IR 05000219/1989020

Insp Rept 50-219/89-20 on 890829-30.No Exercise Weaknesses Noted.Major Areas Inspected:Licensee Emergency Preparedness Exercise Conducted on 890829-30

ML20247K986
Person / Time
Site:	Oyster Creek
Issue date:	09/07/1989
From:	Amato C, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20247K983	List: IR 05000219/1989020 ML20247K977
References
50-219-89-20, NUDOCS 8909220085
Download: ML20247K986 (6)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /89-20 Docket N License No. DPR-16 Priority ------- Category C Licensee: GPU Nuclear Corporation P. O. Box 388 Forked River. New Jersev 08731-0388 Facility Name: Oyster Creek Nuclear Generatina Station Inspection at: Lakewood and Forked River New Jerscv Inspection Conducted: Auaust 29-30. 1989 i

Inspectors:

C. GC -AffiatoCftergency Preparedness -

b 9 7 date

Specialist, EPS, FRSSB, DRSS L. Bettenhausen, NRC, RI, DRSS E. Fox, Jr., Sr. EPS, EPS, RI C. Cardon, EPS, EPS, RI T. Guilfoil, Sonalysts, In B. Haagensen, Sonalysts, In Approved by: et 9 #

/ j W. J.z'14zar(s) Chief date' d Emergency Preparedness Section, FRSSB, DRSS Inspection Summary: Inspection on Auaust 29-30. 1989 (Report No. 50-219/89-201 0 Areas Inspected: Routine, announced, safety inspection of the licensee's emergency preparedness exercise conducted on August 29-30, 198 The inspection was performed by a team of six Region I personne Results: No exercise weaknesses were identified. The licensee's response actions were adequate to provide protective measures for the health and safety of the publi {

8909220085 890912 ]

PDR ADOCK 05000219  ;

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DETAILS Persons Contacted

.The following GPU Nuclear Corporation (GPUNC) personnel attended the exit meeting.

! J. Barton, Deputy Director,.0yster Creek Division

~ T. Blount, Lead Emergency Planner J. Bontempo, Lead Emergency Planner B. DeMerchant, Licensing Engineer E. Fitzpatrick, Director, Oyster Creek Division and Vice President G. Giangi, Manager, Emergency Preparedness Department J. Hildebrand, Director, Environmental and Radiological Controls Division and Vice President S. Kempf, Jr., Lead Offsite Emergency Planner

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P. Scallon, Jr., Director, Radiological Waste E. Scheyder, Director, Maintenance, Construction & Facilities

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R. Sullivan, Oyster Creek Emergency Preparedness Department Manager M. Slobodien, Director Radiological Control' Department The inspectors also observed the actions of, and interviewed other licensee personne .0 Emeroency Exercise The Oyster Creek announced, partial participation exercise was conducted on August 29, 1989, from 5:29 p.m. to 10:30 p.m. The State of New Jersey, Bureau of Nuclear Engineering and the New Jersey State Police Office of Emergency Management participated to a limited degre Pre-exercise Activities o

The exercise objectives submitted to NRC Region I on January 30, 1989 were reviewed'and, following revision, determined to be adequate to test the licensee's Emergency Plan. On August 1,1989, the licensee submitted the complete scenario package for NRC review and evaluation. Region I representatives had telephone conversations with the licensee's emergency preparedness staff to discuss the scope and content of the scenario. As a result, minor revisions were made to the scenario which allowed adequate testing of the major portions of the Oyster Creek Nuclecr Generating Station Emergency Plan and Implementing Procedures and also provided the opportunity for the licensee to demonstrate those areas previously identified by the NRC as in need of corrective actio NRC observers attended a licensee briefing on August 29, 198 Suggested NRC changes to the scenario made by the licensee were discussed during the briefing. The licensee stated that certain emergency response activities would be simulated and that controllers would intercede in exercise activities to prevent disruption to normal plant activitie _ _ - _- - _ _ _ _ _ - _________ _ _-__ _ _ ___- -__-_-- _ _ _ _ _ _ _ _ -

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L-3 H 2.2: Exercise Scenario The exercise scenario included the followingl events:

-. Inability to determine drywell oxygen concentration;

- Small break' loss of coolant accident inside. containment;

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i!  :- Feed and condensate systems inability to maintain reactor vessel. water

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- Torus leak and containment flooding;

- Loss of one cere~ spray loop;

- Core uncovery and metal water reaction;

- Drywell hydrogen concentration in the inflammable range (6%); and,

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- Drywell. ventin .3 Activities Observed During'the' conduct of the licensee's exercise, NRC team members made detailed observations of the activation'and augmentation of the Emergency Response Facilities (ERFs) and the Emergency Response Organization (ERO) staff and actions of ERO staff during operation of the ERFs. The following activities were observed: Detection, classification, and assessment of scenario events; Direction and coordination of emergency response; Augmentation of the Initial Emergency Response and Support Organizations and Emergency Response Facilities; Notification of licensee personnel and off-site agencies of pertinent plant status information; Communications /information flow, and record keeping; and Assessment and projection of off-site radiological dose and consideration of protective action _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ - _ _ _ - '

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3.0 Exercise Observations The NRC team noted.that the licensee's activation of the Emergency Response Organization, Emergency Response Facilities, and use of these facilities were generally consistent with their Emergency Plan and Emergency Plan Implementing Procedure .1 Exercise Strenaths The team also noted the following actions that were indicative of their ability to cope with abnormal plant conditions and implement their Emergency Plan: Selection and use of Abnormal Operating Procedures, Emergency Operating Procedures and Annunicator Response Procedures; Shift Technical Advisor and Group Operating Supervisor continually tracked problems and developed recommendations; Effective command and control and staff use by the Emergency Director; The Technical Support Center (TSC) staff actively diagnosed problems and developed accident migitation steps; . The Operations Support Center (OSC) was well organized, l dispatching 20 in-plant teams; Detailed briefing and debriefing of OSC teams; Proactive response by the Emergency Operations Facility (EOF)

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Frequent E0F staff briefings by the Emergency Support Director l (ESD) and E0F manager's conferences which included the leader of L the New Jersey Bureau of Nuclear Engineering E0F team; Use of Emergency Operating Procedures and good record keeping in the E0F; 1 Consideration of evacuation or sheltering as Protective Action Recommendation options given weather conditions, the nature of the plume and the tentative venting schedule; 1 The Environmental Assessment Command Center staff (dose projection group in the E0F) considered plant conditions, different source terms and possible effects of forecasted weather changes when calculating projected doses; and, 1 Use of realistic iodine to noble gas ratios.

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3.2 . Exercise Weaknesses An exercise weakness is a. finding that the licensee's demonstrated level of preparedness could have precluded' effective implementation of the j emergency plan in the event of an actual emergency in the area being 1 observe No exercise weaknesses were identifie .3 Areas For Improvement An area for improvement is a finding that did not have a 'significant negative impact on overall performance during the exercise,.none-the-less these items should be evaluated for correction by the license The Group Shift Supervisor did not maintain the ED's check list enrrent;.

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There was an entry delay of over two hours for OSC.in plart team 17. This team may not have clearly known the actions expected of them. A team in the turbine building was not diverted to do the tasks assigned to team 17;

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Shift control room operators and controllers prompted exercise operators;

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Core damage assessments were not coordinated with the Parsippany Technical Functions Center due to failure to communicate plant data in a timely manner;

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The OSC Coordinator's log book was not maintained in a manner that would support activity reconstruction and support in-depth turnover briefings;

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OSC staff briefings did not always update workers as to changes in plant conditions;

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EOF security was not always maintained at the rear of the EOF (two doors were unlocked);

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There was confusion, at times, as to whether the radioactive release was monitored or unmonitored; and,

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The EOF staff did not initially recognize the pressure spike in the drywell due to a hyrogen bur .0 Licensee Critiaue The NRC team attended the licensee's exercise critique on August 30, 1989 during which the licensee's lead controllers discussed observations of the exercise. The licensee's critique was thorough. The licensee indicated that the NRC observations would be evaluated and appropriate

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corrective actions take < Exit Meetino Following the licensee's self critique, the NRC team met with the licensee's representatives listed in Section 1 to discuss findings as detailed in this repor The NRC team leader summarized the observations made during the-exercis The licensee was advised no exercise weaknesses were identified. Although areas for improvement were identified, the NRC team determined that within the scope and limitations of the scenario,

'the licensee's performance demonstrated they could implement- their Emergency Plan and Emergency Plan Implementing Procedures in a manner that would adequately provide protective measures for the health and safety.of the publi At no time during the course of the inspection did the inspectors

. provide any written'information to the license a I

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