ML20072G577

Forwards Revised Table 3.9.2B-3 of Fsar,Per SER Item 10, Denoting Fuel Lift Under Combined SSE & LOCA Loadings as Zero.Value Based on 84% Nonexceedence Probability at 50% Confidence Level,Consistent w/NEDE-21175-3-P

ML20072G577
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	06/20/1983
From:	James Smith LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SNRC-908, NUDOCS 8306280547
Download: ML20072G577 (4)

Text

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% s % %3w aw w d P.O. BOX 618, NORTH COUNTRY ROAD + WADING RIVER, N.Y.11792 Dueet Dhl Numkr June 20, 1983 SNRC-908 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 I

SER Item No. 10 - Seismic & LOCA Loading "

Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Reference:

(1) Letter from General Electric (J. F. Quirk) to NRC (H. Bernard) dated July 27, 1982.

(2) Letter SNRC-752 dated 8/18/82

Dear Mr. Denton:

In Supplement No. 1 to the Shoreham Safety Evaluation Report (SER) ,

the staff concluded that Shoreham's fuel response when subjected to SSE and LOCA loadings was adequate. This adequacy was based on the staff's review of General Electric Report NEDE-21175-P "BWR/6 Fuel Assembly Evaluation of Combined Safe Shutdown Earthquake (SSE) and Loss-of-Coolant Accident (LOCA) Loadings", and Shoreham specific horizontal SSE acceleration. This report was approved by the staff subject to the condition that sufficient margin against fuel assembly liftoff be demonstrated under SSE and LOCA loading.

To accomplish this, General Electric Report NEDE-21175-3-P (BWR Fuel Assembly Evaluation of Combined SSE and LOCA Loadings, Amendment No. 3) was prepared and submitted to the staff via Ref. 1. LILCO endorsed this report for Shoreham via Ref. 2.

As a result of the staff's review of this report and based on discussions with the staff, LILCO is aware that additional plant specific information is required on fuel lift. To this end, Table 3.9.2B-3 from Shoreham's FSAR has been revised and is included as Attachment A. This table denotes that the fuel lift (fuel assembly gap ooening) under combined SSE and LOCA loadings is zero. This value is based on an 84% non-exceedence probability at a 50%

confidence level, consistent'with the methodology utilized in NED-21175-3-P.

8306280547 830620 PDR ADOCK 05000322 &

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' June'20, 1983 SNRC-908 Page 2 The s'taff's review of NEDE-21175-3-P also precipitated certain

' questions from the staff relative to structural integrity of the fuel assemblies involving allowable loads, hydrodynamic modeling and unirradiated. material properties. On June 10, 1983, General Electric Co. on behalf of the Licensing Review Group (LRG), made a

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presentation to the staff. It is LILCO's understanding that these questions will be formally resolved upon GE's submittal of their presentation material. It should be noted that, as shown in Table 3.9.2B-3, there exists considerable margin between the bounding accelerations contained in NEDE-21175-3-P and Shoreham's calculated peak accelerations.

LILCO feels that tho'information contained herein should be sufficient to completely close this issue on the Shoreham docket.

If you should have any questions, please contact this office.

Very.truly yours, 0 l J. L. Smith Manager, Special Projects Shoreham Nuclear. Power Station RWG:bc Attachment cc: J. Higgins All Parties Listed in Attachment 1

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_ "A .

SHOREHAM FSAR -

' TABLE3.9.2B-3 FUEL-ASSEMBLY (INCLUDING' CHANNEL) Calculated -(1) Evaluation , ,

Peak Basis-Acceptance' Criteria ' Loading Primary Load Type Acceleration- Acceleration

' Acceleration Envelope Horizoatal: Direction: ~Horizo'ntal Acce'leration ' 1. 3'G 3.6G

. Profile 1.. PeakiPressure

,2. Safe'. Shutdown Earthquake

-3. - Annulus- Press ,

urization-Vertical Direction: Vertical Accelerations 2.~0G; 12.OG

1. Peak Pressure

2. SafeJShutdown

^

Esethquake 3 Safety Relief.'

Valve 4 Condensation Oscillation NOTES:

(1) Evaluation Basis Accelerations'and Evaluations-are contained'in~NEDE-21175-3 P. The evaluation basis acceleration envelope is defined by a coincident 8G vertical acceleration with the 3.6G. horizontal acceleration ~. The 3.6G horizontal value is reduced linearly to-zero as the-corresponding vertical acceleration increased from 87to 12-G's.

(2) The calculated maximum' fuel-' assembly gap _ opening for the most limiting load combination is 0.0 inch.

This is less than the gap ( 0.' 5 2 inch) required to start the disengagement of the lower tie plate.

from the fuel support casting.

(3) The fatigue analysis indicates that the fuel assembly _has adequate fatigue capability to withstand the loadings:resulting'from multiple SRV actuations over the lifetime of the fuel.

o ATTACHMENT 1

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Lawrence Brenner, Esq. Herbert H. Brown, Esq.

Administrative Judge Lawrence Coe Lanpher, Esq.

Atomic Safety and Licensing Karla J. Letsche, Esq.

Board Panel Kirkpatrick, Lockhart, Hill U.S. Nuclear Regulatory Commission Christoper & Phillips Washington, D.C. 20555 8th Floor 1900 M Street, N.W.

Washington, D.C. 20036 Dr.. Peter A. Morris Administrative Judge Atomic Safety and Licensing Mr. Marc W. Goldsmith Board Panel Energy Research Group U.S. Nuclear Regulatory Commission 4001 Totten Pond Road Washington, D.C. 20555 Waltham, Massachusetts 02154 Dr. James H. Carpenter MHB Technical Associates Administrative Judge 1723 Hamilton Avenue Atomic Safety and Licensing Suite K Board Panel San Jose, California 95125 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 '

. Stephen B. Latham, Esq.

Twomey, Latham & Shea Daniel F. Brown, Esq. 33 West Second Street Attorney P.O. Box 398 Atomic Safety and Licensing Riverhead, New York 11901 Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Ralph Shapiro, Esq.

Cammer and Shapiro, P.C.

9 East 40th Street Bernard M. Bordenick, Esq. New York, New York 10016 David A. Repka, Esq.

. U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Matthew J. Kelly, Esq.

State of New York

, Department of Public Service James Dougherty Three Empire State Plaza 3045 Porter Street Albany, New York 12223 Washington, D.C.- 20008

.