ML19326C790
| ML19326C790 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/29/1973 |
| From: | Bernero R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Deyoung R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8004280725 | |
| Download: ML19326C790 (3) | |
Text
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WAY 2 9 M Docket No. 50-313 R. C. DeYoung, Assistant Director for Pressurized Water Reactors, Licensing A. Schweneer, Chief, Pressurized Water Reacto N 4tizstJh % 4, Licensing THRU A Schweaang "'
TRIP REPORT: SITE VISIT TO ARKANSAS NUCLEAR ONE MAY 3-4, 1973 Enc 1osed is a sumary of the site visit made to Arkansas Nuclear One on May 3-4, 1973. An attendance list is also enclosed.
Original Signed by Robert M. Bernero E. M. Bernero, Project Manager Pressurized Water Reactors Branch 30. 4 Directorate of Licensing Enclosures 1.
Trip Report 1.
Attendance List THIS DOCUMENT CONTAINS I ** ' [ f,*,,'g*
POOR QUAUTY PAGES '-
D. Skovbolt AEC PDE DISTRIBUTION Local FDR Docket T1 Assistant Directors RP Reading TR Breach Chiefs FWR-4 Reading FWR 3rsach Chiafs RMBernero L w. Elechar E Bases no (3) acomiboures Participants from AEC F. J. Miraglia
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. ENCLOSURE 1 REPORT OF SITE VISIT TO ARKANSAS NUCLEAR ONE May 3-4, 1973 May 3, 1973 Unit 1 was toured to review construction status and especially to review
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at_as affected by high energy line ruptures outside containment. The erangement of the reactor coolant letdown line was particularly noted.
The letdown line is located in the north penetration room and traverses that entire room before reaching the components which produce the principal
. pressure drop in the line. The applicant agreed to evaluate the. effects i
of a break in the high pressure portion of the letdown line inside the l
penetration room.
The emergency feedwater system was reviewed especially with regard to the suction connections with the service water system where two redundant
- supply lines come through normally open manual valves and then tee together to pass through a single normally closed motor-operated valve. Thus
. failure of this single valve could frustrate service water supply to the i-emergency feedwater pumps. The applicant is considering converting the two I
service water valves to normally closed motor-operated valves so that the single valve may be locked open.
1 The performance of the emergency cooling pond was discussed with the applicant. The applicant was informed that the AEC model showed that the rond temperature could exceed 120'F by a few degrees about 20 days after a DJA in Unit 1 (with shutdown of Unit 2) if the worst meteorological conditions-Prevailed. Resolution of this concern is lef t for licensing action on Unit-2.
The applicant was told he has two choices:
i 1.
Demonstrate that the AEC model is too conservative, or 2.
Show that exceeding the 120*F return temperature limit is acceptable.
i 13 e applicant was also informed that we consider their proposed Technical i
Specification of'344-feet'(half of the pond depth) as inadequate for operation of Unit 1 alone.
May 4, 1973 i
A' site tour was conducted for the subcommittee of the Advisory Committee on Reactor Safeguards (ACRS) which is responsible for review of Unit 1.
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ENCLOSURE 2 i
ATTEhTANCE ACRS SITE'IDUR OF ARKANSAS NUCLEAR ONE hMY 4, 1973 AEC Dr. Isbin - ACRS Dr. hbeller - ACRS Mr. Gaske - ACRS Staff A. Schwencer - DL R. Bernero - DL C. hbon - DL APGL_
H. T. Holmes - Mgr. of Production, Design S Construction W. Cavanaugh - Project Mgr.
W. H. Jewell - Attorney P. Lyon - Attorney S. Grimmett - Mgr. of Substation Design
. J. Anderson - ANO Superintendent D. Rueter - Nuclear Engr.
N. hbore - Chief QA CoordinatorR. Carroll - Chem. 6 Radiation T. Baker - Chem.6 Radiation Protection Engr. (Chemistry)
BEOffEL G. Katanics Project Engr.
J. Haidinger - Elect. Engr. Supv.
J. Oszewski - Licensing Engr.
K. hbthe - Plant Design Engr. Supv.
E H. Baker - Assoc. Proj. Mgr.
G. Glei - Licensing Supv.
G. M. Olds - Senior Project Mgr.
C. Thomas - Mgr. of Reactor Contracts i
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