ML19323C473
| ML19323C473 | |
| Person / Time | |
|---|---|
| Issue date: | 04/25/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8005150682 | |
| Download: ML19323C473 (5) | |
Text
8005150 a n, ipi g
UNITED STATES NUCLEAR REGULATORY COMMISSION n
t
- j WASHINGTON, D. C. 20555
\\****/
April 25,1980
)
i 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 TSC 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, 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 i
NRC Project Manager for your facility.
Sincerely, C-s'en 1
1 ctor Division of perating Reactors Office of Nuclear Reactor Regulation Enclosure Emergency Response Facilities b.
EMERGENCY RESPONSE FACILITIES MDL I
l CONTROL ROOM OPERATIONAL SUPPORT CENTER MDL Close
. consnunications to i
Proximity CR, OTSC, EOF N(
. assembly area for b
j support personnel Nbt l
Technical Data ONSITE TECHNICAL Emphasis - Reactor / Systems Status SUPPORT Essential Radiological Data l
Management Presence NRC CENTER Sr. Plant Management l
Sr. Plant Engineers
. NRC Emergency Response Team (5 persons) l Communications
. Main link to EOF and NRC Habitable (CR criteria) - If TSC not habitable, backup habitable TSC must be provided on or near site.
1 Plant Security Boundary NEARSITE rechnical Data EMERGENCY 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 use.
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 location designated l
4 EMERGENCY RESPONSE FACILITIES Onsite Technical Support Center An ensite technical support center (TSC) shall be maintained by each operating nuclear power 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 rocs 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 i
emphasis in designing the TSC information displays should be on reactor systems status. Those individuals who are knowledgeable of and responsible for engineering 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 are responsible for the overall management of the utility resources including recovery following an accident (e.g., corporate managers) should report to the EOF (see below). Upon activation, the TSC will provide the main communication 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, i
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 ayailable for display in the TSC and the j
EOF.
i Onsite Operational Support Center (Assembly Area)
The Operational Support Center shall be the place to which the operations support personnel report in an emergency si nation. Communications will be provided with the control room, OTSC and EOF.
Emergency Operations Facility (Near-Site) i The Emergency Operations Facility (EOF) will be operated by the licensee for con-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 raciological information as will be.
j required for transmittal to the NRC. The EOF will have sufficient space to accommodate representatives from Federal, State end 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 perfore -
s data analysis jointly with the licensee. Overall management of utility resorrces including recovery operations following an accident (e.g., by corporate manage ent) 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 BOF 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 (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.
Emergency Response Facilities Occupants Activation Buk-up if Center Location Required?
In Charge Number Skills Function Data Display Habitability Net Habitable O
Existing Shift Utility -
Operational Plant Control Wide Accident Control Room Supervisor Variable
& Technical Spectrum (SRP 6.4 In Plant No or with NUREG-0660)
Upgraded Senior Plant NRC (1)
Control Room Official Interin Should be Yes Senior Plant Utility -
Engineering &
Emergocy Direct Display No Requirement Control Room Technical near Official Variable Senior Plant Engineering or Call-up of NRC (5)
Management Support for Plant Parameters Support Control Center (TSC)
Room Control Room Necessary for (by 1/1/81)
Assessment Pemanent 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-seme 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 during Accidents radiological Redundancy (by 1/1/81) parameters Emergency Near Site Yes, for Senior Plant 10 NRC, Corporate 1
Overall Direct display Shielding Alternate EOF Operations (within Alert, Site or Corporate including rianagement, Management of of radiologi-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 rological tilation isolation habitability Emergency 20 utility Assessment 2.
Analysis parameters, capability reqairements Class including of Plant At least that for alternate radiologi effluents met; provioed to NRC cal acci-offsite mont-dent toring for assessment offstee action and decisions Corporate 3.
Briefing management, location for 5 State and offsite local.
officials and (periodic) l 9
PLANTS UNDER OL REVIEW l.
Parley 2 50-364
,4 2.
Byron 1/2 50-454, 455 3.
Braidwood 1/2 50-456/457 4.
LaSalle 1/2 50-373, 374 5.
Midland 1/2 50-329,330 6.
McGuire 1/2 50-369, 370 7.
So. Texas 1/2 50-498, 499 8.
Shoreham 50-322 9.
Waterford 50-382 10.
Grand Gulf 1/2 50-416/417 11.
Diablo Canyon 1/2 50-275, 323 12.
Susquehana 1/2 50-387, 388 13.
Salem 2 50-311 14.
Summer 1 50-395 15.
San Onofre 2/3 50-361, 362 16.
Bellefonte 1/2 50-438, 439 17.
Watts'Bar 1/2 50-390, 391 10.
Sequoyah 1/2 50-327, 328 19.
Comanche Peak 1/2 50-445, 446 20.
North Anna 2 50-331 21.
WPPSS-2 50-397 22.
Fermi 2 50-341 23.
Zimmer 1 50-358 l
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