ML18025A279

Letter Regarding the Structural Integrity Test Procedure and an Amended Response to Question 5.37 on Compliance with Regulatory Guide 1.18

ML18025A279
Person / Time
Site:	Susquehanna
Issue date:	03/23/1976
From:	Curtis N Pennsylvania Power & Light Co
To:	Butler W Office of Nuclear Reactor Regulation
References
840-2, ER 100450, PLA-110
Download: ML18025A279 (6)

Text

NRC FORM 195 U.S. NUCLEAR REGULATORY CO~SION OOC~UMB~

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F I LE NRC DISTRIBOTION FOR PART 50 DOCKET MATERIAL TO: NRC Pa Pwr & Light Co DATE OF DOCUMENT Allentown, Pa 3-23-76

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to question 5.37 which will be includ'ed with material .submitted in Amdt ij16 to the PSAR....

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INTERNAL D IST Rl BUTION REG L NRC PDR ERNST I&E BENAROYA AL RD SPANGLER GOSSICK & STAFF EN NEER N IPPOLITO SITE TECH KNIGHT OPERATING REACTORS . GAMMILL SDMEIL STELLO STEPP PAMLICKI HULMAN OPERATING TECH PROJECT MANAGEMENT REACTOR SAFETY EISENHUT SITE ANALYSIS BOYD ROSS SHAO VOLLMER P, COLLINS NOVAK BAER BUNCH HOUSTON ROSZTOCZY SCHMENCER J, COLLINS PETERSON CHECK GRIMES KRE GER MELTZ HELTEMES SKOVHOLT AT & I SITE SAFETY & E R SALTZMAN ANALYSIS RUTBERG DENTON & MULLER EXTERNAL ISTR IBUTION CONTROL NUMBE R LPDR e NATL LAB BROOK VEN NATL LAB TIC REG, V"IE ULRIKSON (ORNL)

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TWO NORTH NINTH STREET, ALLENTOWN, P ER (2I5) 821-5151 March 231 1976 RECUQTORY I)OCI(ET FlLE COPY, @X.~~i '

Director of Nuclear Reactor Regulation Light Water Reactors Branch No. 1-2 U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Dr. Walter R. Butler, Chief Docket Nos. 50-387 50-388 SUSQUEHANNA STEAM ELECTRIC STATION MODIFICATION TO QUESTION 5.37 ER 100450 FILE 840-2 PLA-110

Dear Dr. Butler:

We are in the process of writing our Structural Integrity Test Procedure to be submitted to you in late April, 1976. In Amendment ¹16, we submitted an amended response to Question 5.37 on compliance with Regulatory Guide 1.18. This response listed our exceptions to Regulatory Guide 1.18. We have two additional exceptions.

They are as follows:

l.

Reference:

Paragraph C.2 of the Regulatory Guide. We intend to select the number and distribution of measuring points for monitoring radial deflections so that the as-built conditions can be considered in the assessment of general shell response.

In general the locations of measuring points for radial deflections are in agreement with Figure B, except point 1. Point 1 is provided at a distance of two times the wall thickness (12') from the base slab. This variation is made to properly predict the containment behavior near the base slab to wall connection. If point 1 were to be provided. at a height of three times the wall thickness (18') it would. be located very close to point 2 (suppression chamber wa11 midheight is 26') and. would not yield. any additional behavior pattern of the containment.

2.

Reference:

Paragraph C.5 of the Regulatory Guide. Because of the current state of the art, triaxial concrete strain distortion measurements, while taken, may not be used. to evaluate the containment strain distribu-tion. The concrete strain will be evaluated using linear strain measurements in the meridiona1 and radial directions.

PENNSYLVANIA POWER 5 LIGHT COMPANY

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Page 2 March 23, 1976 As we stated before, we intend to submit our Structural Integrity Test Procedure in late April and would like your comments on these exceptions prior to that dates Very truly yours, 4@3 N. W. Curtis Vice President-Engineering Ec Construction NWC: AAW

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