ML18017A153

Notifies That Date & Location of Meeting to Resolve Open Items in FSAR Sections 3.63.10 Will Be Provided by 800515. Agenda Will Be Provided by 800615

ML18017A153
Person / Time
Site:	Susquehanna
Issue date:	04/29/1980
From:	CURTIS N W PENNSYLVANIA POWER & LIGHT CO.
To:	PARR O D Office of Nuclear Reactor Regulation
References
PLA-476, NUDOCS 8005070402
Download: ML18017A153 (7)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR 8005070402 DOC~DATE!80/04/29 NOTARIZED!

NO FACIL:50 387 Susquehanna Steam Electric Station~Unit ir Pennsylva S0 388 Susquehanna Steam Electric Stations Unit 2i Pennsylva AUTH BYNAME AUTHOR AFFILIATION CURT 1St N~Wo Pennsylvania Power 8 Light Co.REC IP~NAME RECIPIENT AFF ILlATION PARRgO F 0'uxiliary Systems Branch

SUBJECT:

Notifies that date 8 location of meetingito resolve open items in FSAR Sections F 6 ,10rwill be provided by 800515'genda will be provided by 800615.DISTRIBUTION COOK: 80018 COPIES RECEIVED:LTR ENCL~SIZE: TITLEi PSAR/FSAR AMDTS and Related Correspondence NOTES'~+'Q

+%g.DOCKET¹tg 388 REC IP IENT IO COOK/NAME ACTION: 05 PM W/~Kg BC INTERNAL<01 RGG K~l.)0 I 8 K 09 GEOSCIKN BR 11 MECH ENG BR 13 MATL,.ENG BR 16 ANALYSIS BR 18 AUX SYS BR 20 I 8 C SYS BR 22 AD SITE TECH 27 EFFL TRT SYS 29 KIRKAOOO AD PLANT SYS AD SITE ANLYSIS HYDRO METEOR BR OELO EXTERNAL: 03 LPDR 30 ACRS COPIES I.TTR EN 1 1 1 3 1 1 2 2 1 1 1 1 11 1 1 2 1 1 10 1 RECIPIENT IO QQDK/AME AD L4d LA LOUR 9 02 NRC PDR 08 OPERA I.IC BR 10 QAB 12 STRUC ENG BR 15 RKAC SYS BR 17 CORE PERF BR 19 CONTAIN SYS 21 POWER SYS BR 26 ACCDNT ANLYS 28 RAD ASMT BR AD FOR ENG AD RKAC SAFETY DIRECTOR NRR MPA 04 NSIC COPIES LTTR ENCl.1 1 1 1'1 1 1 1.1 1 1 1 0 1 1 1 L&NooWE EP8 e~ae O'a~ep a~a~~~~'~~s>>>>O TOTAL NUMBER OF COPIES REQUIRED'TTR 52 ENCL PAL TWO NORTH NINTH STREET, ALLENTOWN, PA.18101 80 000VOIt~PHONEME t215)821-5151 April 29, 1980 Mr.Olan D.Parr, Chief Light Water Reactors Branch No.3 Division of Project Management U.S.Nuclear Regulatory Commission Washington, D.C.20555 SUSQUEHANNA STEAM ELECTRIC STATlON MEETING TO RESOLVE OPEN ITEMS IN FSAR SECTIONS 3.6 THROUGH 3.10 INCLUSIVE ER 100450 FILE 841-2 PLA-476

Dear Mr.Parr:

With regard to your letter dated April 21, 1980 which proposes a meeting to resolve open items in FSAR Sections 3.6 through 3.10, Pennsylvania Power&Light Company fully supports this experimental approach to close out open items.It is our understanding that the intent of this meeting is to close out open items and terminate review of the FSAR sections under discussion.

We will provide proposed meeting dates and place by May 15, 1980 and an agenda by June 15, 1980.It is our hope that.this approach will'accelerate the review process to minimize potential delays in issuance of an operating license.Very truly yours, N.W.Curtis Vice President-Engineering

&Construction PENNSYLVANIA POWER 8 L I GH T COMPANY W~o

~p AEC>~o Op Cl C 0 cA 0 w+~O++*++0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.20555 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,

Enclosure:

Emergency Response Facilities rre 1.sen , ctsng s ector Division of perating Reactors Office of Nuclear Reactor Regulation

EMERGENCY RESPONSE FACILITIES CONTROL ROOM OPERATIONAL SUPPORT CENTER Close Proximity~communications to CR, OTSC, EOF o assembly area for support personnel NRC ONSITE TECHNICAL SUPPORT*CENTER Technical Data.Emphasis-Reactor/Systems Status Essential Radiological Data Management Presence~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 EMERGENCY OPERATIONS FACILITY Technical Data~Emphasis on Radiological Info.;(meteorology)

~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 EMERGENCY RESPONSE FACILITIES Onsite Technical Su ort'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.Hhile 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 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, 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.

~~I~I KlRHPl%R)~Mid%~

I~~~I I~~~~~~~~~I~~I~I~If~I I~'~~~~I I~I~I~I~~~I~~I~I~I~I~~'I~I I'I I I~I~~I~~I I~I~I~I~I~I~I I~I~'~I'I~~I~~~I~I~I I~~~'I I~~~,~I I~~~~I'~I~I~I~I I~~~'~~I~I~~~~~~~~I I~~