ML19291C385
| ML19291C385 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 12/07/1979 |
| From: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-79-02, IEB-79-2, NUDOCS 8001240330 | |
| Download: ML19291C385 (5) | |
Text
.
-f %
CONNECTICUT YANKEE ATOMIC POWER COMPANY BERLIN, CO N N ECTIC U T P.O. BOX 270 H ARTFORD. CONNECTICUT 06 tot Tatspwo=e 203-666-6911 December 7,1979 Docket No. 50-213 Mr. Boyce 11. Grier, Director Region 1 Of fice of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
References:
(1)
B. H. Grier letter to W. G. Counsil dated March 8,1979, transmitting I&E Bulletin No. 79-02.
(2)
B. H. Grier letter to W. G. Counsil dated June 21, 1979.
(3)
W. G. Counsil letter to B. H. Grier dated July 6, 1979.
(4)
B. H. Grier letter to W. G. Counsil dated August 20, 1979.
(5) Teledyne Engineering Services Report TR-3501-1, Revision 1, submitted to U.S. NRC Region I dated September 7,1979.
(6)
W. G. Counsil letter to B. H. Grier dated September 19, 1979.
(7)
B. H. Grier letter to W. G. Counsil dated November 8,1979.
transuitting I&E Bulletin No. 79-02, Revision 2.
Gentlemen:
Haddam Neck Plant Pipe Support Base Plate Design Using Concrete Expansion Anchor Bolts - I&E Bulletin No. 79-02 Reference (1), as supplemented by References (2), (4), and (7), requested that Connecticut Yankee Atomic Power Company (CYAPCO) provide information regarding pipe support base plate designs using concrete expansion anchor bolts on Category I systems.
Additionally, Reference (7) requested CYAPCO provide a schedule that details the completion dates for Items 1, 2, and 4 of Reference (7).
As reported in References (3) and (6), CYAPCO is a member of the Owners Group who contracted with Teledyne Engineering Services (TES) to a6'ress the generic questions of the Subject Bulletin.
(1)
In response to Question (1) of I&E Bulletin No. 79-02, the base plates utilizing concrete expansion bolts are being analyzed using the TES modeling approach as described in Reference (5). Shear tension inter.
action is being accounted for as well as minimum edge distage and proper bolt spacing.
1/95 219
/
0 012'10 33 G 3
, (2)
In response to Question 2 of I&E Bulletin No. 79-02, ultimate shear-tension interaction values as listed in Reference (5) are used and appropriate factors of safety applied to determine allowable design loads on the expansion bolts.
(3)
In response to Question 3 of I&E Bulletin No. 79-02, Reference (5) specifically addresses the cyclic load carrying ability of expansion bolts at both high and low frequencies.
No significant decrease in the static load carrying ability was detected for the types of bolts used at the Haddam Neck Plant.
(4)
In response to Question 4(a) of I&E Bulletin No. 79-02, Reference (5) concluded that preload is not required to develop cyclic capacity if the expansion bolts are installed properly.
In response to Question 4(b) of I&E Bulletin No. 79-02, a testing program was initiated since sufficient QC documentation did not exist for the installation of the expansion bolts.
The types of bolts used at the Haddam Neck Plant were primarily Phillips self-drill shells and Hilti-Kwik bolts with some Wej-Its.
Testing and inspections of systems located in accessible areas is complete.
The recent outage to inspect the feedwater nozzles afforded the opportunity to perform inspections and tests on those bolts used in systems located in inaccessible portions of the plant.
These inspections and tests are nearing completion.
The results of the tests performed to date are presented in Table 1.
Included in this table is the statistical analysis which was performed on the bolt sampling for each system.
The self-drilling shells were tension-tested to one quarter of the manufacturer's published ultimate value. Testing procedures included assuring no contact between the shell and the back of the plate during the test.
The Hilti bolts and Wej-Its were torque-tested. Torque values were obtained from Bechtel Power Corporation for wedge-type bolts.
These torque values were confirmed with field tests done by Hilti fastening systems at Millstone Nuclear Power Station, Unit No. 3, and other sites. Resultant tension values were above one quarter of the ultimate tensile values.
(5)
In response to Question 5 of I&E Bulletin No. 79-02, CYAPCO has reviewed the Seismic Category I systems and Safety-Related Systems as required by Reference (2). CYAPCO has determined that one support utilizes shell-type concrete expansion anchor bolts in a concrete block wall.
The support is located on a 1-1/2 inch fuel oil line supplying the emergency diesel generator. The support is located in an accessible area of the plant.
The adequacy of this support is presently being evaluated by CYAPCO and an alternate design will be developed if required.
1795 220
_3_
(6) In response to Question 6 of I&E Bulletin No. 79-02, CYAPC0 has made no distinction between base plates and structural steel plates in the evaluation performed pursuant to the criteria of I&E Bulletin No. 79-02.
Structural steel shapes were included in CYAPCO's evaluation performed in response to References (1), (2), (4), and (7).
(7) In response to Item 7 of I&E Bulletin No. 79-02, CYAPCO has completed preliminary analyses on the inaccessible supports in compliance with Reference (4). These analyses are currently scheduled for completion on or about February 1, 1980, at which time the responses to Questions (1) and (2) of Reference (7) will be completed.
The testing and inspections required by Item 4 of Reference (7) have been completed for those systems located in accessible areas. The testing and inspections of those systems located in inaccessible areas are nearing completion and are scheduled to be completed during the 1980 refueling outage. However, CYAPC0 will make every effort to complete this program during any outage of sufficient duration prior to the refu eling.
CYAFC0 will continue to modify any support which is found to not have the required factor of safety between postulated bolt loads and ultimate bolt strengths. Any support located in inaccessible areas found not to have the required factor of safety is scheduled to be reworked during the 1980 refueling outage.
A final report will be submitted following completion of all testing, inspections, and analyses.
We trust this information satisfactorily dispositions the concerns of References (1), (2), (4), and (7).
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY l/
f, hN{
W.'d. Counsil Vice President Attachment 1795 221
DOCKET No. 50-213 ATTACIDIENT HADDAM NECK PLANT PIPE SUPPORT BASE PLATE DESIGN USING CONCRETE EXPANSION ANCil0R BOLTS - I&E BULLETIN No. 79-02 1795 222 DECEMBER, 1979
EtNDCTICUP YRIKEC A70MIC 1%"R COFTR1Y - IINM NECK PIR?T I&E BULIrrIN 79-02 TESTING RESULTS hHYE SHELL TORQUE DOLTS IDLTS tbte #1: Several Supports Inside Cbntainment VALL'ES FOR WEDGE TYPE TORQUE THISIOJ Will Be Retested During The Next DOLTS CA M RY TES7H)
TESTED Outage.
I Note #2: The 'Iko Peactor Coolant Supports Were y
d Not Tested. These Supports Are Dead-N_
A M
N 6
weight Only And Have Been Evaluated By MJ g
SYSrmS b
b y
y t!
y Engineering As Ibt Being Essential For P3
}
M 2
System Ooerability In Accordance With y
G h p
The Subject Bulletin Guidelines. They
[3 4
y Will, However, Be Tested During The b
<b b b<
b m
Next Outage.
1/2 30 PRIN STF#1 50 5
64 12 0
Yes 5/8 55 Sequential Sanpling Technique 251 109 72 19 1
Yes 3/4 75 (See Note 1)
P = Probability of x or fewer defectives in a sanple GEMICAL of size m fran a population of size N with D 7/8 105 62 39 60 22 3
Yes VOL. CatTrROL defectives. This must be.95 or greater.
RES M
1 150 P=(XixlN,D,m)=
106 33 1
Yes 1=0
[ N' 1\\
250
\\mf
^
49 13 0
Yes SAFLTI ITU.
N = Populatial Size M
N 65 15 0
Yes D =.05 x N number of allowable defectives m = Sample Size RFAC70R 6
(See Notc 2)
X = Randmt Variable of the Nunber of Defectives 000N x = Actual Nutber of Defectives MNULUS PIPE 20 4
0
- One Dolt Per Plate Tested R/CK SERVICE 1&TEF 51 18 0
Yes y
4 48 36 23 16 1
Yes N
CONTA M IENT 6
2 0
N SPRAY u
Other Field Run Lines Smaller Than 2 " Were Walked Down And Bolts Were Randomly Tested - Ib Failures Reported.
.