ML19210B135

Forwards Portion of Fsar,Amend 50,incorporating Info in Reg Guide 1.70.3,in Response to 750108 Ltr

ML19210B135
Person / Time
Site:	Three Mile Island
Issue date:	02/24/1975
From:	Arnold R METROPOLITAN EDISON CO.
To:	Lear G Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.070.03, RTR-REGGD-1.070.03 GQL-0792, GQL-792, NUDOCS 7911040070
Download: ML19210B135 (6)

Text

,..NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL (TEMPORARY FORM)

CONTROL NO: 22N FILE:e SS FROM: 1:etropclitan Edison Co DATE OF DOC DATE REC'D LTR TWX RPT i OTHERlacacing, ?a 19603 XXX' C ?314 9 2 /. 7 c 9.?7 7;TO: ORIG CC OTHER SENT AEC PDR XX XX Me Lear one si;ned SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

XXXXXXXX 1 50-289 DESCRIPTION:

ENCLOSURES:

L r re their 1-30-75 submittal....& cur Items requested in support of an And te 1-8-75 ltr. . . . . .trans the following:

their Tech Specs with regard to Air Trcat-ncnt Systems & the Control loom Filterin; Systen.......

PLANT NAME: Three Mile Island el FOR ACTION /INFORMATION 2-28-75 ehf BUTLER (L)

SCHWENCER (L) ZIEMANN (L)

REGAN (E)W/ Copies W/ Copies W/ Copies W/ Copies CLARK (L)STO LZ (L)

DICKER (E),J.E AR (L)

'W/ Copies W/ Copies W/ Copies W/hCopies PARR (L)V ASSALLO (L)

KNIGHTON (E)

SPELS W/ Copies W/ Copies W/ Copies W/ Copies KNIEL (L)PURPLE (L)

YOUNGBLOOD (E)

W/ Copies W/ Copies W/ Copies W/ Copies M INTERNAL DISTRIBUTION REG M TECH REVIEW _

DENTON LIC ASST A/T IND panu eDR SCHROEDER GRIMES R. DIGGS (L)

BRAITMAN AGC. ROOM P 506A MACCARY GAMMILL H. GEARIN (L)

SALTZMAN/GOSSICK/STAF F KNIGHT K ASTN E R E. GOULBOURNE (L)

MELTZ CASE PAWLICKl BALLARD P. KREUTZER (E)

GIAMBUSSO SHAO SPANG LE R J. LEE (L)

PLANS BOYD STELLO M. MAIGRET (L)

MCDONALD MOORE (L)HOUSTON ENVIRO S. REED (E)

CHAPMAN DEYOU"!G (L)

NOVAK MULLER M. SERVICE (L)

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SKOVHDLT (L)

ROSS DICKER S. SHEPPARD (L)

E. COUPE fGOLLER (L) (Ltr)

IPPOLITO KNIGHTON M. SLATER (E)

PETERSON P. CO LLINS TEDESCO YOUNGBLOOD H. SMITH (L)

HARTFIELD (2)

DENISE LONG REGAN S. TEETS (L)

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'G. WILLI AMS (E)

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BENAROYA Alo **K V. WILSON (L)

WIGGINTON T.R. WILSON VOLLMER H AR LESS R. INGRAM (L)

STEELE EXTERN AL DISTRIBUTION A - LOCAL PDR.flAyra be<s , b f1 - TIC (ABERNATHY) (1)(2)(10) - N ATION AL LABS 1 - PDR SAN /LA/NY

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TE LE P"O' E OF - M. ' t l..,-..FEB 2 4 1975

..,%. .~GQL G792.-/Mr. George Lear, Chief

, ,*Operating Reactors Branch #3 ,g'N/Division of Reacter Licensing

_.,.y nuclear Regulatory Co==issien ,g-Washington, D.C.

20555

Dear Mr. Lear:

Three Mile Island Nuclear Statien Unit 1 (TMI-1)

Operating License No. DPR-50 Docket Ho. 50-289 In respense to your letter of January 8,1975, regarding the licensing of special nuclear, by product, and source materials, and as a follow-up to our Mr. Creit.'s letter of January 30, 1975, enclosed please find a portion of Amendment 50 to the TMI-1 Final Safety Analysis Report (FSAR). Amendment 50 was filed under separate cover with the Nuclear Regulatory Commission en February 21, 1975, and the enclosed pertion serves to incorporate inte the TMI-1 FSAR information described in Regulatory Guide 1.70.3 (dated February, 197h ) .

With regard to the other two items of information that you requested in your January 8, 1975, letter, please be informed that draft changes to existing license conditions and sections of the TMI-1 Technical Specificatiens are still under review, and that we presently anticipate being able to conplete w reviews and to ' submit the requested preposed amendments by March 10, 1975..Sincerely, ,/0[.[(]. m. 4.. w

.h. C.. 1d-RCA: DUG:cas Vice President File: 20.1.1/7.7.h.3.3 cc: v/ enclosures GPU Service Corporation G. F. Trowbridge, Esquire Richard W. Heward, Project Mgr.

Shaw, Pittman, Potts, Trowbridge & Madden Thomas M. Crimmins, Jr., Safety Barr Building and Licensing Manager 910 17th St., U.W.

260 Cherry Hill Read Washington, D.C.

20006 Parsippany, NJ 0705k Goverrcent Publications Section State Library of Pennsylvania c<M 3cx 1601 (Education Elde.)

Earrisburg, PA 17126 g f provided in an appropriately shielded counting room for detecting and =easur-

.ing all types of, radiation as well as equip =ent (such as a multi-channel analyzer) for the identification of specific radionuclides.

11.5.6 HEALTH PHYSICS INSTRLSINTATION Portable radiation survey instru ents are provide'd for use by the Health Physics section as well as for operating and maintenance personnel. A variety of instruments has been seletted to cover the entire spectrum of lradiation measurement problems anticipated at the Three Mile Island Nuclear 5 cation. Sufficient quantities will be obtained to allow for use, calibration, maintenance, and repair. This includes instruments for detecting and measur-ing alpha, beta, gamma, and neutron radiation. In addition to the portable radiation monitoring instru=ents , fixed monitoring instru=ents , i .e . , count rate meters, are located at exits fro: radiation control areas. These in-strtments are intended to prevent any contamination on personnel, material,-or equipmnnt from being spread into unrestricted areas. Appropriate mon-itoring instruments are available at various locations within the radiation control areas for contamination control purposes. The station has permanently installed area and process radiation monitoring systems. These systems monitor airbo.rne particulate and gaseous radioactivity including iodine , as well as external radiation levels. The systems present audible alarm and radiation level indication in the areas of concern in addition to reading out in the control room.

11.5.7 MEDICAL PROGRAM A comprehensive medical examination program will be conducted to establish and maintain records of the physical status of each employee at the Three Mile Island nuclear facility. Subsequent medical examinations will be held as necessary. The Radiation Protection Supervisor is responsible for the program and will assist the physicians in maintaining medical control of p ersonnel .

11.6 RADIOACTIVE MATERIALS SAFETY 11.6.1 MATERIALS SAFETY PROGRAM The following program vill be imple ented to assure the safe storage, handling, and use of sealed and unsealed special nuclear, source, and byproduct materials.

11.6.1.1 Receipt of Source Material The method of receipt, date, and description of the contents will be recorded.

Each radioactive source will be surveyed for removable contamination at time of rece'.pt.

Records of the survey will be maintained. Each source and/or source containef'will be smeared using cotton swabs c; small filter papers.

These smears will be counted in the counting laboratory for alpha and/or beta-ga=ma activity as appropriate . If leakage is confirmed from any source, the source will be repaired vr replaced.

..Each source will be numbered and recorded in the Health Physics Source Invent-g ory Log.1586 275 11-23 Am. 50 (2-21-75) a., 11.6.1.2 Storage of Sour:e >bterial

(]h All sources, when not being used, will be stored under lock and ey.The key will be under the ad=inistrative control of the Radiation Protection Supervisor.

11.6.1.3 Source Preparation and Handling Only personnel trained in Eealth Physics practices are permitted to handle radioactive sources. These personnel will wear dosimeters /TLD's while handling radioactive sources. When radioactive caterial containers are opened, a radiation and contamination survey will be taken.

Protective clothing, consisting of rubber gloves, lab coats, and shoe covers will be worn as required during the preparation of the radioactive calibration sources.All liquid or gaseous radioactive =aterials will be opended under a ventilation hood. The area where the opened radioactive caterial is handled'will be appropriately marked and posted. Health Physics practices appropriate to the material being handled will be followed.

Standards prepared at the station will be carefully made so as to limit the spread of radioactivity. For liquid sources a cover will be provided for the source container to prevent spillage during transport from the source storage area to the source preparation area and vice versa.

A smear sample will be taken of each prepared source for detection of removable

, contamination. The detection limit of instrumentation used should be able to detect the presence of .005 microcuries of removable contamination.

11.6.1.4 Disposal of Radioactive Waste Resulting from Source Preparation Liquid waste which is expected to result from source preparation will be stored in a radioactive vaste storage area prior to disposal.

Solid waste consisting of absorbant paper and kievipes, etc. will be handled in accordance with solid waste handling procedures.

11.6.1.5 Radiological Surveys A radiation survey and a survey for contamination will be conducted in the labora-tory source preparation area af ter the sources are prepared. In addition, a radiation and contamination survey will be conducted once per week in laboratory areas. Leak testing for radioactive surface contamination will be conducted in accordance with Technical Specifications 4.13 and 3.10.1.

Sealed sources are exempt from such leak tests when the source centains 100 pCi or less of alpha-emitting material. The survey detection limit of contamination must be equal to or less than .005 microcuries.

A radiation survey and contamination survey will be conducted once per week in and around the source storage area.

0 11-24 Am. 50 (2-21-75) i5oo 27o p f. -

..TY h" D'J,1 , D**D 11.6 .1 .6 Source Inventory p , A source inventory will be conducted in accordance with Technical Specif-

-ication 3.10.2.

Records of the inventory will be kept in the Health Physics Laboratory .

11.6.2 FACILITIES AND EQUI?ME';T Three Mile Island Nuclear Station includes a Health Physics Laboratory with facilities and equipment for detecting, analyzing, and measuring all types of radiation and for evaluating radiological proble=s which may occur. Count-ing equip =ent (such as G-M, scintillation, and proportional counters) are provided in an appropriately shielded counting room for detecting and measuring all types of radiation. An exa=ple of equipment which will be available to valuate radiolo;; ital prebic:s are contained in Tcble 11-13.

The unit radiochemistry lab and' adjacent area is equipped with the following equipment:

a.Hoods with HEPA and charcoal filters b.Laboratory sinks which drain to the liquid radioactive waste disposal system c.A continous air particulate monitor d.A hand and foot monitor.

11.6.3 PERSONNEL AND PROCEDURES h The Supervisor, Chemistry and Health Physics, Radiation Protection Supervisor, Chemical Supervisor are responsible for the handling and monitoring of the scaled and unsealed special nuclear, source, and byproduct materials. Resumes for these key personnel are available at the TMI-l site.

Station Health Physics procedures are written to provide instructions and guidance on radiation protection, sacpling, laboratory analyses used to determine concentration and species of radioactive liquids and gases, and calibration of laboratory equipment.

Surveillance procedures are written to ensure compliance with Technical Specification require =ents.

11.6.4 REQUIRED SOURCE MATERIAL The following list indicates the isotope, quantity, form and use for required radioactive material.

Material Form and Use 1.Americium A:ericius-Beryllium - Neutron Source 241 - One (1) Scaled Source - AM02 with Be target -

Monsanto Research Corp. - No. MCR-N-SS-W -AmBe-One (1) 5 curie - Model 2720 2.Plutonium 239 Plutonium 239 - 2 microcuries - Four (4) Sealed Sources - Eberline Instru=ent Corp. , Santa Fe, New Mexico - Model No. S94-1 11-25 Am. 50 (2-21-75) 1586 277--.-

I t i, ,.i , 3.Cesium 137 Scaled Source (OR:;L) one (1) 50 curies.L Q@ I F 4.Cesium 137 Sealed Source (Atocches Corp. Model CS-2-10) one (1) 100 cil11 curies l: t.5.Cesiua 137 Sealed Source (Acersham/Searle Model X-7) one (1) 100 nil 11 curies

"'6.Cobalt 60 Sealed Source (Amersham /Searle Model CKC) or (1) 500 til11 curies 7.Americius Beryllium Sealed Sources to be used for reactor start up two (2) 1100 curies total (2 sources) i-8.Uranium 235 Sealed source as reactor fuel assemblies 10,300 kilograms'.

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. . .!A3LE 11-13

_-PADIATION DITECTIC:; 12;STRL'MENTS Window Radiation Sensitivity Thickgess Type of Instrunents Detected Range og/cm Use Eberline E-520 Beta Ga==a 0-2000 R/hr.

30 Survey 6 E'oarlir.e PAC-4S Alpha 0-2:.10 cpa.

1.5 SurveylEberline Teletector Bcta Gama 0-1000 R/hr.

30 Survey#6112lEberline PNC-4 Neutrons 0-500K cps.

Neutron Survey fast / slow Detector BF tube-3 Eberline PNR-4 Neutrons 0-5000 mrem /hr.

Neutron Survey De tector BF3 tube Victoreen Beta Ga=a 0-1000 R/hr.

Survey Radector III Nuclear Measurements Alpha Beta 4.5x10-9ue/cc Laboratory Corp. Internal Equipment Proporational Counter Model PCC-llT Hewlett-Packard Beta Ga=a 1.2x10 'ue/cc 1.5 Laboratory

~#5202L Scaler-Tiner Equipment.1506 279@Am. 50 (2-21-W 11-46 , a M'