ML20063C240
| ML20063C240 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/19/1982 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Haynes R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20063C233 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 5211-82-088, 5211-82-88, NUDOCS 8205040624 | |
| Download: ML20063C240 (4) | |
Text
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P.O. Box 480 Middletown. Pennsylvania 17057 717-944-7621 Writer's Direct Dial Number:
April 19, 1982 5211-82-088 Office of Inspection and Enforcement Attn:
R. C. llaynes Region I, Regional Administrator U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMl-1)
Operating License No. DPR-50 Docket No. 50-289 Response to Inspection Report 50-289/81-20 By letter dated March 5,1982, (transmitting the subject inspection report) you requested notification within 5 days of receipt of your inspection report of the status of Item 6, procedural revisions to reflect precautions and prerequisites for post accident containment atmosphere sampling. As discussed between Mr.
George Giangi (GPUN) and Mr. E. Wojnas (NRC), we are attempting to complete our long term (NUREG 0737) modifications for post accident containment atmosphere sampling prior to restart of TMI-1.
The applicable procedures will be revised to either reflect this long term modification completion, or to reflect our interim sampling capability prior to restart of TMI-1.
Further, in response to your request for written notification upon completion of the procedure (s),
we will advise you upon completion of the modifications and accompanying procedure (s) noted in Attachment A.
Secondly, your inspection report requested a written statement within 30 days of the status, schedule and actions taken with regard to your Appendix A items and our consideration of your Appendix B items. A revised response date of April 19 was agreed to between Mr. William Miller (GPUN) and Mr.
A. Fasano (NRC) and your Supervisor of Files, Mail and Records, Region I.
Attachments 1 and 2, respectively, contain the requested information. We note that the information contained in Attachment 1 was provided on February 25, in a summary form in response to your verbal request.
Finally, in the course of our review of Inspection Report 81-20, we noted several minor points that require clarification. These items are provided as comments in Attachment 3.
Sincerely, 0
l F205040624 820428
/
PDR ADOCK 05000289 H. D. l u ill O
PDR Director, TMI-1 HDH:WJM:GJG:vj f cc:
R. Jacobs E. Wojnas GPU Nuclear is a part of the General Pubhc Utihties System
i ATTACHMENT I' STATUS OF APPENDIX A ITEMS Item 1 Introductory and specialized emergency' plan training for all categories of essential personnel was conducted from April '81 through December '81.
The 1982 training cycle / iteration started in February 1982. The 1982-iteration / cycle of emergency preparedness training continues.- Its intent is to refresh previously trained personnel, and train newly assigned personnel and those who missed or who failed to sucessfully complete the 1981 training iteration. While training will continue throughout the year,uit is anticipated that the bulk of the essential personnel will have completed'the 1982 emergency plan training by August. The remainder of the year will be devoted to make-up training sessions, and to training of personnel newly assigned to emergency plan positions.
Item 2 The Prompt Alerting System has been installed and is operational as reflected in Licensee's January 18, 1982 letter to the NRC.
Item 3 Reactor Building Evacuation Alarm Modification essentially is installed.
Minor component installations and operational testing of the system in plant noise background levels are required prior to completion. _This will be completed prior to and during restart of TMI-1.
Item 4 Appropriate EPIP's will be revised to incorporate high range noble gas and effluent analyses into the accident assessment scheme prior to restart.
Meter conversion factor data, obtained through meter calibration, is required prior to completion.
Item 5 EPIP 1004.33 has been revised to define precautions to be observed to ensure the protection of the counting facility from high activity samples. EPIP 1004.15 has been revised to define the specified limits to be observed to control personnel exposure during post-accident sampling to define a method of labeling and tracking the sample. It was our understanding at the time of the audit that the above actions were sufficient to close out this item.
Item 6 Licensee currently anticipates completion of our long term (NUREG-0737) modifications for post-accident containment atmosphere sampling prior to restart. Procedural guidance will be issued, prior to restart, to reflect i
either the long term modification or the interim sampling capabilityLdescribed in Licensee's letter, L1L-348 dated 12/16/81.
i Item 7 EPIP 1004.14 currently contains provisions for sampling and analyzing liquid l
generated or exisiting post-accident in order to determine the proper disposal method. A PCR (procedure change request) is being processed which references the appropriate chemistry procedure for sample procurement and handling as well as the appropriate EPIP for radiological precautions,
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and which provides guidance on obtaining a dose-rate measurement of the sample. These procedure changes will be implemented prior to restart of TMI-1.
i l
i ATTACHMENT II RESULTS OF CONSIDERATION TO APPENDIX B ITEMS Item 1 A re-evaluation of the number of commercial telephone lines available in the TSC to fully support the functions -of the response organization, including the NRC, during an' emergency has been conducted.
This re-evaluation has concluded that~the number of-
. telephone lines currently available in the TSC are sufficient to properly respond to an emergency. This conclusion is supported through numerous drills conducted in 1981 and 1982.
Item 2 This items appears in the ' ASLB's partial initial decision on the restart of TMI-1.
Licensee has filed an exception.and brief with the Appeal Board on this item.
If the Licensing Boards cendition is not reversed prior to restart, Licensee has co=mitted to desig-nate an Emergency Support Director who will be in place at the EOF-within one hour of notification to activate the EOF.
Item 3 Licensee's current meteorological program is consistent with guidance set forth in NUREG 0654. The lack of backup (redundant) power supplies for the primary meteorological instrumentation is sufficiently compensated for through backup data from the National Weather Service and a mobile meteorological tower from the Environmental Assessment Command Center.
Item 4 EPIP 1004.11 has been cancelled (03/18/82) and ~ incorporated into EPIP 1004.10 which has been revised (03/26/82) to include provision of a desciption of the predetermined offsite sample locations and the method to be used for identification of collected samples, so that this information is readily available to offsite teams.
Item 5 EPIP 1004.10 has been revised (03/26/82) to include provision of radiation protection guidance, as well as identification of a central sample collectimi point for onsite sa=ples.
Item 6 A PCR to EPIP 1004.9 is being processed which includes provision of a checklist to ensure that apprcpriate instrumentation. protective clothing, respiratory devices and personnel monitoring equipment are used for in-plant surveys. This procedure change will be finalized prior to restart of TMI-1.
Item 7 EPIP 1004.12 has been revised (03/15/82) to include provision of protective measures necessary to. protect personnel conducting radiological environmental monitor.ing.
Item 8 PCR's to EPIP's 1004.1, 1004.2, 1004.3 and 1004.4 have-been submitted and include provision of a procedure which ties together the separate emergency implementing procedures and orchestrates the emergency radiological protection actions to be implemented by the Radiological
. Assessment Coordinator. The Radiological Assessment. Coordinator and not the Radiological Controls Coordinator is responsible for over-all orchestration of the radiological protection actions at TMI-1. _These procedure changes will be finalized prior to restart of TMI-1.
= - - - -.
ATTACIDIEN'T 3 Comments on Inspection Report 81-20
- 1) Section 4.1.1.6, p. 8 - A more precise description of radiation monitoring provisions and ranges is contained in Licensee's Restart Report, Section 2.1.2.1.
- 2) Section 4.1.1.8 p. 10 - References to the WECST TMI Unit 2 should refer to the two. tanks of WECST in TMI-1.
A similarly incorrect reference in licensees EPIP will be corrected.
- 3) Section 5.4.2 p. 20, 1st paragraph, 3rd line - Change " Technical Support Center (TSC)" to read " Emergency Control Center (ECC)"
i 4)
Section 5.4.2 p. 21, 5th paragraph, 3rd line - Change " Environmental l
Assessment Command Center" to read " Emergency Control Center (ECC)"
- 5) Section 5.4.2.3 p. 24, lines 4 and 5,1st paragraph change " Health Physics Coordinator" to read " Radiological Controls Coordinator"
- 6) Section 5.4.3.1, p. 30 1st paragraph, 2nd lina - Change " Radiological Control Coordinator" to read " Radiological Assessment Coordinator"
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