ML20212E469
| ML20212E469 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/23/1986 |
| From: | Mark Miller Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8701050333 | |
| Download: ML20212E469 (27) | |
Text
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Docket Nos.: 50-424 and 50-425 3 DEC 1986 2
APPLICANT:
Georgia Power Company FACILITY:
Vogtle Units 1 and 2
SUBJECT:
SUMMARY
OF HEETING HELD DECEMBER 15, 1986, ON NUCLEAR SERVICE COOLING WATER (NSCW) WATER HAMMER ISSUE On December 15, 1986, the staff met with the applicant and its representatives to discuss the Vogtle NSCW water hamer issue.
Participants are listed in l.
The applicant's slides are contained in Enclosure 2.
The applicant explained that during a water hammer test of the NSCW system, two inadvertent water hammers occurred. The second water hammer was of primary concern. The applicant indicated that a computer model was used to estirate the. peak pressure location in the NSCW system for the restart transient; test instrumentetion was then located at the system high pressure point and selected i
low points.
In its presentation, the applicant emphasized that the duration of the transient was very low (on the order of 50 msec). The applicant estimated j
that the actual test water hammer produced a reak oressure of 900 lbs.
Following this water hamer event, the heat excharger was tested for leakage and none was found.
One snubber was danaged in the event. This snubber was replaced by a larger one.
In response to point I concerning Vogtle plant layout compared to other plants the applicant indicated that layout is plant-specific.
In response to point 3, the applicant indicated that.a loss of offsite power event will not occur in combination with an OBE, hence calculations were not provided.
The staff requested that the applicant submit calculations showing the effect of 900 lbs, on piping stresses along with a sumary discussion of meeting topics and why the estimated 900 lb. stress is conservative.
The applicant stated that this submittal would be to the staff by December 23, 1986, Melanie A. Miller, Project Manager PER Project Directorate #4 Division of PWR Licensing-A
Enclosures:
As stated r
cc: See next page y
rfph'R.-A PAEB/DPWR-gA /
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MEETING
SUMMARY
DISTRIBUTION Docket File NRC Participants NRC PDP M. Miller L PDR R. Bosnak NSIC R. Ballard PRC System J. Brammer PWR#4 Reading File G. Bagchi
'1 M. Duncan OGC-Bethesda J. Partlow E. Jordan B. Grimes ACRS (10)
OTHERS bec:
Licensee A Service List
[eng(o UNITED STATES
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p, NUCLEAR REGULATORY COMMISSION
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3 DEC 1996 2
Docket Nos.: 50-424 ard EC-425 APPLICANT:
Georgia Power Company FACILITY:
Vogtle Units 1 and 2
SUBJECT:
SUl?ARY OF MEETING HELD DECEMBER 15, 1986, ON NUCLEAR SERVICE C00 LING UATER (NSCW) WATER HAMMER ISSUE Gn December 15, 1986, the sta'f r.et with the apolicant and its representatives to discuss the Vcgtle NSCW water hamer issue.
Participants are listed in.
The opplicent's slides are contained in Enclosure 2.
The apclicant explained that during a water harrer test of the NSCW system, two inadvertent s.ater hemmers occurred. The secnnd water hanmer was of primary concern. The applicant indicated that a computer model was used to estimate the pee.k pressure location in the NSCW system for the restart transient; test instrt.rrntation was then located at the systen high pressure point and selected low points.
In its presentation, the applicant emphasized thct the duration of the transient wee very low (on the order of 50 msec). The applicant estimated that the actuci test water hammer produced o peak pressure of 900 lbs.
Following this water hammer event, the beet exchanger was tested for leakage ar.d none n.as fot.no. One snubber was damaged in the event. This snubber was replaced by a larger one.
In response to point 1 cor.cerning Vogtle plant layout corrpared to other plants the applicant indicateo that laycut is plant-specific.
In resper.sc to point 3, the ctrifcant indicated that a loss of offsite power event will not occur in combination with an OBE, hence calculations were not provided.
The staff reevested that the applicant submit calculations showing the effect cf SCO lbs. on piping stresses along with a sumary discussion of meeting topics and why the estimated 900 lb. stress is conservative. The applicant stated that this submittal would be to the staff by December 23, 1986
/
N Pelanie A. Miller, Project Manager PWR Project Directorate e4 Division of PWR Licensing-A Enclosuret:
As stated cc:
See next page
Mr. J. P. G'Reilly Crorria Power Company Vogtle Electric Generating Plant cc:
fir. L. T. Cueva Pesidtn* Inspector Chief hi'cirt.r Engineer Nuclear Regulatory Comission Georgia Power Corpany P. C. 1ox 572 P.O. Boy 45a5 Waynesboro, Georgia 30830 Atlanta, Georgia 30302 lr. huble A. Thomas Depoish Kirklanti, III, Counsel i
Vier Fru,icent - Licensing Office of the Consuners' Utility Vogtle Project Council Georgia Power Company /
Suite 225 Scutterr Cemeany Services, Inc.
37 Peachtree Street, N.W.
P.O. Box 26?5 Atlanta, Georgia 30303 Birminghero, Aldben:a 35202 Udmes E. Joiner F.y. Lu:ald O. Foster Troutman, Sanders, Lockertan, Vice Fresident & Project Gercral Peraper 8 Ashmore Georgia Power Company Lancler Building Post 0"irr Ec.y 2994, Route 2 127 Peachtree Street, N.E.
llaynesboro, Georcia 30830 Atlanta, Georgia 30303 Danny Feig A. Eailey 1130 Alta Avenue ir, t.
Frcject Licensing Manager Atlante, Georgia 30307 Southern CerTr.ny Services, Inc.
P.O. Box 2625 Carol Stengler Cirringham, Alabama 3520?
rrcrgians Against Nuclear Energy 425 Euclid lerrace Ernest L. Blake,sr.
Atlanta, Georgia 30307 i
Bruce U. Churchill, Esq.
Shaw, Pittn n, Potts and Trowbridge
?300 N Street, N lf.
Washington, 0. C.
20037 Mr. G. Sockholti, 1r.
Vogtle Plant Manager Georgia Fcwer Company Route 2, Box 299-A
!!ayrett rre, Georgia 30830 Regional Aaministrator, Region II U.S. fsuclear Regulatory Cormiission 101 liarietta Street, f..l!., Suite 2900 Atlantt, Cterpie 30323 t'r. R. E. Conway Senior Vice President and Project Director Georgia Power Correry Rt. 7, P. O. Box 299A Waynesboro, Georgia 30630
_ _-=
i Participants NRC SOUTHERN COMPANY SERVICES PC Miller J. Bailey R. Bosnak R. Thomas R. Ballard O. Batum J. Branoer G. Eagchi BECHTEL GEORGIA POWER COMPANY A. Es1cai L. Sucwa R. Elded R. Rogers J. Ecsner S. Khurana G. Wang T. Yuan S. Fried P. McDaniel D. Capito I
e 4
NSCW SYSTEM ULTIMATE HEAT SINK i
n 8o o
FUNCTION SUPPLY COOLING WATER TO MISC SAFETY AND NON-SAFETY RELATED j
HEAT EXCHA EERS E
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CONFIGURATION TWO TRAIN SYSTEM. ONE NORMALLY ON.
THREE 501 CAPACITY PUMPS PER TRAIN o
OPERATIE MODES SPRAY MODE BYPASS MODE AUTO RESTART AFTER L.O.P.
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NSCW RESTART AFTER LOP SECONDS lf 0 4
LOSS OF 0FFSITE POWER.
SYSTEM DRAINING DIESELS START AND READY TO ACCEPT LOAD y 'L 15 PUMP DISCHARGE VALVES AND TOWER VALVE START TO CLOSE.
ISOLATION 30 PUMP DISCHARGE VALVES FULLY CLOSED.
x 35 TOWER VALVE FULLY CLOSED.
1r 40 TWO NSCW PUMPS START.
TOWER VALVE STARTS TO OPEN.
SPARE NSCW PUMP STARTS IF REQUIRED.
45 TOWER VALVE OPEN Al4D STOPS IN THIS POSITION.
SEQUENCER STEPS COMPLETED.
.1 SLOW REFILL
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JL 100 PUMP DISCHARGE VALVES FULLY OPEN.
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PRESENT THE LOAD COMBINATIONS AND ACCEPTANCE CRITERIA (SPECIFICALLY CODE REQUIREMENT, CODE EDITIONS, ETC) i 1
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LOAD' COMBINATIONS j,
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UPSET CONDITION 1
COMPONENTS I
P0 + DW + OBE P0 + DH., (OBE + >RV0)
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DW + TH + OBE + EQ + BS DH + TH + [(OBE + EQ) + >RV0)] + BS 3
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DH + TH + RVC + BS j
o SHORT DURATION TRANSIENTS ARE NOT COMBINED WITH OBE o
CODE DESIGN CONSIDERATION - ASME CODE 1974 SUMMER 75 i
J NC/ND - 3611.3 j
ALLOWABLE STRESSES FOR NORMAL, UPSET, EMERGENCY AND FAULTED CONDITIONS l
REFERS TO DESIGN SPECIFICATION FOR DEFINITION LOAD CONDITIONS DESIGN SPECIFICATION REFERENCES DC-1017 FOR LOAD COMBINATIONS i
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PROVIDE SAMPLE CALCULATIONS FOR THE ANALYSIS OF THE TRANSIENT l
(WATER HAMMER): PEAK STRESSES FOR THE TRANSIENT IN COMBINATION WITH PERHAPS OBE, SINCE LOSS OF OFFSITE POWER IS LIKELY TO OCCUR
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IN THE EARLY PHASES OF AN OBE.
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PROVIDE THE DETAILS OF VALVE OPENING SEQUENCES, AND INDICATE HOW AN INADVERTENT OPENING OF A VALVE TO A LARGER OPENING ANGLE IS ACCOUNTED FOR, IN THE PEAK STRESS ESTIMATE FOR CRITICAL PIPING AND COMPONENT SECTIONS.
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Fyn2A - l 2-NSCW RESTART AFTER LOR g4 W SECONDS
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30 4
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sr 35 4
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7c 40 TOWER VALVE STARTS TO GPEN.
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IT APPEARS THAT CERTAIN ORIFICES HAVE UNDERGONE PERMANENT DEFORMATION.
DESCRIBE THE MANNER IN WHICH THE LINES INCORPORATING THE ORIFICES
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ARE DESIGNED AND ANALYZED FOR THE ANALYSIS OF THE RECORD.
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SEVERAL PRESSURE TRANSDUCERS HERE DAMAGED DURINO CERTAIN TESTS.
DESCRIBE THE LOCATION OF THE INSTRUMENTS AND PROVIDE JUSTIFICATION FOR THE ASSUNPTION THAT THE SYSTEM CANNOT BE SUBJECTED TO A GREATER PRESSURE SURGE THAN THAT RECORDED AT THE FIXED INSTRUMENT LOCATIONS.
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REF. PG. 12. LAST PARAGRAPH (TRAIN A)
WHERE IN THE CODE IS THE BASIS FOR ALLOWING SYSTEM DESIGN PRESSURE TO BE EXCEEDED BY 20% FOR LESS THAN 11 0F THE TIME? (NC/ND 3811.l(c)(2)
STATES THAT WHEN LEVEL B APPLIES, THE PEAK PRESSURE ALONE SHALL NOT EXCEED 1.1 TIMES THE PRESSURE, P....)
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REF. PG. 13 (TRAIN B) 4 A.
WHAT IS BASIS FOR FIRST " BULLET" - 1.5 X P HYDROSTATIC TEST l
REQUIRED FOR CLASS 3 SYSTEMS?
B.
THE REMAINING FOUR " BULLETS" PRESENT QUALITATIVE STATEMENTS THAT REQUIRE CLARIFICATION.
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The hydrostatic pressure has a margin of approximately Sol of material yield strength based on Code requirements.
o The overpressure duration is extremely short.
It is a single peak of approximately 50 milliseconds or less and is not enough to lift relief valves.
o Stresses on piping and components from 20 to 40 cycles of short duration have no effect on the pressure boundary and are significantly below the material endurance limit.
o The use of hydrostatic pressures as an acceptance criteria for extremely short duration pressure pulses has been verified by discussions with vendors and a consultant.
o The peak pressure is less than the piping minimum wall allowable pressure and there is no danger of pressure burst.
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COMPONENT ACTUAL MINIMUM MATERIAL HYDRO PEAK YIELD ENDURANCE PRESSURE PRESSURE CALCULATED STRESS STRENGTH LIMIT COMPONENT MATERIAL (psig)
(psig)
(KSI)
(KSI)
(KSI)
DG JACKET 90-10 CI-NI WATER HEAT SA-111 225 220 2.7 15 10 EXCHANGER TUBES GR. 706 DG JACKET STAINLESS WATER HEAT STEEL 225 220 8.4 38 24.5 EXCHANGER HEAD GR-70 ESF CHILLER 90-010 CU-NI CONDENSER SA-111 225 200 2.7 15 10 TUBES GR. 706 ESF CHILLER CARBON CONDENSER STEEL HEAD SA-285 225 200 16 30 19.3 GR. C REACTOR 90-10 CU-NI CAVITY COOLER SA-111 300 260 4.1 15 10 TUBES GR-706
' NOTE - HYDROSTATIC TEST PRESSURE IS CONSERVATIVELY USED AS THE SYSTEM PEAK PRESSURE IN THE STRESS CALCULATION.
STRESS DATA j
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