ML19210A464
| ML19210A464 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/01/1970 |
| From: | John Miller METROPOLITAN EDISON CO. |
| To: | Morris P US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 7910300498 | |
| Download: ML19210A464 (7) | |
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PRoma DATE OF DOCUMENT:
DATE RECENED N O.
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consistingofrevisedpagesv/ attached AH' MR Rosen C q'r h P W A)liance (2)
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SUPPL E 1 to FSAR ennaisting of a nnt D. Thnenson three (3) part report.
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CERTIFICAT2 W SERVICE, dtd 6-30-70 Dube/ Wilson NSIC(
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Dear Dr. Morris:
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Subject:
Three Mile Island Nuclear Station, Unit 1 M.l?
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Docket No. 50-289 MW' Amendment No. 14 Regulatory File Cy.
Attached are three signec original and 19 conformed copies of Amendment 14 to the Operating License Application for the Three Mile Island Nuclear Station, Unit 1.
In addition, enclosed are one signed and 20 conformed copies of the Certificate of Service of Amendment 14 on the chief executives of the township and county in which the facility is to be located.
This amendment references Babcock and Wilcox topical reports relating to fuel rod failure mechanisms and Xenon Oscillation, Gilbert Associates Topical Report No.1729 " Dynamic Analysis of Vital Piping Systems Subjected to Seismic Motion" and indicates the sections of the TSAR which respond to the ACRS recommendations concerning the scram bus and the separation of safety and control functions. We believe that separation to the extent practicable has been provided.
This amendment also includes Supplement 1 to the FSAR. This supplement is a three part report addressing iodine removal capabilities, evaluation of purging to control post accident hydrogen concentration and evaluation of accident doses using site measured meteorology.
We have recognized the need for a gross fuel failure detection system and have provided the following criteria for an on-the-line system to be installed at Three M.tle Island:
- 1) Autocatic indication of alarm must be given by the system; 2) The system must respond as promptly as feasible to give reliable indication; 3) 'Ihe system must be capable of detecting the coolant activity resulting from the postulated fuel failure over background activity; 4) The system must be able to detect 1.487 117 gmo oy3 Mc J
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Dr. Peter A. Morris July 1, 1970 the release of 1 per cent of the fuel in an assembly or the release of all plenum activity in one fuel assembly.
As indicated during the public hearing on April 10, 1968, pages 259-264 of the Transcr'.pt of Hearing, we performed a scoping study to de.termine how best to achieve our criteria. As a result of our scoping study, we rejected beta and delayed neutrons as a strong source in the detection of failed fuel. Gamma emitters appeared to offer the most feasible means to detect failed fuel during on-line operation. We are presently investigating two on-line gamma detection systems for installation at Three Mile Island.
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Very truly yours
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J. G. Miller M
Vi e President and Chief Engineer Enclosures 1487 118
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_t THREE MILE ISLAND NUCLEAR STATION UNIT 1 APPLICATION FOR CLASS 104 b UTILIZATION FACILITY OPERATING LICENSE Regulatory File Cy.
Docket No. 50-269 Amendment No. 14 Buelved w/ur cato I-/~ f0 Applicant submits by this Amendment, in support of its request for an initial operating license at a reactor power level of 2535 Wt, Supplement No. 1 to the FSAR and change pages to section 1 of the FSAR to include references to B&W topical reports relating to fuel rod failure mechanisms and xenon oscillations.
Supplement 1 to the FSAR is a three part report entitled as follows:
I Iodine Removal Capabilities of the Three Mile Island Unit 1 Reactor Building Spray System.
II Draluation of Purging as a Means of Controlling Post Accident Hydrogen Concentration in the Three Mile Island Unit 1 Reactor Building.
III An Evaluation of Accident Dose Probabilities Using Three Mlle Island Site Measured Meteorology Data.
ACRS recommendations on the scram bus and separation of control and protection function are addressed in Section 7 of the FSAR. The design of the rod drive control system is described in 7.2.2 and tri?
circuitry is shown in figures 7-6 and 7-7 Separation of protection and regulation function is addressed in Sections 7.1 and 7.2 1487 119 2x:
A change page in section 5 is included to reference Gilbert Associates Touical Report No.1729 " Dynamic Analysis of Vital Piping Systems Subjected tr Seismic Ittion".
METROPOLITAN EDISON CQMPANY By J
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Secretary Sworn and subscribed to before me this &2[ day of 1.. w 1970.
0'A._ h._..Y in t Notary Public
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JERSEY CENTRAL POWER & LIGHT CO.
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Secretary Sworn and subscribed to before me this 30th day of June
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.,t, Notary Public CLARA L. LOMBARDI NOTARY FUBL'O OF NE A !ERSEY My Comessioq Esp.tes ed,10,197,,
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DOCKET NO. 50-289
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Regulatory CERTIFICATE OF SERVICE
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Rusivsd w/Ltr Dated I-/- 76 This is to certify that a copy of Amendment No. 14 to the Application for Construction Permit and operating license for Three Mile Island Nuclear Station, Unit 1 dated June 30, 1970, and filed with the U. S. Atomic Energy Commission on July 1,1970, has this 1st day of July,1970, been served on the chief executives of Londonderry Township, Dauphin County, Pennsylvania, and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:
Mr. Richard Menear Chairman, Board of Supervisors of Londonderry Township R. D. #1 Middletown, Pennsylvania and:
Mr. C. Robert Budd Chairman, Board of County Commissioners of Dauphin County Dauphin County Court House P. O. Box 1295 Harrisburg, Pennsylvania METROPOLITAN EDISON COLEANY i i
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Vice President 1487 121 2035
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7 D7cketNo.50-289 July 1, 1970 Aa 7-.;L /- 7 0 i
AMENDMENT NO. 14 THE METROPOLITAN EDISON COMPANY -- JERSEY CENTRAL POWER & LIGHT COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Amendment No. Ih to the Metropolitan Edison Company -- Jersey Central Power &
Light Company application for Three Mile Island Nuclear Station Unit 1, Docket 50-289 includes both insert pages to the Final Safety Analysis Report as listed below and Supplement No.1.
Supplement No.1 describes the acceptability of the Reactor Building spray system for iodine r6moval, an evaluation of contain-ment purging for hydrogen control following an accident, and' a probabilistic evaluation of accident doses using site measured meteorological data. Supplement No.1 should be placed directly behind Section 15 in Volume 4.
The following sheets of the Final Safety Analysis Report are to be deleted and when appropriate revised sheets dated July 1,1970 should be inserted.
Remove the folleving sheets:
Insert the following sheets:
Pages: Table of Contents - xi Pares: Table of Contents - xi (one each, in Volume 1,2,3, and 4).
@ each, in Volu=e 1,2,3, and h).
Pages:
1-45, 1-h6, 1-47, 1-h8 Pages:
1-h5, 1-h6, 1-47, 1-48 Pages:
5-75, 5-76 Pages:
5-75, 5-76 Pages:
6-13, 6-14, 6-29, 6-30 Pages:
6-13, 6-14, 6-29, 6-30 Figures:
6-3, 6-5 Figures:
6-3, 6-5 Pages:
1h-51, 14-52, 14-53, 14-54, Pages:
1h-51, 14-52, 14-53, 14-54, 14-57, 1h-58, 1h-75, lh-76, 1h-85, 14-57, 1h-58, 1h-75, 14-76, 14-85,