ML19320C882
| ML19320C882 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Indian Point, Surry, Haddam Neck, Duane Arnold, Fort Saint Vrain, Trojan File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 07/07/1980 |
| From: | Crutchfield D, Crutchfield D Office of Nuclear Reactor Regulation |
| To: | Hickey A AMERICAN INSTITUTE FOR RESEARCH IN THE BEHAVIORAL |
| Shared Package | |
| ML19320C883 | List: |
| References | |
| NUDOCS 8007180196 | |
| Download: ML19320C882 (2) | |
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- Mr. Albert E. Hickey American Institutes for Research in the Behavioral Sciences 41 North Road 1
Bedford, Massachusetts 01730
Dear Mr. Hickey:
I am pleased to answer your letter d:**d May 29, 1980, addressed to Mr. Darrell G. Eisenhut, Director, Division of Licensing, in which you asked for certain information concarning emergency responses facilities at reactor sites.
Responding to your request, we are enclosing a copy of the April 25, 1980 letter from Mr. Eisenhut to all power reactor licensees. That letter provided clarification of our requirements for the three emergency response facilities, including the Technical Support Center (TSC), as previously defined in Mr. Eisenhut's letter dated September 13, 1979, to all " Operating Nuclear Power Plants."
You have also asked if power plants cther than Yankee-Rowe have received approval to use closed-circuit television as a connanication link between the Control Room and the TSC.
It should be noted that closed-circuit television is one method that meets our short-term requirement for enduring access to technical data by direct display of plant paraneters, necessary for assessment in the TBC of plant status during normal operation and in the event of an accident. The following is a representative listing of power plants that use closed-circuit television for that purpose:
Power Plant Licensee Indian Point 2 Consolidated Edison Trojan Portland General Electric i
Millstone 1 & 2 Northeast Utilities Haddam Neck Connecticut Yankee Atomic Power Co.
Fort St. Vrain Public Service Co. of Colorado Surry 1 & 2 Vepco Duane Arnold Iowa Electric Light & Power Co.
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t 2-l We trust that this infonnation is respoeshc to your request.
i Sincerely, WI WO Dennis M. Crutchsfeld, Chief i
Operating Reactors Branch #5 Division of Licensing
Enclosure:
Copy of April 25;'1980. letter DISTRIBUTION:
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h April 25, 1980 ALL POWER REACTOR LICENSEES Gentlemen:
SUBJECT:
CLARIFICATION OF NRC REQUIREMENTS FOR EMERGENCY RESPONSE FACILITIES AT EACH SITE Over the past several months the NRC staff has been conducting reviews of each licensee's proposal to upgrade their plant to cope with emergencies.
The lessons learned and emergency planning review teams have identified areas where clarification of the NRC position is necessary.
Our previous requirements for the ISC have been modified to allow an onsite TSC in close proximity to the control room that would not meet the habitability require-ments, provided that a backup, habitable TSC is located near the site.
It is the purpose of this letter to set forth clarification of NRR's require-ments for the three emergency response facilities defined in my September 13, 1
1979 letter to "All Operating Nuclear Power Plants". Additional specific criteria for these facilities is under development. The schedule for implementing these requirements has not changed.
If you have any questions regarding this clarification, please contact the NRC Project Manager for your facility.
Sincerely,
(,
Mr sen 1
1 ctor Division of perating Reactors Office of Nuclear Reactor Regulation
Enclosure:
Emergency Response Facilities V
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EMERGENCY RESPONSE FACILITIES 1
i Onsite Technical Support Center An onsite technical support center (TSC) shall be maintained by each operating nuclear pcwer plant. The TSC shall be separate from, but in very close proximity to, the control room and be within the plant security boundary. While care must be taken in selecting technical input available in the TSC, it appears likely that access to additional control roem data would be required during an emergency.
The location of the TSC shall also be such as to facilitate occasional face-to-face contact between key control room and TSC supervisors (management presence). The j
emphasis in designing the TSC information displays should be on reactor systems status.
Those individuals who are knowledgeable of and responsible for engineering
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and management support of reactor operations in the event of an accident will report to the TSC (minimum size 25 persons including 5 NRC).
Those persons who 1
are responsible for the overall management of the utility resources including 4
recovery following an accident (e.g., corporate managers) should report to the EOF (see below).
Upon activation, the TSC will provide the main communication i
link between the plant and the operator's near-site Emergency Operations Facility, and the main communication link to the NRC for-plant operations matters.
The TSC must be habitable to the same degree as the control room for postulated accidents (SRP 6.4 as revised by NUREG-0660). Where the primary, in-plant, TSC is not made habitable because of site-specific considerations, a backup TSC which does meet the habitability requirements must be provided on or near the site.
Parameters transmitted by any nuclear data link installed to meet future NRC requirements should be available for display in the TSC and the EOF.
Onsite Operational Support Center (Assembly Area)
The Operational Support Center shall be the place to which the operations support personnel report in an emergency situation. Communications will be provided with i
j the control room, OTSC and EOF.
Emergency Operations Facility (Near-Site)
The Emergency Operations Facility (EOF) will be operated by the licensee for con-4 tinued evaluation and coordination of licensee activities related to an emergency having or potentially having environmental consequences.
The EOF must have the capability to display the same plant data and radiclogical information as will be required for transmittal to the NRC.
The EOF will have sufficient space to accommodate representatives from Federal, State and local governments if desired by those agencies, including facilities for the senior NRC representative (10) on-site. In addition, the major State and local re ponse agencies may perform s
data analysis jointly with the licensee. Overall management of utility resources including recovery operations following an accident (e.g., by corporate management) shall be managed from this facility.
Press facilities for about 20 people shall be available at the Emergency Operations Facility (periodic use).
Site meteorology should be used to the extent practical for determining the EOF location.
The EOF should be located within about one mile of the reactor. The EOF should be a substantial structure, providing significant shielding factors from direct radiation and the capability to isolate ventilation systems.
Filtration systems
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(at least HEPA filters) shall be provided in new structures. Arrangements shall be made~to activate an alternate EOF in the event that the nearsite EOF becomes uninhabitable.
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EMERGENCY RESPONSE FACILITIES I4f> L.
CONTROL ROOM OPERATIONAL SUPPORT CENTER NDL.
Close
. communications to Proximity CR, OTSC, EOF N(
. assembly area for b
support personnel NDL l
Technical Data ONSITE Emphasis - Reactor / Systems Status TECHNICAL Essential Radiological Data SUPPORT l
Management Presence NRC CENTER
. Sr. Plant Management Sr. Plant Engineers l
. NRC Emergency Response Team (5 persons)
Communications
. Main link to EOF and NRC Habitable (CR criteria) - If TSC not habitable, backup habitable TSC must be provided on or near site.
Plant Security Boundary NEARSITE Technical Data EKERGENCY
. Emphasis on Radiological Info.
OPERATIONS (meteorology)
FACILITY
. Same data as sent to NRC available Licensee Recovery Personnel
. Licensee senior management (corporate level)
. Recovery Manager Federal, State, Local Governments may uae.
NRC including Sr. NRC official Emphasis on off-site emergency plans Press Facility (periodic pool briefings)
Habitability - direct radiation and isolable ventilation systems; HEPA filters in new facilities Alternate lccation designated
q Emergency Response Facilities Activation Occupants l
Center Location Required?
In Charge Number Skills Function Data Display Habitability Not Habitable Back-up if Existing Shift Utility -
Operational Plant Control Wide Accident Cent ol Room Supervisor Variable
& Technical In Plant No or Spectrum (SRP 6.4 Upgraded Senior Plant NRC (1) with NUREG-0660)
Control Room Official Interim Should be Yes Senior Plant Utility -
Engineering &
Dnergency Direct Display No Requirement Control Room Technical near Official Variable Senior Plant Engineering or Call-up of Support Control Center (TSC)
Room NRC (5)
Management Support for Plant Parameters Control Room Necessary for (by 1/1/81)
Assessment Permanent TSC Must be in Yes, for Senior Plant 25 Engineering &
Accident Assess-Direct Display Either TSC or Habitable TSC very close Alert Site Official (5 NRC)
Senior Plant ment by Opera-of plant safety backup must be near site if proximity to Emergency Management tions Engineers; system para-same as Control primary TSC not Control Room or General Support to meters, call-up Room Except for habitable Emergency Control Room display of System Class (by 1/1/81) during Accidents radiological Redundancy parameters Emergency Near Site Yes, for Senior P' ant 10 NRC, Corporate 1
Overall Direct display Shielding Alternate EOF Opera tions (within Alert, Site or Corporate including Management, Management of of radfologi-against direct required away Facility (EOF) about 1 Emergency Official Regional Radiological Utility cal and meteo-radiation & ven-from site; no mile) or General Director.
Accident Resources cological tilation isolation habitability Emergency 20 utility Assessment 2.
Analysis parameters, capability requirements Class including of Plant At least that for alternate radiologi effluents met; provided to NRC cal acci-offsite mont-dent toring for assessment offsite action and decisions Corporate 3.
Briefing management.
location fo-5 State and offsite
- local, officials and press pools.
(periodic)
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