IR 05000010/1981013
| ML17194A225 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/22/1981 |
| From: | Axelson W, Paperiello C, Phillips M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17194A224 | List: |
| References | |
| 50-010-81-13, 50-10-81-13, 50-101-81-13, 50-237-81-26, 50-249-81-19, NUDOCS 8110280195 | |
| Download: ML17194A225 (11) | |
Text
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-10/81-13; 50-237/81-26; 50-249/81-19 Docket Nos. 50-10* 50-237* 50-249 . ' ' Licenses No. DPR-2; DPR-19; DPR-25 Licensee: Commonwealth Edison Company Post Office Box 761 Chicago, IL 60690 Facility Name: Dresden Nuclear Generating Station, Units 1, 2, and 3 Inspection At: Dresden Site, Morris, IL Inspecti~~~ cted~: SeP,tember 23 and September 29 - October 1, 1981 . L-- -** ~~~ ~--* I Inspecto * M. P~ :Phfnips.. /r_:. 2{*/!?) r>>rJ Approved By: W. L. Axel on, Acting Chief /D /'-t /&I Emergency reparedness Section
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C. J. Paperiello, Chief Emergency Preparedness and lc:..(2 *z./ ~{. Program Support Branch Inspection Summary Inspection on September 23 and September 29 - October 1, 1981 (Reports No. 50-10/81-13; 50-237/81-26; 50-249/81-19) Areas Inspected: Routine, announced inspection of a scheduled site assembly drill and of the Dresden emergency exercise involving observations of key functions and locations during the exercis The inspection involved 97 inspector-hours onsite by seven NRC inspectors and one consultan Results: No items of noncompliance or deviations were identifie e110280 PDR ADot~soe11022 G 5000010 . PDR
- DETAILS Persons Contacted NRC Observers and Areas Observed F. Pagano, Jr., Chief, Emergency Preparedness Licensing Branch, Headquarters, Floater D. Matthews, Chief, Section B, Emergency Preparedness Licensing Branch, Headquarters, Floater C. J. Paperiello, Chief, Emergency Preparedness and Program Support Branch, Region III, Operations Support Center (OSC) and Inplant Health Physics Team M. C. Schumacher, Chief, Independent Measurements and Environmental Protection Section, Region III, OSC and Inplant Health Physics Team W. L. Axelson, Acting Chief, Emergency Preparedness Section, Region III, Technical Support Center (TSC)
T. Tongue, Senior Resident Inspector, Control Room M. Jordan, Resident Inspector, Floater M. P. Phillips, Radiation Specialist, Region III, Emergency Operations Facility (EOF) T. H. Essig, NRC Consultant, Radiation Environmental Monitoring Team Commonwealth Edison and Areas Observed D. Scott, Plant Superintendent, TSC R. Ragan, Assistant Superintendent for Operations, T J. Eenigenburg, Assistant Superintendent for Maintenance, TSC D. Farrar, Assistant Superintendent for Administrative and Support Services, TSC G. Wagner, Chief Controller, EOF J. Barr, Controller, EOF T. Gilman, Environmental/Emergency Coordinator, EOF G. Myrich, Rad/Chem Director, TSC R. Meadows, Controller, OSC J. Golden, Radioecology/Emergency Planning Supervisor, EOF J. Toscas, News Information Department, Emergency News Center W. Brenner, Technical Services Nuclear T. Ciesla, Technical Staff, TSC R. Stobert, Quality Assurance Staff D. Reece, GSEP Coordinator, Controller, TSC S~hneider, Plant Chemist The above personnel attended the exit interview on September 30, 198. Licensee Action on Previously Identified Items Related to Emergency Preparedness (Closed) Open Item 010/81-04-01; 237/81-08-01; 249/81-05-01: Interim post-accident primary coolant sampling syste The permanent system is currently being turned over from the manufacturer to the licensee, and will also be used for routine sample collection and analysis. - 2 -
The interim sampling procedure will be deleted, and a new procedure is being written for the permanent syste. General An exercise of the licensee's Generating Stations Emergency Plan (GSEP) and the Dresden Annex was conducted at the Dresden Station on September 30, 1981, testing the integrated responses of the licensee and local organizations to a simulated emergenc The exercise tested the licensee's response to a major release of noble gas with some iodin Attachment 1 describes the scenari The exercise was integrated with a test of Grundy, Kendall, and Will Counties emergency plan On September 23, 1981, the licensee tested the site assembly portions of their emergency plan in conjunction with a full~scale dril. Drill The inspectors observed the_ response by the licensee organization during the site assembly portion of the drill conducted on September 23, 198 This portion of the drill began at approximately 9:05 a.m. with the sounding of the assembly/evacuation alar Individuals reported to one of the designated assembly areas and were accounted for by the individuals' foreman at the assembly area There is no procedure in the Emergency Plan Implementing Procedures (EPIPs) that describes the method by which personnel are accounted for within 30 minute Al~ though EPIP 300-3 describes when the alarm is sounded and where personnel are to report, it does not address personnel accountabilit In preparation for a site evacuation, the Rad/Chem Director determined the proper evacuation route, designated the offsite assembly area, and dispatched technicians to the assembly areas for radiological monitorin All individuals were declared accounted for within thirty minutes of the sounding of the alarm, and this portion of the drill was termin-ated at 10:30 However, the system for accountability is totally dependent upon memor No cross-check provisions are made with the security accountability syste No items of noncompliance or deviations were.identified; however, the licensee should procedurally describe the method to be used for person-nel accountability such that all licensee personnel can be.accounted for at all times (e.g., during lunch breaks).
This area will b examined during the emergency *preparedness implementation appraisa. General Observations Procedures This exercise was conducted in accordance with 10 CFR SO, Appendix E requirements using the GSEP, Dresden Annex, and the EPIPs used by the Corporate Command Center (CCC), Emergency Operations Facility (EOF) and Statio Coordination The response was coordinated, orderly, and timel If the event had been real, the actions of the licensee would have been sufficient to permit the State and local authorities to take appropriate protective action Observers Licensee observers monitored and critiqued this exercise along with ten NRC observers and approximately 25 Federal Emergency Management Agency (FEMA) observer FEMA observed and will report on the responses of the local government Critique The licensee held a critique immediately following the exercise the afternoon of September 30, 1981. * The NRC and the licensee identified the deficiencies as discussed in the exit intervie. Specific Deficiencies Noted Problems identified by the NRC observers during the exit interview included: (1) location ot the OSC did not allow adequate functioning; (2) communications flow between OSC and TSC was inadequate; (3) site evacuation was not ordered until a General Emergency was declared; and (4) inadequate training of radiation monitoring teams covering survey technique. Specific Observations Control Room The operators responded well to cues and made proper notifica-tion Information on plant conditions was routinely passed to the TSC in a timely manne The exercise scenario tested the operator's ability to correct plant malfunctions, and provided a good technical test of operations personnel, who performed wel Technical Support Center (TSC) Activation of the permanent TSC was orderly and timel Command and Control functions performed at the TSC were very goo Monitoring of the TSC for radiological habitability was performed in the room housing the ventilation system for the TSC using an Eberline PING-2A, which measures airborne radioactivit With the exception of trend analysis, TSC personnel responded well to cues regarding mechanical, opera-tional, and technical problems posed as part of the scenari Trend analysis of plant parameters was not initially performed; however, the licensee's current plant computer system will graphically print out plots of various parameters vs time, thus providing graphical trend display Although not currently in - 4 -
- place, the licensee is in the process of placing a copy of the Dresden Site Specific Annex to the Illinois Plan for Radiological Accidents in the TS Additional training of some technical staff personnel with regard to reactor water level and core coverage is neede When initially asked by the inspector, the Technical Director could not tell if the core was covere Emergency Operations Facility (EOF)
The temporary EOF, which is located in the General Electric training facility, was activated in accordance with the Emergency Pla Personnel required to man the EOF were prepositione Communications at the EOF were adequate; however, incoming radio transmissions from the field teams were lou The NRC dedicated Health Physics Network and Emergency Notification System phones were not availabl Installation and maintenance of these phones is under the direction of the NR Command and control functions at the EOF were excellen Adequate briefings of personnel regarding updated plant conditions were held, and all information regarding the event was logged and available to all personne The interface between the senior managers at the EOF and the TSC was excellen The Environmental/Emergency-Coordinator maintained good records, and the offsite dose assessment function was excellen Radiation monitoring and personnel dosimetry functions were implemented prior to any simulated plant release. After the Site Area Emergency had been declared and non-essential personnel were assembled, the decision was made by the Recovery Manager not to evacuate site personnel because no offsite evacuations were taking plac This is in contradiction to Criterion II.J.4 of NUREG-0654, Revision I, and Section 6.4.1 of the GSE Site evacuation was delayed until a General Emergency was declared and offsite evacuation recommende The licensee identified this problem at their critiqu Joint Public Information Center (JPIC) The JPIC was maintained in the EOF, but away from the EOF Manager Security for the JPIC and EOF was implemented prior to the start of the exercise, and was excellen Since very little press interest was observed, most information dissemina-tion was via typed periodic press release CECo's technical spokesperson was available for briefings throughout the exercis Operational Support Center (OSC) The OSC is the assembly area for the health physics and main-tenance emergency teams, and is located in the turbine building adjacent to Unit This area was manned in a timely manner, and radiation monitoring was performed using an Eberline PING-3 continuous air monito The inspectors observed that the noise level in the OSC interfered with radio and telephone communica-tions, that there was no procedure for systematically debriefing - 5 -
- returning survey/sampling teams to obtain pertinent survey information, and that there was no means for recording and displaying such information ih the OS These same problems were previously observed during the licensee's June 19, 1980, exercis These problems were compounded because the OSC Supervisor has no procedure to help him implement his dutie In addition to the above referenced noise problem, communica-tions flow between the OSC and TSC wa~ poo OSC personnel thought that they were in a Site Area Emergency condition even though the TSC had declared a General Emergency two hours earlie Due to the noise level, poor working space available in this area, communications flow problems, and lack of infor-mation status displays; the inspectors determined that the OSC would be iricapable of functioning for a protra~ted p~riod of time as it is currently structure A permanent OSC must be established meeting the design criteria specified in NUREG-0696 prior to October, 198 This is an *open Item, and will be reviewed by the NRC Headquarters Emergency Preparedness Development Branc Health Physics Teams The inplant health physics teams were dispatched from the OSC, and were aware of the location of protective clothing, self contained breathing apparatus, radiological monitoring equipment, and sampling equipmen Adequate exposure control for inplant personnel was maintained by the Rad/Chem Director at the TS The environmental monitoring teams were assembled in a timely manner, briefed by the Environs Director, and assigned to the nearsite environs (within about two miles of the plant).
Com-munications equipment and instrumentation were checked, and all monitoring equipment was within calibratio Sampling locations assigned by the Environs Director were quickly located and required samples were properly take Team members displayed excellent exposure control; however, only 0-200 mR self-reading pocket dosimeters were use.R pocket dosimeters were available in the kit, but were not taken by the team Com-munications between the environmental teams and the EOF were clear, and field teams were provided with information on plant conditions, Some of the information provided (e.g., dose rates in the drywell) was of little use to the tea Radiation measurements were performed with a Cutie Pie used in the closed window mode only; i.e., only gamma measurements were take The teams did not determine whether the exposure results were due to direct radiation from an overhead plume or from actually being.in the plum This must be done to verify that air samples collected actually represent samples of the plume, especially when an elevated release occur The inspectors attributed the failure to determine whether teams were actually in the plume to inadequate training in environmental survey/ sampling technique *
8. Exit Interview The inspectors held an exit interview at the conclusion of the licensee's critique with representatives denoted in Paragraph The licensee agreed to address the inspectors' concerns stated in Paragraph 6; however, the licensee responded by stating that they felt the current OSC did meet the criteria in NUREG-069 Attachment: Exercise Scenario - 7 -
.. PHASE Initial Situation 0650-0700 All!rt (0700-0815) MSC N l 2 A
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7 TIME ISSUED 0650 0655 0700 0700-0815 0700-0815 0700-0815 0700-0815 0700-0815 0700-0815 0715 0715 0730 0745 0745 0800 SCENARIO OUTLINE September 24, 1981 .Paqe l DRESDEN EXERCISE - SEPTEMBER 30, 1981 TYPE MESSAGE Control Control Control Control Continqency Control Control Control ISSUED TO All H.P. Teama RCT in Lab Environs Field Teama Any CECO Center Maintenance Tl!am EOP OUTLINE OP CONTENTS Prepublished Ground Rule NOrmal Operatin9 information WS 4.47 m/HC Stab els D W.D. 67.50 Reactor trouble resultin9 in escape of radioactive liquids and gas to Drywel Dryvell intac High Range Dryvell Radiation MOnitor reads EAL for Aler ws 4.47 m/sec Stab Cls D W.D. 67.50 In-Plant survey informatio Results of Dryvell air and Reactor Coolant Samples drawn between* (0.700 and 0815) Note: Saniples will be simulate oose Rate information in the plant l!nviron Forecast metl!Oroloqical data provided in response to simulated tl!lephone calls to Murray ~ Trette Emergency Core Cooling Parameter "" 0" Thermal overload burned...., breakl!r for valve M02-l402-25A I\\ Plant Status Updat WS 4.47 111/Sec Stab els D liD 67.5° Declare an Alert accident classification Activate TS Notify SPS Plant Status Updatl!. WS 4. 75 ID/Sl!C Stab Cls D WD 67.50 Plant Status Updat WS 4.47 111/sec Stab els D liD 67.5° NARS Porm for All!r Plant Status Updat W5 4.47 JD/Sec Stab Cla D ND 67.5°
PHASE Site Emergency (0815-0945) General Emergency* (NO Release) (0945-1100) MSG N A
ll
12
8C l4 TIMI! ISSUED 0815 0815-0945 0815-0945 0815-0945 0815-0945 0815-0945 0815-0945 0830 0830 0845 0900 0900 0915 0930 0930 0945 0945-1100 0945-1100 SCENARIO OUTLINE September 24, 1981 Page 2 DRl!SDl!ll EXERCISI! - Sl!PTl!MllER JO, 1981 TYPE MESSAGE Control C.I. * Control Contingency Control Control Contingency Control Control Contingency Control ISSUED TO H.P. Temaa Environs Field Teaaa Any CECO Center RCT in Lab Maintenance Team TSC EOF Info: CCC,TSC !!OF, CCC Info: TSC H.P. Teams RCT in Lab OUTLINE OF CO!n'l!NTS Plant Status Updat EAL for Site E11111rgenc:y Me Drywell intac WS 4.47 m/Sec Stab Cls D ilD 67.5° In-plant survey informatio Dose Rate information in the plant environ l"Orecast 11111teorological data provided in response to simulated telephone calls to Murray ' Trette Results of Drywall air and Reactor coolant samples drawn between: (0700-0815) Note: Samples technique will be demonstrate l!lllllrgenc:y Core Cool~nc; Parameter Thermal overload burned up on breaker for valve M02-U02-25A Plant Status Updat ws 4.47 m/sec Stab Cls D wo 67.5° Dispatch Teams to obtain Drywall Air and Reactor Water Sample Plant Status Updat ws 4.47 ID/sec Stab Cls D llD 67.5° Plant Status Updat ws 4.47 m/sec Stab Cls D wo 67.5° NARS Form for Site E11111rgenc Plant Status Updat WS 4.47 m/sec Stab Cls D wo 67.5° Plant Status Updat ws 4.47 ID/sec Stab Cls D ilD 67.5° Results of Drywall air sample for transmission to DN Plant Status Updat EAL for General l!lllllrgency, imminent releas WS 4.47 m/sec Stab els D WD 67.5° In-plant survey informatio Results of Drywall air and Reactor Coolant Samples drawn between (0945 and 1100) NOte: Sample will be simulated
". PHASE General ED>ergency (NO Releasel (0945-11001 (Continued ** 1 General Emergency Release ( 1100-1400 I MSG N l4A
148 l4C
18 19 TIME ISSUED 0945-1100 0945-1100 0945-1100 1000 1005 1015 1015 1030 1030 1045 1100 1100-1230 1100-1230 1100-1230 1100-1230 1100-1230 llQ0-1230 SCENARIO OOTLIN! September 24, 1981 Page 3 DRESDEN EXERCISE - SEPTEMBER 30, 1981 TYPE MESSAGE Control Control Contingency Contingency Control Control Control ISSIJED ro environs Field Telllll8 Any CECO Center Maintenance Team TSC EOF, CCC !OP Info: CCC,TSC H.P. Teams RCT in Lab Environs Field-Teams Any CECO Center Maintenance Team C.R./TSC OUTLINE OF CONTENTS oose Rate information in the plant environ l'Orecast meteorolotical date provided in response to simulated telephone calla to Murray ' Trette Damage assessments of valve 2-1601-2 Plant Status Updat Failure in El:C WS 4.47 m/sec Stab Cla D wo 67.5° Dispatch team to obtain Drywell air and Reactor Coolant Sample Plant Status Updat ws 4.47 111/*ec Stab Cls D wo 67.5° Results of*Dryvell Air Samples for transmission DN NARS Form for General Emergency, Imminent releas Plant Status updat ws 4.47 m/sec Stab els D wo 67.50 Plant Status Updat ws 4.47 m/sec Stab Cl& D wo 67.5° Plant Status Updat Release through chimney is indicate Elevated release pathway WS 4. 47 ID/BOC Stab D WO 67.5° In-plant survey dat Results of Dryvell air and Reactor Coolant Samples drawn between (1100 and 12301 oose rate information in the environ Forecast meteorological data provided in response to requests from Murray ' Trette Information on repair operations and dose field Controllers prevent SBGTS from being secure PHASE General Emergency Release (1100-1400) Recovery Phase (1230-1600) MSG N l l9A 198
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25 26 A o\\
TIME ISSUED 1115 1130 1130 1130 1145 1200 1215 1230 1230 1230-1600 1245 lJOO 1300 1315-1600 1315 1400 1600 Or designaged by Chief Controlle SCENARIO OOTLINZ * September 24, 1981 Page 4 DRESDEN EXERCISE - SEPTEMBER 30, 1981 TYP1! MESSAGE Control Control Contingency Control Control Control Control Control control Control Contingency Control Contingency Control ISSIJED TO EOP Into: CCC,TSC TSC Maintenance Ten Environs Field Tew BOP Into: TSC,CCC C.R., TSC, !!DP, CCC !!DP Into: TSC;ccc** All Cl!Co Participants OOTLI NE 01" COllTEln'S Plant Status Updat ws 4.47 m/aec Stab Cls D WD 67.5° Plant Status Updat ws 4.47 m/sec Stab Cla D WD 67.5° Initial report ot release to all agencie (Sent via MAR NARS form need not be complete.)
Begin actions to repair the release pathwa Plant Status Updat. 47 Ill/sec STab Cla D llD 67.5° Plant Status updat ws 4.47 m/sec Stab Cls D llD 67.5° Plant Status Updat ws 4.47 m/sec Stab Cls D llD 67.5° Report that repairs are complet Release stoppe Plant Status Updat (Indicate release stopped.)
WS - iiJ..OM,14 Stab Cls D wo 67.5° Time/Distance.information to report dissipation of the plum Plant Status Update ws ~ ""p 11 Stab Cla D wo 67.5° Plant Status Updat ws f!!l-0 >'>" ;1 rl Stab Cls D wo 67.5° Report that release has stoppe Explanation of the passage of time and recovery efforts that would be take Plant Status Update; Eo\\LS.for Aler MARS Pora (Indicate.o\\lert and improvement of plant status.)
Exercise Terminatio Time and place for Critique. }}