ML17272A948

Advises of Error in NUREG/CP-0011, Proceedings of Workshops on Proposed Rulemaking on Emergency Planning for Nuclear Power Plants, Re Comments Made by State of Wa.Attendance at Workshop Was as NRC Applicant,Not State Representative

ML17272A948
Person / Time
Site:	Columbia, Washington Public Power Supply System, Satsop
Issue date:	04/30/1980
From:	Renberger D WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Grimes B Office of Nuclear Reactor Regulation
References
RTR-NUREG-CP-0011, RTR-NUREG-CP-11 ELE-GCS-80-122, NUDOCS 8005070544
Download: ML17272A948 (9)

Text

REGULATOR NFORMATION DISTRIBUTION . TEM (AIDS) EU ~R/((

DOC ~ DATE: 80/04/30 NOTARIZED: NO DOCKET FACIL:50 397 WPPSS Nuclear Projectr Unit 2r Washington Public Powe 05000397 5'CCESSION'BR:8005070544 50-46'0 WPPSS Nuclear ProJectr Unit it Washington Public Powe 05000460 STN 50 508 WPPSS Nuclear ProJectr Unit 3P Washington Public- 05000508 AUTH ~ NAME AUTHOR AFF IlI A/ION Washington Public Power Supply System 5'0$

RENBERGERPD ~ LE RECIP ~ NAME RECIPIENT AFFILIATION GRIMESEB ~ K 'mergency Preparedness Program Office

SUBJECT:

Advises of errar in NUREG~CP 0011r "Proceedings of Workshops an Proposed Rulemaking an Emergency Planning for Nuclear Pawer Plantar" re camments made by State of WA ~ Attendance at workshop was as NRC applicantrnot state representative, DISTRIBUTION CODE: XGO IS COPIES RECEIVED iLTR Generic Natl w/No Specific DistrTib, l ENCL Q. SIZE:0

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April 30, 1980 ELE-GCS-80-122 Mr. Brian K. Grimes Assistant Director for Projects and Technology U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

PROCEEDINGS OF WORKSHOPS ON PROPOSED RULEMAKING ON EMERGENCY PLANNING FOR NUCLEAR POWER PLANTS--

NUREG/CP-0011

Dear Mr. Grimes:

The purpose of this letter is to call to your'attention an error in the subject document relative to comments made by the state of Washington'.

On page 45 of NUREG/CP-0011, it is noted that comments on behalf of the state of Washington were made by Gerald Sorensen of the Washington Public Power Supply System.'he Washington Public Power Supply System is 'a joint operating agency of the state of Washington and an NRC applicant. Our attendance at the San Francicso workshop was in the capacity of an NRC applicant and not as a state representative. The state of Washington was very capably represented by Mr. George Hansen of the State Energy Facili-ties Site Evaluation Council and others as noted in the list of attendees on page 88.

The comments attributed to Mr. Sorensen of our staff were, in fact, comments made by Mr. George Hansen representing the state of Washington.

Your correction of this item is appreciated.

Very truly yours, RENB

s Assistant Director, Technology DLR:GCS:crw cc: Mr. George Hansen

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+)t*++ April 25, 1980 ALL POMER 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 NRC Project Manager for your facility.

Sincerely, rre . sen , ct ng s ector Division of perating Reactors Office of Nuclear Reactor Regulation

Enclosure:

Emergency Response Facilities

EMERGENCY RESPONSE FACILITIES CONTROL ROOM OPERATIONAL SUPPORT CENTER Close ~ communications to Proximity CR, OTSC, EOF htyg o assembly area for support personnel Technical Data ONSITE TECHNICAL . Emphasis - Reactor/Systems Status SUPPORT Essential Radiological Data Management Presence NRC CENTER ~ Sr. Plant Management,

~ Sr. Plant Engineers

~

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 EMERGENCY OPERATIONS

~ Emphasis on Radiological Info..

(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

EHERGENCY RESPONSE FACILITIES Onsite Technical Su ort Center An onsite'echnical 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'SC (minimum size 25 persona 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, 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 EOF.

Onsite 0 erational Su ort Center (Assembl 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.

Emer enc 0 erations Facilit (Near-Site)

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 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 ma)or 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 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 (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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