IR 05000219/1989003

Safety Insp Rept 50-219/89-03 on 890117-20.No Violations, Deviations or Unresolved Items Noted.Major Areas Inspected: Licensee Emergency Preparedness Program

ML20236A557
Person / Time
Site:	Oyster Creek
Issue date:	03/03/1989
From:	Amato C, Lazarus W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20236A556	List: ML20236A553 ML20236A557
References
50-219-89-03, 50-219-89-3, IEIN-83-28, NUDOCS 8903170431
Download: ML20236A557 (11)

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U. S. REGULATORY COMMISSION

REGION I

Report N /89-03 Docket N License N DPR-16 Priority -- Category C Licensee: GPU Nuclear Corporation P~ 0. Box 388 Forked River, New Jersey 08731-0388 Facility Name: Oyster Creek Nuclear Generating Station Inspection at: Berkeley Townshia Forked River, Harvey Cedars, Lacey lownship and Toms River, New Jersey Inspection Conducted: January 17-20, 1989 Inspectors: (7 M, M ~ #4,/7///f C. G. Amato, Amergency Preparedness Specialist, date '

Emergency Preparedness Section, FRSSB, DRSS C. Z. Gordon, Emergency Preparedness Specialist, Emergency Preparedness Section, FRSSB, DRSS Approved By: / , WW 4r yazartis) chier, tmergency Preparedness c5date 3 f7 Sect 4 n, FR558, DRSS Inspection Summary: Inspection on January 17-20, 1989 (Inspection Report N F-2T978923)

Areas Inspected: Routine, announced, safety inspection of the licensee's emergency preparedness program conducted on January 17-20, 198 Results: No violations, deviations or unresolved items were identifie ?03170431 sco3ag h'DR ADOO: 03< ico 219 PDC

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DETAILS 1.0 Persons Contacted The following GPU Nuclear Corporation personnel were contacte ** R. Barrett, Director, J. Barton, Plant Operations,k Deputy Director, DivisionOyster Creek Division Oyster Cree

• T. Blount, Lead Emergency Planner, Emergency Planning Section

• J. Bontempo, Lead Emergency Planner, Emergency Planning Section ( * K. Burkholder, Emergency Planner, Emerge:.cy Planning Section

• B. DeMerchant, Licensing Engineer, Plant and Nuclear Safety Department W. Duda, Project Engineer, OC Engineering Projects, Technical Functions Division

• R. Fenti, Manager, QA, Modifications and Operations Department E. Fitzpatrick, Vice President GPU Nuclear Corporation and Director OysterCreekDivision

• R. Hillman, Manager, Plant Chemistry Department S. Kempf, Lead Offsite Emergency Planner, Emergency Preparedness Department

• ' Kowalski, Manager, Plant Training Department, Training Division

• D. Mac Farlene, Oyster Creek Site Audit Manager, Quality Assurance Division S. Polon, Manager, Public Information Department, Communication Division

• D. Ranft M J. Sevilla,anager, Plant EngineeringSergeant, Oyster Creek Site Security Section M. Slobodien, Director, Radiation Controls Division R. Stintzcum, Site Security Manager, Oyster Creek D. Wiegle, Sr. Environmental Engineer, Environmental Controls Section l

• J. Williams, Maintenance / Support Training Section Manager Site TrainingSection,TrainingandEducationDivision

• K. Wolf, Radiological Engineering Section, Manager

• Denotes licensee personnel who attended the exit meetin The inspectors also observed the actions of, and interviewed other licensee personne .0 Licensee Action On Previously Identified Items The following items were identified during previous inspection Based upon observations, review of procedures and discussions with licensee personnel by the inspectors, the following inspector follow up items are close (CLOSED) (50-219/88-05-07) Radio communications capability and radio net control used by security should be reviewed. Channel avail ability and radio net control were reviewed and determined to be adequat (CLOSED A discrepancy may exist between the Emergenc)y(50-219/88-05-08) Plan, it's Implementing Procedures and the site Contingency Plan resulting in possible delayed updating of the NRC l i

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as to the progress of security event Plans and Procedures as well 1 as coordination meetings between Security and the Emergency Preparedness Section staffs ensures procedures are in place and l understood ensuring timely NRC update l (CLOSED) (50-219/88-05-10 An inconsistency may exist within emergency classification p)rocedures with respect to the classification of security events. Revision 5 to classification

procedure 9473-IMP 1300.01 states the bases for classifying  ;

security event (CLOSED) (50-219/88-06-01) Three areas in emergency preparedness training require improvement. A computerized data base for tracking i emergency training status is functional and in use, the number of rescheduled emergency preparedness training sessions has been significantly reduced. Emergency Directors and Emergency Director Assistants are trained in core damage mitigatio i 3.0 The Emergency Preparedness Organization To determine if the licensee has developed, maintains and implements an emergency preparedness program (EPP which meets the standards of 10 CFR 50).47(b) and Section IV ofrequired by Appendix E to 10 CFR 50, or personnel were interviewed,ganizational structure and EPP activities werewas studied, identified, j 3.1 The EPP was transferred to the Radiological and Environmental Controls (R&EC) Division during 1988 and the present Divisional Director-Vice President a) pointed October 1988. He devotes about 20% of his time to EPP activities and regularly briefs the GPUNC President about emergency preparedness. The President is a qualified OC Alternate Emergency Support Directo .2 EPP operations are assigned to a Department; The Department office is staffed by a manager and three emergency planners. OC EPP responsibilities are assigned to a section staffed by a i manager and four professionals with backgrounds in nuclear engineering, health physics and reactor operations. A senior off site emergency planner located at the OC EP Section office i reports to the Emergency Preparedness Department manage .3 Each OC EPP Section member is assigned lead responsibility for  !

one of four on going activity areas which encompass over thirty l activities including 12 special project and 20 improvement activities. The EP Secti u Manager maintains close liaison with the Deputy Director of the OC Division and the OC Training Sectio Based on the above findings, this portion of the licensee's emergency plan is acceptabl _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ]

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i 4.0 Emergency Preparedness Training (EPT)

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In order to determine if emer  !

compliance with 10 CFR 50.47(gency preparedrass training is inb)(15) and Sj to 10 CFR 50, the inspector reviewed EPT activities, trainin  ;

records, lesson plans, Emergency Response Organization (ERO)g qualification roster, and the training matrix, and interviewed  :

Training Section staf .1 The OC Section of GPUNC's Training and Education Department (TED is responsible for EPT. EP Table 23 correlates EPT scope with)emerc ency response organization (ERO) positions. EPT reflects ;ob task analysis and is performance based. Various training modalities are used including classroom instruction and drills. Attendance is checked and where feasible numerical grades are assigned. Three new a introduced. One is a programmed,pproaches have been self paced sequence and or will be another makes use of audio cassettes followed by an open book examination. These innovative approaches are currently limited and do not cover all of EPT. Weekly training drills will begin in the near futur i 1 on shift; 2 initial 4.2 The ERO is and response: divided into three groups: Training matr)icas have bee)n 3 suppor developed for eac)h group. Lessons plans are current and attendance is tracked using a computerized data base. About ;

300 Oyster Creek staff are currently qualified including alternates. At least three personnel are qualified for each ERO position. The need to reschedule EPT has been reduced to one rescheduling within a year as a result of an OC Director i

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golicy requiring his office to be notified whenever there is a no show".

4.3 Accident Management Training (AMT) is given by another TED  !

section and an OC unit including trainia l Assessment, and Core Damage Mitigation. g in Core DamagePlant Engi Department personnel are trained in Systems Engineering including systems classified as engineered safety feature Senior reactor operators now assigned to the TSC fill various positions. The licensee plans to classify currently or formerly licensed senior operators assigned to the TSC as Emergency Director Assistants, establish a fourth duty roster i and provide required training. Severe accident a..alysis training is not given to engineers assigned to the TS .5 Licensed operators receive four hours of EPT which includes classification, notification procedures and Protective Action Recommendations.OnsimulatortrainingIsnotyetprovided.The on site OC simulator will include, upon completion a complete and functional replica of Emergency Command Center communication system This will permit hands on training and conduct of drills and exercises from the simulato Based on the above findings, this portion of the licensee's emergen-cy preparedness / training program is acceptabl i i

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' j 5.0- Audit / Review An inde)endent' audit / review is required at least every twelve months by 10 C:R 50.54Lt) including determination of adequacy of the

' licensee / Stater.ocal government interface and availability of the

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results of this study to State / local government (s). To ascertain if-l these requirements are met, the Quality Assurance evaluation report -

i for the OC. Emergency Pre correspondence checked. paredness-Program (EPP) was reviewed and

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5.1 The OC Site Audit Section undertook the required audit.from January to March 1988 using GPUNC Quality Assurance Procedures (QAP those). The audit noted above.encompassed ten-EPP

- The OC Director hasactivities including established a policy callin chair.g for weekly QA meetings whichand he recommendations or the Deputy Director Resolution of all QA findings is

. required before an audit report may be tabled at a weekly QA meetin Findings 5.2 Results of the EPP recommendations audit were were' satisfactory. interface adequacy was .and resolved evaluated, and report copies w,ere sent to the New Jersey State and Ocean County.0ffices of Emergency Managemen .3 The entrance meeting for the 1989 audit was hcid during the inspection period and was attended by the inspectors. Audit plan references were complete and a matrix was develope For the first time, two members of the audit' team, at the suggestion of the Oyster Creek EPP manager, were drawn from another nuclear utilit Based on the above findings, this portion of the licensee's emergency preparedness / audit program is acceptabl ,

6.0 Plans and Procedures Plans and Procedures' were reviewed to determine if they meet the requirements of 10 CFR 50.47(b)(16) and 50.54(q), and Section IV G of Appendix E to 10 CFR 5 .1 The EP was revised by GPUNC to reflect the altered status of THI Unit 2 and submitted to NRC for review. GPUNC res)onded to NRC concerns and the EP was reissued as Revision 1. Tie EP required changes to OC EPIP 9473-lMP-1300.02, Exhibit 2,

" Direction of Emergency Response". The revision wa; made and the EP and EPIP agree with respect to Protective Action Recom-mendation developmen .2 EPs and EPIPs in each Emergency Response Facility were surveye to find out if the current and correct PAR logic diagram was inserted. Results indicated current EPs and EPIPs were in place and contained the current PAR logic diagra !

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k' 6.3 Section 2.2.2 of the EP identifies related Plans and Procedures

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and their coordination with the EPIPs. These plans and proce-for example, the Site Security Flan Emergency Operation Proce duresinclude,dures-(EOPs)fandtheEmergencyPub1I tion Plan.. E0Ps contain re errals to Emergency Action Level .

(EAL) classification A sampling check indicated the other procedures, procedures.as appropriate, were availabl Based on the above findings, this portion of the licensee's emergen-cy preparedness program is acceptabl . Emergency Response Facilities The inspector conducted an tour of the Emergency Response Facilities (ERFs 50.47)bto determine if they and-(b)(9), meetIV Section the of requirements Appendix E.toof10 10CFR CFR50,

' Supple (me)n(8)1 t to NUREG0737 and Regulatory Guide 1.97. Equipment, status boards, communications systems, plans, procedures and access  ;

control provisions were checked for the Emerg ncy Command Center

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(ECC), the Emergency Operations Facility (E0F , the Technical Support Center (TSC) and a support facility, he Remote Assembly Area (RAA).

7.1 The ECC is within the the Control Room area. The ECC is

.' equipped with meteorological, radiological and plant system parameter readouts in acdition to access to all plant communi-cation systems'. The ECC was maintained-in a state of readines .2 The Technical Support Center (TSC) is located within the protected area. Status boards, maps wall boards, plans,-

proceduresandequipmentweremaintaInedinastateofreadi-nes Provision has been made to project real time data from the plant com System (SPDS)puter' including the Safety Parameter DisplayThis capa

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meteorological variables.specified in Regulatory Guide 1.97.

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Plant records, drawings etc. are also available. Thirteen communication systems link the TSC with other ERFs and off site >

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entities including NRC's Health Physics Network (HPN) phones which were functiona .3 The Emergency Operations Facility (EOF) is a non-dedicated facility located within the auditorium of a Jersey Central Power & Light business office 19 miles from the sit Provision has been made for the projection-of real time data from the plant computer system. Recent upgrades to.the

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facility have been made - the Emergency Support Director's (ESD) Office has been enlarged and the Environmental Assessment Command Center where projected ' doses are calculated has been !

moved to a room providing more space. A communicator's room will also be provided. Provision has been made for an NRC office and conference room. Space is provided for personnel of the New Jersey Bureau of Nuclear Engineering. Fifteen communication systems tie the E0F to other ERFs and off site emergency response centers. Both HPN phones were operative. A

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Certificate of Occupancy has been issued for the building  !

housing the E0 .j e 7.4 The' Remote Assembly Area (RAA) is equipped with monitoring.and !

decontamination equipment and a-security phone. Space is-adequatetoaccommodateslteevacuees. Signs directing evacuees to the RAA and the RAA assembly area are in plac Based on the above findings, this portion of the licensee's emergen-cy plan is acceptabl .0 Emergency Action Levels (EAls)

To determine if the EALs meet the standard of 10 CFR 50.47(b)(4),

the requirements of Section IV B of' Appendix E to 10 CFR 50, the

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guidance of NRC Office of Inspection and Enforcement Information Notice No.' 28 of 1983 (I&E IN 83-28), and Planning Standard D and Appendix 1 to NUREG-0654, Rev. 1, EALs were reviewed and discussed with EPP personne " Classification of Revision Emer ency5 Conditions" of procedure 9473-IMP-1300.01,he was compared with t standard, requirements and uidance. Classification is based on events, defined. Guidancesymptoms, brea barr ers and projected doses. Barrier breech is of I&E IN 83-28 is applied. EALs were sent to the New Jersey Office of Emergency Management; the licensee plans to meet with representatives from the New Jersey Bureau of Nuclear Engineering to-discuss the EAL Based on the above findings, this portion of the licensee's emergen-cy plan is acceptabl .0 Protective Action Recommendations (PARS)

The standard and requirements for PARS are given in 10 CFR 5 b 10

'47(da)n(ce)is gui found in I&E IN 83-28 and. Planning Standard J ofand Section I NUREG-0654, Rev. To determine if the standard and requirement are met and PARS are consistent with federal guidance, PARS were  !

r reviewed, and discussed with licensee's staff I PARS are based on Figure 24 of the GPUNC EP and Exhibit 2 of the OC classification procedure. The licensee advised the N.J. Office of  !

Emergency Management of the revised PAR logic diagram during August 1988, i Based on the above findings, this portion of the licensee's emergen-cy plan is acceptabl I i

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10.0 Notification an ' " communications

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Communications . ,cems were checked to ascertain if the requirements of 10 CFR 50.47(b)(5 and (b Sections IV D.1 and IV E. 9 of AppendixEto10CFR)50,and){6),IN86-97wereme i&E 10.1 Sixteen communication systems were identified. These systems include independent, redundant and diverse capability. Ten phones are provided at the E0F for N.J's Bureau of Nuclear '

Engineering. Operability was checked on a sampling basis and found to be satisfactor I 10.2 Emergency duty roster personnel are called in using an automated system consisting of a commercial pager system and verification system. Site Security activates both system The verification system checks call backs and in the event an acknowledgement is not received automatic. ally goes down the roster until the position is filled or the list is exhauste The inspector observed a drill and concluded the system was  !

rapid and effectiv I

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Based on the above findings, this portion of the licensee's emergen-cy preparedness plan is satisfactor .0 Public Information The Public Information Department Manager was interviewed and printed material distributed to the public studied to determine if i the requirements of 10 CFR 50.47(b)(7) and Section IV D.2 Of '

Appendix E to 10 CFR 50 are me .1 One staff member is sent to the ECC when the initial EAL is declared. Three staffers report to the E0F at the ALERT. A senior OC station engineer is assigned to the Media Center . A duty roster has been established. Monthly training is given to writers, information gatherers and technical briefers. All Media Center charts are being simplifie .2 An annual media briefing is held one week before the annual exercise. Invitations are extended to radio, television and newspaper personne .3 The public is advised as to emergency proceduras by mailed brochures, phone book inserts and newsletters. Eighty thousand brochures are sent two weeks before the annual exercise to the residents living within the ten mile Emergency Planning Zone. To to hotels, provide motels information and camp site to transients, A single pagebrocnures insert are sent appears on the inside. of the last page of the Ocecn County phone book containing a summary of essential information. The brochure is l revised annuall .4 Two quarterly newsletters are mailed, one to residents within

! the EPZ and the other to off site, governmental emergency workers. The latter newsletter is always sent three weeks before the annual exercis L____-_______________ . _ _ . _ _ _ _ _ _ _ _ _ . _ _ . _ . _ . _ _ . ._ _ _ _ _ _ _

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l Based on the above findings, this portion of the licensee's emergen-cy plan is acceptabl I 12.0 Off Site Activities To determine if the standards of 10 CFR 50.47(b)(5) and (b)(12) and the requirements of Sections IV D.3 and IV F of Appendix E to 10 CFR 50, are wt, the lead off site emergency planner was interviewed and appropriate records reviewe .1 Off site, governmental personnel are trained by the State of New Jersey which sends an annual training certification letter to U.S. FEMA-I j

12.2 Community fire comoanies and ambulance squads were offered >

training. Three fire companies sent personnel. Emergency medical training was given by a contractor to first aid squad members during October 198 ,

12.3 A medical training session and drill were held at the primary

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and secondary hospitals. The primary hospital medical facili- '

ties were inspected. Procedures were current, supplies met inventory listings and equipment was functional and within l calibration. Hospital staff interviewed were well versed in the procedures for treating contaminated / injured person ;

12.4 A remote verification system is being installed at all sirens )

locations. Siren freezing has not recurred following heater 1 installation. Corroded carbon steel base plates are being l replaced at 19 locations. Siren availability during 1988 was l 99.8% A letter certifyin U.S. FEMA-II by the N. J.g availability will be sent toOffice of Emergency M

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12.5 Evacuation Time Estimates are being updated; the revised values should be available by iate summer 198 Based on the above findings, this portion of the licensee's emergency plan is acceptabl .0 Security-Emergency Preparedness Interface To determine if the requirements of Section II.D.59 of Appendix B to 10 CFR 73 are met, NUREG/CR3251 was consulted and security personnel were interviewe .1 Security Officers are radiation worker qualified, respirator trained and fitted. Additional training is given in Emergency Preparedness, search and accountability, and activation of the call-in pager and verification syste .

13.2 An area monitor and a continuous air monitor are located within the Main Gate House. Twenty " chirpers" stored there are l are available fcr security officer use. A Guard House evacua-tion exposure rate has been established and fall back locations

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identified. Radiation Control support will be provided upon request. The Guard House ventilation system is not filtered and may be sealed if necessary. Anti-contamination clothing is available at the Operations Support Center (OSC). .

13.3 Security-emergency preparedness interface meetings are held, i There are provisions for Security-EP drills and the 1988 l exercise was security driven. If a security event results in l

declaration of an eat., security information is transmitted to i the Emergency Command Center which will provide the NRC with '

update Based on the above findings, this portion of the licensee's emorgency plan is acceptabl .0 Dose Assessment The standard, requirements and guidance for dose assessment are

, Sections IV B and IV E.2 of Appendix E, given Section in 10 NUREG-0654, 1.23 andII.f.1(2)

1.97 and CFR 50.47(b)(9)0737(V of NUREG-RE , Appendix 1 Supplement To determine if 1)2.,

the licensee is in compliance with these standards and guidance, facilities were inspected, records were cbcked and personnel interviewe .1 Plant releases are monitored by the radioactive gaseous i emission monitoring system (RAGEMS) at the stack base and from multiple points in the Turbine Building. RAGEMS collects particulate samples and iodines and monitors noble gas exposure rate. Both these are being upgraded during an outage and their satisfactory completion is part of the Restart Certification

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packag .2 RAGEMS upgrades include an improved cartridge retrieval system, ,

a heat traced stack sample line and a cartridge retrieval box o

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external to the RAGEMS stack house. Rain water had collected in the retrieval box; the licensee was aware of this and will take corrective action. Before OC restart, the Restart Certification requirements must be completed including RAGEMS detail RAGEMS items include approval of revised operating procedures, training of Chemistry Technicians in these, '

calibration, and retrieval box correction. The resident i inspector will follow up on this matte .3 There are three meteorological towert including one primary tower and two supporting towers. All are enclosed within locked fences. Only the primary tower is equipped with a backup power supply. The other towers serve as backups and provide data used to determine the presence and magnitude of a sea breeze effect. Tower sensor and associated electronic calibration records were reviewed. Calibration was current and effected using approved procedures.

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< m 14.4'The licensee has re' viewed the methodology for collecting. iodine' '

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'off site and concluded the system in use should be replace .

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The licensee plans to use silver zeolite cartridges; th required sample volume will' be. collected in_ five minute '

.14.5 Projected thyroid dose commitments are calculated using;known

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iodine release rates. If RAGEMS data are. not available, conservative default iodine to noble gas ratios will be used to estimate the iodine release rate. Projected dose calculational 'j

.r methods- are detailed in an Emergency Dose Calculations Manua (EDCM).-The licensee has reviewed the EDCM and removed many~

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conservative values but has not changed the iodine to noble gas F

ratio. The ratios in use are being reviewed by tta license ,

15.0 Exit Meeting An exit meeting was. held'with the licensee personnel identified in Section 1 of this'reporttto discuss the exercise findings.' The-licensee was advised no violations were identified.- The inspector-also discussed some areas for improvement. Licensee managemen acknowledged these findings and indicated they would evaluate the o and take. appropriate corrective action regarding.the items identified.

, At-no time during the course of the inspection did the inspectors .,

provide,any written material"to the licensee,

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