } m '
.... E t
= 1 i
PRIOR 7P LIST 02/18/92 TIG$ R . W 1? $2 UNIT 1/C00 MON / UNIT 2 EIORITY 1.IST UNIT 1 HPCI PLAN
'A' RX BUILDING CHILLER PLAN g
UNIT 1 RX BLDG IN-LINE PROCESS TIE-IN PLAN UNIT 1 TURB BLDG IN-LINE PROCESS TIE-IN PLAN
~
' A' RnMU PLAN AUX B0ILER PLAN SURV 1/DWL3A REPORTS APPROVED:
UNIT 1 0 UNIT Z @ LWJ
- VI-6
l UNIT ONE ! l
.EfilORITY UST FROM 02/18/92 THRQUGtLQ2/19fD2
. 'AftQuHnIHE-CLQQLWQRK'
- HPCI MAINT WORK. QUARTERLY FLOW SURVEILLANCE TO FOLLOW COMPLETION OF WORK.
- 2. EXIINDED_HQ.Uf13_WQBK'
'A' RX BLDG CHILLER OOS (SEE ATTACHED PLAN) RESTORATION FRI.
- 3. ' NORMAL HOURS WORK" RX BLDG UNIT I IN LINE PROCESS PROJECT - PLAN ATTACHED.
TURB BLDG UNIT 1 IN LINE PROCESS PROJECT PLAN ATTACHED.
'A' STATOR COOLING HX PM'S (WKG E&SM ECD 02/22).
SUPPRESSION POOL CLEAN UP PP 1P229 OOS TO REPACK PP (WKG MM ECD 02/21).
'C' RFPT LO COOLER 1E118E CORR MAINT (FRl MECH ECD 02/20).
'B' CIG COMP PM'S (WKG - MECH - ECD 02/21).
REMOVE 683' ELEV WALL AND fi70' FLOOR PLUG IN THE RX BLDG TO SUPPORT TRANSPORT OF ROOM COOLERS (WKG E&SM ECD 02/22).
- 'A' CRD PP MAINT. P12592, P12769, S14376,514273, S10273 - (WKG MM LEAD -
ECD 02/23). O - UNIT 1 CENTRIFUGE OOS TO REPAIR PCV (WKG MM - ECD 02/19). TURB BLDG SUPPLY FAN 1V101B OOS TO REPLACE BELTS AND AllGN FAN (THURS MM ECD 02/23).
- 4. ' PROBLEMS UNDEH REVIEW
- UNIT 1 RECOMBINER H2 ANAL LOW FLOW ALARM INVESTIGATION (SYS ENGR LEAD). CURRENT PLAN IS TO SWAP RECOMBINERS WED TO SUPPORT THURSDAY INVESTIGATION.
'C' FEEDWATER HEATER STRING LEVELS OSCILLATING (l&C LEAD).
- 5. ." CHEMISTRY RELAYED PHOBLEMS/ ASSOCIATED WORK ACTIVITIES * ,
- NONE
- 6.
- GENERAL *
- ADD NITROGEN TO UNIT 1 CONTAINMENT WED APPROXIMATELY NOON -
(OPS /MM). LPRM CALIBRATIONS FOLLOWING ClG WORK FRIDAY 0600 (RX ENGR / OPS). INVEST 8NTO VARIOUS OFFGAS RECOMB CONCERNS UNDERWAY (TECH LEAD). ( PLAN UNDER DEVELOPMENT. VI-7
UNIT COMMON PRIORITY LISI_EROM _02/1s/92_ItiRQuGli.02/_19292
- 1. 'AROUND-THE CLOCK WORK'
'B' CS CHILLER Y STRAINER CLEANING (TUES EASM ECD 02/20). h
- 2. ? EXTENDED. HOURS"
- NONE
- 3. NQRMattfDuftS_RQfitC
- 'A' AUX BOILER POST POST PMR TESTING TO RESUME AFTER CONDUCT ;
I METER RESOLUTION AND COMPLETION OF MOD TESTINGl 'B' BOILER WORK TO FOLLOW. MISC. ARM PM'S (WKG l&C ECD 02/22). SIMPLEX PANEL OC551 PWR SPPLY CORR MAINT (WKG l&C ECD 02/19). CARDOX REFRIG COMPR INVEST / REPAIR (WKG ELEC ECD 02/18). D/G JACKET WTR DRAIN TANK OT597 LINER REPAIR (WKG E&SM ECD-02/20). C1 D/G AIR COMPhESSOR/ DRYER PM'S (WKG MM ECD 02/20).
'A' RWMU AND INTAKE PLAN (BOP TEAM LEAD) ATTACHED.
- SBGTS FAN INLET DAMPER 52B ACTUATOR REPAlR - RESOLVE FUSE LOCATION ISSUE SYS ENGR LEAD.
- CENTRAL ACCESS AND CHEM AREA REClRC FAN OV105 OOS TO CHECK BELT TENSION (WKG MM ECD 02/19).
- CHEM LAB FUME HOOD EXHAUST FAN OV106 OOS TO CHECK BELT TENSIOP' (WKG MM - ECD 02/19).
- ACCESS CONTROL AREA GENERAL EXH FAN OV113 OOS TO CHECK BELT TENSION (THURS MM ECD 02/20).
- 4. . PROBLEMS.UNDER REVIEW"
- NONE
- 5.
- CHEMISTRY.RELATED PHOBLEMS/ ASSOCIATED. WORK ACTMTIES"
- NONE
- 6. ?RADWASIE. BELATED _EBQBEMS/ ASSOCIATED WORK ACTMT1ES" WASTE SLUDGE PHASE SEP DISCH PUMP OP332 REWORK (WKG MECH ECD 02/20).
LRW EFFL FLOW RECORDER INOP LCO (WKG l&C). LAUNDRY DRAIN SAMPLE TANK PUMP OP319A REWORK (WKG - MECH /E&SE . ECD 02/20).
'B' WASTE MIX TANK AGITATOR REPAIR (WKG E&SM - ECD UNDER EVAL).
- 7. " GENERAL" l
'B' CREOASS MONTHLY SURV WED (OPS) 'A' SURV THURS.
l - SE-054-006 WED 0800 9SYS ENGR /E&SE). l VI-8 _ __ _. _, _ _._ - _ _ _ _ ._i
UNIT TWO PRK)RITY QSIIRQM 02/18/92 THROUGH _02/19f.92
- 01. 'AHOUND-THE-CLOCK YLQBE
- SEE OUTAGE PRIORITY LIST
- 2. *EXTENQED_HQMRS-WORE
- SEE OUTAGE PRIORITY LIST
- 3. ! NORMAL HOURS WORK'
- SEE OUTAGE PRIORITY LIST
- 4. 'P3QB1. EMS UNDIB_BEYlEYC
- SEE OUTAGE PRIORITY LIST
- 5. "QHEMLSTRY REUEED PROBLEMS / ASSOCIATED WORK ACIDUI1ES'
- SEE OUTAGE PRIORITY LIST
- 6. " GENERAL" ;
- SEE OUTAGE PRIOhiTY LIST O
V1-9
O SECTION VI . INITIAL CONDITIONS PART C - OPERATOR TURNOVER SHEETS O
=
l VI-10 h
UNIT SUPERVISOR TURNOVER SHEET YS/9/9t- Atuchment G AD.gA.003 Date Revision 9
. SHIFT N00 to _0'700 SHIFT to Page 64 of 74 SM Eno su gg I
UNIT UNIT I CONDITION / .. CONDITION POWER LEVEL _ /00 % POWER LEVEL OENERATOR OUTPUT /09/ MWe
- GENERATOR OUTPUT MWe
\
l REMAMKS: UNIT / 4' i) -Hr cr an, ator w e,1 c cr ~ st e r Toc n, v e m7m~7 nw e c ~,n. t M tey A' 76 re m V5 j m y m *7 ers74rr. Tar >As e ~ 4 ; <u n <r r a,7 h hemiter mrse tec t r a e
- , t%durrivut, - o ne r e nina s
A 'C ' Ce est wsren +1rere S % Levets e sea sri a 3 Sh 2ta c o Omek%s sL ecc . *rK' Lul > M r rtG A OM < A / % /A rt
/ /
C) 7m' a a tts dr ug ofe r o 101 D e s er c lo sec e s?t t- MsreL ~ b (m c h CArek" ul o/6- (? rce b Co rt tJ A rtir eveni 4 h o urrs
- 0) v, NPc.r 7 /eo dear?eg. fis a saaro es -<xr n sn T ,o ~ bien ~ . 7%
___ Test 17 ETu rin LiNc 0 A lun . E/ee m o s0 To cLecX COMMON D .Sim picy nawrl Po .a rn h mWw
$ 'N b y 6i,len rieds
- 3) Lea err ffw I?rtmete mop
- . /% PWs
, d 58c,7 m/er o%o cir 5.26 A M70o w~r l - l P.,. aa na mie, w e. oveux. % i r e tree w e . Vl-11
W &_1. Q0 - M *' 9 PLANT CONTROL OPERATOR T
~
VER 5 UNIT / n , ET $6 EI Revision 9 D ate _ d "/4 'M Page 68 of 74 SHFT 1900 to,_0 700 __ gggy 0700 Start Er4 to_1900 Start E.nd Ct. ANT STATUS (AT TURNOVER) CONDITION - PLANT STATUSJAT TURNOVER)
/
POWER LEVEL CONDITION
'00 A _%
GENERATOR OUTPUT /090 POWER LEVEL - MWe % TOTAL CORE FLOW W4 GENERATOM OUTPUT
.M bhr TOTAL CORE FLOW MWe QX PRESSURE 996 CEMARKS; -
PSIG RX PRESSURE M eshr UNIT REMARKS: PS10 UNIT i e ! L C o 's
- HPC2" ~ L P Ld Clo u l?' cS CL /fu-EQuop co r, ? H Pcr *A' W A cL ite or A s tArve cte h_ i Sur rc,o t % pp l
'C ' l'rt L O cit'.
A c3 4' ctp pp
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$7q,a- o se staa r.aq A W
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$ 2 4 tu Sa e k'a ra s t Pr? g on aa Td t el u n e tr A s ne e - 73 A r 8 ' e~ ' A';w f) 8 J7Hi? p s n m ,e i t i .J a HP ?r L t c> <* /e n sert rt.' *s se <**> -, tr ie
<wi ve s T a via - *Tn T Pe rs <~
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- a h' COMMON Eq u , s nos S'CS ct,, t tr or A nuv !% /e e 3i~olvv Ih mi (httOY cem p, f tm ! n k 5~*1*J . Aftt?+ fe ri!**st !"L l '+:
[ kl 9"
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- 1) G1 A M- ? !, $a r Ph ns e See Pi sea ?' d y We y Ca r'*, .1 cirAns*0 L%) fA l $f
- l N .$ $ O$W , S UD as fY$ lA) @ L,0 } Y Popne nSouest, no 9. twuct, Pese 1 et 3 (Pts femmes AS4 YI-12
l PENNSYLVANIA POWER & LIENT COMPANY SUSEUEHANNA SES 1 Attachment A UNIT 1 AD'0^~303 O SYSTEM AND EQUlPMENT Revision 9 page 35 of 74 STATUS , 2/nh1 ante Shift SHIFT INITIAL CONDITIONS Power Level (MW tn) D93 Shift Responsible PCO Conditen / Additional PCO , Mode Sw.tch Positen 8HN Completed by Reviewed by (unit supennw Reviewed by (SMt Swowviwi 1C648 SYSTEM STATUS PMOSLEMS & COMMENTS ggg . . . . . . . . . . . . . . . . . . . j l f g i g y) l yngyll gyto { hydraulic fluid Do A i i Vi ' v' hydraulic fluid Do 8 i v~ t -i > filter oo I 1 v* ; J turt>ene vapor extr I V! I I STEAM SEALING * * * * * * " i I/S ' avt ' unavt Decking exhauster A ! I V! Deckinc exhauster 8 i Vi i main steam supoly ! V"i I aux steem supoly I i Vi CONO DEMIN " * ' " ' ' ' i I / S i S / 8 ! unavt l recyl cond domin A i /I t I cond domin 8 I v' i i i cond domen C ! /t ! cond domin D I /I i cond domin E / 1 i cond demen F _ / l l cond domin G I V j i MIN PLOW " " " " " " " outo men unevilGPM FV 10508 t
. RPPT AUX " " ' "" " " 1/3 avt lunavil auto tuming Qear A Vj l tuming geer 8 /i i tumina oeer C v i A mn t.4 00 A /
A mn L4 00 8 7 8 mn L4 00 C V V 5 mn L4 po O C mn L4 oo E / - 'E' Cte oos C mn CD co F / A vapor extr / 8 vapor extr v ( C vapor extr p-t VI-13 P4 acsousu. now. e. Dupum. Pues t er ia
Attachment A AD-CA-303 Revision 9 Page 36 of 74 1cass SYSTEM STATUS PRO 8LEMS & COMMENTS OFF gas " ' " ' ' " ' ' " " 1/S avi unavi main aux SJAE t- r. MVP v< CIRC W ATER * ' * " ' " ' IIS avi unavii min full Dump A V V pump 8 7 V! oumo C V' ' , vi Dump D i 71 > i SERVICE W ATER ' 1/ S . avt iunavh auto ! Dump A V ' DumpB + 7 i /' oump C v ggggg eeeeeeeeeeeeeeee gf g i gyg yngylj pump A > Vi i Dump B i 7"8 TBCCW ' " " ' ' " " ' ' II S i avl t unavli pumpA i 7' I i Dumo B r: IN S T AIR * ' " ' ' " ' " Auto s unavt! comDressor A i V' I compressor B V. j dryer A i /1 i dryer B 1 vI I dryer C t r1 i SERV AM " * * * * * * ' "" ! Auto l unavi compressor A } v compresect S I V
= ,
O porm mana. me, s.'ourux. Pooe a w tt VI-10
f Attachment A (~ AD-CA-303 t Revision 9 gg7g Page 37 of 74 SYSTEM AND EQUIPMENT STATUS 1C051 SYSTEM STATUS PROBLEMS & COMMENTS ; R WCU ' " ' " ' " ' ' ' ' I/S ave unavlj pump t, 7 i pump 8 v+ fdter dem A v ; filter dem 8 V CONOGNSATR """"' ! IIS i avl 'unavit pump A i vi t j pump 8 v i ; pumpC !ui i oump D v ' i gpp7.................. l/S i avl 'Unavis auto i man : turO/ Dump A V! + 1 V j ture/ pump 8 v> v j turd / pump C ' p i i v! l
\
low load bypass DC L4 og A l
/)
1 y v
*P)
OC L4 pp 8 < vi r, DC L4 op C t i ei 4 RX RSCIRC ' " ' " ' " ' 1/ S avi unavli dnve motor /pp A ! Vi , onve motor /pp 8 i ui i RSCIRC AUXILIARISS '" i 1/S I avt lunavit auto - vent fan A - I v' l !
~ vent fan 8 i v i I AC L O pp A 1 i Vl i AC L4 00 A 2 i I VI AC L4 pp B 1 V i AC L4 pp &2 u*i DC L4 pp A V. I DC L4 op 8 i I Vi .I I
RECIRC CONTROL'""" I auto I rnan ' controller A -l V fl % Speed
~ "~
controller 8 tr: 4 % Speed t p p m aa = a.me.e.oustax.Pese e in VI-15
Attachment A
'AD-QA-303 Revision 9 W
Page 38 of 74 l 1C851 i SYSTEM STATUS PROBLEMS & COMMENTS l SYPASS SWITCH POS norm inst Oyo
- list Cypassec instrument in inst coiumn RBM AiB / ' '
i APRM A/C/E 7 <* I flow A/C y* tRM AICeE/G v .* APRM SIDIF v i' flow S/O ' vf* i i ! IRM 8/0/F/H v i' SRM A/8/CIO V i Rucs " * * * *
- I sis auto BiP l ineo ! sip i RWM -
i W! RBM W I i RSCS p , list rods bypassed MAIN TURS EHC "' ' A i B i pressure set in control 4 v$ > M AIN TURS * "'" ' 1/S i avi i unavli lift pumos i i 71 i auto j turning gear i i u pi OIL SYSTEMS "'"'"' 1/S i avt unavli auto i lock i TOOP i I vi V 1 Mn L O suet pp i i v! iv! l EBOP I i wi i ui ESOP i i i i ei GEN EXCITATION '"' I auto man voltage regulator i ,7 O VI-16 r,mi Acca.ama. n e. oveutz. Paes 4 or is
Attachment A AD-CA-303 : O UNIT 1 Revision 9 Page 39 of 74 l SYSTEM AND EQUlPMENT STATUS 1C601 SYSTEM STATUS PROSLEMS & COMMENTS cao"'"""""""" iis avi unavn pumo A gr i pump 8 p j.;?g6.W) //p flow Contr A ya i j l flow contt 8 p . o gc.i(4he s S SL C " " " " ' ' " " " ' souib continuity let out squit A i 7i i i souee 8 i 71 i , i D/W PLOOR SUMPS avi ! i unavi t sump A pump A vj l i sumoApump8 vj i i sump 8 pump A i vj i i sump 8 pumo B 2 v> ' 6 b . RCtureloump C ' ' ' ' status ' ' ' ' ' ' ' ' ' ' ' ' i' ' < 1/ iei S . avt l unavn RCIC control ! GPM ) auto i man ! controller i* ; 7j i ' tape setooint value L3f GPM l unavil C0AS cump A SPAAY Div i ""' , IIS i ,7 avt pump C ' -- RMR Otv i " . . . . . . . . . . . ! '# d pump A ; 1 *g ! *"**' _ pump C i RHR SW Div I" " . . " " IIS a( unavi pump A 7 A OS " " " ' " ' ' ' " ' " " " ave unavt system VI SPCTMOS ' ' ' ' ' ' ' ' " ' ' ' ' 1/S iunavi gg'em A V system a w I M88V STATUS WOMT'"" ist off light indicanon u 7;p.................... e g open vaNo indicaten v"i , O VI-17 74 anoA.aew. n e. ours.ax. Pese s e is
Attachment A A0-0A-303 Revision 9 Page 40 of 74 1C601 SYSTEM STATUS PROBLEMS & COMMENTS CONTAINMENT H,/0 3 ' Ha% i 0 % AR15746A o,y 2. o : AR157468 sys y sygy SUPP POOL FILTER PP " 1/ S avt unavt i pump ' 7' osa IN S T G A S ' ' ' * * ' ' ' ' ' ' ' auto unavil compressor A 7I i compressor B ' ' v ' oos Pat STORAOR SOTTLES * ',',,* : close ! . ;open: PCV 12643 v' i PCW12648 : - i ' CORE SPRAY DIV 11" * > liS avi unavli pumpB i y j pumo 0 i i sf ; RHR DIV li' ' ' ' ' ' ' * * * * ' 1 1/S , avt t unavtl
,umpB p , ,, i l pumpD i , 6. 4 ,
RHRSW DIV 11"""" i IIS t avi lunavt , oump B j H PCI " ' " ' ' 'T* * * * * * . j 1/ S I ave !unavi turbloump status I ; rj H PCI controi " " * " ' ' ' ' GPM i auto i man controller !' I v-i
- tape setooint value fNo GPM OOS ECCS/Bl8 STATUS" t yes i i no oos leghts tested i v~
all oca lights off ! y I *tist oos systems 9 VI-18 ionn Ammun4. % s. ouPLEx. Pepe e of 13 [
_.. _ ~ - _ . _ . . .- ._ _.- . _ _ . . _ - _ - _ . _ _ _ _ _ _ - . Attachtnent A ) AD-CA-303 {- UNIT 1 Revision 9 l l SYSTEM AND EQUIPMEM #'9' 41 f 7' i STATUS A i~~ ' ' i i T-10 l t1 A l ft1el I12Al M Y T-20 i i i 1 T susto! 4 ous2e! tt 12 u% yM _
~
$ g . __
13.8KV -Z l@ @$ __ 4- ! o A & . e o e A A A A o e e e A A le- A
.A A & o- e o .- A A A A o e o e A A A
_I
~ ~ - ~ ~ -
2A :: CPI ' 7 ' ww6_ C~1 - 7 7 7 I;;21 _ _ _G Q_ Q. .__ Q _Qww O (> mm A a g A o I te l
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. A l io l A A
[ zA l A o I re l e o l ae l e A A e u,
!e A o ltal A i A A A A A A A a b b kb r
A : T : i 4.16KV Y o _L _L w GEN t 500 KV W LEADS m SUNeURY 2 WESCOSVILLE KV U 4 500 KV UNE 7 _ , T-21 , 500KV T
--E /
8-3-* Use an "X" in the applicable boxes to represent closed breaker poortions. v Circle those boxes which represent unavadable breakers. Femi ADeA3054. Rev. 8 DVPLEE. Page 7 et ti VI-19
Attachment A AD-CA-303 Revision 9 Page 42 of 74 OC653 SYSTEM STATUS < PRO 8LEMS & COMMENTS l COND TR ANSF * * * * * * * * *
- t/S avl unavli cumoA V I
,cump B v REFUEL TR ANSF * * * t/S avl unavtl pumoA 7 -
pump B v i M AKE UP DEMIN * * * * "' 1/ S avt unavif pumo A v- j oump B Vi > Jockey op v* < A U X SOIL E R ' ' ' ' ' ' ' ' ' ' ' ' IIS ! ave unavli boder A V j boder B i i vt i . RIVER WATER M U "" 1/S i avt unavtl pump A ,
/ } oos mai=f pumpB 7* i cumo C i /t i oump D i / i ESW'""""'""'" 1/ S Avi t unavtl pump A i v."' : !
! ua <*4 S P'.
oumpC i , vi i pumo B i Vi i i, L( @ Dis A #^e ss Id oumo 0 i p- , 7 DIESEL GENERATOR *"' 1 IIS i avi lunavl OG A i j v DG B , v" DG C i v'l DG O I /! 00 E I' ' /j ' If substrtuted, algned to G
.__a_...... u-w
UNIT 1 Attachu nt A ( SYSTEM AND EQUIPMENT AD-CA-303 Roision 9 STATUS Page 43 of 74 HVAC 3ystems OC681 SYSTEM STATUS PROBLEMS & COMMENTS
~
CREO ASS * * ' " ' ' ' ' ' IIS 4 avi unavi stoo S/B toad start OV101A y j ; ,, OV101B p - ESW PP HSE FANS ' I/ S avi unavli 7V521 A V JV521C / j AVy18 v /+ _OV5210 7-CONT STR CHILL WATER
- i I/S avt i unavli O*171A ,
- t. i i i OP1718 i i p i STn u st c_J , y DO SLOG VENT FAN '"" 1/S i avl + unavi!
_OV512A i ' Vi i OV512C \ V } OV5128 I i /. 7 OV5120 i i vi CONT STR VENT PAN 1/S i avt t unavi t OV103A ! I fi OV1038 i vI COMP ROOM FAN '
- 1/S avl ! unavii OV115A '
i i V! ! OV1158 i u i i
. CONT ROOK F AN "' 1/S avt t unavl OV117A I i Vi OV1178 : Vi i S ATT RM EXN ' " ' " ' ' ' : t/S avi iunavl OV116A i Vj '
OV1168 i V- I
$80T SYS EOUIP FAN '" i 1/S I avi lunavt LV116A I. / I.
OV1188 i vI SSOT RM HEAT FAN'"" i I/S I avi- iunavtl OV1MA i i vi OV1MB i i, 1 R8 RECIRC FAN ' * "'" 1/S avt lunavi stop i S/B lead i stAtt OV201A vi i Vi OV2018 ei ! i v' i
}
CNILL WTR CIRC PP * "' ! ilS avt iunave OP162A i 7'
~
OP1628 i 7 5007 SYS EXN FAN " 1 1/S avi unavt! stop S/S leed I start OV109A i V I Vi OV1098 i V i i I VI sem in n a == s. my s. ouMx enee e w is VI-21
Attachment A AD-QA-303 Revision 9
# age 44 of 74 1C681 SYSTEM STATUS PROBLEMS & COMMENTS l
DRYWELL COOLERS "' 1/S . avt unavt! 1V414A > v i 1 1V416A / 1V415A i 7 i 1V411A 7i 1V412A vr 1V413A v i 1V417A L.- ' j tv41sA . -4 , ! 1V4148 i /i i i IV4168 i vt i 1V4158 i vi . ! 1V4118 ! /I i i 1V4128 i i 7 i 1V4138 i /; i i 1V4178 i vi i 1V4188 i Vi ! I RHR PP ROOM CLR * ' * " i I/ S i avl ' unavl IV210A i i Vi 1V210C i i #I i 1V2108 ! i Vi ! 1V2100 I i Vi I RCIC PP ROOM CLR '"' i IIS avi t unavi' IV206A l Vi tv2068 i VI COR$ SPRAY ROOM CLR' 1/S avi lunavi 1V211A l V
,1V211C v IV2118 V 1V2110 Vi HPCI PP ROOM CLA * "" 11S i avi iunavt 1V209A v 1V2098 -
E MERG SW CLR ' " " '
- 11$ avl ' unavn 1V222A V '
1V2228 V' I RHR$W PP ROOM CLR 1/ S avt unavn 1V506A V 1V5068 V O VI-22 F5ne am na -a h 9, DUPGX Paes 10 et it
l Attachment A (' A0-0A-303
\ Revision 9 UNIT 1 pag. 45 or 74 SYSTEM AND EQUIPMENT STATUS Miscellaneous MISCELL SYSTEM STATUS PROBLEMS & COMMENTS RPS*"'***"*'****'* I/S avi unavi!
A gen feed v B genf.ed r A alt feed , v-B art veed - EXCESS FLOW CH ' * * * * * * * " ges , no ; all vtv open v1 ;
'G EN LOCK OU T S ' ' ' ' " ' ' ' " * *
- yes t no lockouts reset i V. i no relay flags i vt i CONT ATMOS MON "'" anal S/9 off samp zero - span i 1C6908 i V' i i 1C090A i p.- i ! i7 i IS MSIV LEAKAGE ' ' * i 1/ S avi < unavll system y, a power avad i on ,
oH i V bght indk:stes i V: ! 08 MSIV LEAKAGE '"" i 1/S avt 'unavi! system ! i ei i p Agg gyg o . ' ' " " " " " ' ! off i on isol viv permiss switch j Vl l CONT RAD MONT * * " i 1/ S I avl !unavt bwerjuoperl supo - A motor et i j Vj A motor #2 ! v' j l V B motor el i iV B motor #2 # i rI FIRE PROTECT""" I 1/S avt lunavi diesel po l Vi AC pp i /i smoke rem fan A i j 7i smoke tem fan B i i t< - I ! OC497 MOV BYP A$$ """"' yes i no switches in normal V l' U VI-23 Farm Ao4A.3034. Rev. 9. DVPLEX. Page 11 et ij
Attachmen A AD-QA-303 Revision 9 g Page 46 of 74 Miscellaneous MISCELL SYSTEM STATUS PROBLEMS & COMMENTS * ! RECOM01N ER ' ' ' ' ' " ' ' IIS ! avl unavi! unit i V4 Now Ge w e s' i unit 2 v common p ' unit select switch position unit CCW pp 1P145 i v: CCW pp 2P145 i u , CCW po OP145 i v! ~l UNIT 2 RCCS '" * '"" ! l/S avt i unavli U 2 RCIC ! Vi u1 3/o #tCa*t U 2 core spray pp A i vi 1 U 2 core spray po C I i uI i U 2 RHR pp A i ei i i U 2 RHR 00 C i p- I U-2 RHR sw po A I v, t U 2 core spray pp B i 1 V! i U 2 core spray op D , v' l U 2 RHR 00 8 ' I i j U_2 RHR pp D ! i i U 2 RHR sw op B 1 1 ivl U 2 HPCI ( !
- 1. i CROS$ TIED SYS ' * """" i no yes common S.W. from U 2 I V" CRD U 1/U 2 vi lA U 1/U 2 Vi SA U 1/U 2 - !
CST U 1/U 2 7l O VI-24 rem Ao44.m4. m.v. s. Durax. Paes ia at ta
6 INSTRUCTIONS SECTION: OPERATIONS Inst. No. 01-AL-0017 Revision 1
$UBJECT: UNIT 1 CONTROL ROOM Prepared By M> d yCm 00'a ANNUNCIATOR LOG V " "
a _ Reviewed Byt'# " d w [I Approved By . M. 'AM Data 3 [6 h d Section Head ' I Expiration Date
/ d _ Effective Date / ff !
/ l O
LJ l l l l VI-25 ! FGi'.M AD-QA-101-5, Rev. 1, Page 1 of 1 t
UNIT 1 CCNTBOL ROCH MON TUE WED TWU n! SAT s9 ANNUNCIATCR sCG 4 // ? A //t 4/M R /2 o 4m 7/ra 4/d l __N li N liN I i N Il - N 1 L_La i N j "CAUSE/ CORRECTIVE ACTICN" AR 101 10651 l r-A
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FORM 01-AL-0017 Rev. 1, Page 1 of 17 '1-26
UNIT 1 CONTROL ROCH Week Ending .7. / 17 / g ANNUNCIAICR LOG ~ 1N liN Il 4 1 l_ N 1ihj,s . g~. s b) "CAUSE/CCRRECTIVE ACTICN" AR 103 1C551 i A l i B I C !
~
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AR 104 1C651 A I i B C l t 0 i E ! 1 l ' F i l H l
< / v 4
cm Na FORM 01-AL-0017 Rev. 1, Dage 2 of 17 VI-27
UNIT 1 CONTROL ROCM Week Ending A/ /7 /$ ANNUNCIATOR LOG l N j Pll N ! N__J { 'd 1I 'd I l_i "CAUSE/CCRRECTIVE ACT:CN" AR IC, ,, n651 h A f B _ _ _ _ _ C i I E I i F - I ! G ._ I-I H 1 J . w w < O AR 106 1C651 C -IL R B riun t IL 2'C D-it TA SAnde srArzw RB Most ' It 2TX #
- n. is --
S -15 I?B SA mals STATo on f /s off 645 Oc 6 7.1 O p- is TA none te nr C n n- TT Tr . r, ,6 0
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F I H 4 O FORM 01-AL-0017 Rev. 1, Page 3 of 17 VI-2B
i 4JNIT 1 CONTROL ROOM W"k Endi"9 A#12# 3El - t' ANNUNCIATOR LOG - y ; 7y , i y j-l 3 ;y j l y j ;r "CAUSE/ CORRECTIVE ACTION" AR 107 1C501 p.c La w ds !~%
~ l A - - - a B -
C .. - t 0 - E 6 6 6 i F G g - i AR 108 1C601 O ^ B C 0 E F
- ~ ' - - - l G , , , , , , , _ _
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.- =-
n, JI ' O FORM 01-AL-0017 Rev. 1. Page 4 of 17 VI-29
UNIT 1 CCNTROL RCOM Week Ending A/ /7/3 ANNUNCIATOR LOG l N II N Il N l l N ll N i !N i ! 9 -
"CAUSE/ CORRECTIVE ACTION" AR 109 10601 I i A ig 8 _ . . . .
C ! i 0 I I E : 1
~
F l G ,_ _
.. 4
- O -
AR 110 1C601 A B i C l 0 E 9 - : u . G H ! O FORM OI-AL-0017 Rev. 1, Page 5 of 17 VI-30 ; 1
l UNIT 1 CCNTROL ROCM Weak Encing A / n/ 9.1 1 ANNUNCIATOR LOG lNliN ll N l l N 1 i N l l N i iN "CAUSE/ CORRECTIVE ACTION" AR 111 1C501
~
A [ I B i ; i I C 1 1 0 I e F i I i~ G 1
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H ! AR 112 1C601 H -r "s coc c es t i i ,
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( B C D
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E F G e e , i 4 H !! m U l I FORM OI-AL-0017 Rev . 1, Page 6 of 17 VI-31
UNIT 1 CONTROL ROCM Otek Ending ,e / iz / 92
-ANNUNCIATOR LOG l N l LN 1 l N II N !l Nj lN l iN ;
"CAUSE/ CORRECTIVE ACTICN"
]
~~
A _ l B I C ! O E l ! F G v v AR 114 1C601 A _ h ' B C I i 0 i E F i G H v s l l O FORM CI-AL-0017 Rev.1, Page 7 of 17 VI-32
UNIT 1 CONTROL ROCM Week Ending ,1/ /1/ 92 i ANNUNCIATOR LOG IN l l N l l Nll N l N] l N j j y n - kJ "CAUSE/ CORRECTIVE ACTION" AR 015 0C553 C 'lo 'A WL Os v rk C
- t .3 3' 7/c aw ft 4 A !
B l s ., - , ., a . . , C 0 i E I I F l G _,,; H j ( ! A.'l 016 0C553
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l UNIT 1 CONTROL ROCM Week Ending _1/17/B ANNUNCIATOR LCG l 4 IIN IIN IIN liN l! N U.
"CAUSE/ CORRECTIVE ACTICN" AR 117 1C668 i
Al ! B C D E F __ _ _ _ G H t - - AR 118 1C668 A B C _
.t 0 I g 1 g !
l G J H 9 FORM OI-AL-0017 Rev. 1, Page 9 of 17 VI-34 l
UNIT 1 CONTROL ROOM -Week Ending A / n /_ g ANNUNCIATOR LOG c l N l l N l- l N l l N l lTl l *J j i , ,
"CAUSE/ CORRECTIVE ACTION" AR 119 1C663 A ~
l l B . C i 0 I 1 E F - G H !
. / <
AR 120 IC663 d .10 4 c era i ts ma O A I B C , l O __ E i F G Je 70 80 i H I FORM 01-AL-0017 Rev. 1, Page 10 of 17 VI-35
UNIT 1 CONTROL ROCM Week Ending .t /_/L/,g f ANNUNCIATOR LOG lN IIN l l N ll 4 II N lLN IiN :
"CAUSE/ CORRECTIVE ACTION" AR 121 1C663 i
A I B C O I E F ! ! I i G
- I i H l !
AR 122 !C668 c, - q Ic Sir A eio cl n/n A t B __ C D E F
- y 9 ;
G O l FORM OI-AL-0017 Rev. 1, Page 11 of 17 VI-36
UNIT 1 CONTROL ROOM Week Ending 1 /j l/ g [- ANNUNCIATOR LOG 1N IIN ! lN Il N I l- N 1 i N } L{
-f; ) - (,/ CAUSE/ CORRECTIVE ACTION'?
AR 123 1C663 A B C __ 0 i i E p l l G i-I H
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AR 124 1C668 A B - C' 0 _ i
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F G B H t l
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FORM OI-AL-0017 Rev. 1, Page 12 of 17 VI-37
UN17 1 CCNTROL ROOM Woek Ending A / / 7/ 91 ANNUNCIATOR LOG IN7IN IIN l l N l l N l [N j LN i "CAUSE/ CORRECTIVE ACTICN" AR 029 QC631 A B C D
., - e AR 030 0C581 A
i B I C ,_ 0 4. ( 9 FORM 01-AL-0017 Rev. 1, Page 13 of 17 VI-38
UNIT 1 CONTROL ROCM Week Ending -1/ /9/ 92
-l ANNUNCIATOR LOG-l N l l N ] l N l l N ] l y l l y j g , 'L/ "CAUSE/ CORRECTIVE ACTION" AR 127 IC681 A
B C D
< - v AR 128 1C681 A
e : I 0 '
/ / /
i I LO FORM OI-AL-0017 Rev. 1, Page 14 of 17 VI-39 l - l l
UNIT 1 CONTROL ROOM Week Ending .R /--/ 7 / 9 3 ANNUNCIATOR LOG "CAUSE/ CORRECTIVE ACTION" AR 125 1C692 A I B
/ / -
AR 126 1C692 A j B I
~~
AR 148 1C644 8 A , O _ C 0
/ <
AR 147 1C645 1 A l 8 C 0 l O l FORM OI-AL-0017 Rev. 1, Page 15 of 17 VI- 40 l
l 1 UNIT 1 CONTROL ROOM Weak Ending ~4 / n / 9 t-ANNUNCIATOR LOG 1 lN IIN l l N l l N f l N }-l N ; l N , O . (_./ "C'AUSE/ CORRECTIVE ACTION" AR 146 1C693 i A _ B
, - v AR 045 C593 A h I
B i l C o I 0 ,
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AR 036 0C650 01- _- C/ - ! A . __
- b. ,
O FORM OI-AL-0017 Rev. 1, Page 16 of 17 VI-41
L%, .pe UNIT 1 CONTROL L ,M ANNUNCIATOR LOG - l N IiN Il N I IN ll N l l N 1l_N _ "CAUSE/ CORRECTIVE ACTION" AR 131 OC673 A B C 0 I
/ ,
AR 031 OC673 A B C _ 0i
/
(DATE) A/tr92 .2Wh a htM ah*% 2MM2 2N:L 25W PCO Nightsnift , (time) PCO Dayshift ( time) _ .. PCO Afternoonshift (time) . US Afternoonshift _ (time) e FORM OI-AL-0017 Rev. 1, Page 17 of 17 VI-42
O SECTION Vll - RADIOLOGICAL CONDITIONS PART A - 0FFSITE RELEASE DATA Section 1 - Weather and Het Data Log 4 O v u.1 1
SYSTEM WHATHER FORECAST FOR 2/19/92 UPDATE Issued: 1112 Hours From PCC WEDNESDAY: Light winds, 4-5 mph, along with falling temperatures today. A few snow showers / squalls with more than 2" accumulation possible in Hazleton and Williamsport. Clearing in the evening. THURSDAY: Mostly sunny in the morning, then increasing clouds with light snow developing west to east overnight. TEMPERATURES WINDS WEDNESDAY G 1100 0400 1100 Min Time Max Time Winds Allentown 18 22 16 0800 27 1400 SE O 8 Harrisburg/ Lancaster 19 24 13 0600 29 1300 ESE G 4 - Hazleton/ Scranton 14 19 13 0500 23 1500 SSW G 5 Williamsport 14 19 13 0500 24 1400 SE 4 6 FRIDAY: Light snow ending in the morning, then mostly cloudy. Clearing at night. Average Max. Temp. 35; Min. 20 SATURDAY: Fair to partly cloudy. Average Max. Temp. 39; Min. 19 SUNDAY: Variable cloudiness with scattered snow showers. Average Max. Temp. 33: Min. 21 VII-2
. .- . . - .. . -- - . - . . - - . . .. .. ~.-
O 1 92FESt9 OttLL MtfE000LMiceL Defe LM statest 94:53 12/tt/98 85*et#wle Averegos Upose onee4e unc6ver Seene6 wee Mode Levet Teooe feese feeee 8,4tch 15 ute avg. ===----- -~~----- -------- -~~~~~~- ~------ MRIOS PPY MIXING u!W uting u!W utup eft _ $fte TYPt $1' $2 tuttuGeese essee sees sees O.P
- e. T ..
M..(sees m ) FOOR NPWsee see sees FROR eene MPM eseF9en eeneNPW eseFROM se seMP*I to:M Go -- 1000 SM 5 39% 5 299 4 2M E 3 3 14:45 Ce ** 1948 IM $ 204 6 299 4 296 5 3 3 84:M Ge -- teet 196 - 4 294 8 299 4 2M 5 3 3 44:46 Ge --- 8000 tM 5 294 5 299 4 2M $ 3 3 IS:M Go -- 8000 IM S 298 5 299 4 2M E 3 3 15t!5 G4 == 4000 tM S 244 4 399 4 2M E 3 3 IS:M Go . -- 3000 tM S 244 5 299 4 296 6 3 3 16:46 Se == 1990 IM 6 291 8 299 4 206 5 4 to leief 4* -- 3000 - lM 4 Mt 5 209 4 2M 6 8 9* 16:3s . G* -- 1000 tM S 298 6 249 4 246 S I to 16:M Go -- ' t IM S 294 5 299 4 2M S I 9e 16:46 Ge == 1 196 6 296 4 4 2M S t to - 17:00 Go -- 4800 M S 298 6 4 206 6 t to 87:46 g
~~ 1000 )M I
g 294 6 4 2M 5 t to 17:38 -- 1400 lM 241 5 9 4 2M 5 8 to
'- 1F?45 G -= late tM 5 298 5 299 4 2M E 1 **
34;M G -- 8000 lM E 2$6 5 4 2M E 8 to lett$ G -- test 196 5 299 8 4 PM E t to 10:34 C == lett 1M E 2ot 5 4 2M S 1 to 18:46 F -- teet IM E 291 6 299 4 2M 5 4 9e 19:00 F -- 1986 IM S M2 8 980 4 6 9e 19:is i9:M r r i .M iew in iM i i 22 M2 e h. 24. 4 M.r 27 27 e i 8 i i
,o I
EXIT - to exit Sit (M, er say Function Key O VII-3 y
O l i SECTION VII - RADIOLOGICAL CONDITIONS PART A - 0FFSITE RELEASE DATA 1 Section 2 - Plume Trajectory and Plume Deposition Data VII-4 g
. f~ , LJ SELECitD FILE: Ot!LLs.92FEB19-19.es PRESENTATION TIME: 09:23 12/19/91
/
N 1- STR[A.9PUFFPLOT Puf f Locot t ons t
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EXIT - to exit STREAM, or any function Key O VII-5
O SELECTED FILET DAILLe-92FC019-19.94 PRESENTATION TIMC! 09:27 (2/19/91 y .. f ~' - ffilo E STREAM OCPOSITIONPLOT
'4- e......< a ... . .
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11 j' h 'l; UPT0: 02/19/92 MINIMUM VALUC 0F INTEREST IS:
/ /
/ 3. 3C*e3 MICROCU# ttt/M*
- 2 pg ggg
/
[ y
," DE,09ITI04 kg y / \
HA LCTON (MICROCutitt/Me*2)
'I ONYNCHA RCD E .13 AND QVER O els .42 CREEN E .S$13 .912 Exit - to exit STREAM, or any function Key VII-6 1
l
) \
U SPLECTED FILE! DPILL9-92FfB19-19.99 Og ilMC1 09:26 42/19/91 31
- 3. i . : i . .:
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27 i:; s .. .... ..... .. .. in. c,. . 25 l:! 1:! /
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/ ;;; N UP10: 02/19/92 23 N
, / ,
22 /
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MINIMUM V.4.UC of INTEREST 181 s 5 / 1.3C-63 MictoCUAl[S/we*2 28 q j 2'
,/ /y QUADRANT:NE n, l l 1, 7': / \ ouo nio ,cv
' (MICaoCURIES/ Moo 2) n
'/
< /T' t co a i2 . o ovc.
a .eis .i2 is cacc s ...is . ..i2 86 t? 18 19 28 21 22 23 24 26 26 2? 28 29 30 31 EXIT - to exit STREAM, or any function Key VII-7 _+__m
O t SECTION VII - RADIOLOGICAL CONDIT1086 . PART A - 0FFSITE RELEASE DATA Section 3 - Nobel Gas and 1-131 Releast Rate Data k VII-8
O 1 l 92f tas t es0$LC Gas N Ltalt M it THiscib6G PLDT telecoeureos per esmutea STMest 9913P iutt/94
! {
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f l.Mell j . . i ... .q p i . =* i.
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O t.9C+96 4 . GE *M t . W eed l ' M
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b h O VII-9 '
_ _ _ _ _ _ _ _ _ _ _ _ - _ . _ - - . . _ - . . _ - . . . _ _ . - ~ . - . . - . . . . - . _ . . . ~ . . .
.... .. _ - -. . .- - --~. .- ...,= .
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1 i I l I l l l l , 92fE419 100leC-131 RELtatC 9ett tegnetteG PL0f stegen p9:44 33/4t/tg ; tolereeweses per stautep ! l I : I , t.eC+et 1. eg *H 4 . M *M 8 .St+46 ] i 4.et+04 i .9C +44 } t at. Treu mere fasts? rat i t .M*83 1 9E+43 cu more e - -- rurve em s
- ~
F 1.8C+42 1. M *42 j 1.8C+48 1. M *4 8 4.0E*ee I.K+M ! r t.et-et 1.at 4 4 i' t.88-42 8 #C-42 ' $ -** '' I i . i i i i i i i iei EL.I - to exit Sil!M, w 6,.y functica Key 1 i d 9 VII-10 4 i______ . .- .... ..... .. . - - - - . ., . . . . _ , _ . .
L O e 4 SECTION VII - RADIOLOGICAL CONDITIONS ,. PART A - 0FFSITE RELEASE DATA Section 4 - Field Monitoring Team Data O VII-11
FIELD MONITORING TEAM DATA WHOLE BODY DOSE RATES
~
~
~1 5511 150WiesftllD DSSI AleCE (f16t[S) 0 80 0.9 50 SS 70 5.0 to 0 0.3 04 0* 06 0F issol& _. 07 86-42 16:44 16 46 _ l6;48._. ,__ l6 50 _ _l_100_. _ l t< li* o 18:30 89A0_
WS 86:34 86:36 16:38 16 40 5 0 76 19 3__ , #63 to 73
%3 SSS 413 310 16 45 (qu emn< t 181 +)
893 lu) 142 78 +3 5 0 903 555 413 311 7 45 3 f t CW 1880 202 1m as to 5 0 666 4e6 372 794 252 3ftW 2112 1084 8105_ _f/.85_._I7._25_ _ 18i?5_ _ , _ 70 05_ WS 36:49 86St If t3 56 55, _ 16 51 _l6.59 8 / O f _ . __I_ I .0 3 16 13 7 4 0 0 39 79 ;3 no l/ 00 tus emns a 870 d5 52 83 7 4 0 0 29 23 to 46 17o 85 52 33 I O 3 f t i.W 28 ?> 89 16 6 5 802 t,3 47 35 3 ft N JtL _ 37.82 51:14 IF:Ib II:58 87.70 11.30 11:40 88:40 70.20 II:08 11:10 0 h WS 17;04 _ _ 87 06 tso 49 37 28 ?? 17 15 13 6 4 0 0 y 31 35 (us em/t, t 160 ltd> 80 49 37 26 27 SF 15 13 6 4 5 0 0 0
- jftCW [ _
33 26 28 3 ,. t8 15 6
'J 3ftw 192 96 59 44
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O SECTION VII RADIO.0GICAL CONDITIONS PaiiT B - Reactor Water Isotopic O Yll 16
REACTOR WTER DATA: UC1. CC l5iFdi 1545 1600 1615 !630 1645 l'30
- 00lNt131 4.'El 4111 4.9El 4.8 Il 4.7E! 4.7!:
- 0:NE 132 5.' !! 4!! .' 3 i '.'El '.! El 6.6!:
13!NE 134 1.1!! :.1 E2 1.1 E2 1.1 E2 1.1I2 1.1 (2 IODINI 134 1.7E2 1.4(2 1..' [2 7.6il 7.9(1 6.!!! 100lN!!35 '.? El 9.4El 5.2El I.iEl S.? E 6.5El tillLF 137 1.5El 1.5El 1.! !! !.! Il 1.5El .5El OYPT34 6JM 1.6El 3.4 El 3.3El 2.2El 3.1!! 2.9El dtPT2485 1.1 E0 1.1E0 1.1 f0 1.1 E0 1.1 EU !.! E0 01PT24 87 4.5El 4(1 3.!!! ? El 2.6 El 2.)El d1FT2138 6.1El ' e il
. '.! El 6.7El 6.3El e El DEN 24133 1.3 E2 1.8E2 1.9 E2 1.9E2 1.8 E2 1.9(2 tEU4135 ' 4 E2
. 1.4(2 1.5E2 1.5E2 1.5 E2 1.4!!
1715 1730 1745 1600 1915 :330 150 TOPE 100lNE 131 4.9 !! 4.9El 4.8il 4.9 il 4.6 El 4.s!! l00lNE-132 s.1 Ei 5.7El 5.3El 4.9 El 4.5El 4.2El 100lNE-133 1 (2 1 E2 1E2 1 !! ! E2 1 E2 100lNE-134 5.3El 4.4El 3.6El 2.'El 2.4El 2!! l0 DINE 135 9.3El 8El '.3El ' e El
. 7.4 El 7.2il Clilth 137 1.5El 1.5El :.5El :.5El :.5 El 1.5El JYPT24 0F 2.5El 1.7El 2.6El 2.5 El 2,4 El 2.3El d1Pf >B5 : 1 Es 1.1 E0 :.1 EO !.! E0 1.1 EO !.1 E0 dtPT24 97 2 !! 1.7!! 1.5 El 1.3El :.? El 1 El KRYPT 34iB 5.6 El 5.3El 5 El 4.7 El 4.4 El 4.1 El 1.3!2 1.9 !! 1.8 (2 1.8E2 I XG04-133 1.9!2 !.!E2 I
x004135 1.4 E2 1.4 !2 1.4 E2 1.3 E2 1.3E2 1.3 F.2 VII-17
O ft.ACT.1 COOLAVf CONCENTRATIONS (4Vm') A0Pv4 D ANO C0A80$CN 04JCv0TS NUCUDE l it a5 16 00 96 15 16 30 19 45 171JO tY 1) 17 30 17 4S '9 00 18.9$ ' t y) cr-st arat e e rat 44 e 73tu e 73t44 e.7n44 e ritu e est a o set ,34 e 6ete ss4a u e2ro e astu M+ S4 8 9tt44 8 95t44 8 9$t44 4 95t44 095f44 0 95t44 6 95t44 6 94t & 6 94E44 6 $4t44 6 94t44 4 set a ce se 1 c2 44 te2tu , c2t 44 1 c2t44 i en44 $:2 44 + c2:44 sc2 44 , c:t 44 4 ::t44
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O VII-18
l O A SECTION VII - RADIOLOGICAL CONDITIONS PART C - Suppression Pool Water Isotopic O O Vll-19
i SUPPRES$121 POOL DMA UC!/CC !!DT0FE 1545 1600 1615 1630 1645 l'00 IC0!NE 131 4.2 E ! 4.2E-1 4.8E1 4.9 E ! 4.0 E 1 4.7 E 1 100lNE 132 9.4 E 1 ?.8(l 9.1 E ! 7.5E-1 'E1 6.5 E ! 100!NE 133 1.1 EO !.1 E0 1.1 ED !.! ED 1E0 1 E0 100'!NE134 1.7E0 1.4 EO !.! Eg 9.4 E 1 7.7E1 e.3E! 10 DINE-135 9.4 E-1 '.2 E-1 'E1 9.7E! 6.5 E 1 9.'s E 1 CEllW !)? 1.5E-1 1.5E-1 1.5E1 1.5 E l 1.5E-1 1.5 E 1 KRrPY24-Sh 1.4 E 2 1.4E-2 1.3E-2 1.3 E 2 1.2E-2 1.2E-2 61PT2465 4.6 E 4 4.6 ! 4 4.6 E 4 4.6 E 4 4.6 E 4 4.6 E 4 61PT2e87 1.8 E 2 1.6E2 1.4 E 2 1.2E-2 1.1 E 2 '.2 E-3 dtFTON 68 3.2 E 2 3.1 E-2 2.9 E 2 2.7E2 2.6 E 2 2.4E-2 YEN 24133 ?.2 E-2 '2E2
. 7.2E2 7.2 E 2 1.2 E 2 7.2E-2
@ 24 135 s.4 E-2 s.3 E 2 6.2 E 2 s.) E 2 53 E 2 5.BE-2 liOTOPE 1715 M0 ;'45 1200 1915 5M DDINE-131 4.7 E ! 4.7 E ! 4.7E! 4.7E1 4.7E-1 4.7 E 1 10 DINE-132 6E1 5.5 E 1 5.1 E ! 4.8 E 1 4.4 E 1 4.1 E-1 10 DINE lF3 1EO ! E0 1 E0 1 E0 9J E ! 9.6 E 1 10 DINE-134 5.2 E ! 4.3E-! 3.5E-1 2.0 E-1 2.4E-1 1.9 E 1 10 DIN!-135 9.! E-1 7.9E-1 !l
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. 7.3E-1 7.1 E 1 CESIW-137 1.5E-1 1.5 E-! 1.5E! 1.5 E-1 1.5 E-1 1.5 E-1 dTFT24 BS 1.1 E-2 !.! E 2 1.1 E 2 1E2 9.!!-3 9.4 2 .
d15'34-65 4.s E-4 4.sE-4 4.2 ; 4 4.s E-4 4. E-4 4.s E - + '* h-s? !i3 'E3 s. E3 5.3 E 3 4., E 3 4.1 E-3 8 0 i-99 2.3E-2 2.' i-2 : E-2 ';E2
. .9 E-2 1.7 E 2 0 74 133 ' 2 E-2
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. 7.1 E-2 ' ! E-2 xEH74135 5.7 E-2 5.6E-2 5.5E-2 5.4 E-2 5.3E-2 5.2 E-2 VII-20
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- A!ER CONCENTM fKWS (41/m0 ACT1vatcN AND COAROSCN PRODUCis NUCUDEl 15 45 iS M ,
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O ( SECTION VII - RADIOLOGICAL CONDIT10h5 PART D Drywell Air Isotopic g k Vll-22
CM311VldSiW31 WS 4411 %1v1 1M!/30
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- 4diCH8 0 30 0 30 0 30 0 30 0 30 030 53NC!-lC( 0 30 ( 30 0 30 0 30 0 3C 0 30 rJO'-!!i 0 30 0 3} 'i 30 0 30 0 30 i$010di tiiG !!!O !itS 0 00 ISIG !!tO
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' I'l30 I'l 30 rTNCP itE : 0 30 t'630 t'l 30 t'. 30 t'6 30 t'c 30 x3NC>-tis I'S 30 C 30 t'9 30 t'5 iC C't 30 C't30 AII-ZC
O SECTION VII - RADIOLOGICAL CONDITIONS PART E - Wetwell Air Isotepic
l
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O MS SMPLE MTA: '01/C0 J
!!0T0FE !!45 1600 1615 1630 1645 !?00
!00!NE 131 1E1 1E1 1E1 1E1 1E1 E-!
100lNE132 2E! !.;E-! 1.7 E ! 1.6 E 1 1,5 E ! 1.4 E 1 100lNE133 2.3E1 2.3E! 2.3 E-1 2.3E-! 2.2 E 1 2.2E-1 100!N!-!34 3.7E1 3 E-! 2.* E-! 2E1 1.? E 1 1.4 E 1 100lNE135 2E1 2E1 1: E-1 1.9E! 19E1 1.9 E 1 61PTh B5M 2.5EO 2.4E0 2.3E0 2.2E0 2.1 E0 2 !0 KRTPT2465 7.9E2 ?.'E2 E2
. '.' E 2 '.9 E 2 7.9E-2
#RfPT h 97 3.! E0 2.7E0 2.4E0 2.1 E0 1.9 E0 1.6E0 -
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!$0iCFE 1715 ! ?30 1745 1900 1815 1630
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'00lNE-134 8.4E2 4.6 E 2 2.i E 2 2.4 E-2 2E2 1.6 E 2 100lNE 135 1.3 E-1 8.4E-2 6.3 E 2 s.2 E 2 6E.2 5.' E 2 dipt 3H'iM 1.5EO 9.4E1 'E1 6.7 E-1 6.4 E 1 6.2 E !
KRYPTh-95 5.9 i-2 3.0 E 2 3 E-2 3 E-2 3E-2 3E-2 kRfPT3b87 1 60 6E1 4 E-1 3.5E-1 3.1 E 1 2.7 E-1 WRYPT34-98 2.9 E0 1.3 E0 1.3 E0 :.2E0 1.2 E0 1.1 E0
- EN34 133 9.2ED 6.1 EO 4.7E0 4.' E0 4.7EO 4.' E0
*EN h 135 7.4 EO 4.0E0 3.6EO 3.o EO 3.5E0 3.4 E0 VII-25
O SECTION VII - RADIOLOGICAL CONDITIONS PART F Vent Monitor (SPING) Data F e W Vll-26 O
O 93ft8 9 MILL SU.4WEltempte MS Whf #0NITM 8414 LOG 8tRtm M:54 12/ lie 90
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O 92FCB19 CRlLL $U$0V[NANNA $CS VCNT MONit0R D. .t a LOG STREAM 89:59 12.'11/91 PER!00 . NOBLE GAS Ga$ l-131 PuRf!CULAft$ VENT rLO4 V gw #AN fu ( C N. 0.
.. .! N...E.NT G. ...... . . . C. .4,' m e n ).........G.C. . . . C. ......
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SCTS 2.62E+04 LOW 3.1tt-02 4.52[-03 9.00E-8t(M) RCACTOR 2 9,84E+82 LOW 1.10E+88 1. Sit-01 0.00E-OltM) tugg!N[ 2 9.43C+02 LOW 9.99C-01 1.5t[-81 0.00E-04(M) i
$lt[ TOTAL 2.95E*04 3.45E+00 5.0ft-81 l 19:00 #CACTOP t 0.69[-91 LOW 0.00E-01 0.00E-81 0.00C=0ttP)
TUA0!NC 1 1.58C+03 LOW t.51C+44 2.stt-01 8.80t=01(M$
$Gft 3.68[+04 LOW 3.1t[-02 4.52[-03 0.00C-el(M)
*[uCf0R 2 9.84E+02 LOW t.19t+00 1.81C-01 0.00C-01(M) tytt!Nt 2 0.43[+02 LOW 8.99C-81 1.5tC-81 0.00E-Gl(M)
$ltC TOTAL 3.93C+04 3.45C+8e 5.00E-88 18:15 PCact0e 1 0.80t-et LOW 0.00E-01 8.80t-01 8.00E-St(M) i tuttlNC 1 1.51C+03 LOW t.51C+49 2. Sit-et 0.00C-8t(M) l
$ CTS 4.69C+04 LOW 3.11C-62 4.52C-93 0.00E-8t<M) l
#CaCTOR 2 9.84E+02 LOW 1,leC+09 1.81C-81 0.00C-01(Mi I TUR0!NC 2 8.44C+02 LOW 8.09C-01 1.51t-01 0 00C-01(M) l 51TC TOTAL 5.02C+04 3.45C+00 5.00C-01 ;
18:30 a[ ACTOR 1 8.00C-81 LOW 4.00C-91 0.00E-01 0.00E-9t(M) fut0lNC 1 1.51C+03 LOW l.5tC+04 2.51C-et 8.00E-SitM)
$GTS 5.88[+04 LOW 3.1tE-02 4.52C-03 0.00C-01(M)
#[actop 2 9.04C+02 LOW t.10C+06 1.01C-61 0.000-6t(M) tut 9lNC 2 0,44[+02 LOW 8.10C-01 1.51C-91 0.00C 01tM)
$1TC total o.21C+04 3.45C+08 5,ett-01 1 19:45 #EACf08 1 0, set-et LOW 0.00[-01 9.00[-01 0.00E-et<M)
TUR$!NC 1 1.51[+03 LOW !.54C+98 2.51C-01 8.80C-81(M) SGTS 5.9'E*84 LOW 3.1t[-02 4.52C-63 0.00C-el<M) RLwCTCR 2 9.85C+02 LOW l.11C+80 1.8tC-81 0.00C-stcM) TUR91NE 2 8.44C+02 LOW S.18E-88 1.5tC-01 0.00C-81(M)
$!TE TOTAL 6.25C+04 3.46E+06 5.00E-et MORE?(RETURNFORMOREORN&RETURNTOSTOP)
O VII-30
1 (~\ s 1 l 2 l 92r[019 C#1LL tut 0VtmeNNa ECE VENT MON 170R Cafa LOC stetuM 09:41 12 11, e t
'CR100 NotLE Cal Cal !-131 PaRf!CULatt$ VENT FL0w V (w RaN (w tw (
[..N .. D. .I N G . .......
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.t .- e e n ) . . . . C. ......
.t / m i n ) ..cc/ etna 19:00 PEACTOR 1 0.00E-81 LOW 0.00E-01 0.00[-91 0.00E-01(M)
TUR91NC 1 1.58t+03 LOW t.5tt+88 2 lit-01 0.00E*et(M) fCil 6,4tt*84 LOW 3.12t=82 4.52C+03 0.08C-9t(M) AthCfo# 2 9.85t+02 LOW 1.1tt+00 1.01C-91 0.00t*01(MS TURSINE 2 9.44t*02 LCW 0.10C-01 1.Elt-91 0.98t*0ltMs Elft total 6.74t*04 3.46t+00 5 00E-01 19:15 R[ ACTOR 1 0.00E-el LOW 0.00t+01 0. Sot-et 0.eet-el'Ms TV80!NE i 1.51t+03 LOW t.68t*00 2.58t*01 0.00C+01(mi 1C75 9.24t+e4 LOW 3.12C-82 4.52C-93 8.eet-8t(M) PCACTOR 2 9.05C+82 LOW t.11[+0e !. Sit-et 9.00t-el(M) Tute!NE 2 9.44t+02 LOW 0.let-91 1.Elt-St 9.99t-01tMs
$!TE TOTAL 9.57t+04 3.46t+98 5.00E-01 19:30 ptact0R 1 0.00E-01 LOW 0.00C 01 0.08C-01 0.00E-Ol(M)
TUR0!NE I 1.51t+03 LOW t.5tt+ee '2.3tt-01 8.88E-ettMi SGTE 1.13t+05 LOW 3. tit-82 4.52t-93 8.eet-eleM) 8tect0R 2 9.05t+02 LOW t.itt+00 1.08[ 91 0.99t-StfM) (r ~Y TUR0!NE 2 9.45t+02 LOW 0.tSt-01 1. Sit-01 0.09t-8t(M4 im/ l Sitt toful 1.lst+05 3.46t+08 5.00E-81 CND or DATA EXIT - to exit STREAM, or ony function Key 'Q) VII-31
O SECTION VII - RADIOLOGICAL CONDITIONS PART G - Reactor Building Area Radiation Monitor Readings k VII-32 O
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l O UNIT I, P ACE 1 CF 1 GROUP PONT DISH AY SERYCIS 19-f&92 15 45 l GROLP NUMBER .15 RX BLDO ARE A R AD FOlli (E-R AN OfSPt AY) PONT NO. C(SCRPTION ALARM IS VAS HGi LOV STATE N0Y LAST LMIT LMIT UNliS PAR 04 ARM-04-RB/RY S&P ARi A i 80 1 00 15 00 T>E FRAR PAR 25 arf 4-25-MR ROOM A >I000 1220 50.00 NONE FRAR PAR 01 ARM-01-MR ROOM 0 9 20 920 50.00 NOE HRAR PAR 02 ARM-02-RC C ROOM >100 021 4 00 NOK MR/HR PAR 03 ARM-03-fFCI ROOM >100 1.65 0.00 NCNE FR/HR PAP 36 ARM-36-01 RR ACCESS 8 AY 0.11 0.11 4.00 NOE FRAR PAR 16 ARM-16-REM 90N R00M 0.11 0,11 4.00 NONE FRAR PAR 06 Mtt06-CRD SOUTH >1000 1 00 15.00 NOME FRAR PAR 09 APM-09-CRD REP AR ROOM 0 70 0.70 15 00 NONE FRAR PARO5 ARM-05-CRD NORTH >1000 0 40 15.00 NOK FRAR P AR41 ARtt41-TP CH APSCR Sith 0.40 0 40 300.00 NOK tRAR PAR 26 ARM-26-0/T P DRNE ARE A 200.50 0.50 15.00 NOK FRAR P AR10 ARtt10-TVEL P00L PP ARE A 1.00 1.00 15.00 NOE FRAR PAPOS ARM-00-RYCU RECRC ARE A 024 024 4.00 NOK FRAR - P AR13 ARM-13-NEY flEL CRIT MON 0 25 025 15.00 NONE FRAR PAR 11 ARtt11-S AMPLE ROOM 3.06 1.06 4.00 POE MRAR P 912 ARM-12-PECRC F AN ROOM 0.08 0 00 4 00 NOK MRAR P AR14 ARtt14-SPNT FLEL CRIT MON 120 120 15.00 NOK MRAR PM15 Mtt15-RFUEL FLR-NORTH 0.16 0.16 4.00 N0E PRAR PAR 42 ARM-42-RFUEL FLR-YEST 0.40 0.40 4.00 NOE tRAR { l S l Vll 34 1 l l
p O VNIT 1, P AGE 10F 1 GROUP PONT DISPt AY SERYCES 19-F + 92 16.00 GROLP NLtSER .15 RX OLDO ARE A R AD MONIT (E4't AN DISPL AY) PONT NO.- DESCRPil0N ALARM l$ VA$ H0H LOV STATE N0Y LAST Ltiff Lt1IT UNITS
*APO4 APM-04 PB/RY SUMP ARE A 1 80 1 00 15 00 NONE MR/HR F AR25 AAt4-25-RHR POOM A 994 20 a1000 50 00 NCHE if/HR P 401 ARM-01 R$ ROOM B 9 20 920 50.00 NONE HR/HR PAR 02 ARM-02-RCC ROOM >100 >100 4.00 NONE MR/HR PdO3 ARM-034FCI R00M >100 >100 0.00 NONE f1R/HR PAR 36 ARM-36-U1 RR ACCESS B AY 0.11 0.11 4 00 NOK ff/HR P AR16 ARM-16 PEM SM)N ROOM 0,11 0.11 4 00 W.INE MR/HR PAR 06 ARM-06-CRD SOUTH $1000 >1000 15.00 NOK ff/2 PAPO9 ARM-09-CRD REP AP ROOM 241 20 0.70 15 00 NOK ff /*
PARO5 ARM-05-CRO NORTH >1000 >1000 15.00 NOE MR/W i P AR41 ARM-41 TP CH AlfER e.RD 0.40 0.40 300 00 NOK R/HR PAR 26 ARM-26-0/T F DRfYE ARE A 240.50 290.50 15.00 NOK MR/HR PARIO ARM-10-FUEL POOL PP ARE A 1.00 1.00 15.CC NONE ff/* ' PAROS ARM-00-PVCU RECPC ARE A 024 024 4 00 NONE if/* PARl3 ARM-13-NEY FUEL CRli MON O 25 025 15.00 NONE MR/HR A PAR 11 AAM-11-$ AMPLE ROOM 3 06 3.06 4.00 NOE t1R/HR PAR 12 ARM-12-PECPC F AN ROOM 0 08 0.08 4 00 NOK MR/HR PAR 14 ARM-14 SPNT FilEL CRIT MON .I 20 120 15.00 NONE MR/HR P AR15 ARM-15-RFUEL TLR-NORTH 0.16 0.16 4.00 NONE ff/HR PAR 42 ARM-42 RFUEL FLR VEST 0 40 0.40 4 00 NOME MR/HR l I i O VII 35 1
1 O UNIT I, P AGE 10F 1 GROI.P PONT DISPL AY SERYlCES 19-Feb-92 16:15 GROUP NUI EER .15 RX DLDO ARE A R AD MONIT (E-PL AN DISPL AY) PONT N0 DESCR@Tl0N AL ARM IS YAS HGH LOV j
$ TATE POV LAST Ltili L tili UNITS l PAPO4 APM-04 PB/RY SUMP ARE A 1 80 1 80 15 00 NONE MR/HR PAE25 AAt+25-RHR ROOM A 796 20 094 20 50 00 NONE MR/HR j PAP 01 ARM-01-RHR ROOM B 9/20 9 '.9 50.00 NOPC MR/HR ,
fGE P AR02 ARM-02-PC C ROOM > 100 >100 4.00 MR/HR l PAR 03 art 1-03-HPCI ROOM >100 >100 0 00 N0f( t1R/HR PAF36 ARM-36-U1 RR ACCESS BAY 0 11 0,11 4.00 NONE iR/HR PAR 16 APr+16-PEM SHDN ROOM 0.11 0.11 4 00 NONE NAR PAR 06 ARM-06 CRD SOUTH >1000 >1000 15.00 NONE MRAR P AP09 ARM-09-CRD REP AR ROOM 221 20 241 20 15 00 N0ff MR/m PAR 05 ARM-05-CRD NORTH >1000 >1000 15 00 NONE MRAR P AR41 ARtt41-T F CH&BER StLD 0.40 0.40 300.00 NOPE RhR DAP26 ARM-26-0/TP DRNE #RE A 220.50 240.50 15.00 NOPC MR/HR PeR10 ARit10-FUEL POOL PP ARE A 1.00 1.00 15 00 NOPE ISAR PAP 03 ARM-08-RYCU PECRC ARE A 0 24 0.24 4 DO NOPC MRAR P AR13 ARM-13-NEY FUEL CRIT HON 0 25 025 15.00 NONE MR/W PAR 11 ARM-11-S AtfLE ROOM 3 06 3.06 4.00 ft]NE MR/HR P AP12 APM-12-RECPC F AN ROOM 0 08 0 08 4 00 NONE MR/HR PAR 14 ARM-14 $PNT FUEL CRIT MON I20 1 20 15.00 NONE MRihR PAR 15 ARM-15-RFUEL FLR-NORTH 0 16 0.16 4.00 NONE MRhR oAP42 ARM-42-RFUEL FLR-YEST 0 40 0 40 4 00 NONE MR/HR Vil 36 O
l O UNIT 1, P ACE 10F 1 OROLP PONT DISPL AY SERVCES 14-Feb-92 16.30 GROUP NUtEER .15 RX BLDO @f A R AD MONIT (E-PL AN DISPL AY) PONT NO ({iER@T DN ALAFtl IS VAS HOH LOY ST ATE N0Y LAST LMIT L M IT UNITS PARO4 ARM-04-RB/RV SUtf ARE* 1 80 1 80 15 00 NONE tRAR FAR25 ARM-25-Em ROOM A 747 20 7 % 20 50 00 NONE FW/HR PAP 01 ARM-01-RJR ROOM B 9.20 9 20 50 00 NONE MRAR PAPCr2 ARM-02-RCIC ROOM >100 >100 4 00 NONE MR/HR PAR 03 arf 1-03-fFCI ROOM >100 #100 0.00 N0ff MR/HR PARI 6 ARM-!6-U1 RR ACCESS B AY 0,11 0.11 4.00 NOE MRAR P AR16 ARM-16-REM SH(W ROOM 0 11 0.11 4 00 NOK MRAR PAR 06 ARM-06-CRD SOUTH >1000 >1000 15.00 NOK FRAR PAP 09 ARM-09-CR0 REP AR ROOM 201_20 221.20 15 00 NONE MRAR PAROS AEti-05-CRD NORTH >1000 >1000 15.00 NONE MRAR PAR 41 ARM-41-T P CH AFSER SH.D 0 40 0 40 300.00 NOE RAR PAR 26 ARM-26-O/TP DRIVE ARE A 200.50 220.50 15.00 NOK MRAR PARIO AM-10-FUEL POOL PP ARE A 1 00 1 00 15.00 NOK MRAR PAR 03 AFti-00-RYCU RECRC ARE A 0 24 0.24 4 00 NOK MRAR P AR13 ARM-13-NEY FLEL CRIT MON O 25 0 25 15 00 N0E FR/HR PM11 MM-11-S AMPLE ROOM 3 06 3 06 4.00 NOME MRAR O P AP12 P AR14 ARM-12-RECRC F AN ROOM AAM-14-sPNT FUEL CRIT MON 0.00 1 20 0 08 1 20 4.00 15 00 NONE NONE MRAR MR/HR P AR15 ARM-15-RFUEL FLR-NORTH 0.16 0.16 4 00 NOK MRAR P AP42 ARM-42-PfUEL FLR-vtST 0 40 0.40 4 00 NONE MRAR O VII-37 i
l l O UNIT 1, P AGE I 0F 1 GROUP PONT DISPL AY SERVCES 19-feb-92 16.45 GROUP NLt'EER :15 RX BLDO ARE A R AD iTWIT (E-PL AN DE#L AY) PONT NO. ((SER PT ON AL ARM is YAS HOH LOV ST ATE NOV LAST Ltiff L tiff UNITS PAR 04 ARM-04-PB/RY SLt1P ARE A 9 93 1 00 15 00 NONE MR/HR FAR25 art +25-RHR ROOM A 706.33 747.20 '4 00 NONE MRAR PARO1 ARM-01-RHR ROOM 0 17 33 9.20 50.00 NCNC MR/HR 0AR02 ARM-02-RCC ROOM >100 >100 4 00 NONE MR/HR P 403 ARfi-03-WCI R00M >100 >100 8 CO NONE 11R/HR PAR 36 ARM-36-U1 RR ACCESS B AY 9 24 0.11 4 00 NONE MR/HR P AP16 AR?tl6 REM SHDN R00M 8 24 0,11 4.00 NONE MR/HR PAR 06 ARM-06-CRD SOUTH 959.13 >1000 15.00 NONE MRAR PAP 09 ARM-09-CRD REP A R ROOM 207.46 201 20 15 00 NONE MRAM P 405 ARM-05-CRD NORTH 950 53 >I000 15.00 NONE MRAR PAR 41 ARM-41-T P CH AMBER SFLD 8 53 0.40 300 00 NONE RAR PAR 26 ARM-26-0/TP DRf4 ARE A 190.63 200.50 15.00 NOE MRAR P ARIO ARft10-FUEL POOL PP ARE A 9 13 1 00 15.00 NOE t1RAR PAR 08 ARM-00-RYCU RECRC ARE A 8 37 0.24 4.00 NONE MRAR - P AR13 ARM-13-NEY FUEL CRIT MON 8 38 0 25 15.00 KF MRAR PARl1 ARftl1-S AMPLE ROOM 11.19 3.06 4 00 f( .( MR/tR P AP12 AR*+12-RECRC F AN ROOM 8 21 0 00 4.00 NONE MP/HR PAR 14 ARM-14-5PNT FUEL CRIT MON 9 33 1.20 15.00 NONE MR/HR bARI5 ARM-15-RFUEL FLR-NORTH 0 29 0.16 4.00 NOE MRAR PAR 42 ARiv42-RFUEL FLR-YEST 8.33 0.40 4.00 NONE MR/HR VII-38 l [
UNIT 1, P AGE 10f 1 GROUP PONT DISPL AY SERYCES 19-Feb-92 17.00 GROUP MltBER :15 RX BLD0 ARE A R AD MONIT (E-PL AN DISPL AY) PONT NO. DESCRPTON ALARM $ YAS H0H LOY STATE N0Y LAST LNIT LMIT UNITS PAR 04 ARM-04 R9/RY SUtf ARE A 4.70 9.93 15 00 NOK MR/HR PAR 25 ARM-25-RHR ROCM A 603.10 706.33 50.00 NONE MR/HR PAROI ARM-01-Rm R00M B 12,10 17.33 50.00 NONE MR/HR PAR 02 ARM-02 RCC ROOM >100 >100 4.00 NOK MR/HR PAR 03 ARM-03-HPCI ROOM >100 >100 8 00 NONE t1R/HR PAR 36 ARM-36-U1 RR ACCESS 8 AY 3 =01 8.24 4.00 NONE MR/HR ' PAP 16 ARtt16-RCM SNDN ROOM 3 01 8.24 4.00 NONE MR/HR PAR 06 ARM-06-CR0 SOUTH 853.90 959.13 15.00 NONE ff/HR PAR 09 ARM-09-CRD REP AR ROOM 177.00 207,46 15 00 NONE FR/* PAR 05 ARM-05-CR0 NORTH 853 30 958 53 15.00 NONE MR/HR P AR41 ~ ARM-41-TP CHAT 9ER SHLD 3.30 8.53 300 00 NOK R/* PAR 26 ARM-26-0/TF DRIVE ARE A 173.40 198.63 15.00 NONE ff/* PAR 10 mRM-10-FUEL P00L PP ARE A 3.90 9.13 15.00 NOE m/m PAR 08- ARM-08 RYCU RECRC ARE A 3.14 8.37 4.00 NONE tR/M . PAR 13 art +13-NEY FUEL CRIT MCW 3.15 8,38 15.00 NOK ff/HR AKit t i-$ AMPLE R00M 5.% 11.19 4.00 MR/HR O PAR 11 NONE P AR12 ARM-12-RfC RC F AN R00M 2.98 8.21 4.00 NONE MR/HR
. PAR 14 ARft14-SFHT FUEL CRIT MON 4.10 9.33 15.00 NONE MR/HR P AR15 ARtti5-RFUEL FLR-HORTH 3 06 8.29 4.00 NONE t1/HR PAR 42 ARM-42-PfUEL FLR-YEST 3 30 8 53 4.00 NOK MR/HR ,
VII-39
i l O LNIT 1, P AGE 1 Of i OROUP PONT DISPL AY SERYCIS 19-feb-92 17:15 EROUP nut @ER .15 RX BLDO AE!A R AD MONIT (E-PL AN D!?PL AY) PONT NO. DESCRPTION AL AFtt IS VAS HIGH LOY STATE N0Y LAST L t1lT L t11T UNITS PAPO4 ARM-04-RB/RY SUMP ARE A 7.70 4.70 15 00 NONE MR/HR PAR 25 ARM '25-PHR 900M A 557.10 603.10 50 00 NONE MR/HR PAR 01 art +01 PJR ROOM B 15.10 12.10 50.00 NOPE MR/HR PAR 02 ARM-02-RC C ROOM >100 >100 4 00 NOPE HR/HR PrR03 ARM-03-tPCI R00M >100 >100 8.00 NOT t1R/HR PAR 36 ARM-36-Ut RR ACCESS B AY 6 01 3.01 4.00 NONE MR/HR P AP16 ARM-16-PEM SHDN POOM 6 01 3.01 4 00 NONE MR/HR PAR 06 ARM-06-CRD SOUTH B06.90 853.90 15 00 NONE t@hR PAR 09 ARM-09-CRD REP AR ROOM 173 00 177 00 15 00 NOPC MRAR PARO5 art 1 <35-CRD NORTH 806 30 853.30 15.00 NONE ISAR PAR 41 ARM-41-T P CH At@ER SFLD 6.30 3.30 300.00 NOPE RAR PAR 26 ARM-26-0/TP DRfYE ARE A 166 40 173.40 15 00 NONE MR/W PARIO ARM-10-FUEL POOL PP ARE A 6.90 3.90 15.00 NONE ifAR PAR 00 ARM-08-RYCU RECRC ARE A 6.14 3.14 4.00 N0fC IPAR "- P ARl3 arf +13-NEY FUEL CRIT MON 6.15 3.15 15 00 NONE MRAR P AR11 ARM-11 -S AMPLE ROOM 7.% 5.96 4.00 :.JPC t1R/HR P ARI: ARM-12-REC RC F AN ROOM 5 63 2 90 4.00 NONE MRAR PAR 14 ARtti4 c,PNT FUEL CRIT MON 7.10 4.10 15 00 TONE MR/HR PARl5 ARM-15-PfUEL FLR-NORTH 6.06 3.06 4.00 NONE MR/HR PAR 42 ARM-42-PfUEL FLR-YEST 6.30 3.30 4.00 NONE MRAR VI!-40 O
. . . - - - . - - - - . . _ - - - ~ . _ _ . . -. - - =. -. . _ . - - -.
LNIT 1, P A0210F 1 GROUP PONT DISPL AY SERVCES 19-f +92 17.30 GROUP NUMBER :15 RX BLDO ARE A R AD MONIT (E-PL AN DISPL AY) PONT NO. DESCPPT10N ALARM 19 YAS H10H LOY l STATE NOV LAST L MIT LMIT UNITS PAR 04 ARM-04-RB/RY SUtf ARE A 11 30 7.70 15 00 NONE ff /HR 1 PAR 25 apt +25-RHR ROOM A 560.70 $57.10 50 00 NONE MR/HR PAR 01 ARM-01-Rm ROOM B 16.70 l'.10 50 00 M MR/HR PAR 02 ARM-02-RC C ROOM >100 >1CC 4 00 NONE MR/HR PAR 03 ARM-03-WCI R00M 91.15 >100 0 00 NONE MR/HR PAR 36 art +36-01 RR ACCESS B AY 9 61 6.01 4.00 NONE MR/HR P AR16 ARM-16+CM SHDN ROOM 9 61 6.01 4.00 NONE MR/HR PAR 06 ARM-06-CRD SOUTH 760.50 806.90 15.00 NONE ff/* PAP 09 ARM-09-CRD REP AR ROOM 170.20 173 00 15.00 NOK MRM PAkO5 ARM-05-CR0 NORTH 759.90 806 % 15.00 NONE MRM PAR 41 ARM-41 TP CHAteER SH.D 9.90 6.30 300 00 NOE RM PAR 26 MM-26-10/TP DR!YE ARE A 160 00 166.40 15.00 NONE ff M PARIO art +10-FUEL POOL PP ARE A 10 50 6.90 15.00 . .JE ff/HR
- P AROS art +00-RYCU RECRC arf A 9 74 6.14 4.00 NOE ff M **
PARl3 art +13-EY F1CL CRIT MON - 9.75 6.15 15 00 NONE MR/HR p P AR11 MM-11-S AlftE ROOM 11.56 7.% 4.00 NOME ff /k - Q PAR 12
&AWI4 ARM-12-PECRC F AN ROOM ARft14-$PNT FUEL CRIT MON 9.58 10.70 5 98 7.10 4 00 15 00 NOK NONE MR/HR MR/HR P ARl5 ARM-15-PfUEL FLR-NORTH 9 66 6.06 4 00 NOK MR/HR PAR 42 ARM-42-PFUEL FLR-VEST 9.90 6.30 4.00 NONE tt/HR
_\ YI$ 4} l l-o ! v
- l. WIT 1, P ACE 1 Cf 1 GROLP PONT DISFt AY SERYCES 19-F&92 17.45 O
GROUP FREER 15 RX OLDO ARE A R AD t1CNIT (E-PL AN DISPL AY) POWT NO DLir.PIPT10N AL4H IS YAS HGi LOV ST ATE !"1Y LAST L M IT L MIT UNil s PAPO4 APM-04-PB/RV SLtf ARE A 1520 11 30 15.00 NONE MR/HR PAROS AEt+25-Etn ROOM A 505 00 560 70 50.00 NCNE ff/HR P ARD1 ARM-01-RHR ROOM B 22 60 10.70 50 00 NONE MR/HR PAR 02 APf4-02-RCC ROOM > 100 > 100 4.00 NONE MR/HR PAR 03 ARM 03-HPCIROOM 70 05 91.15 0.00 fl0NE MRAE PAR 36 APti-36-U1 RR ACCESS B AY 13 51 9 61 4 00 NONE t1RAR P ARib ARM-16-PEM SHCW ROOM 13.51 9 61 4 00 NONE MRAR PAR 06 ARti-06-CRD $0VTH 714 40 760.50 15.00 N0tt MRAR PAP 09 APM-09-CRD REP AR R00M 168 03 17020 15.00 NONE MRAR PAkO5 Akt+05-CRD NORTH 713 00 7790 15.00 NONE MRAR P AR41 ARM-41-T F CH AttER QLD 1380 9.90 300.00 NONE RAR PAR 26 art +26-10/T P DRfYE ARE A 153 90 160 00 15 00 NOE MRAR P ARIO arf +10-FUEL POOL PP ARE A 14.40 10.50 15.00 NONE MRAR P AROO ARM-08-RYCU RECRC ARE A 13 64 9.7( 4.00 NOK ifAR . PAR 13 APM-13-NEY FUEL CPIT MON I3 65 9.75 15.00 NOT MRAR P AR11 eRM-11-S AMPLE ROOM 15 46 11.56 4.00 NONE t1R/HR P AR12 ARM-12=RECRC F AN ROOM 13.48 9 58 4 00 NONE fP /HR PARl4 apt +14-SPNT FUEL CRIT MON I4 60 10 70 15.00 NONE l@/HR P ARIS ARM-15-RFUEL FLR-NORTH 13 56 9 66 4 00 NONE MRAR PAR 42 ARM-42-RFUEL FLR-VEST 13 80 9 90 4 00 N0ft MR /HR 4 Vll 42
- - - . . . - - _ .- - -. _ - . . . . ~ . --- . . ~ . . . . - .
f~
& > UNIT 1, P AGE 10F 1 GROUP PONT DISPL AY SERVICES - 19-Feb-92 18 <00 GROUP NUr@ER :15 RX BLDO ARE A R AD MONIT (E-PL AN DISPL AY)
PONT NO. MSCRPiloft ALARM is Y AS . HIGH LOV ST ATE N0Y LAST LMIT L MIT UNITS PAR 04 ARM-04-RB/RY Surf .ARE A 19.40 15.20 15.00 NONE MR/HR PA225 ARM-25-RHR R00M A -480.60' 505.80 50 00 NONE MR/HR PAR 01 ARM-01-Rm ROOM D 26.80 22.60 50.00 NONE MR/HR PAR 02 ARM-02-RCIC ROOM '100
>' N 4.00 '
40E MR/HR PAR 03 ARM-03-WCliDOM 74.25 70.05 8.00 NONE t1R/HR 7AR36 ARM-36-Ut RR ACCESS BAY '7.71 13.51 4.00 NONE MR/HR PAR 16 ARM-16-REM SHDN ROOM 17.71 13.51 4.00- Nr*E MR/HR PAR 06 ' ARM-06-CRD SOUTH 668.60 714.40 15.00 NC
- t1R/W PAR 09 ARM-09-CRD REP AR ROOM 16$ 40 168.00 15.00 NOIE MR/*
oAROS - ARM-05-CRD NORTH 668.00 713.80. 15.00 NONE MR/HR PAR 41 ARM-41-TP CH At@ER SM.D 18.00 13.00 300.00 NOK R/M PAR 26 ARM-26-IO/TP DRlYE ARE A 148.10 153.90 15.00 NONE MR/HR PARIO ARM-10-FUEL POOL PP art A 18.60 14.40 15.00 NOK .MR/m PAR 08 ARM-08-RYCU RECRC ARE A '17.84 13.64 4.00 NOE tS/HR ,
' P AR13 ARM-13-NEY FUEL CRIT MON - 17 85 13.65 15.00 NONE ff /HR
; P AR11. ARM-11-S AffLE R00M . 19 66 15.46 4.00 NONE MR/HR PAP 12 ARM-12-RECRC F AN ROOM- 17 68 13 48 4.00 NOE MR/HP P AR14 AEM-14-SPNT FUEL CRIT MON 18.80 14.60 15.00 NONE MR/HR
_ P ARIS ARM-15-RFUEL FLR-NORTH !7.76 13.56 4.00 NONE ff/HR PAR 42. ARM-42-RFUEL FLR-VEST 18.00 13.80 4.00 NONE .MR/HR VII-43
UNIT 1, P AGE 10F 1 GROUP PONT DISPL AY SERYlCES 19-Feb-92 18:15 O GROUP NUrTER :15 RX BLDO ARE A R AD MONIT (E-PL AN DISPL AY) PONT N0. DESCRPT KH ALARM is VAS HGi LOY STATE NOV LASi LIMIT LtilT UNITS PARO4 APM-04-RB/RY SUMP ARE A 23.50 19 40 15.00 NONE tit /HR PAR 25 ARM-25-MR ROOM A 455.30 480 60 50.00 NONE MR/HR PAR 01 ARM-01-Rm ROOM B 30.90 26.80 50.00 N0ff MR/HR PAR 02 ARM-02-RCIC ROOM >100 >100 4.00 NONE MR/HR PAR 03 ARM-03-HPCI ROOM 73.35 74.25 8.00 NONE t1R/HR PAR 36 ARM-36-U1 RR ACCESS B AY 21.81 17.71 4.00 NOE MR/* P AR16 APM-16-PCM SHDN ROOM 21.81 17,71 4.00 NONE MR/HR PARD $ ARM-06-CRD SOUTH 622.70 668.60 15.00 NOPt MR/HR PAR 09 ARM-09-CRD PIP AR ROOM 164.60 166.40 15.00 NCE MR/W PAROS ARM-05-CR0 NORTH 622.10 6(6 00 15.00 NONE MR/* PAR 41 ARM-41 -T P CH AMBER SR.D 22.10 18.00 300.00 NONE R/m PAR 26 ARM-26-73/TP DR!YE ARE A 142.20 148.10 15.00 NOE MR/IN P ARIO ARM-10-FLEL POOL PP AREA 22.70 18 60 15.00 NOPE MR/W PAR 00 ARM-08-RVCU RECRC ARE A 21.9': 17.84 4.00 Ni>E tit /m 8 PAR 13 AM-13-NEY FUEL CRIT MON 21.95 17 85 15 00 NONE MR/HR PARI 1 ARM-11-S AMPLf. ROOM 23.76 19.66 4.00 NONE MR/HR PAR 12 ARM-12-REC RC F AN 't00M 21.78 17 68 4 00 NOK MR/HR P AR14 ARM-14-SPNT FLEL CRIT MON 22.90 18 80 l '. E N0E MR/HR PARIS ARM-15-RFUEL FLR-NORTH 21.86 17.76 4.00 NOT MR/HR P AR42. ARM-41 PFUEL FLR-VEST 22.10 10.00 4.00 NONE MR/HR t VII-44
~
s O LNIT 1, PAGE 10F 1 CROUP POMT DSPL AY SERYlCES 19-F&92 18:30 GRour itJteER :15 RX BLOG ARE A R AD MONIT (E-PL AN DISPL AY) PONT NO. (GC RIPT10N - ALARM $ VAS HlfH LOY
*T ATE N0Y LAST trilT LIMIT LMIT*
PAPO4 ARM-04 R8/RY SUMP ARE A- 27.70 23 50 15 00 NONE MR/HR PAR 25 ARM-25-liHR ROOM A_ _ 435.00 455 30 S0.00 NONE MR/HR
' P AR01 - ARM-01-Rm ROOM 8 35.10 30.90 50.00 NONE MR/HR
' P AR02 ARtt02-RCIC R00M >100 >100 4.00 NONE M/HR PAR 03 ARM-03 HPCIR00M 76.05 73.35 8.00 NONE MR/HR P ARS.. . .., iP RR ACCESS B AY 26.01 21.81 4.00 NONE P /HR P A% - "9 #M SHDN ROOH 26.01 21,81 4.00 NONE MR/HR P' % ,.. e D SOUTH 626.90 622.70 15.00 NONE MR/*
.I c<N D REP AR ROOM 173.00 164.60 15.00 NOK MR/W F J S' :S NORTH 626.30 622.10 15.00 NONE MR/M P#
- P CH AMIER SH.D 26.30 22.10 300.00 NOE R/M PA < O/TP ORNE ARE A 146.40 142.20 15.00 NOE MR/HR P ARit., 80-FUEL POOL PP AREA 26.90 22.70 15.00 NOE . MR/W PAR 08 ARM 08-RYCU RECRC ARE A 26.14 21.94 4.00 NONE MR/M -
P AR13 ARM-13-NEY F1KL CRIT MON 26.15 21.95 15.00 NONE MR/HR PARil ARM-11-S AffLE ROOM 27.96 23.76 4.00 NOE tt/HR [.\ PAR 12 PAR 14 ARM-12-RECRC F AN ROOM arf +14-SPNT FUCL CRIT MON 25.98 27.10 21.78 22.90 4 00 15.00' NONE NONE tt/HR MR/HR
' PAR 15 ARM-15-RFUEL FLR-NORTH 26.06 21.86 4.00 NONE MR/HR PAR 42 ARM-42-RFUEL FLR-YEST 26.30 22.10 4.00 NONE MR/HR I
l' d Vll-45 y5 -. .-
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O UNIT 1, PAGE 1 Of i OROUP PONT DISFt AY SERYCES 19-Feb-92 18:45 GROUP NUTTER :15 RX DLOG ME A R AD MONIT (E-?L AN DISPL AY) PolNT NO. DESCRPTION ALARM IS YAS HIGH LOV STATE fes' LAST LMIT LMIT UNITS PAR 04 ARM-04-R8/RV SUMP ARE A 42.90 27.70 15.00 NONE MR/HR PARI 5 5M-25-RHR ROOM A 445.30 435.00 50.00 NONE MR/HR PARO1 ARM-01-Rm ROOM B 50.30 35.10 50 00 NONE MR/HR PAR 02 ARM-02-RCC ROOM >100 >100 4.00 NOPE MR/HR PAR 03 ARM-03-HPCI ROOM 9125 76 05 8.00 NOPE MR/HR PAR 36 ARM-36-U1 RR ACCESS B AY 4121 26.01 4.00 NONE MR/HR PAR 1, ARM-16-REM SHDN ROOM 41 21 26.01 4 00 NONE MR/HR P A'.06 ARM-06 CRD SOUTH 642.10 626.90 15.00 NOPE MR/W PAR 09 ARM-09-CRD REP AR ROOM 203.40 173.00 15.00 NONE tt/m PAROS ARM-05-CRD NORTH 641.50 626.30 15.00 NOPE MR/HR PAR 41 ARM-41-TP CH APSER SFLD 41.50 26.30 300.00 NOPE R/m PAP 26 ARM-26-O/TP DRfVE AREA 161 60 146.40 15.00 NOPE MR/W PARIO ARM-10-FUEL POOL PP ARE A 42.10 26.90 15.00 NOPE MR /HR ., PAR 00 ARM-08-RYCU RECRC AREA 41.34 26.14 4.00 NOPE MR/W P AR13 ARM-13-NEY FUEL CRIT MON 41.35 26 15 15.00 NONE MR/HR P AR11 ARM-11 -5 AMPLE ROOM 43,16 27.96 4.00 NOPE MR/HR P AR12 APM-12-PEC'RC F AN R00M 41.18 25.98 4.00 NONE MR/HR P AR14 ARM-14-SPNT FUEL CRIT MON 42.30 27.10 15.00 NONE MR/HR P ARIS ARM-15-RFUEL FLR-NORTH 41 26 26.06 4.00 N0fE MR/HR PAR 42 ARM-42-RFUEL FLR-YEST 41 50 26.30 4 00 NONE i9/HR VII-46 O
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REVISION: 12/9/91 UNIT 1, P AGE 10F 1 GROUP PONT DISPL AY SERYlCES 19-Feb-92 15.45 OROUP NUMBER :10 HI R ANGE ARM RE ADWGS (E-PL AN DISPL AY) PCWT NO. DESCRIPT10N ALARM IS VAS HIGH LOV ST ATE NOV LAST LIM lT LIMIT UNITS P AR56 ARM-56-RHR POOM LOOP B 0.44 0.30 15.00 NONE P/HR PAR 55 ARM-55-RHR ROOM LOOP A 1.04 0.36 15.00 NONE R/HR PAR 57 ARM-57-RCIC PP TURB RM 0.38 0.44 15.00 NONE R/HR PAR 48 ARM-48-HPCI PP/TUR8 RM 0.29 0.38 15.00 NONE R/HR PAR 53 ARM ACCS TO REM SHUTD 0.31 0.23 15.00 NONE R MR PARSO ARM-50-CRD NORTH 1.40 0.30 15.00 NONE F /HP PAR 51 APM-51-CPD SOUTH 1.40 0.31 15 00 NONE P/HR PAR 52 ARM-52-RYCU PP ACCESS 0.50 0.41 15.00 NONE R/HR PAR 54 ARM-54-FUEL POOL PP ROOM 0.21 0.41 15.00 NONE R/HR PAR 49 ARM-49-REFUEL FLOOR ARE A 0.41 0.28 15.00 NONE R/HR UNIT 1, P AGE 10F 1 GROUP POWT DISPL AY SERVICES 19-Feb-92 16.00 GROUP NUMBER :10 HI R ANGE ARM RE ADINOS (E-PL AN DISPL AY) POINT NO DESCRIP110N ALARM (S YAS Hl0H LOV STATE NOV LAST LIMIT LIMIT UNITS PARS 6 ARM-56-RHR ROOM LOOP B 0.44 0.44 15.00 NONE RihR PAR 55 ARM-55-RHR ROOM LOOP A 0.89 1 04 15.00 NONE R/HR PAR 57 ARM-57-RCIC PP TURB RM 0.38 0.38 15.00 NONE R/HR PAR 48 ARM-48-HPCI PP/TURB RM 0.23 0.29 15.00 NONE R/HR PAR 53 ARM ACCS TO REM SHUTD 0.31 0.31 15.00 NONE P/HP PARb0 ARM-50-CRO NORTH 1.20 1.40 15.00 NONE R/HR PAR 51 ARM-51-CRD SOUTH 1.20 1.40 15.00 NONE P/HR PAR 52 ARM-52-RVCU PP ACCESS 0.50 0 50 15.00 NONE R/HR P AR54 ARM-54-FUEL POOL PP ROOM 0.21 0.21 15.00 NONE R/H" PAR 49 ARM-49-REFUEL FLOOR ARE A 0.41 0.41 15.00 NONE R ihr. Vll-48 O
-%d UNIT 1; P AGE 10F 1 OROUP PONT DISPL AY SERYlCES - 19-Feb-92 16.15
-GROUP NUMBER :10 HI R ANOE ARM RE ADNOS (E-PL AN DISPL AY)
POWT NO.- DESCRIPTION AL ARM is VAS HIGH LOV PAR 56 ARM-56-RHR ROOM LOOP B 0 44 -0 44 5 - P PAR 55 ARM-55-RHR ROOM LOOP A- 0.80 0.89 15.00 NONE R/HP PAR 57 ARM-57-RCIC PP TURB Ft1 0.38 0.38- 15.00 NONE R/HR PAR 48 ARM-48-HPCI PP/TURB RM 0.23 0.23 15.00 NONE P/HR PAR 53 ARM ACCS TO REM SHUTD 0.31 0.31 15.00 NONE R/HR PAR 50- ARM-50-CRD NORTH 1.10 1.20 15.00 NONE R/HP PAPSI ARM-51-CRD SOUTH - 1.10 1.20 15.00 NONE R/HR P AR*,s2 ARM-52-RVCU PP ACCESS 0.50 0.50 15.00 NONE R/HR
' P AR54 ARM-54-FUEL POOL PP ROOM 0.21 0.21 15.00 NONE R/HR PAR 49 ARM-49-RErVEL FLOOR ARE A 0.41 0.41 15.00 NONE R/HR UNIT 1, P AGE 10F i GROUP PONT DISPL AY SERVICES 19-Feb-92 16.30 GP00P NUMBER :10 HI R ANOE ARM RE ADINGS (E-PL AN DISPL AY) l POINT NO._ DESCRIPT10N ALARM IS YAS Hl0H LOV STATE NOV LAST LIMIT LIMIT UNITS PARS 6 ARM-56-RHR ROOM LOOP B 0.44 0.44 15 00 NONE R /HR PAP 55 ARM-55-RHR ROOM LOOP A 0,75 0.80 15.00 NONE F/HP PAR 57 ARM-57-RCIC PP TURB RM 0.38 0.38 15.00 NONE 9/HR PAR 48 ARM-48-HPCI PP/TUR9 RM 0.23 0.23 15.00 NOTE R/HR PARS 3- APM ACCS TO REM SHUTD 0.31 0.31 15.00 NONE P/HR PAR 5O ARM-50-CRD NORTH- 1.00 1.10 15.00 HONE R/HR PAR 51 ARM-51-CR0 SOUTH 1 00 1.10 15.00 NONE R/HR PAfiS2 ARM-52-RVCU PP ACCESS 0.50 0.50- 15 00 NONE R/HR PAR 54 ARM-54-FUEL POOL PP ROOM O.21 0.21 15.00 NONE R/HR PAR 49 ARM-49-REFUEL FLOOR ARE A 0.41 0.41 15.00 NONE P/HR n
O VII-49 u
l UNIT 1, PAGE 10F 1 19-Feb-92 O GROUP POINT DISPL AY SERVCES 16 45 GROUP NUMBER :10 HI R ANGE ARM RE ADINGS (E-PL AN DiSPL AY) POINT NO. DESCRIPTION ALARM IS VAS HIGH LOV ST ATE NOV LAST LIMIT LIMIT UNITS PAR 56 ARM-56-RHR ROOM LOOP B 0.44 0.44 15.00 NONE R/HR PAR 55 ARM-55-RW ROOM LOOP A 0,71 0.75 15.00 NONE R/HR
-PAR 57 ARM-57-PCC PP TURB RM 17.19 0.38 15.00 NONE R/HR PAR 48 ARM-48-HPCI PP/TURB RM 0.23 0.23 15.00 NONE R/HR PAR 53 ARM ACCS TO REM SHUTD 0.31 0.31 15 00 NONE R/HR PAR 50 ARM-50-CRD NORTH 0.96 1.00 15.00 NONE R/HR PAR 5i ARM-51-CRD SOUTH 0.96 1.00 15.00 NONE P/HR PAR 52 ARM-52-RVCU PP ACCESS 0.50 0.50 15.00 NONE R/HR P AR54 ARM-54-FUEL POOL PP ROOM 0.21 0.21 15.00 NONE R/HR PAR 49 ARM-49-REFUEL FLOOR ARE A 0.41 0.41 15.00 NONE R/HR UNIT 1,, P AGE 10F 1 GROUP PolNT DISPL AY SERVICES 19-Feb-92 17:00 GROUF NUMBER :10 HI R ANOE ARM RE ADINOS (E-E L AN DISPL AY)
POINT NO. DESCRIPTION AL ARM IS YAS H10H LOV STATE NOV LAST LIMIT LIMIT UNITS PARS 6 ARM-56-RbR ROOM LOOP B 0.44 0.44 15.00 NONE R/HR PAR 55 ARM-55-RHR ROOM LOOP A O.60 0.71 15.00 NONE R/HR PAR 57 ARM-57-RCIC PP TURO RM 3.28 17.19 15 00 NONE R/HR PAR 48 ARM-48-HPCI PP /TURB RM 0.23 0.23 15.00 NONE R/HR PAR 53 ARM ACCS TO REM SHUTD 0.31 0.31 15.00 NONE R/HR PARSO ARM-50-CRD NORTH 0.85 0.96 15.00 NONE R/HR PAR 51 ARM-51 CRD SOUTH 0.85 0.% 15.00 NONE R/HR PAR 52 ARM-52-RYCU PP ACCESS 0.50 0.50 15.00 NONE R/HR PAR 54 ARM-54-FUEL POOL PP ROOM 0.21 0.21 15.00 NONE R/HR PAR 49 ARM-49-REFUEL FLOOR ARE A 0.41 0.41 15.00 NONE R/HR O VII-50
/* L) UNIT 1. P AGE 10F 1 GROUP POINT DISPL AY SERYlCES 19-Feb-92 17:15 GROUP NUMBER :10 HI R ANGE ARM RE ADINGS (E-PL AN DISPL AY) POINT NO. DESCRIPT10N ALARM IS YAS HIGH LOV STATE NOV LAST LIMIT LIMIT UNITS P AR56 ARM-5(-RHR ROOM LOOP B 0.44 0.44 15.00 NONE R/HR PAR 55 ARM-55-RHR ROOM LOOP A 0.56 0.60 15.00 NONE P/HP PAR 57 ARM-57-PC!O PP 1 URB RM 4.37 3.28 15.00 NONE FiHP PAR 48 ARM-48-HPCI PP /TURB RM 0.23 0.23 15.00 NONE P/HR PAR 53 ARM ACCS TO REM SHUTD 0.31 0.31 15.00 NONE P/HR PAR 50 ARM-50-CRD NORTH 0 81 0.85 15.00 NONE R/HP P AR51 ARM-51-CRD SOUTH 0.81 0.85 15.00 NONE P/HR PAR 52 APM-52-RVCU PP ACCESS 0 50 0.50 15 00 NONE - P/HO PAR 54 ARM-54-FUEL POOL PP ROOM O.21 0.21 15.00 NONE R/HR PAR 49 APM-49-REFUEL FLOOR ARE A 0.41 0.41 15 00 NONE R/HR UNIT 1, P AGE 10F 1 GROUP PONT DISPL AY SERYlCES 19-Feb-92 17 ?0 GROUP NUMBER :10 HI R ANGE ARM RE ADINGS (E-PL AN DISPL AY) /] ( ,/ PONT NO. DESCRIPTl04 AL ARM STATE is NOV YAS LAST Hi0h 211V LOY LIMIT UNITS PAR 56 ARM-56-PHR ROOM LOOP B 0.44 0.44 i5.00 NONE F.4 PAR 55 ARM-55-RHR ROOM LOOP A 0.56 0.56 15.00 NONE R/HF P AR$7 ARM-57-RCIC PP TURB RM 5.23 4.37 15 00 NONE P/HP PAR 48 ARM-48-HPCI PP/TURB RM 0,23 0.23 15 00 NONE R/HP P ARS3 ARM ACCS TO REM SHUTD 0.31 0.31 15.00 NONE P/HP PAR 50 ARM-50-CR0 NORTH 0.76 0 81 15.00 NONE R/HP P AR51 ARM-51-CRD SOUTH 0.76 0.81 15.00 NONE R/HP PAR 52 ARM-52-RYCU PP ACCESS 0.50 0.50 15.00 NONE R/HP P AR54 ARM-54-FUEL POOL PP ROOM 0.21 0.21 15.00 NONE R/HR PAR 49 ARM-49-REFUEL FLOOR ARE A 0.41 0.41 15 00 NONE P/HP VII-51
UNIT 1, P AGE 10F i GROUP POINT DISPL AY SERVICES 19-Feb-92 17 45 GROUP NUMBER :10 HI R ANGE ARM RE ADINGS (E-PL AN DISPL AY) POINT NO. DESLRIPT10N ALARM IS VAS HIGH LOV ST ATE NOV LAST Ltili LIMI . UNITS I PAR 56 ARM-56-RHR ROOM LOOP 8 0.44 0.44 15.00 NONE RiHR j PAP 55 ARM-55-RHR ROOM LOOP A 0.51 0.56 15.00 NONE R/HP l P AR57 ARM-57-RCIC PP TUR8 RM 5.91 5.23 15 00 NONE R/HR P AR48 ARM-48-HPCI PP/TUR8 RM 0.23 0.23 15.00 NONE R/HR PAR 53 ARM ACCS TO REM SHUTD 0.31 0.31 15.00 NONE R/HR PAR 50 ARM-50-CRD NORTH 0.71 0.76 15.00 NONE R/HR PAR 51 ARM-51 -CRD SOUTH 0.71 0.76 15.00 NONE R/HP PAR 52 ARM-52-RVCU PP ACCESS 0.50 0.50 15.00 NONE R/HP PAR 54 ARM-54-FUEL POOL PP ROOM 0.21 0.21 15.00 NONE R/HR PAR 49 ARM-49-REFUEL FLOOR ARE A 0.41 0 41 15.00 NONE R/HR UNIT 1, P AGE 10F 1 GROUP POINT DISPL AY SERvlCES 19-Feb-92 18 00 GROUP NUMBER :10 HI R ANGE ARM RE ADINGS (E-PL AN DISPL AY) . PONT NO. DESCRiPT10N AL ARM IS YAS Hl0H LOV STATE NOV LAST LIMIT LIMIT UNITS PAR 56 ARM-56-RHR ROOM LOOP B 0.44 0.44 15.00 NONE RiHE PAR 55 ARM-55-RHR ROOM LOOP A 0.48 0.51 15.00 NONE R/HR PAR 57 ARM-57-RCIC PP TURB Rc1 6.47 5.91 15.00 NONE R/HR PAR 48 ARM-48-HPCI PP/TURB RM 0.23 0.23 15.00 NONE R/HR P AR53 ARM ACCS TO REM SHUTD 0.31 0.31 15.00 NONE R/HP . PAR 50 ARM-50-CRD NORTH 0.67 0.71 15.00 NONE R/HP PAR 51 ARM-51-CRD SOUTH 0.67 0.71 15.00 NONE R/HR PAR 32 ARM-52-RVCU PP ACCESS 0.50 0.50 15.00 NONE R/HR PAR 54 ARM-54-FUEL P008 *P ROOM 0.21 0.21 15.00 NONE R /HR P AR49 ARM-49-REFUEL FLOOR ARE A 0.41 0.41 15.00 NONE R/HR VII-52
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V UNIT 1, P AGE 10F 1 GROUP POINT DISPL AY SERYlCES 19-Feb-92 18.15 OROUP NUMBER :10 HI R ANGE ARM RE ADINOS (E-PL AN DtSPL AY) POINT NO. DESCPIPTION AL ARM IS VAS HIGH LOV STATE NOV LAST LIMIT LeilT UNITS PAR 56 ARM-56-RHR ROOM LOOP B 0.44 0.44 15.00 NONE P/HR PAR 55 ARM-55-RHR ROOM LOOP A 0.46 0 48 15.00 NONE P/HR PAR 57 ARM-57-RCIC PP TURB RM 6.90 6.47 15.00 NONE P/HR PAR 48 ARM-48-HPCI PP/TURB RM 0.23 0.23 15.00 NONE P/HP PAR 53 ARM ACCS TO REM SHUTD 0 31 0.31 15.00 NONE R/HP PAR 50 ARM-50-CRD NORTH 0.62 0.67 15.00 NONE F/HP PAR 51 ARM-51-CRD SOUTH 0 62 0.67 15 00 NONE R/HP PARS 2 - APM-t.i2-RVCU PP ACCESS 0.50 0.50 15 00 NONE o/HR PAR 54 ARM-54-FUEL POOL PP ROOM 0 21 0.21 15 00 NONE R/HR P AR49 ARM-49-REFUEL FLOOR ARE A 0.41 0 41 15.00 NONE R/HP UNIT 1, P AGE 10F 1 OROUP POINT DISPL AY SERVICES 19-Feb-92 18 30 GROUP NUMBER 10 HI R ANGE ARM RL ADINGS (E-PL AN DISPL AY) , - POINT NO. DESCRIPTION ALARM is Y AS H10H LOY ! C ST ATE NOV LAST LIMIT LIMIT UNITi P AR56 ARM-56-RHR ROOM LOOP B 0,44 0.44 15 00 NONE FiHP PAR 55 AP.M-55-RHR ROOM LOOP A 0.44 0.46 15.00 NONE P/HP PAR 57 ARM-57-RCIC PP TURB RM 7 22 6.90 15.00 NONE P/HP PAR 48 ARM-48-HPCI PP/TURB RM 0.23 0.23 15.00 NONE R/HP PAR 53 ARM ACCS TO REM SHUTD 0.31 0.31 15.00 NONE P/HR PAR 50 APM-50-CPD NORTH 0.63 0.62 15.00 NONE P/Ho PAR 51 ARM-51-CRD SOUTH 0.63 0.62 15.00 NONE P/HP PAR 52 ARM-52-RVCU PP ACCESS 0.50- 0.50 15.00 NONE P/HP PAR 54 ARM-54-FUEL POOL PP ROOM 0.21 0.21 15.00 NONE R/HR PAR 49 ARM-49-REFUEL FLOOR ARE A O.41 0.41 15.00 NONE P/HP v VII-53 I
UNIT 1, P AGE I 0F 1 GROUP PONT DISPL AY SERVICES 19-Feb-92 18 45 OROUP NUMBER :10 HI R ANGE ARM RE ADWOS (E-PL AN DISPL AY) PolNT NO. DESCRIPTION ALARM IS VAS HIGH LOV STATE Nov LAST LIMIT LIMIT UNITS P AR56 ARM-56-RtR ROOM LOOP B 0.44 0.44 15.00 NONE R/HR P AR55 ARM-55-RHR ROOM LOOP A 0.45 0.44 15.00 NONE R/HR PAR 57 ARM-57-RCIC PP TURB RM 7.82 7.22 15.00 NONE R/HR PAR 48 ARM-48-HPCI PP/TURB RM 0.23 0.23 15.00 NONE R/HR PAR 53 ARM ACCS TU REM SHUTD 0.31 0.31 15 00 NONE P/HP PAR 50 ARM-50-CRD NORTH 0.64 0.63 15.00 NONE R/HF PAR 51 ARM-51-CR0 SOUTH 0.64 0 63 15.00 NONE R/HR PAP 52 ARM-52-RYCU PP ACCESS 0 50 0.50 15.00 NONE R/HP PAR 54 ARM-54-FUEL POOL PP ROOM 0.21 0 21 15.00 NONE RiHR PAR 49 ARM-49-REFUEL FLOOR ARE A O.41 0.41 15.00 NONE R/HR O 9 VII-54
O , SECTION Vil - RADIOLOGICAL CONDITIONS PART H - Control Structure & Turb. Bldg. Area Radiation Monitor Readings Vll-55
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UNIT 1, P AGE 10F 1 GROUP P0HT OtSPL AY SERYlCES 19-Feb-92 15:45 GROUP nut 2ER .17 CNTRL STR APO RADY.4TE ARMS (E-PL AN DISPL AY) PONT N0. . C(SCRIPTION ALARM IS YAS HIGH LOY STATE N0Y LAST LtilT Lrili UNITS OAR 30 APM-38-P AD CEM L AB 0 03 0 03 4.00 NONE MR/H PAR 39 ARM-39-CONTROL ROOM 020 020 4 00 NONE MR/H
- t 1 ARO1
- CONTMN ACC R ANO HI R AD A 192 8.00 NONE NONE R/HR
- M AP02* CONTMN ACC R ANG HI R AD 8_ 184 5.00 NOE NONE G At Pd37 ARM-3"-STBY OAS TRE AT RM 0 03 0 03 4.00 NONE MR/H PAR 31 ARM-74-RY 646 CORR-SOUTH 0.40 0.40 15.00 NONE MR/H
-PAR 29 ARM-29-PY 646 COPR-NORTH 0.30 0.30 15.00 NONE MR/H P AR30 . ARM-30-RY 646 CORR-YEST 0.50 0.50 15.00 NONE MR/H ~ PAP 32 ARM-32-CTP1 ZONE SHOP 020 0 20 15.00 Nr% MR/H PAR 34 ARM-34-STOR + EQUP O 20 020 15.00 rXWE MR/H PAR 33 ARM-33-R AD Y ASTE CTRL ROOM 0.40 0.40 15.00 NOE t1t/H DAP29 ARM-29-RY DR TO 2 FL S A 0.30 0.30 4.00 NONE MR/H (
, P AGE 10F 1 GROUP PONT DISPL AY SERVICES I9-Feb-92 16 00 "sROUP NUMBER .17 CNTRL STR APO R ADY ASTE ARMS (E-PL AN DISPL AY)
PONT NO. . C{SCRPT10N AL ARM 15 YAS HIGH LOY STATE NOV LAST Lt1IT LtilT UNITS = P AR38 APM-38-9 AD CHEM L AB 0.03 0.03 4.00 NONE MR/HR PAR 39 ARM-39-CONTROL ROOM 0.18 020 4.00 NONE MR/HR M ARO14 CONTtt ACC RANO HIR AD A 188 192 NOE NONE R/HR M AR02* - . CONTtid ACC R ANO Hi R AD B 182 184 NOE NOE R/HR FAR37 AR!t37-STBY O AS TRE AT RM 0.03 0.03 4.00 NOM MR/HR PAR 31 arf +31-RY 646 CORR-SOUTH 0 40 0.40 15.00 NONE MR/HR P d29 AR!t29-RY 646 CORR-NORTH 0 30 0.30 15.00 NOE MR/HR PAR 30 ARM-30-RV 646 CORR-YEST 0.50 0.50 15.00 NONE MR/HR 0A&32 ARM-32-CTPL 20E SHOP 020 020 15.00 NOE MR/HR PAR 34 ARM-34-STOR + EQUP 020 020 15.00 NOE MR/HR -PAR 33 ARM-33-R AD V ASTE CTRL 'wo0M 0 40 0.40 15 00 NOE HR/}4t -PAR 28 arf +28-RY OR TO 2 FL S A '0.30 0.30 4.00 NONE MR/HR VII-57
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- NIT i, P AGE 10F 1 OROUP PONT DISPL AY SERYCES 19-Feb -92 16:15 ROUP nut 1BER .17 CNTRL STR MO R ADY ASTE ARMS (E-PL AN DISPL AY) 0"It NO. DESCRPT10N ALARM is YAS H10H LOY STATE foY LAST L MIT LMIT UNITS .AR38 ARM-38-R AD CHEM L AB 0.03 0 03 4.00 NONE MR/HR AR39 Asti-39-CONTROL ROOM 0.17 0.18 4.00 NONE MR/HR !AR01
- CONTMN ACC R ANO HIRAD A 186 188 NONE NONE R/HR
! AR02
- CONTMN ACC R ANO HI R AD 8 177 182 NONE NONE R/HR M37 MM-37-STBY G AS TRE AT RM 0.02 0.03 4.00 NONE MR/HR AP31 ARM-31-RY 646 CORR-SOUTH 0.40 0.40 15.00 NONE MR/HR AP29 ARM-29-RY 646 CORR-NORTH 0.30 0.30 15.00 NONE MR/HR AR30 ARM-30-RY 646 CORR-YEST 0.50 0.50 15.00 NONE MR/HR AR32 ARM-32-CTRL 30NE SHOP 0.20 0.20 15 00 N0ff W /HR AR34 ARM-34-STOR + EQUP 0.20 0.20 15.00 NONE MR/HR AR33 ARM-33-R AD Y ASTE CTRL ROOM 0.40 0.40 15.00 NONE MR/HR AR28 ARM-28-RY OR TO 2 FL S A 0.30 0.30 4.00 NONE MR/HR 1, P AGE 10F 1 GROUP PONT DISPl. AY SERYCES 19-Feb-92 16 30 M P N.lliBER :17 CNTRL STR NO R ADY ASTE ARMS (E-PL AN DISPLM)
)lNT NO. DESCRPTION ALARM IS YAS HIGH LOY STATE N0Y LAST LMIT LIMIT UNITS AR38 ARM-38-R AD CHEM L A8 0.03 0.03 4.00 NONE MR/HR
'>AR39 ARM-39-CONTROL ROOM - 0 15 0.17 4.00 NONE MR/HR 1 AR01 + - CONTMN ACC R ANG HI R AD A 184 186 NOK NOE R/HR IAR02* CONTMN ACC 0 ANO Hi R AD B 173 177 N0E NONE R/HR 2AR37 ARM-37-STBY 0 AS TRE AT RM 0.02 0.02 4.00 NONE MR/HR EAR 31 APf4-31-RY 646 CORR-SOUTH 0.40 0.40 15.00 NONE MR/HR
.AR29 ARM-29-RY 646 CORR-NORTH 0.30 0.30 15.00 NONE MR/HR AR30 ARM-30-RY 646 CORR-YEST 0.50 0.50 15.00 NONE MR/HR 4R32 ARM-32-CTRL ZtM SHOP 0.20 0.20 15.00 NONE MR/HR
.34 ARM-34-STOR + EQUP 0.20 0.20 15.00 NONE MR/HR AR33 art 4-33-R AD Y ASTE CTRL ROOM 0.40 0 40 15 00 NOK MR /HR 4A28 arf 4-28-RY DR TO 2 FL S A 0.30 0.30 4.00 NONE MR s'HR VII-58
O JNIT 1, P A0E 10F 1_- GROLP PONT DISPL AY SERYCES 19-Feb-92 I6.45 AOUP NLt@ER :l7 CNTRL STR AE R ADY ASTE ARMS (E-PL AN DieJ'l AY) 20NT NO. - DESCRPTKW ALARM is YAS HOW LOY STATE N0Y LAST. L M IT LMIT UNITS
*AR38 ARM-38-R AD CEM L A8 0.03' O.03 4.00 NONE MR/HR *AR39- arf 4-39-CONTROL ROOM 0.14 0.15 4.00 NONE MR/HR 1 AR01
- CONTiti ACC R ANO HI R AD A 183 104- NOE - NOK R/HR MAR 02* CONTit ACC RANG HIRAD B 171 173 NONE NONE R/HR
*AR37 ARM-3T-STBY O AS TRE AT RM 0.02 0.02 4.00 NOME MR/HR
*AR31 ARM-31-RY 646 CORR-SOUTH 0.40 0.40 15.00 NOK MR/HR
*AR29- ARM-29-RY 646 CORR-NORTH 0 30 0.30 15 00 NONE MR/HR
*AR30 ARM-30-RY 646 CORR-VEST 0.50 0.50 15.00 N0E MR/HR SAP 32 ARM-32-CTRL ZONE SHOP 020 0 20 15.00 NONE tf/*
*AR34 ARM-34-STOR + EQUP 020 020 15 00 NONE ff/m
)AR33 ARM-33-R AD Y ASTE CTRL ROOM 0,40 0.40 15 00 NOK tP/HR 2AR28 ARM-29-RY DR TO 2 FL S A 0.30 0 30 4.00 NOME MR/HR
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, P AGE 10F 1 OROUP PONT DISPt AY SERVCES 19-Feb-92 17 'ROUP
> NUMBER :17 CNTRL STR AND R ADY ASTE ARMS (E-PL AN DISPL AY) 20NT NO. C{SCRPTION AL ARM IS YAS ' H KiH LOY STATE NOV LAST LMIT L MIT UNITS
*AR36 - ARM-58-R AD CHFM L A8 0.03 0.03 4.00 NONE MR/HR
- fAR39 - ARM-39-CONTROL ROOM 0.12 0.14 - 4 00 N0E MR/HR
- M AR01
- CONTit ACC R ANO HI R AD A 177 183 NOE NOE R/HR M AR02
- CONTMN ACC R ANG HI RAD D 170 171 N0E NONE R/HR FAR37 ARM-37-STBY 0 AS TRE AT RM 0.02 0,02 4.00 NOK MR/*
PA831 ARM-31-RY 646 CORR-SOUTH 0.40 0.40- 15.00 NOE MR/HR SAR29- ARM-29-RY 646 CORR-NORTH 0.30 0.30 15.00 NONE MR/HR
*AR30 ARM-30-RY 646 CORR-VEST - 0.50 0.50 15.00 NOK MR/HR *AR32 ARM-32-CTRL 20E SHOP 020 020 15.00 NONE MR/HR *AR34 ARM-34-STOR + EQUP 020 020 15.00 NONE t1R/HR SAP 33- ARM-33-R AD YASTE CTRL ROOM 0 40 0 40 15.00 NOK MR/HR *AR28 ARM-28-RY DR TO 2 FL S A 0.30 0.30 4.00 NONE MR/HR VII-59
I O NIT 1, P AGE 10F 1 OPOUP PONT DISPL AY SERVICES 19-Feb-92 17.15 ROUP NUMEtR ;l7 CNTRL STR Ato R ADY ASTE ARMS (E-PL AN DISPL AY) ONT NO. E(SCR PTION ALARM t$ VAS HIGH LOV STATE POV LAST L M IT LMIT UNITS AR38 ARM-38-R AD CEM t. A8 0.03 0.03 4 00 NOE MR/HR AR39 ARtt39-CONTROL ROOM 0.11 0.12 4 00 NONE MR/HR ltR01i CONTit ACC R Atc HI R AD A 175 177 NOT NONE R/HR 1 AR02 + CONTMN ACC RANG HI R AD 0 168 170 NOK NONE R/HR AR37 ARM-37-STBY O AS TRE AT RM 0.02 0.02 4.00 NONE MRAR AR31 ARM-31-RY 646 CORR-SOUTH 0.40 0.40 15.00 NONE MR/HR AR29 ARM-29-RY 646 CORR-NORTH 0.30 0.30 15.00 NONE MR/HR AR30 ARtt30-RY 646 CORR-VEST 0.50 0.50 15.00 NOE MR/HR AR32 ARM-32-CTRL ZOE SHOP 020 020 15.00 NOK tR/HR AR34 ARtt34-STOR + E0VP 020 020 15.00 NONE MR/HR AR33 ARtt33-R AD Y ASTE CTRL ROOM 0.40 0.40 15.00 NOE MR/HR AR28 ARtt28-RV DR TO 2 FL S A 0.30 0.30 4 00 NONE MR/HR 1, P AGE 10F 1 GROUP PONT DISPL AY SERVICES 19-Feb-92 17 30 ROUP NUMBER .17 CNTRL STR AND R ADY ASTE ARMS (E-Pt. AN DISPL AY) ORT NO. DESCRPTION AL ARM IS YAS HIGH LOV STATE NOV LAST LNIT L M IT UNITS AR38 ARtt38-R AD CHEM L AB 0.03 0.03 4.00 NONE PW/HR 2AR3C ARtt39-CONTRCL ROOM 0.10 0.11 4.00 NOK MR/HR
'i ARb CONTMN ACC R ANG HI R AD A 174 175 POE NONE R/HR 1AR02* CONTMN ACC R ANG Hi R AD 8 166 168 N0E NONE R/HR *AR37 ARtt37-STBY 0 AS TRE AT RM 0.03 0.02 4.00 NOE MR/HR 'AR31 ARM-31-RY 646 CORR-SOUTH 0.40 0.40 15.00 NONE MR/HR AR29 ARit29-RV 646 CORR-NORTH 0.30 0.30 15.00 NONE MR/HR M30 ARtt30-RY 646 CORR-VEST 0.50 0.50 15.00 NONE MR/HR AR32 ARtt32-CTRL ZOE SHOP 020 020 15.00 NOE MR/HR AR34 ARtt34-STOR + EQUP 020 020 15.00 NOE MR/HR ARI3 ARM-33-R AD V ASTE CTRL ROOM 0 40 0.40 15.00 NOE MR/HR AR28 art &28-RY DR TO 2 FL S A 0.30 0.30 4.00 NONE MR/HR t
VII-60
__ _ _. . ._ _ _ - . . _. m 1 JNIT 1, P AGE 10F 1 GROLP PONT DISPL AY SERYlCES 19-Feb-92 17.45 3ROUP NUMBER ;17 CNTRL STR AND R ADY ASTE ARMS (E-PL AN DISPL AY)
'ONT W DESC9Pil0N ALARM is YAS HIGH LOY STATE N0Y LAST L MIT LMIT UNITS '>AR38 ARM-38-R AD CKM L AB 0 03 0 03 4 00 NONE MR/HR 1AR39- ARM-39-CONTROL ROOM 0.09 0.10 4.00 NONE MR/HR 1 AR01
- CONTit ACC R ANO HI R AD A 172 174 NCE NONE R/HR 1AR02+ CONTMN ACC R ANG HI R AD 8 165 166 NOE NONE R/HR
AR37 ARM-37-STBY 0 AS TRE AT RM 0.03 0.03 4.00 NONE MR/HR
'AR31 ARM-31-RY 646 CORR-SOUTH 0 40 0.40 15.00 NONE N /HR
~?AR29 ARM-29-RY 646 CORR-NORTH 0 30 0.30 15.00 NONE MR/HR
*AR30 ARM-30-RY 646 CORR-YEST 0.50 0.50 15.00 NONE MR/HR
'AR32 ARM-32-CTRL ZOE SHOP 020 020 15 00 NONE MR/HR
'AR34 ARM-34-5 TOR + EOUP- 020 0 20 15 00 NONE MR/HR
'AR33 ARM-33-R AD Y ASTE CTRL RO3M 0.40 0.40 _15.00 NOK MR/HR
'AR28 - APfv29-RY DR TO 2 FL S A 0.30 0.30 4.00 NONE MR/HR O .
h P ACE 10F 1 GROUP PONT DISPL AY SERVICES 19-Feb-92 18 00 iROUP NUMBER :l7 CNTRL STR AND R ADY ASTE ARMS (E-PL AN DISPL AY) LOMT NO. DESCRPTION ALARM IS YAS H10H LOY
' ST ATE NOV LAST LMIT LNIT UNITS
'AR30 ARM-38-R AD CHEM L A8 0.03 0.03 4.00 NONE MR/HR PAR 39 ARtt39-CONTROL ROOM 0.09 0.09 4 00 . NOM MR/*
M AR01 + CONTW ACC R ANG HI R AD A 170 172 NOM NOK R/HR M AR02
- CONTMN ACC R ANG HI R AD B 165 165 NOK NONE R/N PAR 37 ARM-37-STBY 0 AS TRE AT RM 0.03 0.03 4.00 NOE MR/HR
*AR31 APJ&31-RY 646 CORR-SnUTH 0,40 0.40 15,00 NONE MR/HR
, W- ARM-29-RY 646 CORR-NORTH - 0 30 0.30 15 00 NOE MR/HR
'AR30 ARM-30-RV 646 CORR-YEST 0.50 0.50 15.00 NONE MR/HR
*AR32 ARM-32-CTRL 20E SHOP 020 0 20 15.00 NONE MR/HR
'AR34 ARh-34-STOR + EQUP 020 020 15.00 NONE MR/HR
*Apl3 ARM-33-R AD Y ASTE CTRL ROOM 0 40 0 40 15.00 NOK MR /HR
-'AR18 art +28-RY OR TO 2 FL S A 0.30 0.30 4.00 NONE MR/HR O VII-61
O JNIT 1, P AGE 10F 1 GROUP PONT DISPL AY SERVICES 19-Feb-92 18:15 3R0lP NUMBER :17 - CNTRL STR AND RADY ASTE ARMS (E-Pt AN DISPL AY) DONT NO. DESCRPTION ALARM IS YAS HIGH LOY ST ATE N0Y LAST LNIT L NIT UNITS MP39 art +38-R AD CHEM L AB 0.03 0.03 4.00 NONE MR/HR SAR39 ARM-39-CONTROL ROOM 0.08 0.09 4.00 NONE MR/HR
'1 AR01
- CONTFW ACC R ANG HI R AD A 170 170 N0E NONE R/HR MAR 020 CONTMN ACC R ANG HI R AD B 164 165 NOE NONE R/HR
*AR37 ARM-37-STBY G AS TRE AT RM 0.03 0.03 4.00 NONE MR/HR 2AR31 ARM-31-RY 646 CORR-SOUTH 0 40 0.40 15.00 NunE MR/HR *AR39 ARM-29-RY 646 CORR-NORTH 0.30 0.30 15 00 NONE MR/HR *AR30 ARM-30-RY 646 CORR-YEST 0.50 0.50 15.00 POC MR/HR >AR32 ARM-32-CTRL ZOE SHOP 020 020 15.00 NOE PR/HR 4 34 ARM-34-STOR + EOUP 0 20 020 15 00 NONE MR/HR aR33 ARM-33-R AD Y ASTE CTRL ROOM 0,40 0.40 15.00 NONE MR/HR )AR28 ARtt28-RV DR TO 2 FL SA 0.30 0.30 4.00 NONE MR/HR 1, P AGE 10F 1 GROUP PONT DtSPt AY SERVICES 19-Feb-92 18:30 3ROUP NUMBER .17 CNTRL STR AND R ADY ASTE ARMS (E-Pt AN DISPL AY) ,
20NT NO. DESCRPTION ALARM IS YAS HIGH LOY STATE NOV LAST LMIT LNIT UNITS
)AR38 ARti-38-R AD CEM L A8 0.03 0.03 4.00 NONE MR/HR PAR 39 ARtt39-CONTROL ROOM 0.07 0.08 4.00 NOE MR/HR MAR 010 CONTMN ACC R ANG HI R AD A 170 170 NCE NOE R/HR HAR02* CONTFW ACC R ANG HI R AD B 164 164 NOE NONE R/HR PAR 37 ARM-37-STBY G AS TREAT RM 0.03 0.G3 4.00 NOE MR/HR PAR 31 art +31-RY 646 CORR-SOUTH 0.40 0.40 15.00 NOE FR/HR *AR29 art 4-29-RY 646 CORR-NORTH 0 30 0.30 15.00 NONE MR/HR l)AR30 ARM-30-RY 646 CORR-VEST 0.50 0.50 15.00 NOE MR/HR l)AR32 art +32-CTRL 20E SHOP 020 0 20 15.00 NONE MR/HR >AR34 ARM-34-STOR + EQUP 020 020 15.00 NONE MR/HR >AR33 ARM-33-R AD VASTE CTRL ROOM 0 40 0.40 15.00 NOK MR/HR )AR28 art +28-RY OR TO 2 FL S A 0.30 0.30 4.00 NONE MR/HR 1
VII-62
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d NIT i,P AGE 10F 1 GROUP PONT DISPL AY SERYlCES 19-Feb ^2 18:45 ' R0l# NUMBER :17 CNTRL STR MO R ADY ASTE ARMS (E-PL AN DGPL AY) CMT NO. ((SCRPT KW ALARM iS YA$ HIGH LOV STATE N0Y LAST- L MIT LIMIT UNITS
'AR38; ARM-38-R AD CHEM L A8 0 03 0.03 4 00 NONE MR/HR 'AR39 art +39-CONTROL ROOM 0.06 0.07 4 00 NONE MR/HR 1 AR01 * - CONTMN ACC R ANO HI R AD A 170 170 NONE NONE R/HR 1AR02+ CONTMN ACC R ANO HI R AD B 164 164 NONE NONE R/HR *AR37 ARtt37-5TBY 0 AS TRE AT RM 0,03 0 03 4.00 NONE MR/HR AR31- APM-31-RV 646 CORR-SOUTH 0.40 0 40 15.00 NONE tiR/HR AP29= - ARM-29-RY 646 COPR-NORTH 0.30 0 30 15.00 NONE MR/HR AR30 ARM-30-RY 646 CORR-YEST 0.50 0.50 15.00 NONE MR/HR -AR32 ARM-32-CTRL ZONE SHOP 020 020 15.00 NONE MR/HR AR34 arf +34-STOR + EQUP 020 020 15.00 NONE MR/HR AR33 APft33-R AD VASTE CTRL ROOM 0 40 0.40 15.00 NONE MR/W.
AR29 ARtt28-RY DR TO 2 FL S A 0.30 0.30 4.00 NONE MR/HR VII-63
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1 NIT 1, P AGE 1 OF 1 GROUP Por4T Dl'dL AY SERYlCES 19-Feb-92 15 45 ROUP NUTTER .16 TURB BLDG ARE A R AD MONITORS (E-PL AN DISPL AY) ONT NO E{SCRPTION ALARM tS YAS HOH LOV 3 TATE N0Y LAST LtilT LtilT UNITS AP17 ARM-17-COND PUMP ARE A 0 59 0.59 4 00 NONE MW /H 4 07 ARM-07-OFFG AS BYP ASS ARE A 2.00 2.00 30 OG NONE MR/H AR18 ARM-18-RFPT ARE A 0 43 0.43 4.00 NONE MR/H c.R40 ARM-40-TURB BLDG ACCESS 0.05 0.05 4 00 NONE MR/H eR19 ARM AR EJECTOR ROOM 102.00 102.00 000.00 NONE 11R/H AR20 #FM-20-FDYTR E ATER ARE A 020 020 15.00 NONE t1R/H
*P21 APM-21-PECR MG SET APE A 0.38 0.38 4 00 NONE MR/H AR27 ARti-27-TURB ACCESS ROUTE 0.10 0 10 4.00 NONE MR/H AP24 ARM-24-TURB!NE FRONT END 0.12 0 12 4 00 NONE MR/H AR22 #M-22-GEN BAY ARE A 0 20 020 4 00 NONE MR/H AR23 ARM-23-HV AC EQUP ROOM 0 07 0 07 4.00 NONE MR/H s
GROUP PortT DISPt AY SERYlCES 19-Feb-92 161D0 OP AGE 1 OF 1 001.P NUMBER '16 TLM BLDG ARE A R AD MONITORS (E-PL AN DISPL AY) JNT NO. DESCRPTION AL ARM ts VAS HIGH LOV ST ATE NOV LAST LtilT LIMIT UNITS AP17 ARti-17-COND FUMP ARE A 0.59 0 59 4 00 NONE t1R/H A907 ARM-07-OFFG AS BYP ASS ARE A 2.00 2 00 30 00 NONE MR/H F' ARI S ARM-18-RfPT AP~ A 0 43 0 43 4 00 NONE MR/H PAR 40 A"ti-40-TURB Bt DG ACCESS 0 05 0 05 4 OG NOK MR/H PAR 19 ARM AR EJECTOR R00M 102.00 102.00 200 00 NOE MR/H P AR20 ARM-20-FDYTR FE ATER ARE A 020 0 20 15.00 NONE MR/H OAR 21 ARM-21-RECR MG SET ARE A 0 38 0.38 4 00 NONE MR/H AR27 ARti-27-TURB ACCESS R0lfTE 0.10 0.10 4.00 NONE MR/H AR24 AFM-24-TURB PE FRONT DO O 12 0.12 4.00 NONE t1R /H AR22 APM-22-GEN B AY ARE A 0 20 0.20 4.00 NONE MR/H AR23 ARM-23-HV AC EQUP ROOM 0.07 0 07 4.00 NON t1R/H O VII-65
I , P AGE 1 Cf 1 GROUP P0WT DISPL AY SERYlCES 19-Feb-92 16 15
>POUP NJMBER ;16 TURB BLDG ARE A R AD MONITORS (E-PL AN DISPL AY)
TNT NO. DESCRPTION ALARM IS VAS HIGH LOY STATE N0Y LAST LMIT LIMIT UNITS
'AR17 ARM-17-COND PUMP ARE A 0.59 0.59 4.00 NONE t1R/H *AR07 APM-07-OFF0 AS BYP ASS ARE A 2.00 2.00 30 00 NONE FR/H 4AR18 ARM-t 8-DFPT ARE A 0 43 0 43 4.00 NONE MR/H 'AR40 ARM-40-TURB BLDG ACCESS 0.05 0.05 4.00 f0T MR/H
~)AP19 ' 01 AR EJECTOR R00M 102.00 102.00 200.00 NOE MR/H
'AR20 ARM-20-FDVTR HE ATER ARE A 020 0.20 15.00 NONE MR/H 'AR21 ARM-21-FECR MG SET ARE A 0 38 0.38 4.00 NOE MR/H 'AP27 ARM-27-TURB ACCESS ROUTE 0.10 0.10 4.00 N0E MR/H ?AR24 ARM-24-TURBME FRONT END 0.12 0.12 4.00 NONE MR/H 'AR22 ARM-22-GEN B AY ARE A 020 020 4.00 NONE PR/H 'AR23 ARM-23-HY AC EQUP ROOM 0.07 0 07 4.00 NONE MR/H
. C'li
. I , P AGE 1 OF 1 GROUP PONT DISPL AY SERVCES 19-Feb-92 16.30 JP NUMBER 16 TURB BLDG ARE A R AD MONITORS (E-PL AN DISPL AY) 9 TNT NO. DESCRPTION AL ARM IS YAS H0H LOY ST ATE N0Y LAST LIMIT LIMIT UNITS 'AR17 ARM-17-COND PUMP ARE A 0.59 0.59 4 00 NONE MP/H 'AR07 ARM-07-OFFG A5 BYP ASS ARE A 2.00 2.00 30.00 NONE MD/H 'AR18 ARM-18-RFPT ARE A 0,43 0.43 4.00 NONE MR/H PAR 40 ARM-40-TUR9 BLDG ACCESS 0 05 0.05 4 00 NONE MR/H PAR 19' ARM AR EJECTOR ROOM 102.00 102.00 200.00 NOT FR/H PAR 20 ARM-20-FDYTR HC ATER ARE A 020 020 15.00 NONE MR/H OAR 21 dM-21-RECR MG SET ARE A 0.38 0.38 4.00 NONE MR/H
- AR27 ARM-27-TLRB ACCESS ROUTE 0.10 0.10 4.00 N0E MR/H
'AF24 ARM-24-TUR9NE FRONT END 0.12 0.12 4.00 NONE MR/H 'AP22 ARM-22-GEN B AY AREA 0 20 0 20 4.00 NONE MR/H 'AR23 ARM-23-HYAC EQUP ROOM 0.07 0.07 4.00 NOE MR/H VII-66
k i Ater, P AGE 10F 1 GROUP PONT D$PL AY SERVICES 19-Feb-92 16.45 ROUP !s)MBER :16 TlRB BLDO ARE A R AD MONITORS (E-PL AN DGPL AY) ONT NO. DESCRPTION ALARM G YAS HIGH ' LOV STATE N0Y LAST LtilT LtilT UNITS AR17 ARM-17-COND PUMP ARE A 0.59 'O.59 4.00 NONE MR/H AR07 ARM-07-OFF0 AS BYP ASS ARE A 2.00 2.00 30.00 NONE MR/H AR18 ARM-l8-RFPT AREA 0.43 0,43 4.00 NONE MR/H AR40 ARM-40-TURB BLDO ACCESS 0.05 0.05 4.00 NONE MR/H AR19 ARM AR EJECTOR ROOM 102.00 102.00 200.00 NONE MR/H
-AR20 . ARM"20-FDYTR E ATER ARE A 020 020 15.00 NOE MR/H
~
'AP21 ARM 21-REC't M0 SET ARE A 0.38 0.38 4.00 N0E MR/H
'AR27 ARM-27-TUR8 ACCESS POUTE 0.10 0.10 4.00 NONE MR/H
-AR24 ARM-24-TlRBNE FRONT E2 0.12 0.12 4.00 NONE MR/H AR22 ARM-22-GEN B AY ARE A 020 020 4.00 NONE W /H
'AR23 ARM-23-W AC EQUP ROOM 0 07 0.07 4 00 NONE MR/H s
P AGE 10F 1 GROUP PONT DISPL AY SERVCES 19-Fetr-92 17.00 GOUP RNBER :I6 TURS BLDO ARE A R AD MONITORS (E-PL AN DGPL AY)
- - ORT NO.. C{SCRPTON ALARM _ $ YAS H0H LOV
- ST ATE N0Y LAST LIMIT- LlilT _ UNITS AR17 ARM-17-COND PUMP AREA 0.59 0.59 4.00 NONE MR/H AP07 ARM-07-OFFO AS BYP ASS ARE A 2.00 2.00 30.00 'ONE MR/H 4AR18 ARM-18-RFPT AREA 0.43 0.43 4.00 NONE MR/H
*AR40 ARM-40-TURB BLDO ACCESS 0 05 0.05 4.00 NOE W /H
*AR19 ARM AR EJECTOR ROOM 102.00 102.00 200.00 NOM MR/H 5AR20 ARM-20-FDYTR HE ATER ARE A - 0 20 020 15.00 NOE MR/H
'AR21 ARM-21-RECR M0 SET ARE A 0.38 0.38 -4 00 - NOE MR/H AR27 ARM-27-TURS ACCESS ROUTE 0.10 0.10 4.00 NOE W /H
-AR24 ARM-24-TURBDE FRONT EE 0.12 0.12 4.00- NOE MR/H AP22 ARM-22-GEN BAY AREA 0 20 0.20 4.00 NONE MR/H
'AR23 ARM-23-HVAC EQUP ROOM 0.07 0.07 4.00 NOE . MR/H i
l . O VII-67 l
mT I, P A0E I 0F 1 GROUP PONT 0ISPL AY SERVCES 19-Feb-92 17.t5 O ROUP NUMEER :16 TLRB BLDG ARE A R AD MONITORS (E-PL AN DISPL AY) 1)MT NO. DESCRPTION ALARM 'S YAS HIGH LOV STATE N0Y LAST LIMIT tr11T LNITS
'AR17 ARM-17-COND P1XP ARE A 0.59 0.59 4.00 N0E MR/H
' AP07 ARM-07-OFF0 AS BYP ASS ARE A 2.00 2.00 30 00 NOT MR/H
'AR18 ARM-18-RfPT ARE A 0 43 0 43 4.00 NONE l-R /H
'ARGO ARM-40-TLRB BLDO ACCESS 0.05 0.05 4.00 NONE MR/H
'AR19 ARM AR EJECTOR R00M 102.00 102.00 200.00 NONE MR/H
*AR20 ARM-20-FDVTR HE ATER ARE A 020 020 15.00 NONE MR/H
'AR21 ARM-21-RECR MG SET ARE A 0.38 0.38 4 00 NOT MR/H
'AR27 ARM-27-TURB ACCESS ROUTE 0.10 0.10 4.00 NONE MR/H
'AR24 ARM-24-TURBNE FRONT END 0.12 0.12 4.00 PONE MR/H
'AR22 ARM-22-0EN B AY ARE A 020 020 4.00 NONE ff/H AR23 ARM-23-HYAC EQUP ROOM 0.07 0.07 4.00 NONE MP/H
' 1, P AGE 1 0F I OROUP PONT DISPL AY SERVICES 19-Feb-92 17.30 ROUP NUMBER :16 TLRB BLDG ARE A R AD MONITORS (E-Pt AN DISPL AY)
ONT NO. DESCRPTION ALARM IS VAS HIGH LOY STATE FOY LAST LIMIT LitilT UNITS AR17 art + 17-COND PUMP ARE A 0.59 0.59 4 00 NONE MR/H
'AP07 ARM-07-OfFG AS BYPASS ARE A 2.00 2.00 30.00 NONE MR/H
- PAR 1B . ARM-18-RFPT AREA 0.43 0.43 4.00 NOK MR/H
-PAR 40 ARM-40-TUR8 BtDG ACCESS 0.05 0.05 4 00 NOK MR/H IPAR19 ARM AR EJECTOR R00M 102.00 102.00 200.00 NONE MR/H PAR 20 ARM-20-FDYTR EATER AREA 020 0.20 15.00 NONE MR/H
'AR21 ARM-21-RECR MG SET ARE A 0.38 0.38 4.00 NONE MP/H 'AR27 ARM-27-TURB ACCESS ROUTE 0.10 0.10 4.00 NONE MR/H AR2O ARM-24-TURBNE FRONT DO 0,12 0.12 4.00 NONE t R/H l-AR22 ARM-22-GEN BAY AREA 0.20 0 20 4.00 NONE MR/H AR23 ARM-23-HVAC EQUP ROOM 0.07 0.07 4.00 NONE MR/H l
1 VII-68 9 l l
./ ( C'If)1, P AGE 10F 1 GROUP PONT DISPt AY SERYlCES 19-Feb-92 17.45
,ROUP NUMBER :16 TLRB BLDG ARE A R AD MONITORS (E-PL AN DISPL AY)
'ONT NO. DESCRPTION ALARM tS YAS HGH LOV
$ TATE NOV L45T LtilT L filT UNITS AR17 art 1- 17-COND PUMP ARE A 0.59 0.59 4.00 NONE MR/H
'AR07 ARM-07-OFF0 AS BYP ASS ARE A 2 00 2.00 30 JO NCNE MR/H
'ARIO ARM-18-RFPT ARE A 0 43 0.43 4.00 NONE MRiH AR40 ARM-40-TURB BLDO ACCESS 0.05 0 05 4.00 NONE MR/H AR19 ARM AR EJECTOR R00M 102 00 102.00 200.00 NONE MR/H AR20 ARM-20-FDYTR HE ATER ARE A 0 20 020 15.00 NONE MR/H AR21 ARM-21-RECR M0 SET ARE A 0.38 0.39 4 00 NONE t1R/H AR27 ARM-27-TUR9 ACCESS ROUTE 0.10 0.10 4.00 NONE MR/H AR24 ARM-24-TURONE FRONT END 0.12 0.12 4.00 NONE MR/H AR22 ARM-22-GEN B AY ARE A 020 0 20 4.00 N0f( MR/H AR23 ARM-23-HV AC EOUP ROOM 0 07 0.07 4.00 NONE MR/H
[ P AGE 10F 1 GROUP PONT DISPL AY SERYlCES 19-Feb-92 18 00
%/
ROUP NUMBER 16 TUR8 BLDG ARE A R AD MONITORS (E-Pt AN DISPL AY) ONT NO. DESCRPTION AL ARM IS VAS HIGH LOY STATE N0Y LAST L tilt trilT UNITS AR17 ARM-17-COND PUtf ARE A 0 59 0.59 4.00 NONE MR /H AR07 ARM-07-OFFG AS BYP ASS ARE A 2.00 2.00 30.00 NONE MR/H PARIS ARti-18-RFPT ARE A 0.43 0.43 4.00 NONE MRih o art.0 ARM-40-TURB BLDG ACCESS 0.05 0.05 4,00 NONE MR/H PAR 19 ARM AR EJECTOR ROOM 102.00 102.00 200.00 NONE MR/H PAR 20 ARM-20-FDYTR HE ATER Mtf A 020 020 15.00 NONE MR /H
'AR21 ARM-21-RECR MG SET AREA 0 38 0.38 4.00 NONE MR /H AR27 ARM-27-TURB ACCESS ROUTE 0.10 0.10 4 00 NONE MR/H AP24 ARM-24-TURSPE FRONT EM) 0.12 0.12 4.00 NONE MR/H AR22 ARM-22-GEN B AY ARE A 0.20 0 20 4 00 NONE MP/H AR23 ARM-23-HV AC EQUP ROOM 0.07 0.07 4 00 NONE MR/H VII-69 1
1 1
l
.. I , P AGE 10F 1 GROUP PONT DISPL AY SERYlCES 19-Feb-92 18 15 20UP NUMBER :16 TLRB BLDO ARE A R AD MOMTORS (E-PL AN DISPL AY) 3NT NO. DESCRPTION ALARM is VAS HIGH LOY STATE N0Y LAST LMIT L MIT UNITS AR17 ARM-17-COND PUMP ARE A 0.59 0.5) 4 00 NONE MR/H AP07 ARM-07-OFF0 AS BYP ASS ARE A 2.00 2.00 30.00 NONE MR/H ARIS ARM-18-RFPT ARE A 0 43 0.43 4.00 NONE MR/H AR40 ARM-40-TURB BLDO ACCESS 0.05 0.05 4.00 NONE MR/H AR19 ARM AR EJECTOR ROOM 102.00 102.00 200 00 NONE MR/H AR20 ARM-20-FDYTR E ATER ARE A 020 020 15.00 NOE MR/H
@ 21 ARM-21-RECR MO SET ARE A 0.38 0.38 4 00 NONE MR/H AR27 ARM-27-TURB ACCESS ROUTE 0.10 0.10 4.00 NONE MP/H 4R2O ARM-24-TUR8NE FRONT END 0.12 0.12 4.00 NONE MR/H AR22 ARM-22-0EN B AY ARE A 020 020 4.00 NONE MR/H AR23 ARM-23-HY AC E00F ROOM 0.07 0 07 4 00 NONE MR/H
~
"Y 1, P AGE 10F 1 GROUP PONT DISP 1 AY SERVICES 19-Feb-92 18:30 M)UP NUMBER .16 TUR8 BLDG AEt A R AD MONITORS (E-PL AN DISPL AY)
INTPC E{SCRPTION AL ARM fS VAS HIGH LOV ST ATE N0Y LAST L MIT LIMIT UNITS AR17 ARM-17-COND PUMP ARE A 0 59 0 59 4 00 NONE MR/H AP07 ARM-07-OFF0 AS BYP ASS ARE A 2.00 2.00 30.00 NONE MR/H P AR18 ARM-18-RFPT ARE A 0.43 ').43 4.00 N0E MR/H OAR 40 ARM-40-TURB BLDG ACCESS 0 05 105 4.00 NOE MR/H PAR 19 ARM AR EJECTOR R00M 102 A .02.00 200.00 NONE MR/H
?AR20 ARM-20-FDYTR H TER ARE A 020 020 15.00 NOE MR/H *AR21 ARM-21-RECR M0 SF" ARE A 0.38 0.38 4.00 NONE MR/H d27 ARM-27-TURB ACCESS ROUTE 0.10 0.10 4.00 NOK MR/H AR2O ARM-24-TUR9NE FRCHT DO O 12 0,12 4 00 NONE MR/H 4 22 ARM-22-0EN DAY AREA 0 20 0 20 4.00 NONE MR/H W23 ARM-23-HY AC EOUP ROOM 0.07 0.07 4.00 NONE MR/H Vll-70 1
P AOL I 0F 1 GROUP POINT DISPL AY SERYlCES 19-f eb-92 18 45 iROUP NUMBER :16 TURB BLDO ARE A R AD MONITORS (E PL AN DISF't AY) 1)NT NO. DESCRPTION M ARM IS VAS HG4 LOV STATE Nov LAST LIMIT LIMIT UNITS
'AR17 ARM-17-COND FW1P ARE A 0.59 0.59 4 00 NCHE MR/H 'AP07 ARM-01-O'FG AS BYP ASS ARE A 2 00 2 00 30 00 NONE MR/H 'AE18 AEti-18-kFPT ARE A 0 43 0 43 4 00 NONE MK/H 'AR40 ARM-40-TURO BLDO ACCESS 0.05 0.05 4 00 NONE MR/H 'AR19 ARM-t 9- AIR EJCTCR ROUM 102.00 102 00 200.00 NONE MR/H 'AR20 .TM-20-FDYTR tE ATER ARE A 0 20 0.20 lb 00 NONE MR/H 'AR21 ARM-21-RECR M0 SET ARE A 0 30 0 30 4 00 NONE MR/H 'AR27 ARM-27-TURB ACCISS ROUTE 0.10 0 10 4.00 NONE MR /H AR24 AE1+24-TUR8FE FRONT EPO 0.12 0 12 4 00 NCtd MR/H 'AR22 Arti-22JI4 8 AY AAf / 0.20 0 20 4.00 NO K MR/H AR23 ARti-23-HV AC E00? ROOM 0 07 0 07 4 00 tK M MR/H O
Vll 71
m 4 a _ _ +.-=.e m , m _.maa ama .w--a4 m- .Aa m. l l 4 j
~~
SECTION VII - RADIOLOGICAL CONDITIONS PART I In Plant Dose Survey Haps h i t l l VII 72 9 l r i-I
FEB, 1992 DRILL DATA REACTOR BUILDIWG - ELEY 645 RCIC AIRBORNE LEVELS AIRD0RNE - IODIME AIRBORNE - NOBLE GAS TIME CONC. WPC CONC. NPC 1330 TO HORMAL NORMAL NORMAL NORMAL 1630 1645 1.3 E-6 40 1.6 EO 4.4 E5 1700 2.4 E-7 8 3.1 E-1 9.1 E 4 1715 3.3 E-7 11 4.5 E-1 1.2 E 5 1730 4.2 E-7 14 5.7 E-1 1.5 E 5 1745 4.9 E-7 18 6.8 E*1 1.8 E 5 1800 5.5 E-7 21 7.8 E-1 1.9 E 5 1815 6.2 E-7 24 8.7 E-1 2.1 E 5 1830 6.7 E-7 26 8.8 E-1 2.2 E 5 1845 8.2 E-7 35 1.2 EO 2.6 E 5 CT v e s V11-73
l -. i E + NENOO . cMJ f O
@O, O"g..
"m8 9:N e ty e
49 x i o3 L h PO x 04 IL~., l lh h~ , p
* ====w-
*O g a
~
ll' 1* 7
= [~ 7 __
y C _ n'* *" d 55 % _ $y 01 0 F.* O ~6 O _ O A 21 8t [_ m @$ ,. m> TIB, 1992 DRILL DATA REACTOR BUILDING - ELEY 645 DO8E RATE IN NR/RR TIME AAEA A AREA B AM7 C AMA D AREA 5 l AARA F
- AIR 30mA!E AIRaoRNE RHR RER COM 100!ME NCBLE CAS A B RCIC HPCI SPRAY SUMF CONC KPC CONC KPC l
(( to NORMAL NORMAL NOMAL NCANAL NORMAL NOMAL HQM NOM NOM NOM S 1630 4 1545 1050 . 285 285 1600 900 225 225 T615 800 210 210 1630 750 200 200 7 1645 700 17 17,200 185 13 10 1.2 .01 1.5 E-4 45 E-10 1700 600 12 3,300 175 13 5 4.4 .005 5.7 E-5 16 E-11 1715 550 15 4,375 130 16 8 1.1 .01 1.2 E-4 J3
, _ 3-10 1730 560 20 5,250 90 20 11 1.5 __.01 2.1 E-4 54
~ 3-10
- 1745 505 22 5,900 70 23 15 2.2 .02 3.1 E-4 78 E-10 1800 480 27 T,475 75 28 20 3.0 .03 4.2 E-4 104 __
~ E-10 1415 455 31 6,900 75 32 24 3.9 .04 1.5 E-4 131 2-10 1830 435 35 7,225 75 36 28 4.8 .C5 6.9 E-4 159 j 3-10 1845 445 50 7,820 90 50 42 8.9 .10 1.3 E-3 213 E-10 A!RBORNE AND 0085 RATES ARI 1/10 IN STAIRWAYS VII-74 mrezn____ _- ___ _ ___ _
c= 3 c.3 - 2-c:s es ri '1 .r - . M 4.. k ). ') O Srw C m' . J
% 1 i
.. b A B R*p
- e b l
- x .
. ; a:k...d a.
...:7
?
m.
"R FEB, 1992 0111J. DATA ,
REAC19R SUILDING - RIJV 883 . Dose RA*E IN MR/NR TIME AREA A AREA B AAAA C AAAA D AAAA B ATh F AIA90ANE O AIRBORNE IODINE NOBLE CAS EQUIP EQUIP RALLWAY CONC KPC CONC MPC SPACE SPACE ARRAS ~ 13JO to NORMAL NORMAI, NORMAL NORM NORM NORM NORM 1530
~
1845 1050 200
~ ~ ~
1600 900 185
~l'e ll 400 175 \
l 1630 ~150 160 V \ / 7 7 7 ? 1645 700 150 3 \ / 1.2 .01 1.5 E-4 45
\ / t-10 1700 , 600 150 3 \/ 4.4 _.005 8.7 E-l 16 A 3-11 1716 $50 140 6 /\ 1.1 . 0.* 1.2 E-4 33
/ \ E-10 1730 $60 135 10 / \ 1.5 .01 2.1 E-4 54
[ \ 3-10 1746___ Sol 130 13 j ( 2.2 .02 3.1 E-4 78
/ \ 3-10 1800 440 120 it / \ 3.0 .03 I2 E-4 104
/ \ 3-10 ~
~1618 "" 455 til 22 / \ 3.9 .04 S.h E-4 131
/ ~
\ 5-10 1830 435 110 26 \ 4.4 .06 6.9 t-4 159
~ \ 3-10 1845 448 115 40 j 8.9 .10 1.3 E-! 273
\
AzamRn AxD ooas urts ARs 1/10 IN stAtawArs V11-75
3-~ m e ;,,,
'tal x 26 l
'l o g7 g
- Du E 3 O _ , , , ,, . , . . . .
--e 1
~ "
gp /"3 ' A = g __ , .j s
- 4 ll=
* 'C5 J --A 1 . ii A--
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m R' E @ Ulllllll1 h - FEB, 1992 DRILL DATA ' RAACTOR SUILDING = FLEV 719 DOSE RATE IN MA/MR TIMA ARAA A ARRA B ,ARSA C AAAA D AAAA 8 AREA F AIRNORms AIRaoRNE 100!NE NOBLE CAS HCU's TIP RALLWAYS TIP CONC MFC CCNC KPC D R IVE S .._ NXet 1330 to NORMAL NoseEAL NORMAL NORMAL NORMAL Wolut NORM NORM NORM 1530~ 1548 1400 260 280 240 1600 1200 260 200 240 161$ 1100 220 188 220 1630 1000 200 160 200 y .,, ,, p 1645 950 190 130 190 ll 1.2 .01 1.5 E-4 en
\l 3-10 1700 850 110 100 170 U 4.4 .005 5.7 E-1 76
~ telt 1715 400 165 to 166 Ji 1.1 .01 E2 E-4 33 I\ E-10 1730 760 160 $$ 160 /\ 1.8 .01 2.1 E-4 54 f \ ~
W-10 ~ 1745 715 185 75 155 f \ 2.2 .02 3.1 E-4 78 I \ s-10 1400 670 150 70 160 3.0 .03 4.2 E-4 104 E-10 E9 1815 6U, 145 70 146 / \ .04 S.6 E-4_ 131
~ f \ R-10 ~30 1 ~7 ell 145 75 145 f \ 4.8 .05 6.9 E-4 159 1 \ _E-10 .
1845 640 160 90 160 f \ 8.9 .30 1.3 E-3 273 _ 7 I t-10 AIADORNE AND '9088 RATES AAB 1/10 IN STAIRWAYS VII-76
l M OOO M oo o l P O k
' 6 # '
O [ / I x 10 54 l ,
~~
A i 32 B "- " 5 ; k _
~
5 0 OO l __- A # ! _ v v.-amF - B Y_ l [l I C"3 ]I 1 FER, 1992 DRILL DATA
- REACTOR SUILDING - ELEY 149 D005 RATE IN MR/ER TIME A*AA A AAAA B AREA C AREA D ARSA E ASEA F AIRSORNE AIRBCMS 100!NE ?s05LE CAS OUTSIDE OUTSIDE CONC MPC CONC MPC RWCU FP PP RM 1J30 NO NORMAL
\ /
NORM NORM NOM NOM
~ ~ ~~~*
1545 1600 - 1616 mr- y y -- 1646 _ 3 3 y
\
7 1.2 y y , y
.41 1.5 8-4 45
\ I-10~
1700 3 3
%/ 4. 4 .0CS 5.7 E-l 16 A 5-11, 1715 4 6 1.1 .01 1.2 E-4 33 E-10~
1730 10 10 I.5 ~~
.01 2.1 E-4 54
'~~~ :-10 1745 13 13 I.2 ~ i.* 02 3.1 E-4 78 .
E-10 ~ 1800 it is / I.0
~ 03
. 4.2 E. 4 104 1816
~ / ~
\ E-10 22 22
/
/ \ I.9 ~
.04 5.5 8-4 131
\ 5-10 1830 26 26 / 4.8 .05 6.9 R-4_ 159 O _
1845 40 40 _/ ,,5*10 , 9 .10 1.3 E-3 273 A!MORNE AMU DOSE RATE 8 ARE 1/10 IN STAIRWAYS VI!-77
Ol NO '
,,A_ - # A* " _
I _. A 4 6 t_ , 1 1 I
\ h 9)
O r , 00 w- ( 2f 7 8:=8 ' t c==B, p [ 2 s eq [ WA. x 11 e FRS, 1992 DRI14 DATA REACT 00t 80!LDING = ILEY 779 , Does Rafs 1r an/nm T!WE AAAA A AAAA 8 AAAA C AREA D AAAA 3 AAAA F 'i AIRSORNh' AIRSORN! MALLWAT 10 DINE NOhLE GhJ COEC MP3 CCHC lAPC NORMAL
~
RW NO NORM NOAH "1845 i 1615 N / ~ l 1630 y ~
~
1645 J
\ ' '
y 9 9 y 1.2 .01 1.5 E-4 1700 J
\ / ~~ 3-10 ~
45
\/
A 4.4 .005 5.7 E-5 16 1718 4 ~ 3-11
\ I.1 .01 1.2 E-4 JJ 1730 10 '
~
I.S 1748 13
/ '\ -10 ~
.01 2.1 E-4 54 I.2 .02 3.1 E-4 78 lle7 18 /
/ \ I.0 ~
.03 4.2 E-4 104 Ital 22 % t-10 I9 .04 b,5 E-4 1J1 1830 26 /
/ \ 4.8 .05 6.9 E-4 159 1848
~~
40 T 8-10 8.9 .10 1.J E-J 273
- _ t - 10,, [
AIRDOmJr3 AMD Does RATas PJta 1/10 2M STAIRWAYS VII-78
[L . - e m" ,i in a a.. i -
,e aan j
~
AN O O _ . E x 46 *'
=x O o, .o e x 13 isg,{
g 15 s, 3
=,
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f l R 4 . i
.c- . - -: cap i;. . . : xa A t
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{'.': ,
, a m .
b,- "W wm ** 6 . TIB. 1992 DRILL DATA
- REACTOR BUILDING = ELEY 818 DOSE RATE IN MA/NA O TIME AAEA A ABRA B AAEA C AAAA D AREA 8 AAAA F AIADOME
!ODINE AIRSOME NOBLE GAS CONC MFC CONC MPC 1330 to NORMAL
, NORM NOM NOM NORM
_1530_ 1600 N% _/ _ I
\
/ I i 1615
/ '
i na 1645 y 3 x-% /
/ v v v e 1.2 .01 1.5 E-4 45 1700 3
\ / _s-10_
\/ 4.4 .005 4.7 E-5 16 1715 Y 5-11~
6 I.1 .01 1 2 E-4 33 1730 10 ~
/ % I.S .~ 01 2.1 E-4 54
/ \ E-10 ~
1745 13 I2 7T~~ 3.1 E-4 74 , 1400 la I.0 ~
.03
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- 4. 2 E "4 104 1815 22
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/ T I.9 ~
.04 5.5 E-4 131 1830 26
\ _ -10_
/ \ 4.8 .05 6.9 E-4 159
( 1.u
/ \ -10 40 7 y _.g , ,,,.10 1.3 E-3 m AIRSOME AND DOSI RATES ARI 1/10 IN STAIRWAYS VII-79
_ _ _ _ _ _. _ _ _ - - - - - - - - - - - - - - - - - -- ~
O SECTION Vil - RADIOLOGICAL. CONDITIONS PART J PASS Sample information h Vll-80 O
I O Pals ktAtt0t WAftt $AALL v0L Wt LIQUID Sa,McLt DATA 15:45 16:15 16:45 17:15 17:45 18:15 18n5 19:15 Tim to to to to to to to to 16:15 16:45 17:15 17:45 18:15 18:45 19:15 10:45 Sacote $tetion Stepst 8.1.3) to 8.1.52 2 2 2 1 1 1 1 1 RE*507 Monitor d/hr Sencle Line Dose Rt 664 Monitor W/hr 1064 912 836 760 722 v.6 608 570 leanter to shield Contact (2 inches) d /hr 14 17 11 10 9 8 8 7 6 inches
- W/hr 2 2 2 2 2 1 1 1 18 inches d/hr 0 0 0 0 0 0 0 0 36 inches d/hr 0 0 0 0 3 0 0 0 Sanples in Cask Contact (2 inche6) N /hr 0 0 0 0 0 0 0 0 6 inches d/hr 0 0 0 0 0 0 0 0 18 inches W/hr 0 0 0 0 0 0 0 0 36 inches 2/hr 0 0 0 0 0 0 0 0 a
4 l ( O Vll-81
l e PAtt REACTOR WATER LARGE VOLLME LIQUID $ARPLE DATA 15:45 16:15 16:45 17:15 17:45 18:15 18:45 19:15 Time to to to to to to to to 16:15 16:45 17:15 17:45 18:15 18:45 19:15 19:45 tenete station steps: 8.1.3* o B.1.52 2 2 2 1 1 1 1 1 RE 507 Monitor d/hr sogle Line Dose RE*664 Monitor 2/hr 1064 912 836 760 722 646 608 570 Samlet to Shield Cmtset (2 s. 3.es) 2/hr 1372 1176 '078 980 931 C33 784 735 - 6 inches d,': 224 192 176 160 152 136 128 120 18 inches e/hr 28 24 22 20 19 17 16 15 36 inches me /hr 7 6 6 5 5 4 4 4 sagte: In Cask Contact (2 inches) 2 /hr 0 0 0 0 0 0 0 0 6 inches ed/hr 0 0 0 0 0 0 0 0 16 inches 2/hr 0 0 0 0 0 0 0 0 36 inches e/hr 0 0 0 0 0 0 0 0 O VII-82 1
O SECTION VII - RADIOLOGICAL CONDITIONS PART K - CST Berm Water Concentrations O O Vil-83
l O 1 CST BERM AREA WATER CONC.!NTRATIONS (uCl/mi) NUCUDE 16:00 16:15 17:15 18:15 l131 1.20E-04 2.?9E44 7.09E44 1.17E43 Cr-51 1.24E 10 2.48E 10 7.40E 10 1.22E49 . Co 60 1.25E 10 2.49E 10 7.44E 10 1.23E 09 Cs-134 2.00E 10 3.99E 10 1.19E49 1.97E49 Cs 137 3 00E 10 S 005 10 1.79E 09 2 96E49 O l 9 Vil-84
O' e SECTION VII - RADIOLOGICAL CONDITIONS O raa1 i. - a e ste 8e4,84 2 orre act4v4 tie-I e O Vil-85
TBl /oFFGA $
?CW *E I TE1 tdt -
14:30 *EL. ' h.e OX TOT AL NUCLIOE ipCt/mm) i C1/cci (V8 mRhr)
, 6 c M L.lC.
0 00E+00 0.00C+00 2.56E-03 l I-131 i l-132 0.00E+00 0 00E+00 . LebCicM rit M f 713 I 0.00E+00 0 00E+00 l l-133 l-134 0.00E+00 0 00E+00 l l-135 0 00E+00___ 0.00E+00 i 10 00E+00 l l
', KR-85M I ? 00E+00 1t/.E-09 i KR-85 0 00(+00 0 GiX+00
', KR-87 , 517!-01 9 04E-M
'; KR-98 I01E+01 516E-09 i XE-133 IJTE+00 23?E-10
!XE-135 2 "E+ 01 475E-09
!1 19E+021 ctv ec c i 11/19/91 14:45 EEL FFOM NUCLIDE t pCi/mm'J J
S l-I31 0 00E+00 U l-132 0 00E+00 M l-133 0 00E+00 M l-134 0 00C+00 A i l -I35 0 00E+00 R I i0 00E+00 Y ! I 1 40C+01 lKR-85M KR-85 0 00E+00 l KR-87 7.10E+01 j KR-88 4 4eC+01 231E+00 lXE-133 XE-135 4 04E+01 i
~
- I . 73Ed2 , Etv cot 1P 1 11 0 /41 15*45 PElfROM
_NUCLtDE ipCl/mm') S l-131 0 00E+00 U I-132 0 00E+00 M l-133 0.00E+00 M l-134 0 00E+00 . A i l-135 0 00E+n0 R i 0 00E+00 Y ! I KR-85M 1 ?SC+01 KR-85 0 00E+00 KR-87 5 68E+01 KR-98 512E+01 , XE-133 431 E +00
)
VII-86 i XE-135 5 6SE+01 ' 1 87E+02
O SECTION VII RADIOLOGICAL CONDITIONS PART H RCIC Room Activities Vll 87
RC/C acv o 1 } C . ii A 9/;e/91 17:15 FEL FROM CONC 10TAL CONC TO T AL 5GT5 NUCLIDE (#Ct/mm) (pC1/ce) (v0 mR/tri (sti/cc) (YD mR/tr) (pCi/mmi g
4.24E+03
() S U
l-131 l-132 8 04E-02 7.t 8C-02 5.68E-08 5.00E 08 1 55E-1I 1 !!E-11 5 92E+00 1 32E-05 M l-133 1.70E-01 120E-07 3 2SE-11 M l-134 3 62E-02 2.56E-09 6 27E-12 A l-135 1 21E-01 8.56E-08 2 3'E-11 R 4 80E-01 Y TCT AL k0 KR-63M 394E+04 2??C-02 7 45E-06 1 04E+04 KR-85 452E+03 129E-03 3 5t E-07 KR-07 1.79E+04 1.2?E-02 3 20E-06 KR-88 637E+04 4 9?E-02 1 30E-05 XE-133 234E+05 2.06E-01 5 68E-05 XE-135 215E+05 1 52E-01 4 11 E-05 16.38E+05 ptv cce e i oc c oc c ccee a l tcmc#3 ccee 2 1 1 i , ." /41 17:30 PEL FRt't1 00K TOT AL CONC TOTAL Wi5 NUCLIDE (pct /mm) (pC1/ce) IVB mR/hr) (pct /cci (VB mR/tr) (pct /mm)
S l-131 1.0$E-01 7 41E-09 5 14E+03_ 2.71 E-11 9 50E+00 2.30E-05 U 1-t32 8.40E-02 5.9?E-08 2 (PE-t l-.
M l-133 2.20E-01 155E-07 5 65E-11
- M l-134 3.56E-02 2.52E-08 7 94E-12
/' -
A l-135 1 $~T-01 106E-07 3 %E-11
\ R 5.97E-O t Y TOT AL NG KR-85M 4 96E+04 34?E-02 1 22C-05 1 75E+04 KR-85 2 37E+03 166E-03 615E-07 KR-87 1.9?E+04 1!6E-02 4.50E-%
KR-88 9 32E+04 5 88E-02 2 06E-05 XE-133 3S4E+05 2.71E-01 9.90E-05 XE-135 273E+05 1 9?E-01 6 9?E-05 8.10E+05 ptv l cce* i occ pcc comp 2 I cone I,1 co#41 l il/29/91 17:45 PEL FROM CONC TOT AL CONC IOT AL SGT5 NUCLIDE (gCt/mm) (pC1/cc) (YB mR/hr) (pct /ce) (YD mR/tr) (pct /mm) S l-131 1.28E-01 9 07E-08 5.84E+03 415E-11 1.34E+01 [53E-05 0 1-132 9.21E-02 6.5 t E-08 2.79E-11 M l-133 2 66E-0$ 1 88E-07 8 55E-11 M l-134 3.30E-02 2.33E-08 9 96E-12 A l-135 1 90E-01 127E-07 5 68E-11 R 6.99E-01 Y TOT AL NO KR-85M !62E+04 3.9?E-02 1.76E-05 2 62E+04 KR-85 2.9 I E+03 2 06E-03 9 42E-07 (' N , KR-07 1.94E+04 137E-02
. 5 54E-06 KR-88 9 32E+04 6 59E-02 285E-05 XE-133 4 69E+05 3 32E-01 152E-04 XE-135 326E+05 130E-01 1 04E-04 L 9.67E+05 VII-89
scv ccm i cec oc e ece.e A I acw i,a e cm 2 1 11/;1/91 18:00 6 EL f FiX t GWC TOTAL CONC TOT AL WT5 leuCLIDE (pct /mm) (pct /cc) (VB mR/tr) (pct /cc) (VB mR/tr) (pci/mmi S l-131 1 51E-01 1.07E-07 6.40E + 03 567E-11 136E+01 4.98E-05 U 1-132 971E-02 6.36E-08 3 48E-11 M l-133 3.09E-01 2.1 BE-07 1.1 oE-10 M l-134 2.95E-02 2.09E-08 914E-12 A l-135 2 04E-01 1 44E-07 7.71 E-11 R 7.90E-01 Y TOTAtto
' KR-85M 624E+04 4 41E-02 2 33C-05 3 60E+04 KR-85 3 4;E+03 24:E-03 1 33E-06 KR-87 1 ?M+04 1 ?!E-02 6 30E-06 KR-88 100E+05 7 09E-02 I65E-05 XE-133 5 51E+05 3 ??E-01 214E-04 XE-135 l T "TE+05 263E-01 1 42E-04 (1.1IE+06 ctv comp i ccc occ comp 2 I tcM 1,1 comp 1 l t1/29/91 18:15 PEL FROM CONC TOT AL CONC TOT AL %I5 NUCLIDE (pct /mm) (gCi/cci (VB mR/tr) (pCl/cc) (VB mR/tr) (pct / min)_
S l-131 1.72E-01 122E-07 6.83E+03 7 84E-11 217E+01 6.66E-05 U 1-132 9 97E-02 7.04E-08 4.1 I E-11 M l-t33 3.49E-01 2.4 7E-07 1 5&E-10 - M l-134 2.58E-02 182E-08 8 ?5C-12 A l-135 2 24E-01 1,58E-07 9 89E-11 R 8.71E-01 Y TOT AL NO KR-85M 6 75E+04 4 77E-02 2 92C-05 4.69E +04 KR-85 331E+03 237E-03 1 78E-06 KR-87 1.7tE+04 1 26 E-02 6 77E-06 KR-88 105E+05 7 43E-02 4 42C-05 XE-133 6 2?E+05 4 44E-01 2.86E-04 XE-13'i 4 1 M+05 2 9?E-01 1 85E-04 I.24E+06j , ocv ccee i oce oc c ec*e a l :cu i 2 cc+w a j iiit' .t t 8:30 PEL f ROM CCNC TOTAL CONC TOT AL MI5 feUCLIOE (pCl/mm) (pct /cc) (VB mR /tc) (pCi/cc) (VB mR /tr) (pct /mm'l__ S l-131 l.93E-01 1 36E-07 7.15E+03 i ole-10 2.59E+01 8 54E-05 U 1-132 1.00E-01 7.0*E-08 4 66E-11 M l-133 3.87E 01 2.73E-07 199E-10 M l-134 221E-02 II.6E-08 8.43E-12 A l-135 242E-01 1.7tE-07 Il2E-10 , R 9 44E-01 Y TOTALNO KR-85M 715E+04 5 05E-02 3.52E-05 5.88E+04 I KR-85 4 39E+03 310E-03 229E-06 KR-87 166E+04 1.17E-02 7.00E-06 l l KR-88 1OSE+05 7 62E-02 513E-OL l XE-133 7 03E+05 4 97E-01 3 67E-04 l XE-135 4 5TE+05 : 1 20E-01 2 30E-04 I.36E+06l VII-90
i prv coes i occ acc cc++ 2 i ross t1 cc+o i 1 ' 11/29/91 19:50 PEL FROM CONC 107 AL CONC TOT AL %T5 i IIUCLSE (MC1/mm) (DCike) (YB mR/k) (pCi/cc) (YBmRhr) (DCt/ min) S l-131 2.66E-01 1.96E-07 7.73E+03 2.1 I E-10 4.11 C+01 1.79E-04 U I-132 9.14E-02 6.46E-08 6.00E-11 M l-133 511E-01 3 61E-07 3.97E-10 M l-134 1.10E-02 7.77E-09 5.30E-12 A l-135 t W -01 205E-07 7.17f-10 R 1.17E+00 Y TOT At NO , KR-85H 7 %E+04 5 62E-02 5 74E-05 I.13E+05 KR-85 6 09E+03 8 30E-03 4 82E-06 l KR-87 1.1:E@ 7 37E-03 670E-06 KR-88 106E+05 7 5 E-02 7 27E-05 XE-133- 9 69E+05 6.85C-01 7.65E-04 XE-135 5 65E+05 3 90E-01 4 29C-04 I.74E+06
&
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O 9 SECTION VIII , O acssaac turoas411ou s"<<1s i r 2 ? e . O VIII-l
. . ~ , . . .. .-..-. .-. _-.. -._ - . _ . . - _ . - _ - - . . - . . - _ . _ _ _ _ _ . _ _ _ -
IS No. 1 Time: 1300 MESSAGE INFORMATION SHEET O MESSAGE FOR: Operations Personnel in Control Room MESSAGE FROM: Control Room Referee LOCATION: Training Center Simulator MESSAGE: "THIS IS A DRILL." The Initial Conditions of the plant which is the material under the tab of INITIAL CONDITION SECTION VI of the exercise manual. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: This material provides the initial conditions of the plant for the participants. Included in this section are the Daily Operating Reports, previous logs and turnover sheets, and Station Priority List. EXPECTED ACTIONS: The Operators will process the information as a normal shift briefing. After the classroom briefing the Operators will enter the simulator control room and start a walkdown of the control boards to familiarize themselves with the plant conditions. O VI!!-2 l
i IS No. 2 Time: 1300 MESSAGE INFORMATION SHEET 'V l MESSAGE FOR: Phone Company P6 1el l MESSAGE FROM: Lead Referee LOCATI0ll: S&A phone room and Simulator Control Room MESSAGE: "THIS IS A DRILL." SLA phone room telephone number - 3999. Hook up the Exercise communications equipment in the S&A phone room and the simulator control room, both the page and the telephones. Ensure the NRC red phone is hooked up and the plant radio is activated in the simulator control room. "THIS IS A DRILL." w_/ FOR REFEREE USE ONLY REFEREE NOTES: The communications equipment needs to be set up prior to the start of the exercise. EXPECTiD ACTIONS: The systems will be checked out prior to the start of the exercise. V Vill-3
IS No. 3 Time: 2300 MESSAGE INFORMATION SHEET O MESSAGE FOR: Simulator Instructor NESSAGE FROM: Referee Manual LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." Initialize simulator to IC #125. The following files are included in the IC: RH.92NRC - Initial Conditions RH.RADI - SPDS and Containment Rad initial Conditions RH.PMS65,60,67 - Initial ARM Data RH.WE3.1 Initial Weather Conditions "THIS IS A DRil.L" FOR REFEREE USE ONLY llll REFEREE NOTES: The IC sets the initial conditions sup)orted by the annunciator, operator logs, turnover sleets, etc. EXPECTED ACTIONS: Check the alarms aga4 st the annunciator 109, check equipment status of s1m versus status sheets, verify SPDS rad points active, verify weather conditions per Radiological section, verify ARMS are active and Unit 2 electrical line up. O Vill-4
IS No. 4 Time: 1300 MESSAGE INFORMATION SHEET MESSAGE FOR: Control Room and Onsite Personnel MESSAGE FROM: Operations in the plant Control Room LOCATION: Control Room A d[11ASE: "THIS IS A DRILL." The 1991 NRC GRADED FULL SCALE EXERCISE has begun. All exercise communications shall begin with "This is a Drill" and end with "This is a Drill." Line 3 of the plant page system is to be used for the exercise. Exercise Referees please mark the time as . "THIS IS A DRILL." REPEAT AB0VE MESSAGE. FOR REFEREE USE ONLY REFEREE NOTES: This message is to be passed over the PA system by Operations to note the beginning of the exercise. [XPECTED ACTIONS: Message to be announced over plant page system on line 3. The message shall be announced from the actual Control Room. O Vill-5
i l 10 No. 5 Time: 1330 MESSAGE INFORMCION SHEET O MESSAGE FOR: Public Information Center MESSAGE FROM: Actor at the River Intake Structure LOCATION: River Intake Structure HESSAGE: "THIS IS A DRILL." You don't know me but I have some important information for you and you should listen very carefully. Do I have your attention?? Something very unfortunate is going to happen at the power plant today and there is going to be a release of radioactive material that is going to cause some major problems for you. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: The message from an actor calling from the River intake Structure. The call is to initiate an UNUSVAL EVENT Classification. The call is being made from the River Intake Structure to provide information for the organization to investigate. The Information Center should hear the River Water Makeup pumps running in the background and the plant page. This information should be passed on to Security when the call is reported. EXPECTED ACTIONS: The Information Center will attempt to get as much information as possible from the caller before allowing him to hang up. They should attempt to determine who the caller is, why they are making the call, and the location that the call is being made from. When all the information is collected by the Information Center security will be called and a report made on what has transpired with the caller. O VI!!-6
IS No. 6 Time: 1415 NESSAGE INFORMATION SHEET O ESSAGE FOR: Operations Cc1 trol Room MESSAGE FROM: Simulator Instructor LOCATION: Simulated Control Room
-MESSAGE:' "THIS IS A DRILL." The "0FFGAS TROUBLE PANEL OC673" alarm is brought in by depressing the prearranged function button. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The alarm is to simulate an offgas explosion in the offgas inlet HEPA filter inlet isolation valve. The alarm is caused by pressure flow perturbations that would be expected by such an event. EXPECTED AtlLQRE: The Plant Control Operator will acknowledge the main control panel alarm and go to offgas panel 0C673 back-panel-to determine the cause of the event.- The information on the ba,k panel will indicate that an event occurred that requires investigation. Check of other plant parameters reveals that there is no obvious-effects as a result,.such as a loss of condenser vacuum. Vill-7
..._.._......a_,__._______ - _ _ __.,_.. _. _
IS No. 7 Time: 1415 e
.MISSAGE INFORMATION SHEET MESSAGE fur. Operators in Rad Waste Control Room MESSAGE FROM: In-Plant Team Referee LOCATION: Simulated Rad Waste Control Room MESSAGE: "THIS IS A DRILL." The "0FFGAS TROUBLE PANEL 1C322" alarm is alarming. "THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The alarm is to simulate an offgas explosion in the offgas . inlet HEPA Filter inlet isolation valve. The alarms are caused by pressure flow perturbations that would be expected by such an event EXPECTED ACTIONS: The Rad Wasto Operator will acknowledge the panel alarm and monitor the provided indications to determine the cause of the event. The Rad Waste Control Room Operator will dispatch an operator to attempt to determine the cause of the alarms. O Vlit 5
l-1 IS No. 8 Time: 1415 MESSAGE INFORMATION SHEET (~j v MESSAGE FOR: Simulated Rad Waste Control Room Operators MESSAGE FROM: Simulated Plant Worker 4 LOCATION: Simulated Rad Waste Control Room MESSAGE: "THIS IS A DRILL." This is John S*ir et in the Rad Waste Bnilding by the air coi.., -..er that is in the central area. I was out here cleaning up some oil dry and I heard a muffled bang or something and some vibration out here. It sounded like a water hammer but a little different if you know what I mean. "THIS IS A DRILL." G r -~s !) FOR REFEREE USE ONLY REFEREE NOTES: The Opere'. ors will acknowledge the call and tie it to the alarms just received and may determine that some kind of explosion took place in the offgas system. The operators will monitor the charcoal bed temperaturas closely to see if _ they are increasing which would indicate a fire in the beds. EXPECTED ACTIONS: The operators will init'. ate walkdowns of the ple t looking for equipment damage, and call the Cont Room to report what has happened along with the call from the field, r^x C VIII-9
IS No. 9 Time: 1420 MESSAGE INFORMATION SHEET O MESSAGE FOR: Turbine Building Operator MESSAGE FROM: In-Plant Team Referee LOCATION: Turbine Building Offgas Panel MESSAGE: "THIS IS A ORILL." The rei ee will provide the attached information for the operator investigating the panel alarms. The information is the alarms that are flashing and the meter indications. "THIS IS A DRILL." FOR REFEREE USE ONLY BfffREE NOTES: The indications given to the investigating operator are that a pressure flow perturbation has occurred in the system. No other abnormal indication will be observed. EXPECTED ACTIONS: The operator to investigate the panel, monitor the indications and will pass the information on that he has received to the Plant Control Operator. e i VIII-10
'IS No. 10 Time: 1420:
aESSAGE INFORMATION SHEET
. ti[$. SAGE FOR: Operator-Investigating Report in LRW MESSAGE ERQti: 'In-Plant Team Referee LOCATION: Rad _ Waste Building 4
MESSAGE: THIS IS A DRILL." Refer to the attached drawings of the Rad Waste Building for- the location- of.the damage and leak in the - offgas. system. The release from the-leak will cause high airborne in the valve vault but will not be detected outside the room since ventilation is into the. room. .The operator wili-see damaged lagging and packing. "THIS IS A DRILL." p
'FOR REFEREE'USE ONLY
. REFEREE NOTES: _The leak in the offgas: system is to push towards a
-classification at the ALERT level but not push a plant shut down. The plant needs to be as close _as possible to 100%
- for the next plant transient to provide credible fuel damage.
When it_is determined that there is a problem with the
- offgas system the_ determination will have-to be made-if it -
was/is an explosion-which affects plant operation. :The determinatior, will cause either an ALERT classification or remain.at an UNUSUAL EVENT. EXPECTED ACTIONS': The in-plant operat'or will report the findings to the Rad
- Waste Control Room, who will in turn brief the Control Room on.the findings of the plant walk down.
4%' O VIII-11 l l . 1
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l IS No. 11 Time: 1430 MESSAGE INFORMATION SHEET (D
%)
MESSAGE FQB: Control Room Operators MESSAGE FROB: Simulator Instructor LQClHQN: Simulator Control Room MESSAGE: "THIS IS A DRILL." The simulator Instructor to initiate the Stack Honitoring alarm by tH nging in OVR A15E04. The STACK MONITORING HIGH ALARM is received due to the offgas leak in the valve vault in Rad Waste. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NQH S: The alarm is caused by offgas leakage into the valve vault room. -To control contamination the air flow is into the room, into the LRL' ventilation system which discharges into the Turbine Building Stack and monitored by the Turbine Building SPING. EXPECTED ACTIONS: The operators will acknowledge the alarm, inform the STA, and investigate the source. The operator. will not have other indications, such as rcom temperatures, area radiation monitors to help track down where the leak is coming from. Actual walk down of the plant will have to be done to determine the scurce of the leak. o e O Vill-IS l
IS No.12 Time: 1500 MESSAGE INFORMATION SHEET O
-MESSAGE FOR: Emergency Director MESSAGE FROM: Control Room or TSC Referee LOCATION: Simulator Control Room or TSC MESSAGE: "THIS IS A DRILL." When the results of the accountability are complete release the people from their accountability stations.
"THIS IS A DRILL."
FOR REFEREE USE ONLY k REFEREE NOTES: The release of the people from their accountability stations will allow them to resume their normal plant activities , EXPECTED ACTIONS: The Emergency Director will announce over the plant page system that the accountabilid.y is complete and all people may continue with their normal routine. 9 e 4 9 Vill-16
= . . . - -- . . . . . . . - .-- - - - - - ~. _- - . -
-IS No. 13 Time: 1505
~
-MESSAGE INFORMATION SHEET
^
MESSAGE-FOR: Emergency Director MESSAGE-FROM: Control Room or TSC Referee J.0 CATION: Simulator Control Room or TSC MESSAGE:' "THIS IS A DRILL." The Vice President to initiate a phone call to the Emergency Director-in the Control Room or in the TSC to ask if the EOF and General Office responders have been called out to support the security event. .The.VP is making the point that the event is already widely _known and there has been an enormous number of. inquires already from the general public and the press. FOR REFEREE USELONLY REFEREE NOTES: ~ The: call fram the VP is a prompt to ran the E0F and the General-Office facilities. The intent is to get the EOF responder:, on their way to the. EOF in a reasonable time frame so the exercise is not dragged out as a result.
-EXPECTED ACTIONS: The Emergency Director.will acknowledge the conversation of the-VP.and most;likely call out the EOF and General Office responders. If tne_ED does not-agree with the VP another promptLis to be issued at 1515 hours to initiate activation of the EOF and the General Office.
VIII-17
l IS No. 14 Time: 1515 MESSAGE INFORMATION SHEEY O MESSAGE F08: Emergency Director ESSAGE FROM: Control Room /TSC Referee LOCATION: TSC/ Control Room MESSAGE: "THIS IS A DRILL." Activation of the EOF and General Office response personnel is to be initiated at this time to support the exercise timeline. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: The exercise needs to be kept fairly close to the planned time line due to the large number of people involved with the exercise. EXPECTED ACTIONS: The Emergency Director will direct the communicator to initiate activation of the E0F and General Office facilities to support the security event that has occurred. 4 O l VIII-18
. .. . . . .. . - . - . _ - - . . , - - . ~ . .
l IS No. 15 Time: 1545 ; MESSAGE 'INFORMATION SHEET MESSAGE FOR: Simulater Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor will initiate the file RH.TUR0S. "THIS IS A ORILL." FOR EEFEREE USE ONLY
-REFEREE NOTES: ~ This file simulates a' load reject with a delayed turbine trip, slow reactor scram time, turbine over speed d damage, and indicated fuel damage as a result of the slow
' scram time.
The turbine overspeed is: caused by a control and stop valve sticking open on the. turbine trip. The fuel damage is caused by the power excursion as a result of the slow scram and high pressure transient.
--IXPECTED ACTIONS: The operators will follow their procedures and closely monitor the radiological instruments such as the Stack Monitoring, and Area Radiation Monitors. The suppression pool temperature will be monitored closely due to the unusually high temperature. The ' temperature of the .
suppression pool- started at an elevated value due to previous HPCI testing. , Declaration of the SITE AREA EMERGENCY will require activation of the EOF. O VIII-19
IS No. 16 Time: 1545 MESSAGE INFORMATION SHEET O liESSAGE FOR: Simulator Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room lie 15AG_f: "THIS IS A DRILL." The Simulator Instructor will initiate the file RH. . "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: This file simulates a decrease in the CST level as a result of the line break outside the HPCI room at the CST berm area on the HPCI full flow test return line to the CST. The level in the CST will not decrease below the 50% level unless the operators continue to run HPCI in the full flow test line up. The line penetrates the CST at the 50% level so water will not drain below that point. The suction of the HPCI and RCIC system are low in the tank so if the HPCI pump
- continues to run it will pump CST water out the break in the return to the CST.
EXPECTED ACTIONS: The operators will not recognize the problem with the broken l'.' at the CST until it is called in with the i next mes. age sheet. The CST low level alarm will-be received and the control room operators will initiate an , inves'.igation. VIII-20 L
IS No. 17 Time: 1550 s MESSAGE INFORMATION SHETT y3 V MESSAGE FOR: Control Room Operators MESSAGE FROM: Simulated Plant Worker LOCATION: Unit 1 CST Berm area MESSAGE: "THIS~IS A D?.ILL." 'This is John Doe out at the CST bers area. I'm-standing here at the page looking at water spraying all over trom what looks like a break in one of the pipes out here. "THIS IS A DRILL." 5'"# FOR REFEREE USE ONLY 1 REFEREE-NOTES: The Operators will acknr,wledge the call and monitor the CST indications. The break.in the line is not to inhibit any of
=the-plant operations.but'to provide a potential environmental problem for the E0F to deal with.
. EXPECTED'ACTIQHS: The operators will initiate an investigation of-the report from the CSi berm area by dispatching an operator Lto'the area to determine which pipe is leaking. -
4
- 'O VIII-21
- , - - - , , - , , , , ,.v. .c , y r
t IS No. 18 Time: 1615 MESSAGE INFORMA110N SHEET O MESSAGE FOR: Emergency Director MESSAGE FROM: Control Room /TSC Referee LOCATION: TSC/ Control Room MESSAGE: "THIS IS A DRILL." The classification at the ALERT classification level needs to be made at this time. The classification is to be made in accordance with the Fuel Cladding Failure. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: The exercise needs to be kept fairly close to the planned timeline due to the large number of people involved with the exercise. EXPECTED ACTIONS: The operators will continue monitoring the plant parareters and doing the required surveillances to prove that all the required equipment is operable. O VIII-22
IS No. 19 Time: 1630 MESSAGE INFORMATION SHEET (~y L) MESSAGE FOR: Simulator Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate the FILE: RH.RCOST which simulates a RCIC Turbine trip on overspeed. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: The Operators will acknowledge the main control room alarms and monitor the inox stions on the RCIC panel to determine the cause of the alarms. The transient starts with the RCIC turbine speed oscillating then increasi.ig rapidly _to the point of over speed. When the turbine goes to an over speed condition the steam lir' breaks causing steam to be released to the RCIC room. The RCIC room pressurizes lifting the steam vent panel blowing steam / vapor outside the building. The plume will be seen by the North Gate House portal monitors and the offsite teams. EXPECTED ACTIONS: The operators will follow their procedures and initiate an investigation of the alarms in the RCIC room. The operators will contact the TSC to explain the indications and the potential for upgrading the emergency to a SITE ' AREA EMERGENCY. The operators will be expected to rapidly depressurize the plant as soon as it is recognized that there is en unmonitored, untreated release going out the side of the (y) Reactor Building. VIII-23
IS Ho. 20 Time: 1630 i MESSAGE INFORMATION SHEET O MESSAGE F03: ASCC Security Controller MESSAGE FROM: Security Referee LOCATION: ASCC MESSAGE: "THIS IS A DRILL." You have just received a tamper switch alarm from the RCIC raom steam vent panel (TS 875). As you pan the TV camera to the area you observe a gray vapor escaping from the vent panel area. "THIS IS A DRILL." n FOR REFEREE USE ONLY REFEREE NOTES: Tt.e release of vapor out the steam vent will be for a limited amount of time, approximately a half hour. The vapor coming from the vent panel will be going in tne direction Of the Nortn Gate House, causing contamination on the ground around the vent and in the direction of the NGH. - EXPECTED ACTIONS: The ASCC controller will inform the Secur;ty Shift Supervisor of the alarm and the visual observations, dispatch a mobil patrol to verify the indications, and possibly dispatch a security officer to check the inside of the reactor building to determine if anyone entered the building via the steam vent panel. O VIII-24
IS No. 21 Time: 1635 MESSAGE INFORMATION SHEET MESSAGE tW: Mobil Security Officer Investigating RCIC Steam Vent Panel [ Alarm MESSAGE FROM: Security Referee Fi LQCA]!2<l: . Outside Reactor Building RCIC Steam Vent C
~
'E:
IL E: , liESSAGE: "THIS IS A DRILL." You see a gray vapor coming from the steam ? vent panel. The side of the building and the surrounding area is ?4 wet. "THIS IS A DRILL." 4 L FOR REFEREE USE ONLY REFEREE NOTES: The release of vapor out the steam vent will be for a limited amount of time, approximately a half hour. The vapor coming from the vent panel will be going in the direction of the North Gate House, causing contamination on the ground around the vent and in the direction of the NGH. If the officer ventures into this area or the plume path he f-will be considered contaminated. EXPECTED ACTIONS: The Mobil Patrol Officer will report back to the ASCC controller what he/she has observed in the area of the RCIC STEAM VENT. O VIII-25
m.-m --. IS No. 22 Time: I645 MESSAGE INFORMATION SHEET O 3 MESSAGE FOR: Security Access Control Officer MESSAGE FROM: Security Referee LOCATIO.H: North Gato House Portal Monitors ! . j Ne m. NESSAGE: "THIS IS A DRILL." The personnel portal monitors are alarming. p ' i. "THIS IS A DRILL." i
\
FOR REFEREE USE ONLY REFEREE NOTES: The monitors are alarming due to the plume travel over the North Gate House (NGH) from the RCIC room steam vent. For ti 3 exact radiation levels at the applicable time, use the radiological data in section VII of the manual. The portal monitors will not reset until the plume has passed over the NGH, EXPECTED ACTIONS: The Access Control Security Officer will inform the ASCC controller of what he has found from investigating the scene and request that Health Physics be contacted for support. O VIII-26
IS No. 23 Time: 1645 MESSAGE INFORMATION SHEET g U MESSAGE FOR: Public Information Center MESSAGE FROM: Actor at the River Intake Structure LOCATION: River Intake Structure MESSAGE: "THIS IS A' DRILL." - You don't knew me but I called before and want you to know I really didn't mean anything_to happen there at the plant and it really wasn't me that is causing all. the problems in
,the plant. Okay? Everything I said was just a joke. "THIS IS A-DRILL."
D U FOR REFEREE USE ONLY REFEREE NOTES: .The: message from an actor calling from-the River Intake Structure. The call is to stop any further investigations that.may be ongoing as a result of the initial call at the Deginning of the exercise. It'is also intended to tie-up any pieces so that:the referees do not have.to contini-support this piece of the exercise. EXPECTED ACTIONS: The'Information Center will attempt to get as much information as possible from the caller before allowing him to hang up. They should attempt to determine who the caller is, why they are making the call, and the location l that the. call is being'made from. 1 When all- the information is collected by the Information Center security will be called and a report made on what has. transpired with the caller.
'VIII-27
IS No. 24 Time: 1645 MESSAGE INFORMATION SHEET O MESSAGE FOR: Control Room Operators MESSAGE FROM: Simulator Inst rctor LOCATI0B:- Simulator Control Room MESSAGE: "THIS IS A DRILL." The Simulator Instructor to initiate the FILE RH.WE3.2 which is the meteorological conditions around the plant as indicated on PMS Format #47. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: There is no simulator model which drives the various computer points or meter indications for the weather conditions around the site. The weather conditions are required by the control room during an emergency exercise to plot plume travel, direct evacuation and response routes, and protect site personnel not evacuated. The rad levels in the plant for the in-plant team referees are provida on the building radiological maps in section VII of the Referee Manual. EXPECTED ACTIONS: The control room operators will monitor the weather conditions as indic ted on meters and computer displays and take appropriate action as dictated by plume travel and resultant doses / contamination. O VIII-28
'IS No. 25 !
Time: 1650 m MESSAGE INFORMATION SHEET MESSAGE'FOR: Operator Investigating the break in the RCIC Room MESSAGE FRON: In-Plant Team Referee LOCATION: Reactor Building-- MESSAGE:- '"THIS IS_A DRILL," The following information will be given to the investigating team when they have demonstrated the ability to obtain the information.- Any information that would be provided by - the senses, are to'be provided. (If it was supposed to be very hot and humid,1:it would be felt by the individual investigating.) The dose rates inside th? Reactor Building are normal, except in
- the RCIC room. See the Rad a p for RCIC room dose rates.
Reaching the RC10 Room door, the door will be warm with the sound of running water _ on the other side of the door. The running water is due-to the fire protection system being started automatically.
- Inside the room the dose rates are elevated, the room is warm, and
,f -the fire protection system has operated. The deluge of the fire A protection was-due to a_ steam leak in the room.
-The' simulated steam leak is located at the point where the main steam line.and the Aux steam line come together at the 1F045.
"THIS IS A DRILL." '
FOR REFEREE USE ONLY REFEREE NOTES: Ensure the any information given out is " earned" by the
-individual' investigating. The leakage after the RCIC steam line isolation valves go closed to the RCIC room is .
As long as the fire protection system is in service, fire protection water will accumulate on the RCIC Room floor at - the rate of 2 inches-an hour, unless the operators open the room drain or isolate fire protection to the room. EXPECTED ACTIONS: The investigating individual will be checking their-accumulated dose as they-enter the' Reactor Building. The individual will follow the directions provided at the TSC briefing and will report back to the TSC all that is determined. O v VIII-29
IS No. 26 Time: 1650 MESSAGE INFORMATION SHEET O MESSAGE FOR: Pump House Operator lifJi10GE FROM: In-Plant Team Referee LOCATIOB: Circ Water Pump House MESSAGE: "THIS IS A DRILL." The Motor driven fire pump is running and any attempts to shut it down cause it to restart. The level in the Clarified Water Tank is decreasing indicating flow in the system.
"THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The Fire Pump will remain running and not be able to be shut down until the fire protection to the RCIC room is isolated. EXPECTED ACTIONS: The operator will contact the Control Room and report that he is unable to shut down the fire pump that it continues to run. He will also pass on that the Clarified Water tank level is decreasing and ask if the suction should be shifted to the cooling tower. O VIII-30
IS No. 27 Time: 1650-NESSASE INFORMATION SHEET
. MESSAGE FOR:' Chemistry Technician MESSAGE FROM: -Chemistry Referee -
- LOCATION: Chemistry _ Lab
- MESSAGE:- "THIS IS A DRILL." Provide the Chemist with the values provided in the R diological section,- Section VI of the manual. "THIS IS A DRILL.
4 _. _
. .FOR REFEREE USE ONLY kEFEREE NOTES: The sample will come from the PASS station at the-Training Center.and will indicate the damaged fuel. The chemists will receive information based on~ t',teir proper actions to obtain.-the sample and the results from counting the samples.
EXPECTED ACTIONS: The Chemist, providing the proper steps were taken to obtain the sample results and the proper technique was-used, will receive the sample results. and pass that information to-the Chemistry Coordinator. t-9 i 1 r VIII-31
IS No. 28 Time: 1655 MESSAGE INFORMATION SHEET O MESSAGE FOR: Offsite Monitoring Teams MESSAGE FROM: Offsite Monitoring Team Referee LOCATION: In Field HESSAGE: "THIS IS A DRILL." The radiological data for the offsite teams is located in section seven (7) of the exercise manual. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: The monitoring teams will be given infortc. tion (raw data) based on sampling procedures / techniques, location in the field relative to plume centerline, and questions asked. EXPECTED ACTIONS: The EOF Emergency Monitoring Team Director is expected to have the teams dispatched to the sectors between North and West. O VIII-32
IS No. 29 Time: 1655 l MESSAGE INFORMATION SHEET p G MESSAGE FOR: Control Room Operators MESSAGE FROM: Simulator Instructor LOCATION: Simulator Control Room MESSAGE: "THIS IS A DRILL." The simulator Instructor to initiate the FILE RH.WE3.3 which is the meteorological conditions around the plant as indicated on PMS Format #47. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: There is no simulator model which drives the various computer points or meter indications for the weather conditions around the site. The weather conditions are required by the control room during an emergency exercise to plot plume travel, direct evacuation and response routes, and protect site personnel not evacuated. The rad levels in the plant for the in-plant team referees are provided on the building radiological maps in section VII of the Referee Manual. f2fECTED ACT_lg!1: The control room operators will monitor the weather conditions as indicated on meters and computer displays and take appropriate action as dictated by plume travel and resultant doses / contamination. 4 l l VIII-33
IS No. 30 Time: 1655 MESSAGE INFORMATION SHEET O MESSAGE FOR: Health Physics Tech nosponding to NGH ) HESSAGE FROM: In-Plant Team Referees ; LOCATION: Plant and Site MESSAGE: "THIS IS A DRILL." The Health Physics Tech will respond from the Unit one HP office and walk out the S&A building toward the North Gate House to investigate the alarming portal monitors. "THIS IS
^ DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The HP Tech will be informed of the radiological conditions to the extent he can measure. Only the information that the tech will be able to receive from the instruments that he has brought to the scene will be given and it will be given only to the extent that proper collection technique is demonstrated for the samples. EXPECTED ACTIONS: The Health Physics Tech will obtain radiation and contamination readings from the Gate House and inform the TSC of the information collected. , O VIII-34
't IS No. 31 Time: 1700 MESSAGE INFORMATION SHEET MESSAGE FOR: In-Plant Teams Resetting RCIC BDDs MESSAGE FROM: In-Plant Team Referee LOCATION: RCIC Back Draft Dampers HESSAGE: "THIS IS A Drill." The operators will be dispatched to the Reactor Building to reset the RCIC back draft dampers so that the SBGTS will take suction on the room and reduce the activity that will leak out of the building through the unmonitored pathway.
"THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTF.S: To ensure that a minimum of radioactive material leaves the building through an unmonitored, untreated leak path the BDDs for the RCIC room will be reset. This will allow SBGTS to maintain a negative pressure in the room. EXPECTED ACTIONS: The operators will be briefed by the TSC and go into the plant to reset the BDDs. The Control Room will monitor the building delta P when the BDDs are reset. l O I
. f Vill-35 w
IS No. 32 l Time: 1700 1 MESSAGE INFORMATION SHEET MESSAGE FOR: Emergency Director Mf,SSAGE FROM: TSC Referee LOCATION: TSC HESSAGE: "THIS IS A DRILL." The r.lassification at the SITE AREA EMERGENCY level needs to be made at this time. The classification is to be made in accordance with the Steam Line Break EAL. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: The exercise needs to be kept fairly close to the planned timeline due to the large number af people involved with the exercise. EXPECTED ACTIONS: The Emergency Cirector will make the SITC AREA EMERGENCY classification and direct the comunicator tc bagin upgrade notifications, site evacuation, activation of the EOF and combat the emergency. O Vill 36
15 No. 33 Time: 1700 ; MESSAGE INFORMATION SHEET ! O l E.SSAGE FOR: General Office Engineering Support Manager E SSAGE FROM: Corporate Crisis Center
. LOCATION: General Office MESSAGE: "THIS IS A DRILL " This is the Corporate Crisis Center calling.
We have received numerous requests for information con:erning the site from within the company and also from outside. Would you please provide an overview of what-has happened so far, what you expect could happen from now on, when do you expect to have the plant in a stable condition, and is this going to be a long term shutdown for both units? If asked about grid stability the answer should be that the PP&L grid is in good shape, with no major problems foreseen. "THIS !S A DRILL." FOR REFEREE USE ONLY REFfREE NOTES: The information provided by the General Office should compare favorably with what has happened in the plant, fjPECTED ACT10Ei: The information received from the Corporate Crisis Center should be passed on to the_ remainder of the General E Office Staff. If the question of grid stability was asked that information is exoected to be passed on to the site as well as the EOF, L l I l l. l Vill-37
IS No. 34 Time: 1710 MESSAGE INFORMATION SHEET BEISAGE FOR: Operators / Security Walking Down Plant as a result of Security Threat MESSAGE FRQd: In Plant Team Referee LOCATION: Plant MESSAGE: THIS IS A DRILL." The original message that was called into the plant was not real thus no problems were found. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NOTES: The in plant investigation will reveal no problems since there never was an actual security threat inside the plant. EXPECTED ACTIONS: The in-plant operator / security will report the findings to the respective Shift Supervisors who will in turn brief the TSC Coordinators. O Vill-38
15 No. 35 Time: 1750
< ~s MESSAGE INFORMATION SHEET
( ) , 'u> MESSAGE FOR: OSCAR Monitoring Team MESSAGE FROM: OSCAR Referee LOCATION: In Field MESSAGE: "THIS IS A DRILL." Passing by the North East Cerner of the SLA Parking lot there is vapor coming off of the Storm sewer outlet.
"THIS IS A DRILL."
FOR REFEREE USE ONLY REFEREE NOTES: The monitoring team passing through the SLA North parking lot notices a vapor plume ccming from where the storm sewer discharges to the outfall. The warm water is coming from the CST berm drain. The water is leaking thr ugh a valve into the storm sewer. EXPECTED ACTIONS: The monitoring team will report the findings to the HP radioman who will inform the Rad Protection Coordinator. An investigation will be initiated to determine where the water is coming from and the extent of contamination. p V VIII-39
IS No. 36 Time: 1800 MF.SSAGE INFORMAT!0N SHEET 1 MESSAGE FOR: Offsite Monitoring Teams MESSAGE FROM: Offsite Monitoring Team Referee LOCATION: In Field ! l I MESSAGE: "THIS IS A DRILL." The radiological data for the offsite teams is located in section seven (7) of the exercise manual. "THIS IS A DRILL." FOR REFEREE USE ONLY-REFEREE NOTES: The monitoring teams will be given information (raw data) based on sampling procedures / techniques, location in the field relative to plume centerline, and questions asked. EEEE.CIED ACTIONS: The E0F Emergency Manitoring Team Director is expected to have the teams dispatched to the sectors between North and West. l till Vill-40 l
IS No. 37 Time: 1800 MESSAGE INFORMATION SHEET MESSAGE FOR: OSCAR Honitoring Team MESSAGE FROM: OSCAR Referee LOCATION: In Field MESSAGE: "THIS IS A DRILL " OSCAR reports the contamination valuas found on the vehicles in the NGH parking lot as a result of the plume passage. "THIS IS A DRILL," FOR REFEREE USE ONLY REFEREE NOTES: The monitoring team passing through the S&A North parking lot took surveys of the contamination found on the vehicles parked in the lot and is passing the information on to the TSC Rad Protection Coordinator, [E((TED ACTIONS: The monitoring team will report the findings to the HP radioman who will inform the Rad Protection Coordinator. A determination will have to be made as to what wili be done with the vehicles and_the personnel that have been evacuated from the site. d O l Vill-41 l
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IS No. 38 Tiine: 1830 MESSAGE INFORMATION SHEET tiESIMI_EQB: General Ofrice tiESSAGE FROM: Simulated Lieutenant Governor LOCATION: General Office MESSAGE: "THIS IS A DRILL." This is the Lieutenant Governor. The State is responding to the emergency and expects to have a team at the site by 1930 hours. We are also considering dispttching a team to your Main Offic( in Allentown, we-would like the following information, please:
- 1. ' need directions to the General Office from Harrisburg.
- 2. We will need space for 6 individuals at the General Office with phones available that have outside line capability.
- 3. The Governor is requesting a tour of the plant site first thino in the morning (0900) and will require escorted access for 6 people at the power station.
A briefing for each team upon arrival which includes current h 4. status of the plant, releases, and duration: plans for stopping releases; schedule and content of future briefings.
- 5. The Governor would like to hold a joint news conference in the morning after the tour of the nlant at you Media Operations Center.
Please FAX the above requested information to (717) 759 4946 marked ATTENTION: A. Male. "THIS IS A DRILL." FOR RErIREE USE ONLY
- REFEREE NOTES
- The General Office is expected to prepare the above requests i for transmission.
l EXPECTED ACTIONS: The General Office will fulfill the requests of the State and fax the material. O Vill 42
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IS No. 39 Time: 1845 MESSAGE IWFORMATION SHEET U MESSAGE FOR: Control Room Operators MESSA6E .f.[E: Simulator Instructor ' ' LOCATION: $1mulator Control Room j tiESSA01: "THIS IS A DRILL." The Simulator instructor to initiate the flLE RH.WE3.6 which is the meteorological conditions around the plant as indicated on PMS Format #47. "THIS IS A ORILL." O i l V FOR REFEREE USE ONLY i BEFEREE NOTES: There is no simulator model which drives the various i computer points or meter indications for the weather conditions around the site. The weather conditions are required by the control room during an emergency exercita to plot plume travel, direct evacuation and response routes, and protect site personrel not evacuated. The rad levels in the plant for the in-plant team referees are provided on the buil(ing radiological maps in section VII of the Referee Manual. EXPECTED ACTIONS: The control room operators will monitor the weather conditiont as indicated on meters and computer displays and take appropriate action as dictated by plume travel and resultant doses / contamination. Ylli-43 '
l 15 No. 40 Time: 1930 MESSAGE INFORMATION SHEET HESSAGE FOR: All Areas Via thL Plant Page NESSAGE FROM: TSC Comunications Referee and All Facility lead Referees LOCATION: Plant Control Room and All Errergency Response Facilities HESSAGE: "THIS IS A DRILL." The following page anr.ouncement is to be made from the plant Control Room: "The 1992 FULL 5CALE NRC GRADED EXERCISE is now terminated; the 1992 FULL SCALE NRC GRADED EXERCISE is now terminated." ( The Facility Lead Referees shall ensure that the exercise records are turned in and key individuals attend the area debriefing. Ensure that the telephone system and the plant page system are restored. Transfer the simulator radio back to the training condition and restore the simulator computer to normal operation. Ensure the response facilities are picked up and ready to respond to an actual emergency. "THIS IS A DRILL." FOR REFEREE USE ONLY REFEREE NAlli: The page announcement is to ae made in the following areas: The Simulator Coatrol Room The TSC The Plant The OSC The EOF The M0C The General Office EXPECTED ACTIONS: Ensure that all the previously notified offsite agencie:, are informed that the exercise is terminated. k O Vill-44 l
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lt O I I SECTION IX , EXERCISE QUESTIONS PART A - NRC QUESTIONS d n 4 IX-1
SSES ENERGENCY EXERCISE HRC QUESTIONS When the Control Room Comunicator calls for the initial notification, the simulated on-duty NRC Operations Center individual will ask if the Control Room is prepared to maintain an open line. The Control Room should respond with an affirmative. The following is a list of questions that can be asked of the Control Room /TSC/ EOF Comunicators. These questions en be asked periodically during the exercise to determine if the participan*.s are aware of plant conditions. Refer to the timeline for when significant events occur and note the time the Comunicator provides updated information. Verification of the information provided ty the Comunicator can be done by reviewing the print out of information from the simulator. The print out is located in the EOF next to the Offsite Dose overhead projector.
- What was the initiating event of the emergency?
e What is the expected duration of the emergency?
- Has there been any injuries to plant personnel?
e Have the NRC residents report to the Control Room yet? e What emergency operating procedures are presently in use? e Has a news release been initiated? e What is the Control Room ventilation line upt e What is the Reactor E ilding ventilation line up? e is the elet.tric plant line up normal? e is the Reactor completely shutdown? e Has boron been injected in the reactor vessel? e is the plant responding in a normal fashion? L 1 IX-2 O
o Give me the valaes for the following parameters: Steam Flow - Core Flow - Recire Pump Flow - Reactor Pressure - Reactor level - Recire Loop Temperature - Gross Coolant Activity - Dose Equivalent lodine - Drywell Pressure - Drywell Temperature - Drywell Radiation Levels - Drywell Oxygen Concentration - Drywell Hydrogen Concentration - Suppression Pool. Pressure - Suppression Pool Temperature - Suppression Pool Level - e What ECCS is in operation? HPCI ADS Core Spray
- LPCI ESW T Diesel Generators l - {v l
1 Batteries Ventilation e Is the TSC being manned? e is-the ECF being manned? e Has any outside support been requested? i e Has the stability of the grid been affected by the unit coming off line?
- Due to grid stability, what are the chances for a loss of offsite power?
I l () IX-3
o Review the values of the parameters given previously: Steam Flow - O Core Flow - Recirc Pump Flow - Reactor Pressure - Reactor level - Recire Loop Temperature - Gross Coolant Activity - Dose Equivalent lodine - Dryvell Pressure - Drywell lemperature - Drywell Rsdiation Levels - Drywell Oxygen Concer.tration - Drywell Hydrogen Concentration - Suppression Pool Pressure - Suppression Pool Temperature - Suppression Pool level - e Has the answer to any of the other questions changed? SECURITY EVENT QUESTIONS
- 1. How many individuals are attempting to penetrate the site? ,
- 2. Are any of the individuals armec^
- 3. Have you notified the local law enforcement authorities?
- 4. Has outside assistance been requested?
- 5. Have any of the individuals been apprehended?
ADDITIONAL QUESTIONS
- 1. Are there any abnormal inplant radiation levels?
- 2. What is the radiation level in the coatainment?
- 3. Is there a release in progress; if so, what are the current levels at the EPB, what is the current trend, hcw long do you expect to continue?
IX-4 O
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O 1 SEC;'ON IX - EXERCISE QUESTIONS , PART 8 - QUESTIONS / TOPICS OF DISCUSSION FOR HPN COMMUNICAiOR f. l O IX-5 l l _ _ . . . _ - . - - - _ _ , . . _ , . . _ _ _ _ . _ . - _ , , , . , , _ . ~ . . . . , . . _ . . . . = . . , _ _ _ _ . , . ._ . . . . . . . , . , , . _ , . - . . _ , - _ _ . , _ , - . . . _ ,
SSES EMERGENCY EXERCISE QUESTIONS / TOPICS OF DISCUSSION FOR HPN COMMUNICATOR The following questions to be asked by the individual playing the NRC Health Physics are generic in nature and can be made more specific and pointed depending on the type of scenario. This particular scenario has seasonal met condit(ons, including snow. Many different questions should be asked as a result of a release with precipitation; see the DOSE CALCULATOR and LICENSEE OFFSITE MONtTORING , tions. IN-PLANT QUESTIONS
- 1. Which unit is the affected unit?
- 2. What it the present classificationi
- a. What is the <.lassification based on?
- b. Is there a release in progress?
- c. Is the release monitored?
- d. Is the release being filtered?
- e. Is there fuel damage?
- 3. What is the Containment Radiation levels?
- 4. What is the airborne concentrations inside the containment?
- 5. What is the suppression pool activity?
- 6. What are the results of the reactor coolant samples? Is this a PASS sample? Wi,4t is the dose of the 10 ml PASS sample?
- 7. Has there been any emergency exposures?
- a. How many pcople?
- b. To what exposure level?
c, k* hat are the reasons for the emergency exposures? ,
- 8. What actions are being taken to terminate the release?
- a. What actions are being taken to minimize the release?
- b. Is there any way to hold up the release for decay?
- c. Is there any liquid release in progress?
- 9. Is the TSC, OSC, Control Room E0F all habitable? ,
- 10. Have all the non-essential people beer eva,.uated f om the site?
IX-6
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- 11. Was everyone accounted for during the accountability?
- a. Was search and rescue required to find any of the missing individuals?
- b. Is anyone still missing? j
- 12. Are 1%e countirg labs on site operable?
13, What is the operating status of your ventilation systems? l
- 14. What areas of the plant are affected radiologically by the accident? )
- 15. Are there any areas of the site that are enaccessible?
- 16. What are the contamination levels in the pl:nt and around the site?
- 11. What are'the airborne levels in the plant and around the site?
- 18. Has K1 been <iistributed or administered to the onsite emergency workers?
- 19. Kno or what group are your consulting physician (s)?
- 20. At what time was the TSC activated?
- 21. At what time was the EOF activated?
- 22. Who is the Radiation Protection Manager on duty?
- 23. Who is the Emergency Director?
- 24. Have there been any security events?
I' h r there been any injuries or fatalities? 2f; . W - there been anyone transported offsite to an area hospital?
- 27. Are you prepared to grant unfettered access to our NRC Response Team?
- 28. What protective action recommendations have been made for the sito personnel and/or the offsite populace at this time?
- 29. What-is the basis for making or not making a protective action recommendation at this time?
- 30. Have any of_the area sirens been sounded?
- 31. Have any surface sources such as the Spray Pond or lakes and reservoirs been affected.by the release?
- 32. Are these bodiu 9f water used for drinking water by anyone?
IX-7
- 33. Have environmental teams been dispatched at this time?
- 34. Are there any protective action recommendations being considered as a result of the environmental samples?
- 35. Are there any damage control teams presently dispatched in the plant? l What is the damage control team attempting to do at this time? l
- 36. Have any traffic patterns around the plant beer, changea due to the plume path? Are there any delays expected as a result of the plume path? .
l
- 37. Has the-site requested any additional offsite response support such as i fire company, ambulance, police, outside contractors?
- 38. Have you established communications with DER /BRP? Who?
- 39. Is anyone from DER /BRP being dispatched to the site? Who?
- 40. At what time will the organization make a shift change? Who is your relief?
DOSE CALCULATOR QUESTIONS
- 1. Is there a release in progress in excess of the tech spec limit or causing offsite dovs? *
- 2. What are the dose rates at the EPB?
- a. What are the projected doses at the EPB?
- b. What are the projected thyroid doses at the EPB7
- c. What are the integrated doses at the EPB?
- d. How long are you expecting to release thraugh the present release path?
- e. Is that time the same as what you are using for your projected doses?
- 3. What sectors are affected by the release? How many people live in the affected sectors?
- 4. What is the present weather and what is the weather forecast?
- 5. What isotope is the primary contributor to the dose at the EPB?
- 6. Is the thyroid dose or whole body dose limiting?
- 7. Is any particulate being released?
Are the field monitoring teams and dose calculations in agreement? What 8. are the relative errors to one another?
- 9. What h the source term in the primary containment?
IX-8
y
- 10. What is the source term in the secondary containment?
- 11. What would the dose rates at the EPB be if the source term in either the primary or secondary containment were immediately released?
- 12. Is the release monitoring instrumentation working properly? Is the instrumentation expected to remain in service? What is the backup if the instrumentation dose not remain in service?
- 13. What is the trend of the nobel gases and lodine releases? (Increasing, decreasing, no change).
- 14. Is this an analyzed accident scenario as fouad in tne FSAR? If so what are the predicted releases and offsite consequences?
- 15. How do your dose calculations take into account the snow and the resultant washout? What would be the difference if the precipitation turned to rain; would the dose projections be different?
- 16. Does your dose calc;1ation model take into account the run-off when the snow melts?
LICENSEE OFFSITE MONITORING
- 1. What is the distance from the plant that your onsite team is doing it's monitoring?
- 2. What method does the offsite team use te calculate iodine activity, particulate activity?
- 3. Are the individuals that are offsite monitoring wearing respirator protection, have they been given Kl?
- 4. What type of respirators are the team members wearing, what is the protection factor?
- 5. What exposures are the offsite monitoring teams allowed to receive?
What is their present exposure? Is that value all from today?
- 6. Where are the offsite teams located?
- 7. What are the results of the environmental samples? Where and when were the environmental samples taken?
- 8. Is the area around the EOF contaminated, was the area surveyed prior to activation? ,
- 9. Have any of the field monitoring teams experienced any radio interference by any offsite source?
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- 10. How are the monitors collecting air samples in the snow?
IX-9
- 11. What efficiency are they using for the detectors in the field?
- 12. Is there a lower .imit of temperature for use of your field monitoring instruments?
- 13. Would you please explain how you take snow samples?
- 14. What factor are you using for shielding from the deposited radioactivity or how much is the snow affecting the ground contamination reading?
O IX-10
F O SECTION IX - EXERCISE QUESTIONS PART C - GENERAL OFFICE QUESTIONS / PROJECTS t l O IX-11 i i 1 l
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SSES EMERGEHCY EXERCISE GENERAL OFFICE QUESTIONS / PROJECTS g The following areas / topics should be covered / investigated by the General Office Staff at some time during the emergency exercise. A. General Office Questions to be researched:
- 1. To what extent has the core been damaged?
- 2. What are the possible c ases of the fuel damage?
- 3. Given the extent of the fuel damage, 40uld RHR shutdown cooling mode be placed in service?
- 4. What, if any, precautions should be taken prior to placing RHR in the shutdown cooling mode of operation?
- 5. What RPV level and pressure is required to stop the CRD leakage?
- 6. What means are available for isolating the CRD leakage?
- 7. What, if anything, should be done to contain the CRD leakage?
- 8. What alternatives are available to red"ce the iodine release from
- the Unit 2 Reactor Building ventilation system?
B. Ceneral Office Modifications to be considered:
- 1. Shielding for RHR shutdown cooling mode piping.
- 2. Piping / structural changes to stop the CRD leak.
. Piping changes te contain the CRD leakage and return it to some other location euch as the drywell.
- 4. HVAC mods to reduce the release to the atmosphere.
NOTE: The followina items need to be considered for any orocosed j mod Dacka.g.it: 1 l Purpose Testing requirements RcJundance Review and approval authority l Shielding requirements Leak tightness Power supply l Material availability , l Instrumentation Constructability i Temperature / pressure requirements Welding requirements l Tie-in with operating systems l l IX-12 l
C. It is expected that NPE will make the following phone contacts to collect information. Q-m
- a. Reactor Coolant Activity level (isotopic)
- b. Suppression Pool Activity Level
- c. Feedwater conductivity and turbidity levels
- d. Source and magnitude of drywell leakage
- e. Radiation levels throughout the plant LDL
- a. Protective Action Recommendation
- b. Contacts with State, Federal, and local public officials
- c. What and when is the expected Federal support
- d. What are the plans for recovery /re-entry N
p ( IX-13 L
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SECTION IX - EXERCISE QUESTIONS PART D - MOC/Special Office g, IX-14 5
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i 1 l l l i c SSES EMERGENCY EXERCISE QUESTIONS / TOPICS OF DISCUS $10N FORMEDIAOPERATIONSCENTER/SPECIALOFFICE The following questions are generic in nature and can be asked for any exercise. The questions are to be asked by individuals simulating members of the general public, news media, public officials, local residents, plant workers and their families and others. Attached to the list of questions is a listing of names and their occupation. Use these names and the appropriate type of question when calling the H0C/Special Office. The questions are generic in nature but can be made more pointed depending on the type of scenario. When calling and asking questions of the staff at the H0C/Special Office press for as much detail as possible and be specific requesting a call back if necessary.
- 1. What was initiating event for the emergency?
- 2. What caused (specific) initiating event?
- 3. What is the expected duration?
- 4. What is present classification and what is it based on?
t 5. Which is the affected unit? L
- 6. Have there been any injuries to plant personnel?
- 7. Is the NRC at the plant?
- 8. Is the reactor completely shutdown? What is power level?
- 9. Is the plant still producing electricity?
- 10. Shouldn't the plant be shutdown? Or the unaffected unit?
- 11. Who is in charga of the -argency? How many people are involved?
- 12. How/where can I get news releases?
- 13. Is the-plant responding in a normal fashion to the emergency?
- 14. Is the fuel covered? If not. '.ow will it be covered?
- 15. What is current water level above fuel in the reactor? .
- 16. How is reactor being cooled? Are there backup cooling systems? Status?
- 17. Is there fuel damage?
U IX-15 l
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- 18. What is the reactor temperature and pressure?
- 19. Do you have abnormal radiation inside the plant?
O
- 20. What is the radiation level in the containment? What is normal?
- 21. Is anyone inside the containment?
- 22. Is a release in progress? If so, please provide additional information.
- 23. How long will the release continue?
- 24. Is the release being filtered, monitored?
- 25. What are radiation levels on the site?
- 26. Is there airborne contamination inside containment?
- 27. Have any plant employees been exposed to radiation because of emergency?
- 28. How many people?
- 29. To what exposure level? Is that dangerous?
- 30. What actions are being taken to minimize the release?
- 31. Is there a way to hold up the release for decay? g
- 32. Is a liquid release in progress? Pathway (s)?
- 33. How much radiation is needed before I start getting sick?
- 34. Do radiation leaks from power plants increase infant mortality & cancer?
- 35. Can you compare the heath risks of nuclear versus coal?
- 36. How does radiation get out of the plant?
- 37. What is first downstretm community that uses water for domestic purposes?
- 38. How do liquid releases get to the river?
- 39. How long would it take to get to Danville?
- 40. What is the potential for increased radioactive releases?
_41. What is the magnitude of the release?
- 42. What is the dose projection?
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- 43. What is the prognosis for ending the release?
IX-16 l 1
f 1 44 What is the potential for increased release levels?
- 45. Has airborne radioactivity been evaluated to detarmine if protective action is required for area residents?
- 46. What area around the site is affected by the release?
- 17. What can you tell me about radioac' 'eleases off site?
- 48. Who measures and how is it done? i e they protected?
- 49. What actions have you taken to stabilize the problem?
- 50. Is anyone attempting to penatrate the site?
- 51. Are any of the individuals armed?
- 52. Do you have adequate security?
- 53. Do you have back-up from Jccal police? If so, who?
- 54. Have you asked for their assistance?
- 55. Has anyone been apprehended? ,
- 56. Is there a connection between the would be saboteurs and plant problems?
- 57. Has anyone been evacuated from the plant?
- 58. Are plant buildings habitable?
- 59. Can you account for all plant employees? If not, what is the problem?
- 60. Are there areas of the site that are unaccessible?
- 61. Has anyone been taken to a hospital? Who or number -- which hospital (s)?
- 62. Have protective action recommendations been made? If so, what are they?
- 63. What is the basis for making protective actions?
- 64. How many sirens are there? Who sounds them and what it public to do?
65.- In which direction is the plume headed?
- 66. Has offsite support (fire, ambulance, police, etc.) been requested? ,
- 67. Have state officials been contacted? What are they doing?
- 68. How many people live in the Emergency Planning Zone (EPZ)?
i k- IX.17
- 69. Are you distributing potassium iodide?
- 70. What radio-tv stations will provide accurate information on what to do?
- 71. Where do I go when I evacuate? What do I take?
- 72. Where do I pick up my children from school?
- 73. What does shaltering mean?
- 74. When I evacuate, what do I do with my pets?
- 75. What kind of insurance does PP&L have to cover damages?
- 76. Where will replacement power come from and who will pay?
- 77. Who is the NRC contact for information? Phone aumber?
- 78. What facility is used when Y is evacuataa? How do I get there?
- 79. What are the emergency classifications and which one are you in?
- 80. Do the operators have to leave the control room?
- 81. What is the purpose of the containment?
- 82. How good can the containment be if you have a release?
- 83. How big is the containment?
- 84. What will you do with the damaged plant?
- 85. How are you able to determine the amount of fuel damaged?
- 86. When will be public be allowed to return?
- 87. What does the public do if they don't have transportation?
- 88. Has the NRC been notified? Time?
- 89. Has an emergency organization been established to deal with the problem?
- 90. How many people are involved? Describe the organization?
- 91. What is the status of your key plant safety systems?
- 92. What steps are being taken to correct the problem? .
- 93. Does the weather have any affect on the plant emergency?
- 94. How will public be reimbursed for unusable property?
IX-18
- 95. For contaminated animals that are destroyed?
- 96. Who is representing the State? Is the governor there?
- 97. Where is your backup emergency facility? How do you get there?
- 98. What is the special filtering system that I was told out on a tour?
- 99. What is its status?
100. What affect might high radiation fields have on equipment? 101. Will this result in increased amounts of high/ low radioactive waste? 102. Can the undamaged components function in present environment? 103. Any special shielding being employed to reduce exposures? 104. Will the 'C allow you to restart the undamaged unit? 105. What is the sequence of key events in this emergency? 106. When did these units first begin operation? 107. How long does the license last? How long will plant last? 108. What kind of toxic gases are kept at the plant? 109. What if the sirens don't work? 110. Will my electric rates be affected by the emergency? 111. How does this compare to Chernobyl? 112. Is this worse than THI? 113. Is there an emergency bick up for shutting the reactor down? 114. Explain in more detail automatic depressurization system. 115. Has boroc been used for shutting the reactor down? Why? 116. What is cold shutdown? 117. How is containment vented? Why? , 118. What is decay heat and why is it significant? . l l 119. How many fuel assemblies are there? Where do they come from? l 120. Is this what is called a "LOCA"? i
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IX-19 1
s 17.1. Are the main steam isolation valves operating?
!?I Is .he suppression pool playing an integral part in the emergency? O
"'; - 123, w many people work there? How many are needed for the emergency? h If so, what? 124. Have any buildings been damaged? F e t is the generating capacity of the plant? Percentap of system!
. 2 . did it ccst to build? Original cost? How lons did it take?
- i. - l - tos <h water is required to run the plant?
128. ,wns the plant? 12L m- .nd of reactor is it? Who manufactured the system? L 130. how mgch urarium is required for the reactor? U ia. How big are the c elinn towers? 132. What do the cooling towers do? 133. How rad 4 active is the steam in the cooling towers? Explaint 134. What are the larsest communities in the EPZ? 135. How far is SJi m a cre from the plant? 136. Ew have an emergency before at t e plant? If so, when and details? 137. Have you ever toen fined by the NRC? If so .vhen and why? g 138. Where are the nearest hospitals? 139. What kind of training do the operators have? 140. Has thi: ever caused a problein before? When? What happened? 141. Was search and rescue required to find any of the missing individuals? , 142. Is anyone still missing? 143. Do patients have to be evacuated from hospitals / nursing homes? 144. Has highwa> traffic in the general plant area been affected? 145. Are there any existing threats to continued containment integrity? 146. What is or/ential for further degradation? IX-20
147. What it :.RC phone number at M0C? O 148. Who can I call for information on county preparedness? Phone number? ) 149. Who can I call for information on state prep;. redness? Pnone number? 150. Who are the resident NRC inspectors? Phone number? 151. Are all major plant safety systems available? 152. Is stability of power grid affected by unit coming off line? ~ 153. Is there a chance offsite power could be lost? What happens then? 154. How much spent fuel is on site? - 155. Where is it stored and how much space is left? 156, What happens when you run out of space for the spent fuel? 157. Why use dangerous uranium when we have so much safe, clean coal? 158. Why doesn't my homeowners insurance policy cover losses resulting from an accident at SSES? - 159. Why even use nuc'ev power when accidents like this can happen? 160. Is plutonium deadly? How much is at SSES? Why use it? 161. How do you get rid of it? D;'3 162. Isn't this used for making bombs? 163. What safeguards are there to prevent theft by terrorists? 164. Isn't this accident going to affect property values? 165. How does this nuclear plant differ from THI? 166. What is the most serious type of accident you can have? 167. What would happen if a bomb were dropped on SSES? 168. Is the plant designed to withstand a serious earthquake? 169. What's to prevent on employee with an emotional or mental illness from taking over the plant or blowing it up? . 170. I remember you were recently fined because of certain equipment not being certified to perform in a U rsh environment. What is the story? 171. Is it safer to work at SSES compared to a coal plant? Expl ain t IX-21
l 172. I understand the older a piant gets, the more it leaks radiatior Is ' the Press-Enterprise correct? Explain! '
-173. How can you operate this plant when a National Research Council comittee of radiation experts states that well demonstrated health effects from low-level radiation " include the induction of cancer, genetically determined ill-health, developmental abnormalities, and some degenerative diseases....."
174. If they are building safer nuclear plants, why aren't "ou using them? 175. Isn't there anything you can do to neut.alize the radia6.on? Match the qcastions to the appropriate category (REPORTERS, POLITICIANS, AREA RESIDENTS, and ANONYMOUS CALLERS). For example, question #48 would be more appropriate coming from one of the REPORTERS than from the others. REPORTERS (Call 759-2285) Dawn Capewe11........ Press Enterprise Bob Salitza. . . . . . . . . .Hazleton Standard Speaker Dawn Shurmaitis...... Times Leader . Fred Ney............. Sunday Indaoendent Tim Vincent..........WHi4 Nolan Johannes.......WNEP-TV Dave DeCosmo.........WY00-TV
^ndy Mahalchic.......WBRE-TV h
derry Heller......... WARM Mark Lawrence........WK0K POLITICIANS (Call 759-4957) l Mike Carroll......... Aide to Congressmar Kanjorski Lou Blacchi..........Berwick Mayor Walt Sokolowski......Nanticoke Mayor Oscar Wel sh. . . . . . . . . . Briar Creek Boro Mayor Rep. George Hasay....Shickshinny Abe Spaide...........Nescopeck Mayor l Don Graves...........Shickshinny Mayor Charles Lemmond. . . . . . State Senator Dave Robinholt.......Nescopeck Township Supervisors Chairman L Artfe Dawson.........SSES citizens Committee Member (sometime politician) L L AREA RESIDENTS / ANONYMOUS CALLERS (Call 759-2281) l Bill Johnson......... Plant Neighbor George Petruskin..... Plant Neighbor Harold Robins........ Plant Neighbor Tom Reynolds......... Plant Neighbor-Betty Selvert. . . . . . . . Plant Neighbor g IX-22 l
a .. u.. . usa ar.,. 3.2t- 4 , # n;. _am.* r.,&+-, -A = .m.s. p s.--- 4a.<, w4 -e_.~.se--. m. -.4%.-s.h-a.c.-..a 24u%--... .m &w.m+- ...a . > .22.4 .-.s. l O 9 SECTION X SIMULATOR INFORMATION 4 O 4 x.,
'RH. RAD 1
- FILE * (USER FILE) -
- RH. RAD 1-
** ENABLE SPDS SPING RAD POINTS FOR E-PLAN DRILL **
MENU-LOA MSC9 T SW SPFMV020=.13E+06 SW SPFMV021=.11227E+6 SW SPFMV022=.22883E&6 SW SPFMV023=3285.9 SW SPFMV024= 15878E+6 SW SPRMV020=0.72E-05 SW SPRMV021=0.82E-05 SW SPRMV022=4.2 SW SPRMV023=5.1 SW SPRMV024=4.4 SW SPRMV03O=0.71E-05 SW SPRMV031=0.89E-05 SW SPRMV032=4.3 SW SPRMV033=4.4 SW SPRMV034=4.3 SW SPRMV035=0.84E-05 SW SPRMV036a0.75E-05 SW SPRMV037=4.2 SW SPRMV008=4.3 . SW SPRMV039=4.2 SW SPRMV025=0.72E-05 _ SW SPRMV026=0.92E-05 SW SPPWO'47=4. 5 SW SPR* '/s8=A.1 SW SPRd nJ9=4.2 SW SPRMV040=0.98E-04 SW SPRMV041=0.88E-05 SW SPRMV042=9.6 SW SPRMV043=4.5 SW SPRMV044=5.3 XFILE 2 9
.+
2
.f~k i
(,/ RH.PMS65-
- 1. --
'*FILE * (USER FILE)
-**: REACTOR BUILDING AREA RADIATION MONITOR POINTS **
2. MERU
-- 3 . SW PDVPAR35=0.25
- 4. SW PDVPAR15=0.14~
- 5. SW PDVPAR42=0.15
- 6. SW PDVPAR13=0.82
- 7. SW PDVPAR12=0.08
- 8. SW PDVPAR11=1.10
- 9. SW PDVPAR08=0.29 10 . -- SW PDVPAR36=0.10
- 11. SW PDVPAR16=0.10.
12 '. SW PDVPAR02=0 20
- 13. SW PDVPAR41=0.30 14 . - SW PDVPAR14=0.40
- 15. SW PDVPAR26=0.50
- 16. SW PDVPAR10=0.80- ,
- 17. SW PDVPAR09=0.-90 18.- SW PDVPAR05=0.40 19 . - SW PDVPAR06=0'.70-
~ 2 0. - SW PDVPAR25=13.7
=21.- SW.PDVPARO1=10.4
- 22. SW-PDVPAR04=1.50
- 23. SW PDVPAR03=1.76 *
-24. :XFILE-Q;r z ~.
, -Q -3
i
-RH.PMS65
- FILE * (USER FILE)
** NORMAL TB ARM INDICATIONS **
MENU SW PDVPAR23=0.12 SW PDVPAR24=0.10 SW PDVPAR22=0.23 SW PDVPAR27=0.1004
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- FILE * (USER FILE)
**JJ.PMS67
** UNIT 1 AREA RAD MONITORS MISCELLANEOUS **
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- FILE * (USLR FILE)
- 1. *** INITIAL WEATHER FOR 1992 NRC GRADED EXERCISE ***
- 2. MENU
- 4. SW-PDKVMS01=05.0
- 5. SW FDKVMSO2=05.0
- 6. SW PDKVMT08=45.0
- 7. SW PDKVMX01=201.0
- 8. SW PDKVMXO2=11.0
- 9. OVR 93X15B 37.8
- 10. OVR 93X15C 5.0
- 11. XFILE
n.-. . . . - . . . . . - . - . . . - . . . . - _- . _ - .-. - D RM.TUROS
- FILE *=(USER FILE) b.. - *** MAIN: TURBINE LOAD REJECT AND OVERSPEED ***
. IAA MSC9 T MAL TUR7 ACT MAL RPO2 ACT,0.0,10 MAL TUR8 ACT -
MAL TUR17B ACT MAL MSC21 ACT MAL GEN 1 ACT MAL' GEN 4 ACT.
- MAL' RAD 1-ACT,3 MAL--TUR11 ACT,4
- OVR A05F05 l'
- OVR A05D05-1
- MAL FDW1 ACT,5 RAMP URMTOT,5.85ES,18,0
- RAMP FWMCSTKA,-1~.5E6,1200,45 RAMP PCRADA,192.O,60,O.O RAMP PCRADB,184.0,60,0.0
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- RAMP PDVYAR02,100,60,58 XFILE *
, !- - RH.RCIOS
- FILE *-(USER FILE)
. ***-RCIC OVERSPEED ON MANUAL START *** '
[-)S l--- MENU l-
. OVR.17X1 15.0,5.0,8.0 OVR 17X2 100.0,5.0,8.0
- OVR 17X3-100.0,5.0,8.0 -
OVR 17X14-_100.0,5.0,8.0
-MAL ECS4 ACT,11.0
- OVR A08F02 1,8.0
= SW-PDVPAR02=74.0 g
XFILE RH.RCCLR-
- FILE *.(USER FILE)
, 1. - ***-RC~.C'OVERSPEED RESET'OF INSTRUMENTS INDICATION AFTER OVERSPD *** p 2. MENU j '. - 3.. - OVR 17X1~.0
- 4. ' OVR 17X2'O 5 ', . OVR 17X3 0
- 6. - OVR 17X14 0
- 7.. MAL ECS4 CLR
~8. OVR A08F02 0 -
- 10. XFILE j.
u 1... g -- e -,+.-w
RH.RCOST.
- FILE * (USER FILE)
- 1. *** RCIC STEAM LINE BRK ON MAN S/U AFTER O/S ***
- 2. MINU
- 3. OVR 17X1 15.0,5.0,8.0
- 4. OVR 17X2 100.0,5.0,8.0
- 5. OVR 17X3 100.0,5.0,8.0
- 6. OVR 17X14 100.0 5.0,8.0 7 MAL ECS4 ACT,11.0
- 8. OVR A08F02 1,8.0
- 9. OVR 17X7B 1,12
- 10. OVR 17X33B 2,12
- 11. OVR 17X33C 2,12
- 12. OVR 17X34C 2,12
- 13. OVR 17X8B 1,12
- 14. OVR 17X11B 1,12
- 15. OVR 27X12B 1,12
- 16. RAMP RC:KN, 1.0,100,12
- 17. OVR 17X3'7 2,10
- 18. OVR 17X3.' 1,12 {
- 19. OVR 17X;1. 1,12
- 20. OVR A06AJL 1,15
- 21. OVR A06B12 1,15
- 22. OVR A08B05 1,12
- 23. OVR A08E05 .1,10 -
- 24. OVR A08F04 1,10
- 25. OVR A08F05 1,11
- 26. OVR A08A02 1,11
- 27. OVR A08A03 1,10
- 28. OVR A16G15 1,20
- 29. OVR A01B05 1,25
- 30. OVR A06C16 1,25
- 31. OVR A06D16 1,27
- 32. OVR A08H03 1,300
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- 35. XFILE e
; AH.RB3.2
- FILE * (USER FILE)
! 1. **"AB ARM INDICATIONS FOR RCIC STM BRK IN RX BLDG ***
- 2. !1ENU
- 3. LOA MSC15 T
- 6. RAMP PDVPARS1,017.3,800,0.0
- 7. RAMP PDVPAR34,009.9,800,0.0
- 8. RAMP PDVPAR16,008.2,800,0.0
- 10. RAMP PDVPAP36,08.4,800,0.0
- 11. RAMP PDVPAR41,09.1,800,0.0
- 12. RAM? PDVPAR08,09.6,800,0.0
- 13. RAMP PDVPAR10,09.1,800,0.0
- 14. SW PDVPAR11=11.3
- 15. SW PDVPAR12=08.4
- 16. SW PDVPAR14=09.1
- 17. SW PDVPAR15=9.1
- 18. SW PDVPAR02=100
- 19. SW PDVPAR35=8.8
- 20. SW PDVPAR13=G.5
- 21. SW PDVPAR42=8.3
- 23. XFILE 4
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i ' p? RH.TB3.1
- FILE * (USER FILE)
- 1. *** TURB BLDG RELEASE MF NG DUE TO O/G EXPLOSION ***
- 2. MENU
- 3. RAMP SPRMV032,7.0,0120,900.0
- 4. ANN 722 CLR
- 5. OVR A15E04 1,30
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- 7. OVR A21G01 1 C. OVR A1GH15 1
- 9. OVR A06F15 1
- 10. XFILE kH.SB3.1
- FILE * (USER FILE)
- 1. *** RX BLDG SPING FOR RCIC STM LK RUN AT 1645 ***
- 2. MENUP
- 3. RAMP SPRMV037,950.0,800,0.0
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- FILE * (USER FILE)
- 1. *** RX BLDG SPING FOR RCIC STM LK RUN AT 1700 ***
- 2. MENU
- 3. RAMP SPRMV037,2034.0,800,0.0
- 5. XFILE ,
RH.SB3.3
- FILE * (USER FILE)
- 1. *** RX BLDG SPING FOR RCIC STM LK RUN AT 1715 ***
- 2. MENU
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- 1. *** RX BLDG SPING FOR RCIC STM LK RUN AT 1730 ***
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- FILE * (USER FILE)
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- RH.SB3.6
- FILE * (USER FILE)
- 1. *** RX BLOG SPING FOR RCIC STM LK RUN AT 1800 ***
- 2. MENU 3, RAMP SPRMV037,9178.0,800,0.0 ,
- 5. XFILE 8
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'j RH.SB3.7 ..
.* FILE *,(USER FILE)
% 2 1. *** RX BLDG SPING FOR RCIC STM LK RUN AT 1815 ***
~ 2. MENU
- 3. -RAMP-SPRMV037,1.15E4,800,0.0-5.- XFILE
-RH.SB3.8
- FILE * (USER FILE)
, l'.- *** RX BLDG SPING FOR RCIC STM LK RUN AT 1830 ***
- 2. MENU ;
3.- RAMP SPRMV037,1,15E4,800,0.0
- 5. - lXFIL"-
RH.SB3.9l - *FILEA (USER ?ILE). l' . *** RX BLDG SPING FOR ACIC STM LK RUN AT 1845 *** 2 .- MENU
-3.- RAMP SPRMV037,1.25E4,800,0.0
- 5.- -XFILE RH.S3.'10.
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- 1. ***JRX BLDG-SPING FOR-RCIC.STM LK F.UN AT 1900 ***
. 2.- MENU
- 3.- _ RAMP SPRMV037,1.BE4,800,O.C=-
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? -- 1.- *** RX BLDG.,SPING FOR RCIC STM LK RUN AT 1915 ***
- 2. MENU
- 3. RAMP SPRMV037,2.2E4,000,0.0
' 5. XFILE f
t-4 l t= - -
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