ML19290C068
| ML19290C068 | |
| Person / Time | |
|---|---|
| Issue date: | 07/18/1979 |
| From: | Szukiewicz A Office of Nuclear Reactor Regulation |
| To: | Hanauer S NRC - TMI-2 UNRESOLVED SAFETY ISSUES TASK FORCE |
| References | |
| CON-FIN-B-0726, CON-FIN-B-726, REF-GTECI-A-24, REF-GTECI-EL, REF-GTECI-IS, TASK-A-24, TASK-OR NUDOCS 8001090116 | |
| Download: ML19290C068 (6) | |
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UNITE D STATES NUCLEAR REGULATORY COMM!SSION 5
n E WASHINGTON, D. C. 20555 4
o JUL 18 n;3 MEMORAfiDUM FOR:
S. H. Hanauer, Director of USIP FROM:
A. J. Szukiewicz, Task Manager A-24
SUBJECT:
MEETING
SUMMARY
- URill TECHNICAL ASSIST At!CE PROGRAM (FIN # B0726) ON EQUIPMENT QUALIFICATION A meeting was held in Bethesda with ORNL on July 11 and 12, 1979 to:
1.
discuss the status and work generated by ORNL to-date for the project (FIN B0726).
2.
provide guidance and additional training to ORNL for understanding staff requirements regarding equipment qualification and to broaden ORNL's scope when evaluating qualification plans and requesting information from applicants.
A list of Attendees is enclosed (Attachment 1).
The following summary highlights areas discussed:
A.
Reviewed content and scope of ORNL questions that were submitted for Rosemount Pressure transmitters.
(ORNL letter dated June 25, 1979, BCP item 5) and for Low Voltage Cable (CRNL letter dated June 6, 1979, B0P item 13).
B.
Format and scope of typical questions that should be developed by ORNL was discussed. The objective of developing broad questions was discussed.
These questions and responses should establish the basis for qualification adequacy of the programs that are being evaluated. This basis is to be described and provided by ORNL for each qualification package reviewed.
The questions that are developed should reflect the staffs requirements C.
and/or concerns identified in the interim position (Draf t 3).
D.
The AN0-2 SER supplement was discussed as a typical sample of the scope, and content of what should be included and expected of ORNL when safety evaluation reports are written.
Copies of the SSER were provided to ORNL for information.
ORNL was requested to develop a summary sieet for each qualification E.
report they review. These summary sheets are to be submitted to the staff when submitting the questions that are to be issued to the 1730 330 8001090 \\ \\ f -
. applicant.
Two sample summary sheets (Attachment 2) were provided to ORNL to serve as a guide in developing a summary sheet.
A draft summary sheet that is to be used by ORNL should be submitted to us by the week of July 23, 1979.
ORNL was requested to modify and resubmit the previously developed F.
BUP questions (i.e. for BOP items 2, 4, 5, and 13) to reflect the These revised questions concerns identified during our review session.
are to be re-submitted the week of July 23, 1979.
G.
Another two day meeting will be held in August in Oak Ridge to discuss accomplishments.
A Main Steam Line Break and LOCA, Temperature vs Time profile for Commanche H.
Peak was provided to ORNL. The qualification programs for Commanche Peak should envelope the values shown (Attachment 3).
]
flb$lhcLrl I
A'.
S uk 6 icz T c nica M nitor FIN 76 Enclosures As stated cc:
F. Schroeder V. Moore A. Satterfield F. Rosa T. Dunning tF(. Aycock J. Anderson ORNL G. Holt ORNL l[}Q j}l F. Manning ORNL E. Waught ORNL A-24 File Tech Assistance File B0726
List of Attendees - July 11 and 12, 1979 J. Anderson ORNL - Part-time F. Manning ORNL G. Holt ORNL E. Waugh ORNL
%. Szuk1ewicz NRC F. Rosa NRC - Part-time 1730 332 e
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ATTACHMENT 2 (Con't)
(
SEISMIC TESTihG OF CLASS IE EQUIPMENT
- N1 A y' b 3
i P
1 Equipment Manufacturer Typel Model f Test Report Test Pro-NRC Consnents Appil m f
gram D8E Requirements Plants Iimit W Static See Coninents See Consnents WCAP 7817 &
< 0.2g lloriz.
- 1. Only applicable for 1.
W to identify type PG&E W
Inverter Su Ground plants having CP and model f*s.
NRC Plants Y
{[pp.2 l
y~~
Acceleration appilcations docketed questions to W A
3 prior to 10/72 & will 1/15/79 F
be reviewed on a case-by-case basis for plants c
having CP applications docketed af ter 10/72.
N l
- 2. The following reports shall be referenced as a group and be properly documented. WCAPs' 8373, 7558, 8673, 8674, 8624 8695. 8694, 8655, 8830 J,
8831, 8832, 8833, 8828 B829. 8848. and 8849.
1 u Static W
See Comments See Conments WCAP 7821 &
0.2g to <0.4g Same as 182 previous
- 1. Same as above Same as Inverter Supp. 2 lloriz. Ground
?
above Addendum 1 Acceleration Foxboro Foxboro See Coneneats See Comments WCAP,7817-
<0.29 Horiz.
Same as 182 previous
- 1. Same as 1 above Point Bear U'
WCAP 8848 fround
- 2. App. A (Table 2-1 &A)
&Prairle l
ntr Acceleration lists only some module Island A
Equipment identification & models Actuation See Coments See Coments WCAP 7817
< 0.29 Horiz.
Same as 182 previous
- 1. Same as I above Safeguards W
Eround backs Acceleration PI21 ear in-
~
See Coments See Cocunents WCAP 7817 &
<0.29 Horiz.
Same as 1 & 2 previous 4ppendix 8 (Table 2-1 &
W strumentation WCAP 8830 Cround 2-2). Identify equipment System Acceleration tested Nuclear In-W_
See Coments See Conunents WCAP 7821 &
0.29 to <0.4g Same as 112 previous
\\ppendix B (Table 2-1 &
strumentation 8
,WCAP 8830 lloriz. Grcund
?-2). Identify equipnient Systen Acceleration tested huBear In-g See Coments See Comments WCAP 8021 P.
0.4g Horiz.
Same as 152 previous
\\ppendix B (Table 2-1 &
Diablo strumentation WCAP 8830 Ground Acce-
?-2). Identify equipment Canyot*
Sys tein leration & a tested t
hard soll foundation Page 1 of 6 t
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