ML18025A279
| 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 I2 76)
U.S. NUCLEAR REGULATORYCO~SION OOC~UMB~
CEO'O'It '72 38 NRC DISTRIBOTION FOR PART 50 DOCKET MATERIAL F ILE QB~
TO:
NRC
~ Pf
~'ROM:Pa Pwr & Light Co Allentown, Pa N N Curtis DATE OF DOCUMENT 3-23-76 DATE RECEIVED 3 2$
76 LETTE R
ORIGINAL CIcop Y DESCRIPTION ONOTORIZED 8 UNC LASS IF I E D PROP INPUT FORM ENCLOSURE NUMBER OF COPIES RECEIVED one s igned-Ltr furnishing info concerning modificatio).
to question 5.37 which will be includ'ed with material.submitted in Amdt ij16 to the PSAR....
DONGA RRMO~~
E
." HJINT NAME:
Susquehanna 1 & 2
~ ~~&OWL Q<DpjgD SAFETY.
FOR ACTION/INFORMATION ENVIRO eni ASSIGNED 'AD.
BRANCH CHIEF:
PROJECT MANAGER:
LIC~
ST E
Ovn U+I V "ASSIGNED AD:
BRANCH CHIEF
~
PROJECT MANAGER.
LIC~ ASST+
REG L
NRC PDR I&E GOSSICK & STAFF PROJECT MANAGEMENT BOYD P,
COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT INTERNALD EN NEER N KNIGHT SDMEIL PAMLICKI REACTOR SAFETY ROSS NOVAK ROSZTOCZY CHECK AT & I SALTZMAN RUTBERG ISTRl BUTION BENAROYA IPPOLITO SITE SAFETY & E R
ANALYSIS DENTON & MULLER OPERATING REACTORS STELLO OPERATING TECH EISENHUT SHAO BAER SCHMENCER GRIMES ERNST AL RD SPANGLER SITE TECH GAMMILL STEPP HULMAN SITE ANALYSIS VOLLMER BUNCH J,
COLLINS KREGER LPDR TIC NS ASLB e
EXTERNAL ISTR IBUTION NATL LAB REG, V"IE LA PDR CONSULTANTS 0
I-vs v66 BROOK VEN NATL LAB ULRIKSON (ORNL)
CONTROL NUMBE R 3t l2 NRC FORM 196 (2.76)
+A-/
C V
1'
~
~
~
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 SUSQUEHANNA STEAM ELECTRIC STATION MODIFICATION TO QUESTION 5.37 ER 100450 FILE 840-2 PLA-110 Docket Nos.
50-387 50-388
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
F
~ ~
~
~
> ~
~
~
H
/
~
~
~
~
J
~ '
~ ~
~
(
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
I'1
~ '
H hi
~
~ 'i i I
- I I
~ 4
~