ML20067A283
| ML20067A283 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 08/25/1975 |
| From: | Wofford A LONG ISLAND LIGHTING CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20067A201 | List: |
| References | |
| FOIA-82-455 SNRC-60, NUDOCS 8212010397 | |
| Download: ML20067A283 (6) | |
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'..I kEGUTE"Y pn0KET FILE COPY gf,CO LONG ISLAND LIGHTING COMPANY das #4Aes gernes r
175 EAST OLDCOUNTRY ROAD
- M I C K S V I L L E, N E W Y O R K 11801 a omcw w.worrono
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v.c m. or.a SNRC-60 August 25, 1975
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Mr.
J.
F. Stolz, Chief
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Light Water Reactors Branch 2-1
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Division of Reactor Licensing O[r,de p
U.
S. Nuclear Regulatory Commission L ::.
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Washington, D.
C.
20555 Qj gOw BWR Mark II Containment
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- n Shoreham Nuclear Power Station - Unit i vii '-
Nf'.e,.I'IT'4,h' Docket #50-322 y
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Dear Mr. Stolz:
Transmitted herewith is a description of the BWR Mark II Containment Supporting Program presented at a meeting with members.of the NRC staff on June 30, 1975.
7 The description has been expanded to identify the testing -
and analytical portions of the program and indicates the objective and schedule for completion of each portion.
Two items, Analysis of Alternate Load, Mitigation Design and "SRL-1" Mitigating Fix Testing, have been deleted from the preliminary Supporting Program discussed at the June 30, 1975 meeting, since they would be undertaken if needed only as the backup for the ramshead and quencher load mitigating devices.- Full scale in-plant testing of a ramshead device has been added to the program.
l Generally, the Supporting Program is intended to confirm the Preliminary Forcing. Function Report which is scheduled to be submitted to you in September 1975 as indicated in our letter of June 3, 1975, concerning this subject.
The Supporting Program contains a more detailed schedule for Item 5 of the schedule attached to the above-l referenced letter.
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LbN'O lO) AND LIGHT 1NG COM Y
. August 25, 1975 J.
F.
Stolz Page 2 As, further discussed at the June 30, 1975 meeting, '
it'is intended that the Preliminary Forcing Function Report
-will be reviewed and approved by the NRC as an acceptable method for handling Safety Relief Valve and LOCA hydro-dynamic loads for containment design.
Very truly yours, A. N. Wof Vice President Enclosure e
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q MARX II SUPPORTING PROGRAM ACTIVITY TARGET MARK II PROGRAM ACTIVITY TYPE SCHEDULE A;
LOCA RELATED 1.
"4T" Poo"1 Swell Test Test lat. Quarter 1976 2.
Pool Swell Velocity Breakthrough Model Analysis 2nd. Quarter 1976 3.
Impact Tests on Pool'
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Internal Structures Test 3rd. Quarter 1975 4.' Qualify Impact Model Analysis 4th. Quarter 1975 B.
SAFETY / RELIEF VALVE RELATED 1.
Relief Valve Pipe Clearing Model for Quencher Analysis 4th. Quarter 1976 2.
Relief Valve Pipe Clearing Analysis Model for Ramshead
& Test.
3rd. Quarter 1975 3.
In-Plant Test of S/R Valve Discharge Loads During Con-Test secutive Actuations Ramshead Test 3rd. Quarter 1976 l
4.
Relief Valve Consecutive I
Actuation Transient Analysis 4th. Quarter 1976 i
i Analysis l
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MARK'II SUPPORTING PROGRAM A.1 "4T" POOL SWELL TEST Objective Evaluate the pool swell phenomena for a typical Mark II
~ containment. geometry to determine pool swell veloci. ties, water slug thickness, breakthrough elevations and wet-well pressures in a near full scale vertical vent sup-pression system using one vent at the General Electric Pressure Suppression Test Facility (PSTF). The informa-tion will be used to predict the loading on wetwell structural members and the diaphragm floor between the wetwell and drywell.
A.2 POOL SWELL VELOCIIT BREAKTHROUGH MODEL Objective Develop an~ analytical model for predicting water slug velocity, pool swell breakthrough and froth character-istics.
Impact loads on structures above the pool are dependent on these parameters.
An anh19tical model is desired to bridge the gap between test results and actual containment geometry.
This activity complements the "4T" test program as its analytical counter-part.
l A. 3 IMPACT TESTS ON POOL INTERNAL STRUCTURES l
l Objective 1
l Conduct pool swell testing on various structural shapes of pool internals to estimate impact loadings on internal structures.
This activity involves one third scale shapes in the Pressure Suppression Test Facility (PSTF).
The shapes include circular pipes and I-beams of various sizes plus steel grating.
Test results will be used to predict impact loads.
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MARK II SUPPORTING PROGRAM A.4 QUALIFY IMPACT MODEL Objective Confirm applicability of PSTF data to. Mark II geometry and structures.
Evaluate impact test data for design applica-tion and analytical model verification.
If necessary modify current analytical models.
Confirm design adequacy of analytical methods with pool swell data.
Document analytical methods, assumptions, experimental verification of analytical methods, and experimental basis for specified loads.
This activity provides analytical modeling of the impact tests on pool internal structures and components.
B.1 RELIEF VALVE PIPE CLEARING MODEL FOR QUENCHER Objective Develop an analytical model of this phenomenon to provide an improved technical basis for design and greater flexibility on design details.
Compare this analytical model to current test data.
This model will not include prediction of internal pipe pressure effects since they are being developed in activity B.2.
B.2 RELIEF VALVE PIPE CLEARING MODEL FOR RA13 HEAD Objective, Document the Safety / Relief Valve Pipe Clearing Analytical Model in a supplement to the Quad Cities Topical Report (NEDO-10859).
This activity includes documentation of the Safety / Relief Valve Pipe Clearing Analytical Model for a ramshead including assumptions, justification of analytical methods, and description of the experimental basis for the analytical models.
This will al so include the development of analytical models to predict 1::ternal pipe pressures applicable to both the ramshead and the quencher.
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'B.3 IN-PLANT TEST OF SAFETY / RELIEF VALVE DISCHARGE LOADS DURING CONSECUTIVE ACTUATIONS Objective Measure the effect of consecutive safety / Relief Valve discharges on suppression pool pressures and internal
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pipe pressure.
Test data will be used to verify pipe internal pressure and water level for consecutive Sa'fety/ Relief Valve actuations.
Measurements will be made of strains imposed on a pressure suppression c'n-o tainment torus during consecutive valve actuations with varying delay times (i.e., time between valve closure and re-opening) in order to determine maximum strain and variation of strain with delay time.
Additional data will be obtained to aid in defining the phenomena causing load changes.
Internal pipe pressure data and pipe reaction forces will be obtained for verification of analytical model.
Pressure measurements at various locations in the pressure. suppression pool will be taken.'
This testing is being conducted by the Mark I Group, however, the Mark II group is participating in order to obtain additional test data on pipe internal pressures, pipe reaction forces and pressure attenuation in the suppression pool.
B.4 RELIEF VALVE CONSECUTIVE ACTUATION TRANSIENT ANALYSIS Objective Develop analytical methods for. predicting Safety / Relief valve discharge pipe pres'sures for both ramshead and quencher devices and containment loads associated with consecutive Safety / Relief valve actuations.
This analy-l tical model includes the effec'ts of a vacuum breaker and j
reflooding due to rapid stream condensation.
Both internal pipe pressures and pressures in the suppression pool will be predicted.
Current test data will b'e eval-uated and analytical models will be verified.
If neces-sary analytical models will be modified.
Verified anal '
ytical models for first and subsequent Safety / Relief valve actuations will be documented.
This activity provides the analytical modeling of the testing done in Item B-3 in order to correlate its applicability to the Mark II Containment geometry.
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