ML19312C881

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Forwards Summary of Inputs Needed to Complete Facility Review by 730601 & Finalize SER Suppl & Tech Specs in Time for ACRS Jul 1973 Meeting
ML19312C881
Person / Time
Site: Oconee  
Issue date: 04/02/1973
From: Deyoung R
US ATOMIC ENERGY COMMISSION (AEC)
To: Hendrie J
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8001130054
Download: ML19312C881 (5)


Text

o APR 2 1373 Docket I;os. 5 @ /287 J. Hendrie, Deputy Director for Technical Eeview, L OCO::EE 2/3 REVII'J, SER SUPPLO:E:1T AND TFCC'ICAL SPECIFICATI0';S In order to complete the Oconce 2/3 review by June 1,1973 and finalize the Oconce SER Supplerent and Technical Specifications in tine for a July ACRS necting, the enclosed ntenary of inputs are needed from Technical Review. The enclosed curiary is so:cuhat cryptic and chould be discussed between the L-PH nnd the responsible review branches but the items are listed according to teajor review area.

Crt;!nal R of by R. C. (;Y nng R. C. DeYoung, Assistant Director for Pressurized L'ater Reactors Directorate of Licensing Encio rour e:

As stated cc: D!accary RVollmer DISTRIBUTION JKnight VBenaraya

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J. Hendrie, Deputy Director for Technical Review, L -

N OCONEE 2/3 REVIEV SER SUPPLDIEUT AND TECEIICAL SPECIFICATI0;;S

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In order to co=pleth the Oconce 2/3 review by June 1,1973 and finalize the Oconce SER Supplement and Technical Specifications in time for a July ACRS cceting, the enclosed nu=ary of inputs i

are needed from Technical, Review. The enclosed suranry is I

soncuhat cryptic and should. be discussed between the L-FM cud the responsible review branches but are listed according to A

l r.sjor review area.

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' R. C.XDcToung, Assistant Director for Pressurized Water Reactors Directorate of Licensing

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Enclosure:

DISTRIBUTION S

As Stated Docket Files

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OCONEE 2/3 REVIEW Engineering 1.

Testing Program for Active Valves Status: Duke's response to our January 2, 1973 request is anticipated prior to May 1, 1973.

2.

Mechanical Design and Installation of the Floodline Flow Limiters Status: Duke described the limiters in FSAR Supplement No.14, Revision 26, Amendment 39, January 29, 1973 3.

Oconce 1 as Prototype for Oconee 2/3 Vessel Internals Status:

Duke is scheduled to submit s qualification report by May 1, 1973 4.

High Energy Line Rupture External to Containment Status:

Duke is scheduled to make its completed response to our December 15, 1972 letter by April 25, 1973.

This is a LPM review task but TR assistance may be required in some technical areas.

Containment Safety 1.

Reactor Containment Overpressure Status: Duke responded to our October 25, 1972 letter in FSAR Supplement No. 13, Revision 26, Amendment 39,

_ January 29, 1973.

(Also by letter dated Dece=ber 19, 1972) a 2.

Subcompartment Overpressure Status:

Duke responded to our January 8, 1973 letter by letter dated March 2, 1973 3.

Net Positive Suction Ucad Status: Duke responded to our request for information on NPSH in FSAR Supplement 11, Revision 20,-Amendment 32, May 25,1972.

(This item was in the original Oconee 2/3 review but to our knowledge we do not have TR's evaluation).

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i 4.

Non-Category I Equipment Failure l

Status: Duke responded to our September 26, 1972 Ictter by j

letter dated October 24, 1972 and in FSAR Suppicment No. 13, j

Revision 26, Amendment 39, January 29, 1973.

1 5.

Auxiliary Service Water System 2

Status: Duke responded to our letter of October 21, 1972 by letter dated November 20, 1972 and in FSAR l

Supplement No. 13, Revision 26, Amendment 39, January 29, 1973.

i 6.

High Energy Line Rupture External to Containment l

Status:

(Same as item 4 under Engineering) j Site Safety i

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1.

Revised Meteorology 4

Status: TR has reviewed the revised meteorology data for the Oconee site and arrived at new x/c,'made available to 4

factors.

The impact on accident analysis has not been the LPM.

2.

Also See Item 5 under Reactor Safety Reactor Safety 1.

ECCS Analysis j

Status: TR is preparing SER input on reflood, small break, j

Oconee 1.

It is assumed that these evaluations will floodline break and less than 4 pump operation for

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be equally applicable to Oconee 2/3.

1 2.

Fuel Densification Status: TR is performing lead plant evaluation for Oconee 1.

Acceptable models are required for the LPM to evaluate il Oconee 2/3.

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3.

Review of Control Circuits I

Status: Duke has been requested to respond to our March 7, 1973 4

letter by May 7, 1973 (60 days).

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Q/A for Operations Status:

Duke has been requested to respond to our M.rch 27, 1973 letter by April 27, 1973 (30 days).

This is a Unit 1 item but should apply equally to Unit 2/3.

5.

Review Duke's response to our December 15, 1972 letter on Technical Specifications Status:

Duke is scheduled to respond to the December letter prior to May 1, 1973.

15, 1972 6.

Technical Specification 3.3 Status:

Duek revised this specification in FSAR Revision 24, Amendment 37, I;ovember 15, 1972.

on this revision.

TR should cot ent 7.

Technical Specification 3.7 Status:

We gave Duke our position on this specification in a-letter dated January 4, 1973.

Duke responded by FSAR Revision 26, Amendment 39, January 29, 1973.

TR should evaluate this response.

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