ML18025A576
| ML18025A576 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 08/25/1975 |
| From: | Curtis N Pennsylvania Power & Light Co |
| To: | Butler W Plant Licensing Branch 1 |
| References | |
| 840-2, 9169, ER 100450, PLA-80 | |
| Download: ML18025A576 (6) | |
Text
NRC DISTRIBUTION FOB PART 50 DOCI<ET MATERIAL (TEMPORARY FORM)
CONTROL NO: 9169 FRQM: Penn. Pover & Light Co, DATE OF DOC DATE REC'D LTR TWÃ OTHER Allentown, Pa. 18101 H
8-25 "75 8>>28-75 FILE'LASS TO: ORIG CC OTHER SENTI<RC PDR
'Dr. Walt:er R. Butler 1 si ned SENT LOCAL PDR UNC LASS PROP INFO INPUT NO CYS REC'D OOCKET NO:
'ark XXX 1 50-38 DESCRIPTION: Ltr furnshing addi info re Mar EN RE XX Supporting Program XX contaiments & trans the following: ~ for the Susquehanna Plant Units l & 2....
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A4ggssrw /'-- I. t Dr. Walter R. Butler, Chief Dockets No's 50- 8 Light Water Reactors Branch 1-2 -3 Division of Reactor Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 SUSQUEHANNA SES SUPPORTING PROGRAM FOR NARK II CONTAINMENTS ER 100450 FILE 840-2 PLA- $ 0
Dear Dr. Butler:
Attached. is a copy of the outline of the BWR Mark II Containment "Supporting Program" presented in a meeting with members of your staff on June 30, 1975.
The outline has been expanded to identify the testing and analytical portions of the program and indicates the purpose and. schedule for completion of each portion. Full scale in-plant testing of a ramshead device has been added to the program. Analysis of Alternate Load Mitigating Design. and "SRL-1" Mitigating Fix Testing have been deleted because no additional load mitigating devices have been identified as necessary. The attached. outline. is a more detailed schedule for item 5 of the Mark II Containment Program attached. to our letter dated. June 5, 1975.
The Supporting Program is intended to Confirm the Preliminary Forcing Function Report (PFFR) which is scheduled to be submitted to you in September, 1975. It is intended that the PFFR will be reviewed. and, approved. by the NRC as an acceptable method. for handling S/R valve and LOCA hydrodynamic loads for containment design.
I Very truly yours,
]tJ LU N. W.
~~
Curtis Vice President-Engineering L Construction WEB DEB PENNSYLVANIA POWER 8 L I GHT COMPANY
MARK II SUPPORTING PROGRAM ACTIVITY TARGET MARK II PROGRAM ACTIVITY TYPE SCHEDULE A. LOCA RELATED
- 1. 4T Pool Swell Test Test 1st. Quarter 1976
- 2. Pool Swell Verlocity Break-through Model Analysis 2nd.. Quarter 1976
- 3. Impact Tests on Pool Inter-nal 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 An~sis 4th. Quarter 1976
- 2. Relief Valve Pipe Clearing Analysis Model for Ramshead. and Test 3rd. Quarter 1975
- 3. In-Plant Test of S/R Valve Dis-charge Loads During Consecutive Actuations for Ramshead Test 3rd.. Quarter 1976
- 4. Relief Valve Consecutuve Actuation Transient Analysis Analysis 4th. Quarter 1976
A.l "4T" POOL SWELL TEST
~Ob ective Evaluate the pool swell phenomena for a typical Mark II containment geometry to determine pool swell velocities, water slug thickness, breakthrough elevations and wetwell pressures in anear full scale vertical vent suppression system using one vent at the General Electric Pressure Suppression Test Facility (PSTF). The information will be used. to predict the loading on wetwell structural members and the diaphragm floor between the wetwell and drywell.
Ae2 POOL SWELL VELOCITY BREAKTHROUGH MODEL
~Ob ective Develop an analytical model for predicting water slug velocity, pool swell breakthrough and. fx'oth characteristics. Impact loads on structures above the pool are dependent on these parameters. An analytical 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.
'e3 IMPACT TESTS ON POOL INTERNAL STRUCTURES
~ob ective 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 load.s.
A. 4 UALIFY IMPACT MODEL O~bective Confirm applicability of PSTF data to Mark II geometry and, structures.
Evaluate impact test data for design application and. analyticalmodel 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.l RELIEF VALVE PIPE CLEARING MODEL FOR QUENCHER
~Ob ective 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 RAMSHEAD O~b ective 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 include the development of analytical models to predict internal pipe pressures applicable to both the ramshead. and the quencher.
Be3 IN-PLANT TEST OF SAFETY/RELIEF VALVE DISCHARGE LOADS DURING CONSECUTIVE ACTUATIONS
~Ob ective Measure the effect of consecutive SRV discharges on suppression pool pressur'es and, internal pipe pressure. Test data w'ill be used to verify pipe internal pressure and water level for consecutive SRV actuations. Measurements will be made of strains imposed on a pressure suppression containment torus during consecutive valve actuations with varying delay times (i.w., time 'between valve closure and. reopening) 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 re-action 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 poole B.4 RELIEF VALVE CONSECUTIVE ACTUATION TRANSIENT ANALYSIS O~bective
Develop analytical methods for predicting S/R valve discharge pipe pressures for both ramshead and quencher devices and containment loads associated. with consecutive S/R valve actuations. This analytical model includes the effects of a vacuum breaker and reflooding due to rapid steam condensation. Both internal pipe pressures and pressures in the suppression pool will be predicted. Current test data will be evaluated and analytical models will be verified.. If necessary, analytical models will be modified. Verified. analytical models for first and sub-sequent SRV 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.