ML19256A782
| ML19256A782 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Hatch, Monticello, Dresden, Peach Bottom, Browns Ferry, Nine Mile Point, Fermi, Oyster Creek, Hope Creek, Cooper, Pilgrim, Brunswick, Vermont Yankee, Duane Arnold, Quad Cities, FitzPatrick, 05000000 |
| Issue date: | 01/09/1979 |
| From: | Sobon L GENERAL ELECTRIC CO. |
| To: | Charemagne Grimes Office of Nuclear Reactor Regulation |
| References | |
| TASK-06-02.A, TASK-6-2.A, TASK-RR MFN-006-79, MFN-6-79, NUDOCS 7901160149 | |
| Download: ML19256A782 (12) | |
Text
e
(
GENER AL h ELECTRIC NUCLEAR ENERGY PROJECTS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 Mail Code 905, Telephone (408) 925-3495 MFN '.06-79 January 9, 1979 U. S. Nuclear Regulatory Commission Division of Operating Reactors Office of Nuclear Reactor Regulation Washington, D. C.
20555 Attention:
Mr. C. I. Grimes, Task Manager Mark I Containment Long-Term Program Gentlemen:
SUBJECT:
MARK I CONTAINMENT ACTIVITY REVIEW - NOVEMBER 1978 The purpose of this letter is to forward ten (10) copies of a November 1978 Program Activity Review for your information.
This review lists the meetings held and provides a brief task-by-task activity summary for the month.
It is being provided to you on behalf I
of the Mark I Owners Group.
The document is comprised of information extracted from selected sections of a monthly report prepared by General Electric for the Mark I Owners Group.
Sections on contract at:d billing status have been removed.
Sincerely, L. J. Sobon, Manager BWR Containment Licensing LJS/d Enclosures cc: L. S. Gifford (GE, Bethesda)
File: 2.9.2/2.10 m
N 790116o/y7
\\
,f k
MARK I CONTAINMENT PROGRAM PROGRAM ACTIVITY REVIEW NOVEMBER 1978 s
GENERAL ELECTRIC COMPANY San Jose, California O
I.
MEETING
SUMMARY
~
Date Attendees Place Meeting Content 11/2/78 GE/NUTECH/EDS San Jose Task 7.1.1.1 - Ramshead Model Report Multipliers 11/6/78 TRC/GE
-san Jose Draft LDR Review 11/7/78 TRC/GE San Jose Draft LDR Review 11/8/78 TRC/GE San Jose Draft LDR Review 11/9/78 TRC/GE/EPRI San Jose 1/12 Scale 3D Pool Swell Tests and Other Various Topics 11/13/78 NRC/ SAC Working San Jose Plant Unique Analysis Application Group Representatives
';uide Content Conference Call 11/16/78 PIC/ Utility Executive /
Washington Plant Modification Plans GE 11/17/78 GE/NUTECH San Jose Review Plan for Resolution of Technical Action Items from Utility LDR Review 11/29/78 GE/NUTECH San Jose Status of Task 7.1.1.2 Review V
m.,
e
1 III.
ACTIVITY
SUMMARY
_ Task 3.0 - Structural Acceptance Criteria (SAC)
A conference call was held with NRC/ SAC Working Group representatives on November 13, 1978 to discuss the content of the final version of the Plant Unique Analysis Application Guide (PUAAG) - Task 3.1.3.
The NRC took exception to the draft PUAAG in four areas:
- 1) Zero AP Pipino Analysis - The NRC indicated that a zero AP analysis should be performed for the piping cases associated with a DBA.
- 2) Pump / Valve Operability - The NRC indicated that pump / valve operability must be addressed as part of the Mark I Program.
- 3) SRSS - The NRC indicated that when other than the absolute sum method of combining loads is utilized, plant / case unique CDFs must be generated.
- 4) Service Level Assignment for Main Vent to Rina Header Inter
- section - The NRC stated that Level C cannot be applied to this intersection without an appropriate analysis or test to justify the capability of the intersection.
A TRC/GE/NUTECH conference call was held on December 7,1978 to formulate the program direction on each of the above issues.
The Technical Review Committee directed that the PUAAG should basically remain as is.
Speci f-
'ically, the direction that will be taken on each of the above items is as follows -
- 1) Zero AP Piping Analysis - No piping analysis will be accomplished for cases associated with loss of AP for the DBA. The analysis will be limited to the torus shell, torus support system, and the vent header.
- 2) Pump / Valve Operability - Operability will be addressed in a manner consistent with the original design criteria.
If operability was not addressed in the plant's FSAR, then it will not be a require-ment for this program.
The operability subject will likely become part of the Systematic Evaluation Program (SEP).
- 3) SRSS - The absolute sum method of load combination will be used except where the SAC cannot be met.
For these exceptions, SRSS will be used first at a maximum stress intensity level and then at a stress component level if required.
This approach will apply to piping as well as the Class MC Components ar.d Supports.
- 4) Service Level Assignment for Main Vent to Ring Header Intersection Since the test program to justify increased allowables for this intersection (Task 3.2.2) has been put on hold awaiting identifi-cation of need, the more limiting Service Level assignments will be applicable for this intersection.
S III-l
III.
ACTIVITY
SUMMARY
(Continued)
Task 3.0 - Structural Acceotance Criteria (SAC) - continued The PUAAG is in the final stages of publication and will reflect the TRC direction discussed above.
It is intended that the document will be trans-mitted to the Utilities and the NRC in late December 1978.
Task 5.3 - Flexible Cylinder Tests Bechtel has completed the structural evaluation of the vent bay / vent header, assuming no vent deflector is used.
Results of the analysis (using a plant with moderate pool swell velocity) showed stresses within structural accept-ance criteria limits. Bechtel will issue vent header structural analysis reports for the non-vent bay with deflector and vent bay without deflector.
Task 5.5 - 1/4 Scale 20 Pool Swell Tests The Task 5.5.3 plant unique pool swell tests have been completed. Sections of the test report for several groups of plants have already been issued'for review to minimize the time required for the review cyclc. The final report draft, which includes all the tests in the task, is scheduled for issuance early in February 1979.
It is planned to hold a Utility /AE document review meeting in mid-February 1979 and to issue the final test report to the Mark I Owners and NRC by the end of March 1979.
Several Mark I Owners have requested additional plant unique 1/4 scale pool swell tests to be funded directly by the requesting utility. Tests are now planned for Monticello (completed), Duane Arnold, Pilgrim, Oyster Creek, Nine Mile Point and Millstone. All testing will be completed before the end of February 1979.
It is planned to include load cell measurements for vent deflectors in these tests.
e*
J.'
III-2 4
t
/
III.
ACTIVITY
SUMMARY
(CONTINUED)
Task 5.6 - 1/12 Scale 3D pool Swell Tests In the final report for Task 5.6.1, EPRI presented some test data and a brief discussion which indicated that if orifices were placed upstream in the vent system, the measured pool swell loads (especially for upload and vent header impact) were considerably higher than the loads measured with orifices placed in the downcomers.
General Electric, during Task 5.5.3-1 sensitivity tests in the 1/4 scale 2D pool swell facility, noted some sensitivity of pool swell loads to orifice location.
In order to simulate prototypical conditions, the General Electric plant unique pool swell load tests were accordingly performed with a " split orifice" con-figuration.
In the November 9,1978 TRC meeting, General Electric recommended the per-foruance of additional tests in the EPRI 1/12 scale 3D pool swell facility.
A technical review meeting was held on December 6,1978 to discuss specific details of that recommended test program.
Tests were requested with ori-fices simulating 50% resistance in the vent system and 50% resistance in the downcomers in order to establish the 30 transient pool displacements used to determinate the vent header impact loads. Additional tests were requested for 100% orifice resistance in the vent system and 0% orifice resistance in the downcomers to confirm the use of split orifices in the 1/4 scale 2D pool swell tests. These requests have been transmitted. to TRC along with program required dates for subr equent discussion and plan-ning by TRC and EPRI.
Task 5.10 - Miscellaneous Monitoring The comparison of GE 1/4 scale 2D pool swell tests with EPRI 1/12 scale 3D pool swell tests indicates that the 3D/20 ratio for pool swell norus up and down loads is less than or equal to 1.0.
NRC has informally in-dicated that the Lawrence Livermore Laboratories (LLL) 1/5 scale 20 and 3D pool swell tests show a 1.17 ratio for 3D/2D uploads (with an uncer-tainty error of +12%).
GE has requested a working group meeting with LLL in order to review the detailed results; that meeting is now tentatively scheduled for mid-January 1979 in order to permit LLL to complete their analyses.
Task 5.11 - Full Scale Test Facility All scheduled testing in the FSTF has been completed including a simpli-fied shake test which was performed to identity the predominant vibration modes of the facility.
to TRC in December 1978. The draft test report is scheduled for transmittal Based upon requests from several utilities, a documentary test film is being prepared to describe the FFTF pecqram.
It is currently expected that the film will be shown in the late January 1979 meetings.
Task 5.14 - Submerged Structures Bechtel has initiated generic structural evaluations /or all submerged structures models.
The structural evaluation effort includes a checkout III-3
~
III.
ACTIVITY
SUMMARY
(CONTINUED)
Task 5.14 - Submerged Structures - Continued of accessibility of the submerged structures computer programs via the CDC/Cybernet system.
As discussed in the Mark I Owners LDR review, improvements in the T-quencher model velocity description have been made and incorporated into the computer program to reduce the level of conservatism in loa'd definition.
The final report model/ data comparison for submerged sthucturas loads from pool swell phenomena.has been completed and will be released for review in early December 1978.
The measured forces were generally small and the r.nalytical predictions were shown to be conservative.
Task 5.15 - Structural Hydrodynamic Interaction This task consisted of: (1) a 1/12 scale chugging test using flexible and rigid flat plates; and (2) the development of a structural model, using NASTRAN, to compare analytical predictions to the flat plate data.
The analytical model/ data cocparison report draft is complete and will be issued for review in mid-December 1978.
Task 6.2.1 - T-Quer.cher Development The second phase of testing at NUS has been completed and the draft report has been issued for TRC review.
Final report publication is scheduled for late December 1978.
3 The second test phase investigated the effects of varying water leg geometries on the quencher bubble and wall loads. Preliminary ~ results were reviewed with TRC on November 9, 1978.
Following modification of the air flow rate to the bubble, the air clearing loads model developed in Task 7.1.1.2 is ir agreement with and bounds the 1/4 scale program test data.
4 III-4
Task 7.1.3 - Multiple Consecutive 5/RV Actuation Evaluation The additional information requested by the NRC was transmitted on November 13, 1978, and forwarded to the Utilities..
The transmittal provided a comparison between the hydrodynamic factors for the average S/RV discharge line and the worst S/RV discharge line whose S/RV would be predicted to consecutively actuate for five plants.
Further, it demonstrated that the difference in limiting strength rations resulting from S/RV actuations of the two discharge group lines was negligible for the plants in question. With the transmittal of this requested information, this interim assessment is complete.
Task 7.3.3 - Vent Deflector Load Definition The analytical effort to define pool swell loads on vent deflectors re-sulted in identification of acceleration drag as a major loading sourge.
The plant unique supplementary pool swell tests are being performed for individual utilities (in Task 5.5.4) include load cell measurement of vent deflector loads.
Comparison of the analytical methods to the ex-periinental results. indicates that the analytical results may be conserva-tive by about a factor of 1.7.
A final report defining plant unique vent deflector loads based on analytical predictions, will be issued I
a e
9 9
III-5
III.
ACTIVITY
SUMMARY
(CONTINUED)
Task 7.3.3 - Vent Deflector Load Definition - Continued in late December 1978. After completion of the supplementary 1/4 scale pool swell tests, development of a less conservative semi-empirical approach (using the 1/4 scale test data generated in January / February 1979) will be considered.
Task 7.5.2 - T-Quencher Thermal Mixing The Monticello thermal mixing tests were completed on November 30, 1978.
The first test was an extended blowdown through a T-quencher with holes in the end cap of one arm.
In a second test, pool circulation was aided through operation of one RHR loop with elbows and reducers installed on the return lines. Although the second test clearly produced a lower peak temperature. difference between the bulk and local valves, both tests resulted in a peaking of the bulk to local temperature difference prior to the end of the test.
Comparisons of the thermal mixing model predictions with the test results are underway and will be reviewed at the meetings scheduled for late January 1979. A quick look report for the test effort will be forwarded for information in early December 1978.
Task 7.6 - LDR Preparation i
GE/NUTECH met on November 17, 1978 to review the intended approach for resolution of the 32 technical action items which resulted from the November 6-8, 1978 utility review of the draft LDR.
In addition, Ge/
NUTECH met on December 1, 2, and 8,1978 to review incorporat' ion of the comments in the LDR.
Following these meetings, the final comments were incorporated. The document is now in the final stages of publication.
The December 29, 1978 date for transmittal to NRC will be met.
O e
III-6
.4
.4 MARK ! CONTAINMENT PROGRNt
_ STATUS Or TEST PROGR/RS Jask
. Data for Perfoming Phenoneta Testing Comietton of No. _
Descrfatton Acency/Fectitty
$cale_
fleing Tes ted, Fluid Testino Co m ets 3.2.1 Colu:m Buckling TES/TES N/A Dynamic Laad N/A February 1977 Test Capactty (Complete)-
-~
3.2.2 Ring Header /Yent Bechtel/
N/A Load Capacity N/A Indefinite Task put on hold on April 25. 1978.
Pipe Intersection Anamet Test Reactivation of task will depend upon identification of need.
5. '.1 Monticello S/RV CE/NSP full S/RV Discharge Afr/
July 1976 Ramshead Test Loads Steam (Co plete) 5.1.2 Honticello S/RY GE/NSP Full S/RV Discharge Afr/
December 1977 Quencher Test Loads Steam (Complete) 5.2 4T lifgh Temperature '
Tests CE/CE full Chugging Hall 8 Steam July 1976 Mark !! configuration.
Vent Loads (Complete) s 5.3.2 Flexible Cylinder EPRt/DS!
1/6 &
Fluid / Stricture Water.- July 1977 Tests 1/3 Interactico-1 rent (Complete) l(eader 5s3.3 Flexible Cylinder CE/NSC Tests 1/4 Flufd/Strtcture Afr/ Water November 1977 Interactic<n-Vent (Conplete)
Iteader 5.4 Seismic Slosh CE/SWRt 1/30 Selsmic Slosh Water fuly1977 Loads / Vent (Complete) - - -
Uncovering 5.5.1 1/4-Scale 20 Test CE/NSC 1/4 Pool Swell Air November 1976
- Scaling Lasts (Complete) 5.5.2 1/4-Scale 2D Test CE/NSC 1/4
- Download Air October 1977 Oscillattoos (Complete) 5.5.3 1/4-Scale 20 Test CE/NSC 1/4 -
LOR Loads Air October 1978 Plant tmfque matrix and Vent (Complete)
Deflector Parametric Tests.
e t
s
.[
PARIC ! CON ~AINMENT PROGRA9
~,
STATUS OF TEST PROG 9AMS Test Date for
.Perfoming Phenomena Testing Completton of No.
Deserfptfon Agency / Facility Scale
,Befno Tested Fluid Testino Coments 6.6.1 1/12-Scale 30 Test EPR!/ SRI 1/12 Pool Swell Loads Air July 1978 (Corrplete) 5.6.2 1/30-Scale 30 Test GE/SWRI 1/30 Torus /tylinder Air September 1977 Qualftative supplement to 5.6.1.
~
Geometry (Complete)
.5.8 1/12-Scale 20 Test GE/CE 1/12 Fool Swell Air October 1976 Scaling Laws (Complete) 5.11 Full Scale 30 Test CE/Braun Full Chugging Steam August 1978 (Complete) 5.13 1/12-Scale 30 Test GE/NUTECH 1/11 Chugging Steam September 1977 Qualf tative multivent effects.
(Complete)
- [-*
5.14 Submerged Structures GE/Wyle 1/3 Steady State &
Afr/
June 1977 m
Transient Drag Steam (Complete)
Loads GE/NSC 1/4 Subrnerged Loads Afr January 1978 (Conplete)
CE/SWP.!
N/A Components of Water February 1978 Dro9 (Complete) 5.15.2 Structural / Hydro.
CE/Aerothem 1/12 Fluto/ Structure Steam April 1978 Flat plate enly. Desfgn level %
, dynamic Interactions (Coriplete) feptemented.
5.16.1 Reduced Submergence GE/GE Licensee Full Chugging Steam
- April 1977 Testing at Mark I submergence levels.
(Con:plete) 5.16.2 Chugging Hitigation GE/CE Licensee Full f.huggtng Steam May 1977 Testing mitigator at Mark I submergence.
~
(Complete) 5.17 Condensa tion GE/ARAP 1/12 -
Condensation Steam August 1978 Parametric testing.
Oscillation Oscillattom (Complete)
I
6 I
(
f.VK*! CON 1ATEdtTPROGRN!
t STATUS OF TEST PROGRt.MS Cate for Task Performing Phenomene Testing Co pletion of I
Na Descrfation Agancy/ Facility Scste Being Tested Fluid Testino Coments l
6.l.1 Chugging Parametrics GE/NUTECH 1/12 Chugging Steam Harch 1977 Scoping parametrics.
(Complete) j CE/Creare 1/12 Chugging Steam July 1977 Scaling parametrics.
i 1/6,1/4 (Complete) 6.1.2 Chugging Mittgation GE/NUTECH 1/12 Chugging Steare March 1977 Scoping attigation.
(Conplete)
GE/Creare 1/6
,, C!xgging Steam September 1977 Hittgation screening.
(Complete) s
=
6.2.1 5/RY GE/NUTECH 1/12 5/RV Discharge Steam June 1977 Mitigation confirmation.
Loads (Conplete) l CE/NUS 1/4 5/RV Discharge Steam
, July 1978 Quencher parametrics.,
Loads. Phase I (Complete)
Phase II October 1978 iluencher parametrics.
(Complete) 6.3.1 Pool Swell Scr'eening ' CE/NUTECH 1/12 Pool Swell Air September 1976
~5creen'ing tests.
~~'
Downloads (Complete) 6.3.2 Pool Swell Hitigation GE/NSC 1/4 Pool Swell Air November 1977
. Qualification tests.
(Complete) 6.3.3 Vent Header Device CE/fGC 1/4 Pcol Swell Air November 1977 Vent impact m'tigation.
(Conplete) 7.5.2 T-Quencher The'rmal GE/NSP full Pool Theneal' Steam November 1978 MIxin9 H.Afng. Phases (Complete)
I & !!
e f
.