ML19319D557

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Forwards Amend 18 to CP & OL Applications,Consisting of Revised Pages to Fsar.Also Forwards Gilber Associates,Inc SP-5500, Specs for Subsurface Grouting & SP-5785, Proof Testing of Chemically Consolidated Foundation Elements
ML19319D557
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 04/28/1972
From: Rodgers J
FLORIDA POWER CORP.
To:
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML19319D558 List:
References
NUDOCS 8003170679
Download: ML19319D557 (3)


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AEO MISTFu"irfl0N. _FOR_

PARTJO_. ~'1GCKM MATERIAL CEMPORARY FORM:)

j CONTROL NO: 2514 FROMtFlorida Power Corp DATE OF DOC:.

DATE REC'D LTR MEMO RPT OTHER St. Petersburg 4-28-72 5-8-72 J. T. Rodgers, Fla.

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50-302 DE5CRIPTION:

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Ltr trans the follcuing:

AMDT 18 notarized 4-28-72 consisting of....

....(1) REPORT - Specifications for Subsurface Grouting, dtd 2-28-68. --

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(2) REPORT - GAI-SP-5785-Proof Testing of (3 Orig & 19 conf'd cys Amdt & 70 cys, 22 cys Chemically Consolidated. Foundation Elements, ca rpt rec'd) dtd 1-7-70. />

(3) Rev & Addl pages & Figs to FSAR and

    • Denotes dis tribution w/ Spec Rpts.

ans to questions re our 1-14-72 ltr.

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m FLORIDA POWER C O R P0 H ATIDX ST. PETERSDUHG FLORIDA Regulatory Flie Cy.

April 28, 1972 _.

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Dear Sir:

In re:

Florida Power Corporation Crystal River Nuclear Generating Plaat Docket No. 50-302 Enclosed are three (3) executed originals and nineteen (19) conformed copies of Amendment No. 18, to the Application for Licenses for Crystal River Unit 3 Nuclear Generating Plant. Also included for the staff's review are twenty-two (22) copies of the following documents.

Gilbert Associates (GAI), Inc. SP-5500, Specifications for Subsurface Grouting, Crystal River Unit No. 3, Florida Power Corporation, February 28, 1968.

GAI, SP-5785, Proof Testing of Chemically Consolidated Foundation Elaments, Crystal River Unit No. 3, Florir a Power Corporation, i

January 7, 1970.

These documents are the response to Item 2.10 of the Request for Additional Infor=ation made in the letter dated January 14, 1972.

In addition, in response to Item 2.10 of the Request for Additions'.

Information, an independent engineering evaluation of the entire chemicar grouting program is being conducted by Dr. H. Q. Golder of Golder Associates, Ontario, Canada. This evaluation is being conducted to determine the effectiveness of the chemical grouting program as outlined in the Specificacion for Subsurface Grouting, Crystal River Unit No. 3, SP-5500. At this time, no final report has been issued.

Working documents indicate the chemical grouting program has been successful as outlined in the specification require-ments. At such time as a final report is made, the Division of Re-actor Licensing will be furnished with the resu'ts.

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The Directorate of Licensing April 28, 1972 The specific parameters utilized for estimated hurricane surge analysis used in the design of Crystal River Unit No. 3 were based on theory discussed in Technical Memorandum No. 4, " Shore Protection, Planning and Design, 3rd Edition," June, 1966 by the U. S. Army Corps of Engineers, Coastal Engineering Research Center.

Our Hurricane Parameters were from ESSA Report HUR 7-97, May 7, 1968 which is one of the reports referenced in Q2.1.

Provisional Construction Permit CPPR-51 was issued on September 25, 1968.

Both design and construction have proceeded on the basis of the analysis accepted at that time by the '

Division of Reactor Licensing.

The referenced reports - Technical Memorandum No. 35, " Storm Surge on the Open Coast: Fundamental and Simplified Prediction" by U. S. Army Corps of Engineers, Coastal Engineering Research Center

  • and, " Estimation of Hurricane Surge Hydrograph" by G. Marinos and J. W. Woodward, ASCE Paper 5945, May,1968, WW2 were not used in the plant design or construction.

All PMH parameters, computations, documentation of model studies and wave height effects evaluation were supplied at the construction permit stage of plant licensing.

Amendment No. 16 consists of revised pages to the Final Safety Analysis Report which are in response to the Request for Additional Information made by the Division of Raactor Licensing in the letter dated January 14, 1972. The revised pages to the Final Safety Analysis Report consist of general update information and contain the remainder of the responses to the Request for Addi-tional Information made in the letter dated January 14, 1972 with the exception of Question 2.1.

Very truly yours, h'

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' }&)hf * 'ic : l' J. T. Rodgers Ass t. Vice President

& Nuclear Project Manager JTR/flw I