ML20236A557
| 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: |
| References | |
| 50-219-89-03, 50-219-89-3, IEIN-83-28, NUDOCS 8903170431 | |
| Download: ML20236A557 (11) | |
See also: IR 05000219/1989003
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U. S. REGULATORY COMMISSION
REGION I
Report No.
50-219/89-03
Docket No.
50-219
License No.
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
WW
c5 3 f7
Approved By:
/
,
4r yazartis) chier, tmergency Preparedness
date
Sect 4 n, FR558, DRSS
Inspection Summary:
Inspection on January 17-20, 1989 (Inspection Report No.
Areas Inspected:
Routine, announced, safety inspection of the licensee's
emergency preparedness program conducted on January 17-20, 1989.
Results:
No violations, deviations or unresolved items were identified.
8?03170431 sco3ag
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ADOO: 03< ico 219
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DETAILS
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1.0 Persons Contacted
The following GPU Nuclear Corporation personnel were contacted.
- R. Barrett, Director, Plant Operations,k DivisionOyster Creek Division
- J. Barton, Deputy Director, 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
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- 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
- 'J. 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
J. Sevilla,anager, Plant EngineeringSergeant, Oyster Creek Site Security Section
- D. Ranft M
M. Slobodien, Director, Radiation Controls Division
R. Stintzcum, Site Security Manager, Oyster Creek
D. Wiegle, Sr. Environmental Engineer, Environmental Controls Section
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- J. Williams, Maintenance / Support Training Section Manager Site
TrainingSection,TrainingandEducationDivision
- K. Wolf, Radiological Engineering Section, Manager
- Denotes licensee personnel who attended the exit meeting.
The inspectors also observed the actions of, and interviewed other
licensee personnel.
2.0 Licensee Action On Previously Identified Items
The following items were identified during previous inspections.
Based upon observations, review of procedures and discussions with
licensee personnel by the inspectors, the following inspector follow
up items are closed.
(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
adequate.
(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
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as to the progress of security events.
Plans and Procedures as well
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as coordination meetings between Security and the Emergency
Preparedness Section staffs ensures procedures are in place and
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understood ensuring timely NRC updates.
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(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 events.
(CLOSED) (50-219/88-06-01) Three areas in emergency preparedness
training require improvement. A computerized data base for tracking
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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 mitigation.
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3.0 The Emergency Preparedness Organization
To determine if the licensee has developed, maintains and implements
which meets the standards of 10 CFR 50).47(b) and Section IV ofrequired by
an emergency preparedness program (EPP
personnel were interviewed,ganizational structure was studied,
Appendix E to 10 CFR 50, or
and EPP activities were identified,
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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
Director.
3.2 EPP operations are assigned to a Department; The Department
office is staffed by a manager and three emergency planners. OC
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EPP responsibilities are assigned to a section staffed by a
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
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reports to the Emergency Preparedness Department manager.
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3.3 Each OC EPP Section member is assigned lead responsibility for
one of four on going activity areas which encompass over thirty
activities including 12 special project and 20 improvement
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activities. The EP Secti u Manager maintains close liaison with
the Deputy Director of the OC Division and the OC Training
Section.
Based on the above findings, this portion of the licensee's
emergency plan is acceptable.
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4.0 Emergency Preparedness Training (EPT)
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In order to determine if emer
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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 staff.
4.1 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
One is a programmed,pproaches have been or will be
grades are assigned.
Three new a
self paced sequence and
introduced.
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 future.
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1 on shift; 2 initial
4.2 The ERO is divided into three groups: Training matr)icas have bee)n
developed for eac)h group. Lessons plans are current and
response:
and 3 support.
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
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golicy requiring his office to be notified whenever there is a
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no show".
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4.3 Accident Management Training (AMT) is given by another TED
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section and an OC unit including trainia
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Assessment, and Core Damage Mitigation. g in Core DamagePlant Engi
Department personnel are trained in Systems Engineering
including systems classified as engineered safety features.
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
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and provide required training.
Severe accident a..alysis
training is not given to engineers assigned to the TSC.
4.5 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 systems.
This will permit hands on training and
conduct of drills and exercises from the simulator.
Based on the above findings, this portion of the licensee's emergen-
cy preparedness / training program is acceptable.
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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-
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these requirements are met, the Quality Assurance evaluation report -
correspondence checked. paredness-Program (EPP) was reviewed and
for the OC. Emergency Pre
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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
those). The audit encompassed ten-EPP activities including
(QAP
noted above. - The OC Director has established a policy
chair.g for weekly QA meetings which he or the Deputy Director
callin
Resolution of all QA findings and recommendations is
. required before an audit report may be tabled at a weekly QA
meeting.
5.2 Results of the EPP audit were' satisfactory. interface adequacy was .and
Findings
recommendations were resolved
evaluated, and report copies w,ere sent to the New Jersey State
and Ocean County.0ffices of Emergency Management.
5.3 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 developed.
For
the first time, two members of the audit' team, at the
suggestion of the Oyster Creek EPP manager, were drawn from
another nuclear utility.
Based on the above findings, this portion of the licensee's
emergency preparedness / audit program is acceptable.
6.0 Plans and Procedures
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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 50.
6.1 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 development.
6.2 EPs and EPIPs in each Emergency Response Facility were surveyed.
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 diagram.
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6.3 Section 2.2.2 of the EP identifies related Plans and Procedures
and their coordination with the EPIPs. These plans and proce-
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duresinclude,dures-(EOPs)fandtheEmergencyPub1I
for example, the Site Security Flan Emergency
Operation Proce
tion Plan.. E0Ps contain re errals to Emergency Action Level .
(EAL) classification
A sampling check indicated
the other procedures, procedures.as appropriate, were available.
Based on the above findings, this portion of the licensee's emergen-
cy preparedness program is acceptable.
.7.0
Emergency Response Facilities
The inspector conducted an tour of the Emergency Response Facilities
50.47)bto determine if they meet the requirements of 10 CFR
(ERFs
and-(b)(9),Section IV of Appendix E.to 10 CFR 50,
' Supple (me)n(8)1 to NUREG0737 and Regulatory Guide 1.97. Equipment,
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status boards, communications systems, plans, procedures and access
control provisions were checked for the Emerg ncy Command Center
(ECC), the Emergency Operations Facility (E0F , the Technical
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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 readiness.
7.2 The Technical Support Center (TSC) is located within the
protected area.
Status boards, maps wall boards, plans,-
proceduresandequipmentweremaintaInedinastateofreadi-
ness.
Provision has been made to project real time data from
System (SPDS)puter' including the Safety Parameter DisplayThis capa
the plant com
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meteorological variables.specified in Regulatory Guide 1.97.
Plant records, drawings etc. are also available. Thirteen
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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 functional.
7.3 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 site.
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
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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
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housing the E0F.
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7.4 The' Remote Assembly Area (RAA) is equipped with monitoring.and
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decontamination equipment and a-security phone.
Space is-
adequatetoaccommodateslteevacuees.
Signs directing
evacuees to the RAA and the RAA assembly area are in place.
Based on the above findings, this portion of the licensee's emergen-
cy plan is acceptable.
8.0 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
guidance of NRC Office of Inspection and Enforcement Information
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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 personnel.
" Classification of
Revision 5 of procedure 9473-IMP-1300.01,he standard, requirements
Emer ency Conditions" was compared with t
Classification is based on events, defined. Guidancesymptoms, brea
and uidance.
Barrier breech is
barr ers and projected doses.
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 EALs.
Based on the above findings, this portion of the licensee's emergen-
cy plan is acceptable.
9.0 Protective Action Recommendations (PARS)
The standard and requirements for PARS are given in 10 CFR 50.
'47(da)n(ce)is found in I&E IN 83-28 and. Planning Standard J ofand Section
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NUREG-0654, Rev. 1.
To determine if the standard and requirements.
are met and PARS are consistent with federal guidance, PARS were
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reviewed, and discussed with licensee's staff
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
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Emergency Management of the revised PAR logic diagram during August
1988,
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Based on the above findings, this portion of the licensee's emergen-
cy plan is acceptable.
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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),IN86-97weremet.
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
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Engineering. Operability was checked on a sampling basis and
found to be satisfactory.
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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 systems.
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 exhausted.
The inspector observed a drill and concluded the system was
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rapid and effective.
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Based on the above findings, this portion of the licensee's emergen-
cy preparedness plan is satisfactory.
11.0 Public Information
The Public Information Department Manager was interviewed and
printed material distributed to the public studied to determine if
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the requirements of 10 CFR 50.47(b)(7) and Section IV D.2 Of
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Appendix E to 10 CFR 50 are met.
11.1 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 simplified.
11.2 An annual media briefing is held one week before the annual
exercise.
Invitations are extended to radio, television and
newspaper personnel.
11.3 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
to hotels, provide information to transients, brocnures are sent
Zone. To
motels and camp sites. A single page insert appears
on the inside. of the last page of the Ocecn County phone book
containing a summary of essential information. The brochure is
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revised annually.
11.4 Two quarterly newsletters are mailed, one to residents within
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the EPZ and the other to off site, governmental
emergency
workers. The latter newsletter is always sent three weeks
before the annual exercise.
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Based on the above findings, this portion of the licensee's emergen-
cy plan is acceptable.
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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 reviewed.
12.1 Off site, governmental personnel are trained by the State of
New Jersey which sends an annual training certification letter
to U.S. FEMA-II.
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12.2 Community fire comoanies and ambulance squads were offered
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training. Three fire companies sent personnel. Emergency
medical training was given by a contractor to first aid squad
members during October 1988.
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12.3 A medical training session and drill were held at the primary
and secondary hospitals. The primary hospital medical facili-
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ties were inspected.
Procedures were current, supplies met
inventory listings and equipment was functional and within
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calibration.
Hospital staff interviewed were well versed in
the procedures for treating contaminated / injured persons.
12.4 A remote verification system is being installed at all sirens
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locations.
Siren freezing has not recurred following heater
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installation. Corroded carbon steel base plates are being
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replaced at 19 locations.
Siren availability during 1988 was
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99.8% A letter certifyin
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U.S. FEMA-II by the N. J.g availability will be sent toOffice of Emergency
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12.5 Evacuation Time Estimates are being updated; the revised
values should be available by iate summer 1989.
Based on the above findings, this portion of the licensee's
emergency plan is acceptable.
13.0 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 interviewed.
13.1 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 system.
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13.2 An area monitor and a continuous air monitor are located within
the Main Gate House.
Twenty " chirpers" stored there are
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are available fcr security officer use. A Guard House evacua-
tion exposure rate has been established and fall back locations
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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).
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13.3 Security-emergency preparedness interface meetings are held,
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There are provisions for Security-EP drills and the 1988
exercise was security driven.
If a security event results in
declaration of an eat., security information is transmitted to
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the Emergency Command Center which will provide the NRC with
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updates.
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Based on the above findings, this portion of the licensee's
emorgency plan is acceptable.
14.0 Dose Assessment
The standard, requirements and guidance for dose assessment are
, Sections IV B and IV E.2 of Appendix E,
given in 10 CFR 50.47(b)(9)0737(V 1 Supplement 1)2.,
Section II.f.1(2) NUREG-0654, RE , Appendix
To determine if
of NUREG-
1.23 and 1.97 and
the licensee is in compliance with these standards and guidance,
facilities were inspected, records were cbcked and personnel
interviewed.
14.1 Plant releases are monitored by the radioactive gaseous
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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
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satisfactory completion is part of the Restart Certification
package.
14.2 RAGEMS upgrades include an improved cartridge retrieval system,
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a heat traced stack sample line and a cartridge retrieval box
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external to the RAGEMS stack house.
Rain water had collected
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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
details.
RAGEMS items include approval of revised operating
procedures, training of Chemistry Technicians in these,
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calibration, and retrieval box correction. The resident
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inspector will follow up on this matter.
14.3 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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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 replaced.
The licensee plans to use silver zeolite cartridges; the.
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required sample volume will' be. collected in_ five minutes.
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.14.5 Projected thyroid dose commitments are calculated using;known
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
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methods- are detailed in an Emergency Dose Calculations Manual.
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(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
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ratio. The ratios in use are being reviewed by tta licensee.
15.0 Exit Meeting
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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 management.
acknowledged these findings and indicated they would evaluate them.
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and take. appropriate corrective action regarding.the items
identified.
At-no time during the course of the inspection did the inspectors
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provide,any written material"to the licensee,
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