IR 05000327/1989020

Insp Repts 50-327/89-20 & 50-328/89-20 on 890717-20.No Violations or Deviations Noted.Major Areas Inspected:Annual Emergency Exercise,Including Staffing & Response of Emergency Organizations in Control Room & Support Ctrs

ML20246P712
Person / Time
Site:	Sequoyah
Issue date:	08/29/1989
From:	Rankin W, Sartor W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20246P678	List: IR 05000327/1989020 ML20246P674
References
50-327-89-20, 50-328-89-20, NUDOCS 8909110224
Download: ML20246P712 (22)

Text

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AS M[d  : UNITED STATES .

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' %op* NUCLEAR REGULATORY COMMISSION -

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g 'g? j -J 101 MARIETTA STREET, M M- g, ATLANTA, GEORGI A 30323

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Report Nos.:' 50-327/89-20 and 50-328/89-20 Licenseed JTennessee Valley: Authority '

1; , 6N38'A Lookout Place m

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s Chattanooga..TN .37402'2801

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' Docket Nos.: 50-327 and 50-328 License Nos.: 'DPR-77 and DPR-79

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FacilityNamei.Sequoyahl'and{

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(InspectionConducted: July [7-20,1989 Inspector: [ Od /l

= W. .M. Sartor, J , 7h9hO/

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.Accompan'ing Personnel: .B. Desai D.-Loveless

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. .Haagensen (PNL)

Approved by M N 29!89

.W. H. Rankin, Chief Date Signbd

- Emergency' Preparedness Section r

. Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards

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SUMMARY

. Scope:

This routine, announced inspection was the observation and evaluation of the annual emergency exercise. Selected staffing and response of the. emergency organizations in the Control Room, Technical Support Center, and Operational Support Center was observed. The inspection also included a review of the exercise objectives. and scenario, as well as observation of the licensee's

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l critique to managemen .Results:

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, ,  ::In the areas inspected 'no violations or deviations were identified.

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Based upon the scenario used, the licensee's performance was satisfactory to D . determine that_ they could'. implement their Emergency Plan and procedures to q l ' adequately provide for ,the health and safety of the public and plant personnel, j No exercise' weaknesses were identified, however, inspector followup' till i

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examine .the tim'e'; required to activate the emergency facilities, control of scenario data, informing onsite personnel of accident status, 'and making protective action recommendations according to procedure P J PDR ADOCK 05000327 I Q PDC , j

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REPORT DETAILS-

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- Persons-Contacted Licensee Employees

• D. Adams, Chemistry Technical Support Supervisor

• R. Beecken, Maintenance Superintendent

• L. Bryant, Maintenance Program Manager

• L.7 Bush, Operations Unit Manager

• N. Catron,' Emergency Preparedness Manager, Sequoyah'

• M.' Cooper, Compliance Licensing Supervisor

'*M.;Frye, Maintenance Manager

• G. Gault, Reactor Engineering Supervisor

• J. Hendrix . Site Support Manager

• R.'Kitts, Manager, Emergency Preparedness

• W. Lagergren, Operations Manager

• LaPoint, Site Director

• C. Mason, Plant 1 Manager

• M. Palmer, Radiation Health Manager-

• M. Swafford, Security Supervisor

• J. Vincelli, RadCon Field.0peration Manager

• J. Walker, Manager, Operations Support

' *C. Whittemore, Licensing l Engineer Other licensee. employees contacted during this inspection included engineers, operators,. mechanics, security force members, technicians, and administrative personne Nuclear Regulatory Commission

• J. Brady, Region 11

'*P. Harmon, SRI

- K. Jenison, SRI D. Loveless, R * Attended exit interview

- 2.- ExerciseScenario(83202)

The scenario for the emergency exercise was reviewed to determine that provisions had been made 'to test the licensee's integrated emergency response capability as well as to test a major- portion of the basic elements within the licensee's Emergency Plan as required by 10 CFR 50.54(t), 50.47(b)(14), and Section IV.F of. Appendix E to 10 CFR 5 =The scenario was reviewed in' advance of the scheduled exercise date and discussed briefly with . licensee representatives. While no major problems with- the scenario were identified during the review, several inconsistencies became apparent during the exercise which detracted from

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-2 the overall performance. For example, a General Emergency was declared earlier than the-scenario timeline because of a controller provided errant reading that the whole- body dose rate at the site boundary was 1 R/h Although- the Exercise Lead Controller interceded and told the Site Emergency Director'the data was erroneous, the exercise continued with the General Emergency classification in effec "

- At 0700, the- Control Room Lead Controller altered the plant parameter scenario data without informing any other facility controllers of the changes.- The operators corrcctly determined that they should not initiate RHR-cooling at this point in the accident- and the Control Room Lead Controller accepted their decision and altered key plant parameter data to reflect plant conditions that were based on their decisio This caused confusion in the Technical Support Center (TSC) which believed plant pressure was significantly lower than the altered data because the TSC data sheets were not change The above two observations were identified as an inspector followup item (IFI) 50-327, 328/89-20-01. Exercise inconsistencies and confusion occurred because exercise controllers provided incorrect data and altered data without coordinating the changes with other controller No violations or deviations were identifie ' ~Onsite Emergency Organization (82301)

.The licensee's organization was observed during the simulated emergency to ensure the requirements of Paragraph IV.A of Appendix E to 10 CFR 50 were

' implemented addressing the descriptions, responsibilities, and assignments of the onsite emergency response organizatio _'The inspector observed that the initial onsite emergency organization was adequately defined and that staff was available to fill key functional

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positions within the emergency organizatio The Shift Operations ;

Supervisor (SOS) promptly assumed the duties as the Site Emergency Director (SED) upon initiation of the simulated emergency and directed the response until relieved by the Operations Superintendent who assumed the SED. responsibilities. The-onsite TSC and Operation Support Center (OSC)

were staffed as well as ~ the- Central Emergency Control Center (CECC) and portions- of the Joint Information Center (JIC) which were located in

. Chattanooga. Assignments and training records for selected members of the emergency organization were reviewed and found to be fully adequate. A

' problem noted by both the licensee evaluators and the NRC inspection team was the failure to' activate the TSC, OSC, and CECC within 60 minutes as listed in the exercise objective The licensee identified this as a l- deficiency for corrective action. The licensee's corrective action to the delayed activations of the TSC, OSC, and CECC will be tracked for later review as IFI 50-327,328/89-20-0 No violations or deviations were identifie l

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3 Emergency Classification System (82301)

This area was observed to verify that a standard emergency classification and action level scheme was in use by the licensee as required by

'10 CFR 50.47(b)(4) and Paragraph IV.C of Appendix E to 10 CFR 5 An inspector observed that the emergency classification system was in effect as stated in the Radiological Emergency Plan and implementing procedures. The system appeared to be adequate for the classification of the simulated accident, however, it was not apparent that key emergency managers were proficient in recognizing all conditions to ensure an expeditious entry in to the Emergency Plan Classification Logic. For example, although the SED was notified at 0537 hours0.00622 days <br />0.149 hours <br />8.878968e-4 weeks <br />2.043285e-4 months <br /> that the Waste Gas Decay Tank (WGDT) had been ruptured by an explosion, neither the SED nor his TSC Managers were observed to review the classification logic tables for an emergency classification upgrade. It was not until 0549 hours0.00635 days <br />0.153 hours <br />9.077381e-4 weeks <br />2.088945e-4 months <br />, just after the Operations Manager had been informed by someone in the Control Room that a ruptured WGDT correlated to a Site Area Emergency (SAE) in EPIP-1, that the TSC staff reviewed the tables and the SED made the SAE declaratio No violations or deviations were identifie . Notification Methods and Procedures (82301)

This area was observed to assure that procedures were established for notification of State and local response organizations and emergency personnel by the licensee, and that the content of initial and followup messages to response organizations were establishe This area was further observed to assure that means to provide early notification to the population within the plune exposure pathway were established pursuant to 10 CFR 50.47(b)(5), Paragraph IV.D of Appendix E to 10 CFR 50, and specific guidance promulgated in Section II.E of NUREG-065 An inspector observed that notification methods and procedures had been established and were used to provide information concerning the simulated emergency conditions to Federal, State, and local response organization No violations or deviations were identifie . Emergency Communications (82301)

This area was observed to assure that provisions existed for prompt communications among principal response organizations and emergency personnel pursuant to 10 CFR 50.47(b)(6), Paragraph IV.E of Appendix E to 10 CFR 50, and specific guidance in Section II.F of NUREG-065 Communications among the licensee's emergency response facilities appeared adequate, however, the SOS did not adequately communicate the status of the accident to plant personnel using the plant announcing systems. For example, plant personnel were not informed of the following events via the

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plant announcirg system: (1) declaration of a Notification of- Unusual Event at 0347 hout s; (2) explosion in the Turbine Building at 0356 hours0.00412 days <br />0.0989 hours <br />5.886243e-4 weeks <br />1.35458e-4 months <br />; (3) reactor trip and safety injection at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />; and (4) declaration of an Alert at 0403 hours0.00466 days <br />0.112 hours <br />6.66336e-4 weeks <br />1.533415e-4 months <br />. The failure to keep plant personnel informed of key events during the simulated accident was identified as IFI 50-327, 328/89-20-0 Additional communication problems were noted by the licensee's exercise controller in the CECC. These included communication problems with the Tennessee Emergency Management Agency, between dose assessment and environmental assessment, and radio system problems with offsite monitoring team van No violations or deviations were identifie . AccidentAssessment(82301)

This area was observed to determine whether adequate methods, systems, and equipment for assessing and monitoring actual or potential offsite consequences of a radiological emergency condition were in use as required by 10 CFR 50.47(b)(9); 10 CFR 50, Appendix E Paragraph IV.B; and specific criteria in NUREG-0654,Section I The accident assessment program included an engineering assessment for plant status and an assessment of radiological hazards to both onsite and offsite personnel resulting from the accident. Accident mitigation was j

pursued aggressively and effectively throughout the exercise. The TSC and Control Room were highly effective in diagnosing conditions, following emergency procedures and recommending severe accident management strategies to mitigate the effects of the acciden No violations or deviations were identifie . Protective Responses (82301)

This area was observed to determine that guidelines for protective actions during the emergency, consistent with Federal guidance, are developed and in place, and protective actions for emergency workers, including evacuation of nonessential personnel, are implemented promptly as required by 10 CFR 50.47(b)(10), and specific criteria in NUREG-0654,Section I An inspector verified the licensee had emergency procedures for formulating protective action recommendations (PARS) for offsite populations within the 10 mile Emergency Planning lone (EPZ). The initial PARS that were recommended by the CECC upon reaching the General Emergency classification level did not include sheltering of the 5 mile downwind sector, although the licensee's PAR guidance indicated this as part of the minimum recommended protective action (along with shelter 2 mile radius).

The licensee recommended evacuation of the 2 mile radius as the PAR for this event. This recommendation appeared to be designed to parallel what the : tate authorities were - the process of implementing and was less conservative than required by 'he licensee's PAR guidance since it did not I

address the 2-5 mile dcwnwind actor.

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' The failure to follow the.. licensee's PAR guidance as the basis for their

- recommendatten to the State was identified.as IFI 50-327,328/89-20-0 No violations or deviations were identifie I ' Action on Previous -Inspection Findings (92701)

(Closed)=IFI 50-327,'328/88-57-02: Event notification sheet was not used for NRC- notification in accordance with Administrative Instruction AI-1 .This problem was not observed during the exercis . Exercise Critique (82301) and. Exit-Interview

' The' licensee's critique ' of the emergency exercise was observed to

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determine that.' shortcomings identified as part of the exercise, were brought to the attention of management and documented for corrective action pursuant to 10 CFR 50.47(b)(14), Paragraph IV.F of Appendix E to 10 CFR 50, and' specific guidance promulgated in Section II.N of NUREG-065 Effective player critiques were held following. exercise termination. In addition, the controller / evaluator staff of the exercise prepared a

' detailed and thorough critique and presented it to licensee's management, exercise controllers, observers, and NRC representatives on July 20, 198 The licensee did not identify any of the information provided . the inspector as proprietary. Following the licensee's critique, the NRC Team Leader provided a su nary of the NRC observations. Dissenting comments were not received froin the license Item Number' Description and Reference 50-327, 328/89-20-01 IFI - Exercise inconsistencies resulted from controller provided incorrect data and controller altered data (Paragraph 2).

50-327, 328/89-20-02 IFI - Delayed activations of the TSC, OSC, and CECC identified for corrective action by licensee (Paragraph 3).

50-327, 328/89-20-03 IFI - Plant personnel were not kept apprised of accident status (Paragraph 6).

50-327,328/89-20-04- IFI - Licensee failed to follow PAR guidance as the' basis for recommendation to the State (Paragraph 8).

Attachment:

- Sequoyah Nuclear Plant Goals and Objectives, Narrative Summary, and Timeline

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' SEQUOYAH NUdLEAR PLANT (SQN)

EMERGENCY PLAN (EP) E7,ERCISE 4 ~_

GOALS AND OBJECTIVES The 1989 SQN EP Exercise will be a partial participation exercise requiring full participation by TVA, with limited participation by the State and local emergency response agencies. Government and Fublic Aff airs (TVA) plans to partially activate the'SQN Joint Information Center (JIC), however, activation of the JIC is not an exercise objectiv ,

. Engrnise Goals TVA's goals'for the-19b9 SQN exercise are as follows: To allow plant and CECC personnel to test and demonstrate their response capability in accordance with the ONP-REP, SQF EPIPs', and CECC EPIPs to protect the health and safety of TVA employees and the general publi . To demonstrate that items observed in recent exercises and listed in item H have been correcte . To perform post-exercise critiques to identify emergency response capabilities that can be further improve . To provide training for emergency response personne .

Exercise Obiegtiyg5 Control Room Objectives Demonstrate the ability of the Site Emergency Director (Shift Operations Supervisor) to classify an emergency condition and make required notifications to the Operations Duty Specialist within five minutes and to the NRC within one hou . Demonstrate the ability to provide onsite protective actico measures for plant personne . Demonstrate the precise and clear trensfer of responsibilities from the Control Room staff to the Technical Support Center (TSC) staf Demonstrate the ability of the Shift Operetiens Supervir;er to vedote Control Room and plent personnel ei the status of the emercency situation and actions currently being planned by the TS ,

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5. _ Demonstrate the ability of the Control Room staff to provide information to the NRC on emergency classifications using standard nomenclater (i.e. , NOUE, Alert. etc.). Demonstrate that the Administrative Instruction 18 (AI-18) worksheet-is used to document the NRC notifications. (See 11.2)

' Demonstrate the ability of the Control Room personnel to maintain equipment status, plant status, corrective actions taken and to maintain log * Demonstrate effective command and control by the Shift Operations Supervisor (SOS) in the control roo , TSC Objectives 1. Demonstrate the ability to activate the TSC within 60 minute . Demonstrate effective command and control by the Site Emergency Director (SED) in the TS . Demonstrate the problem solving capabilities of the TSC staff to identify the cause of the incident, and mitigate the consequences of the inciden . Demonstrate the ability of the SED in the TSC to classify an emergency conditio . Demonstrate the ability to effectively utilize in-plant radiation

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monitor . Demonstrate the ability to perform timely assessments of onsite radiological condition . Demonstrate the timely updating of TSC status board . Demonstrate timely updating of the Operation Support Center (OSC) and the Control Room, and the transfer of technical information to the CEC . Demonstrate the ability to assemble onsite personnel and provide an accountability report to 'he SED within 30 minutes af ter sounding the accountability alarm . OSC Objectives Demonstrate the ability to activate the OfC within 60 minute . Demonstrate effective command and control by the OSC manager.

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- Demonstrate the following capabilities: ) OSC teams are briefed on plant condition Adequate Rad Con support is provide c.- Proper use of protective clothin i l OSC teams are tracked in a timely manne Demonstrate that there are adequate communications and efficient ,,

transfer of information between the OSC and the TSC, RadCon

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laboratory, and Chemistry laborator .

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Demonstrate the timely updating of OSC status board . Demonstrate'the radiological control capability to: Ferform ef fective in-plant and site boundary surveys during radiological emergencies while following good RadCon and ALARA practice Track changing radiological conditions through timely documentation of survey result Make timely and effective transfers of survey results from the OSC RadCon staff to the OSC and TS Control the exposure of onsite emergency worker Make a timely and efficient activation of the plant

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environmental monitoring van and the establishment of adequate communications with the TSC and/or CEC . Demonstrate the chemistry capability to obtain and analyze samples or data as necessary to support plant assessment and radiological assessment activitie CECC' Objectives 1. Demonstrate that the Operations Duty Specialist makes the initial emergency. notifications to the State with five minutes after plant notification and offsite TVA emergency personnel are notified in a timely manne . Demonstrate the ability to activate the CECC within 60 minute ,

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3. ' Demonstrate that the CECC Director makes a. clear' announcement-when he declares the CECC operational, maintains effective -

command and control:in the CECC, and'provides periodic briefings to the CECC staf . Demonstrate the' ability to effectively use TVA corporate or outside support organizations and to obtain vendor or other outside resources, if neede . Demonstrate the precise and clear transfer of accurate ,,

information between the TSC staff and the CECC staf . Demonstrate the ability of the CECC staff to. direct and coordinate the deployment of Radiological Monitoring Teams and coordinate TVA dose assessment activitie . Demonstrate the ability of the Dose Assessment Team to obtain, analyze, and use onsite and/or offsite radiological conditions and meteorological information to produce dose assessments to provide to the CECC Director in a clear and timely manne Demonstrate the ability to inform, update, and coordinate with State Radiological Health personnel regarding meteorologica dose assessment information, and plant statu . Demonstrate the ability of the CECC Flant Assessment Team to analyze current plant conditions. identify projected trends and potential consequences, and provide the information to the CECC Directo *

1 Demonstrate the ability of the CECC to provide at least hourly updates of plant status to the Stat . Demonstrate a timely and effective flow of information between CECC Radiological and Plant Assessment Tea . Demonstrate the timely updating of CECC status board . Demonstrate that proper security is established and maintained for the CEC . Demonstrate the ability to alert Federal and industriel emergency contacts as appropriat Demonstrate the adequacy of communicaticus links between the CECC and State Emergency Operation Cente Environs Assessment Activities , Demonstrate the ability of the Radiological Monitoring Teams tn efficiently and effectively utilize their procedures to perform dose rate surveys, collection and analysis of tadiolocicol samples, and other prescribed radiological monitoring activitie ~

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• Demonstrate the ability of the monitoring teams to follow contamination control procedures under field conditions it warrante . Demonstrate the-ability to control the exposure of offsite utility emergency worker . Demonstrate effective command and control of radiological monitoring activities by the plant and/or CECC and that adequate communications links exis ,,

, Public Information Objectives

~ Demonstrate the ability of site media relations to draft the first news release at the site while the CECC is being activate . Simulate the ability to coordinate information with non-TVA agencies from the CEC . Demonstrate the coordination and timely flow of information from the CECC to the TVA Public Information Staff in the JIC and the E1C in Knoxvill . Demonstrate the ability of the information staff in the CECC to develop timely and accurate news release Credit will be taken for the following required EP drill . Plent environmental radiological monitoring dril . Plant RadCon dril . TSC/CECC communications dril . Offsite environmental radiological monitoring dril . CECC dose assessment dril Open NRC identified exercise inspector follow-up items (Ifis): IFI - Failure of Shift Operating Supervisor to recognize explosion as an entry into the emergency classification leci (50-327, 328/S8-57-01) Training on this specific problem will be addressed in requalification trainin Proper classification according to item A.1 should close this ite . IF1 - Event Notification sheet not used f or subsequent NPC Notifications in accordance with Adminis,trative Instruction AI-1 (50-327, 328/88-57-02)

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, IFI - Licensee evacuation map sectors differs from State's map for evacuation. (50-327. 328/88-57-03) . IFI - Evaluate licensee's system test to determine the effectiveness of modifications made in response to 79-EU-1 (50-327, 328/88-57-04) SQN is currently scheduled to enmplete testing of this system' prior to the graded exercis '-

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THY: PAL 6093E '

4/28/89

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SEQUOYAH NUCLEAR PLANT (SQN) 1989 GRADED EXERCISE SLZNARIO

~ NARRATIVE SUMMARY Detailed initial conditions are provided to players through a pre-exercise message and are summarized as follows:

Unit 1 In a refueline outage with fuel being moved from the reactor to the spent fuel 93ol. Waste Gas compressor discharging into waste gas decay tank .

, Unit 2 At full power steady stat.r, operation, core is middle of life on the 45-day of an extended ru Core history is as follows: 150 l days at 100% power, 5 days shutdown, and 45 days at 100% powe A-A Auxiliary Feedwater (AFW) pump is out of service for maintenanc This exercise scenario involves a loss of auxiliary and main feedweter to SQN unit 2.. Feedwater loss at this location is a malfunction capability recently added to the'SQN simulato The initiating event for this exercise is a steam generator (SG) tube leak exceeding technical specifications. A Notification of Unusual Event (HDUE)

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i should be declared when the operators initiate shutdown required by the tech specs limits. The unit 2 operators will initiate a controlled shutdown according to GOI-5 and AOI-24 when they recognize the SG tube leak exceeds the ]

technical specifications leak rate based on radiochemistry sample results red j

. radiation monitor alarm Feedwater to SG loop 1 is disrupted at T=0:20 minutes when the chcckvalve  !

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3-510 bonnet blows out in the west valve room. This releeses slightly radioactive steam and water into the west valve room. Most of the steam is vented to the atmosphere but the level of radioactivity is barely above background offsite. The reactor will trip on low SG 1evel and safety injection (SI) initiates on AP between SG The main feedwater supply to the other three loops is lost when the FCV 3-10 bonnet ruptures in the Turbine Building releasing non-radioactive steam and water. The 2A-A motor-driven AFW pump is out of service but 2B-B motor-driven AFW pump starts and supplies feedwater to SG loops 3 and 4. Operators cannot align the SG loop 4 steam supply to the turbine-driven AFW pump (Terry turbine) and place it in service tecause FCV 1-16 malfunction An ALERI should be declared when the operators analyze a secondary beat sink loss concurrent with a SG tube leak which exceeds the tech specs limits. The Site Emergency Director (SED)/Shif t Operations Supervisor (SOS) will activate the Technical Support Center (TSC), Operations Support Center (OSC), and make required notifications. The SED may initiate assembly and accountability at the ALERT level. The Central Emergency Control Center (CECC) will also be activated at the ALER ,

The operators will identify and isolate the faulted SG and continue a controlled plant shutdow l

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2-At approximately T=2:00 hour into the scenario Waste Cas Decay Tank (WGDT) "A" sustains a hydrogen explosion, ruptures, and releases its contents into the auxiliary building. Area radiation monitors alam, WGDT "A" decreasing pressure, and a auxiliary building isolation will signal this condition. The SED should declare a SITE AREA EMERGENCI when this condition is analyzed and recognized. This event res11ts in a release through the auxiliary building gas treatment system. The maximum dose rate in the auxiliary building is 180

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j mr/ hour on evaluation 669. The maximum dose rate at the site boundry is 115 ^

, ar/ hour. If the assembly and accountability w'ere not performed at the ALERT-level, the SED will initiate site assembly and, accountability at this point by sounding the site assembly alarms / siren At elapsed time T=03:00 hours, the 1B-B MD-AFW pump trips and neither auxiliary or main feedwater is available. The SED should declare a GENERAL RfERGENCY within 30 minutes by proce. dure (EPIP-1) due to total feedwater loss and probable core melt if feedwater is not available for an extended time perio Upon total loss of feedwater,. operators open the pressurizer block and relief valves to establish feed and bleed for core cooling. The CCPs and SI pumps are in service. The pressurizer relief tank ruptures and phase B isolation occurs on Hi-Hi Containment Pressure. Containment spray pumps are placed in servic .At approximately T=03:30 hour operators align the RHR system to the containment sump to supply the CCP and SI pumps and switch containment spray from RWST to containment sump on low RWST leve .

The operators will continue RCS cooldown with RHR in containment sump recirculation mode and will eventually establish RHR shutdown coolin .

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l 8 THY: PAL 7/11/89 6247E l

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