ML20041B850
| ML20041B850 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/18/1982 |
| From: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Phyllis Clark GENERAL PUBLIC UTILITIES CORP. |
| References | |
| CAL-82-03, CAL-82-3, NUDOCS 8202250260 | |
| Download: ML20041B850 (5) | |
Text
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FEB 18 22 O k' '
Docket No. LO-219 CAL 82-03 J' '
GPU Nuclear Corporation ATTN:
Mr. Philip R. Clark lc.
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Vice President - Nuclear
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p, Ys Gentlemen:
This letter refers to the meeting with you and members of your staff, Mr.
J. M. Allan and other members of the NRC Region I staff, Mr. C. R. Van Niel of,
the Office of Inspection and Enforcement; and Mr. J. J. Lombardo of the Office of Nuclear Reactor Regulation; which was held on January 28, 1982, in the Region I office.
The meeting concerned the actions you are going to take regarding the significant findings of the NRC Emergency Preparedness Implementation Appraisal Team which were made during their appraisal of your Oyster Creek Nuclear Generating Station on January 4 through January 15, 1982.
These significant findings and your corrective actions were also discussed among Mr.
P. B. Fiedler, Vice President Oyster Creek, and other members of his staff and Mr. W. W. Kinney, Appraisal Team Leader, and members of the Emergency Preparedness Implementation Appraisal Team on January 15, 1982.
With regard to the matters discussed at the meetings, we understand that you will undertake and complete the following actions.
1.
Improve the Emergency Response Facilities as follows:
a.
Relocate the Emergency Control Center (ECC) so that it is out of the Control Room and is completely contained in the Group Supervisor's Office.
Since the Group Supervisor's Office is not large enough, this will require either a reduction in the number of emergency response organization members working in the ECC, or expansion of the size of the Group Supervisor's Office, or a combination of the two options.
A schedule will be provided to the NRC Region I office no later than February 20, 1982.
b.
In regard to the Technical Support Center (TSC):
(1) Upgrade the present Technical Support Center with:
a ventilation system providing adequately filtered air; instrumentation to detect direct radiation and airborne contamination; a more comprehensive set of plant drawings; a more comprehensive set
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FEB 181982 of plant parameter data from the computer terminal; more space for the occupants; and better spacing of the telephones. Also, provide a copy of the results of the TSC shielding study to Region I of the NRC.
(2) Because you are not providing a permanent Technical Support j
Center as described in your September 11, 1981, letter to the Director of the Office of Nuclear Reactor Regulation by October 1, 1982, resubmit conceptual design information for a suitable TSC which meets the requirements of the Office of Nuclear Reactor Regulation, February 18, 1981, Generic Letter 81-10 concerning " Post-TMI Requirements for the Emergency Operations Facility." Also include a schedule showing milestones and the date when the facility will be operational.
Provide a copy of your complete submittal to the NRC Region I office.
These actions shall be completed no later than April 1, 1982.
1 c.
Locate and equip the Operational Support Center as described in the Emergency Plan and in your September 11, 1981, letter to the Director of the Office of Nuclear Reactor Regulation.
This shall be completed no later than October 1, 1982.
d.
Upgrade the Nearsite Emergency Operations facility located in Building 12 of the Forked River site with equipment and supplies to allow management and technical personnel to perform emergency functions as described in your September 11, 1981, letter to the Director of the Office of Nuclear Reactor Regulation.
This shall be accomplished no later than March 16, 1982.
e.
Provide a Farsite Emergency Operation Facility which has the same capabilities as the Nearsite Emergency Operations Facility as called for in your Emergency Plan and in your September 11, 1981, letter to the Director of the Office of Nuclear Reactor Regulation.
This shall be completed no later than October 1, 1982.
2.
Improve Post-Accident Sampling Capability as follows:
a.
Complete the installation and calibration of your new stack effluent monitoring system. Develop procedures to collect and analyze post-accident gaseous, particulate and iodine samples containing high levels of radioactivity consistent with the activity levels identified in Table II.F.1-2 of NUREG-0737.
This shall be accomplished prior to resumption of reactor operations after your 1982/1983 refueling / maintenance outage.
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Until you have installed your equipment capable of sampling reactor coolant and containment atmosphere under post-accident conditions per NUREG-0737 and have it operational, evaluate and define the 3
post-accident conditions under which reactor building accessibility for such sampling can be reasonably expected and determine radiation levels of the reactor coolant which can be sampled without exceeding appropriate NRC personnel exposure criteria or EPA action guides.
Also, during this interim, define and procure necessary sampling and laboratory equipment and prepare procedures for sampling and analyzing high activity samples including reactor coolant, containment air, and airborne effluents.
Provide the schedule for the expedited i
procurement of equipment to the NRC Region I office.
The above actions, except for the procurement of the necessary sampling and laboratory equipment, will be completed no later than March 1, 1982.
3.
Complete the development of and establishment of a more comprehensive training / retraining program for all emergency response personnel which is consistent with your new Emergency Plan and Emergency Plan Implementing Procedures.
Complete the training of all members of the newly defined onsite and offsite emergency organizations.
In particular, complete the training of offsite monitoring teams; sampling teams taking high activity samples; and analytical chemistry personnel analyzing high activity samples using hands-on type training.
The more comprehensive training / retraining program will be developed and established no later than June 1, 1982. The licensee reports that the upgraded training has been initiated and will continue on an expedited basis, and that the offsite monitoring teams were trained prior to January 21, 1982. The sampling teams and analytical chemistry personnel will be trained no later than one month after the expeditious procurement of the sampling and laboratory equipment previously addressed in item 2.b.
l 4.
Improve your procedures as follows:
l Incorporate appropriate references to the Emergency Plan Implementing a.
Procedures in your operating procedures.
This shall be completed prior to resumption of reactor operations after your 1982/1983 refueling / maintenance outage.
b.
Complete the revision and expansion of your Emergency Plan Implementing Procedures so that personnel are specifically directed in the completion of all required emergency response tasks. Also include in these procedures:
appropriate judgment guidelines, precautions, limitations, and refcrences to other procedures used in completing the emergency responsu tasks.
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This shall be completed no later than June 1, 1982.
c.
As backup to computer based methodology, establish a manual procedure to be used to determine offsite doses to the thyroid based on measured and projected radioiodine concentrations.
The procedure should document assumptions used; incorporate appropriate EPA-520 or ICRP models; and be made consistent with the procedures used by the appropriate offsite agencies.
This shall be completed no later than June 1, 1982.
5.
Perform an engineering study of existing Area Radiation Monitors (ARM's) and Process Radiation Monitors (PRM's) to determine the upgrading necessary to the monitoring system to provide adequate accident detection and classification and post-accident radiation mapping capabilities to meet ANSI-N320.
Provide a schedule to the NRC for the upgrading of the monitoring system as determined by the study.
The study shall be completed no later than June 1,1982. The schedule i
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for upgrading the monitoring system will be provided shortly thereafter.
Another significant finding regarding your lack of installed equipment capable of sampling reactor coolant and containment atmosphere under post-accident conditions per NUREG-0737 was not listed because you have made two requests to the Office of Nuclear Reactor Regulation to allow the postponement of this installation. As soon as we resolve the status of your requests, we will inform you when this sampling equipment must be installed.
If our understanding of your planned actions, described above, is not in accordance with the actual plans and actions being implemented, please contact this office by telephone and in writing within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Your cooperation in this matter is appreciated.
Sincerely, p)
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(Ronald C. Haynes
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Regional Administrator cc:
M. Laggart, Licensing Supervisor i
J. Knubel, BWR Licensing Manaaer Public Document Room (PDR)
Local Public Document Room (LPDR) j Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New Jersey
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Region I Docket Room (with concurrences)
Dr. Steven Long, Administrator for Nuclear Evaluations B. Grimes, DEP, IE:HQ S. Schwartz, DEP, IE:HQ R. Carlson, Region I R. Keimig, DRPI, Region I E. G. Greenman, DRPI, Region I