NRC Generic Letter 80-34, Clarification of NRC Requirements For Emergency Response Facilities at Each Site

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GL80034

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555

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 TSC have been modified to allow an onsite TSC in close proximity to the control room that would not meet the habitability requirements, 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 requirements 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 NRC Project Manager for your facility.

Sincerely,

Darrell G. Eisenhut, Acting Director Division of Reactors Office of Nuclear Reactor Regulation

Enclosure:

Emergency Response Facilities

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EMERGENCY RESPONSE FACILITIES

Onsite Technical Support Center

An onsite 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 room 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 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 mangers) 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 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 the control room, OTSC and EOF.

Emergency Operations Facility (Near-Site)

The Emergency Operations Facility (EOF) will be operated by the licensee for continued 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 radiological 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 response agencies may perform 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 Operation Facility (periodic use). Site meteorology should be used to the extend 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 (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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PLANTS UNDER OL REVIEW

1. Farley 2 50-364
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 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
18. Sequoyah 1/2 50-327, 328
19. Comanche Peak 1/2 50-445, 446
20. North Anna 2 50-339
21. WPPSS-2 50-397
22. Fermi 2 50-341
23. Zimmer 1 50-358
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