ML19329A688

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Outlines Status of Issues Outstanding 730105 on Re Core Flooding Break,Quadrant Tilt,Noncategory 1 Equipment, Containment Pressure,Svc Water Sys for Emergency Cooling, Reflood,Small Break,Fuel Densification & Valve Analyses
ML19329A688
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 01/08/1973
From: Peltier I
US ATOMIC ENERGY COMMISSION (AEC)
To:
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8001090673
Download: ML19329A688 (3)


Text

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s JAN 8 G13 e

Docket Nos 50-269 270/287 Note to Files STATUS OF OUTSTANDING ISSUES, OCONEE 1, 2 & 3 AS OF JANUARY 5, 1973 The following f asues are included in the Oconee 2/3 Review.

l.-

Core Floodline Break Analysis a.

Letter to Duke - July 13, 1972

+

b.

Being reviewed by staff Final applicant analysis and plant modifications will be i'

c.

covered by either a supplement to BAW 10052 or a revision to FSAR d.

A letter report will be submitted January 15, 1973 with an amendment to follow about 10 days later, probably January 29, 1973 at latest.

2.

Quadrant Tilt Analysis a.

Letter to Duke - July 26, 1972 b.

Letter from Duke - August 23, 1972 c.

Resolution has been posponed until results of fuel densification issue are known.

3.

Non-Catagory I Equipment Analysis a.

Letter to Duke - September 26, 1972 b.

Letter from Duke - October 24, 1972,

c.

Being evaluated by staff

~ 'd. Duke will include in supplement to FSAR 4.

Containment Pressure Analysis a.

Letter to Duke - October 25, 1972 b.

Letter from Duke - December 19, 1972 c.

Being reviewed by staff d.

Duke will include in supplement to FSAR 5.

Service Water System for Emergency Cooling Analysis a.

Letter to Duke - October 21, 1972 b.

Letter from Duke - November 20, 1972 c.

Being reviewed by staff d.

Duke will include in supplement to ESAR 4

'8001090h[] Y

/7

e'

, 6.

Reflood-Analysis and Small' Break Analysis a.

Letter to Duke - November 6, 1972 b.

Letter fron Duke - December 19, 1972 c.

Being reviewed by staff d.

Duke will include in supplement to FSAR 7.

Fuel Densification Analysis a.

Letter to Duke - November 20, 1972 b.

B&W Topical Report, BAW 10054, received January 5, 1973 -

Duke letter and supplement mailed January 4, 1973, not received yet, c.

Being evaluated by staff d.

Topical report will be incorporated in application by reference.

8.

Steam-line Break Analysis 4

a.

Letter to Duke - December 15, 1972 b.

Preliminary response from Duke - January 2,1973 c.

Staff reviewing preliminary response d.

Duke will complete its analysis by about February 1,1973 9.

Valve Testing Program a.

Letter to Duke - January 2, 1973 10.- Electric Power Position a.

Letter to Duke - January 4, 1973 11.

Subcompartment Pressure Analysis a.

Letter to Duke - January 8, 1973

12., Internals Test Report Duke estimates a letter report will be mailed by February 1, 1973 a.

b.

Report included in application by February 15, 1973 13.

Industrial Security Plan a.

Letter to Duke - December 6, 1972 b.

Plan mailed from Duke - January 5, 1973 14.

Core By-pass Flow a.

Letter from Duke to be mailed - January 8, 1973 b.

Duke will include in Supplement to FSAR 4

s

15. Keowee Gate Analysis

. Duke will advise in a few days how the safety issue will a.

be resolved b.

Resolution will be included in supplement to FSAR

16. Environmental Tech Specs a.

Being reviewed by staff b.

Target date for final - January.15, 1973

17. Technical Specifications
a. ' Letter to Duke - December 15, 1972 b.

Unit.

approved Unit 1 & 2 being reviewed by staff 4

c.

e

  • d.

Unit 1 will have to be' revised to include:

1.

Quadrant Tilt limits based on Fuel Densification 2.

Power restrictions based on internals, fuel densification and ECCS 3.

Any other restrictions resulting from issues in 2.

The following issues, (listed above), need resolution or partial resolution prior to Unit 1 licensing.

1.

Core Floodline Break Analysis 2.

Quadrant-Tilt Analysis 7.

Fuel Densification Analysis 8.

Steam-line Break Analysis 14.

Core By-pass Flow

15. Keowee Gate Analysis
16. Environmental Tech Specs
17. Technical Specifications (for item 2.only).
f..

I. A. Ec1 tier, Project Manager Pressurized Water Reactors Branch No. 4 Directorate of Licensing cc:

IAPeltier ASchwencer RCDeYoung t

4 A

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