ML20209C508
| ML20209C508 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Diablo Canyon |
| Issue date: | 10/07/1983 |
| From: | Schierling H Office of Nuclear Reactor Regulation |
| To: | Knight J, Kuo P, Wermiel J NRC |
| Shared Package | |
| ML20209B155 | List:
|
| References | |
| FOIA-86-151 NUDOCS 8310200029 | |
| Download: ML20209C508 (8) | |
Text
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- iOTE TO:
J. P. Knight J. Werniel P. T Kuo M. Harztman H. Polk T. Dunning FROM:
H. Schierling
SUBJECT:
DIABLO CANYON SSER 19 SSER 19 is due out Friday, October 14, 1983.
It must cover all issues tha' need resolution prior to fuel load.
It can cover other issues. Attached are scme details.
Schedule is very tight.
Your inouts to me are required as sonn as nossible (even partiel) but no later than Wednesday, October 12, 1983 - 11 ao. All typirc should be done sn it can be transferred to CRESS. Any oues'. inns call ne (x27100).
I t
q us Hans Schierling, Pro.iect 'tanac" Licensing Branch No. 3 Division of Licensing Attacnnent:
As stated cc:
G. W. Knighton 16D o
SSER 19 Fuel Load Recuirements 1.
Open Items resolution / status / commitment / conclusion.on 14 OIs for fuel load, see " items 1" in attachment 1 2.
ITRs attachnent 2 is a list of SSER 18 sections that are incomplete, all ITRS (except Rev. 1 of ITR 65) have been received, closecut to extent necessary for fuel load 3.
Action Items attachment.3 is a list of action items in SSER 18, detenine what is needed for fuel load, present resolution / status 4
Format:
for each item (open item, ITR, Action Item) use Section identification and heading as in SSER 18 state issue as in SSER 18 present resolution / status-l i
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OPEN ITEMS DIABLO CANYDN SER SUPPLEMENT 18 h
1.
Free-nand averaging of spectra for containment annulus structure should be in accorcance with staff approved d---
technique.
(C.3-9) h 2.
Cutoff frecuency of 20 Hz for generation of floor resconse spectra in containment annulus structure should be justified. d.-
(C.3-9) h 3.
Use of AISC Code for design of containment cenetrations should be justified.
(C.3-17)
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h 4
Local yielcing of steel plates arounc coening in containment snoulc be justifiec.
(C.3-17) h 5.
Assumotions in model for auxiliary building ficer slac cuali-fication regarding rigidity / flexibility snoulc ce clarifiec
~and justified, including cocumentation of parametric stacies.
(C.3-22) h 6.
Use of different versions of ACI coce in FSAR and in cesign verification effort of auxiliary builcing snouic be justifiec.
(C.3-22) 7.
Discrecancy between IDVP and DCP sensitivity of soil scring influence on seismic response of auxiliary cuilcing sneuld ce A
reconciled, including resolution of soil precerties anc w
cocumentation of parametric studies.
(C.3-22) h e.
Use of translational and torsional rescanse of auxiliar-building as input to base of fuel hancling builcing snould ce documented, including parametric studies.
(0.3-26) 9.
Selection of set of cegrees of freecem in cynamic mece ice fuel nancling builcing sncule ce justifiec.
'(C.3 ~6; Of 10.
Loac coccinations in analysis of turoine builcinc snoula ce M
clarifiec.
(0.3-36) 3' 11.
Modeling of reof trusses in turbine cuilcing shcolc be clarifiec and justifiec.
(C.3-36) h 12.
Effect of one continuous exterier wal: in analysis of t rcine cuilcing sncule ce evaluated.
G.3-37' 1
Enc!csure 5
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13.
Differences in turbine building modeling of steel frame anc roof truss for two vertical models snould De clarifiec.
(C.3-37) g 14.
The use of alternative procedures for model combinations ey SRSS method should be explained and clarified.
(C.3-37) 15.
Use of increased allowable stresses in accordance with AISC Code 8th Edition should be justified witn respect to criteria delineated in FSAR.
(C.3-37) h 16.
Results of analysis of large bore piping supports should be
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verified.
(C.3-48) h 17.
Buckling criteria for linear supports, specifically the Euler buckling equation for calculating critical buckling loacs A
for all slenderness ratios, should be evaluated and justifiec.
W (C.3-48)
A 18.
Calculations for selected piping systems analyzec previous 1;.-
W in ITR 12 and ITR 17 should be repeated witn revised supcort configurations and current loadings to verify tnat oiping -anc 4
supcorts satisfy corresponding cesign criteria.
Results of Q
piping system reevaluation with hign tnermai lot.c snoulc c3 verified.
(C.3-48) h 19.
Tne scoce of the DCP small bore picing review sncule ce j
clarifiec.
(C.3-57) y h
2C.
All ecuicment listed in Table 2.3.1-1 of CCP Phase I Fina Re ort snould be seismically qualified for no::le loacs anc comoonent configurations snould De verifiec.
(C.3-59; C.3-70' rp 21.
Stresses in extreme fibers at interface between valve cc:: e L
and pice snould be evaluatec anc results ce cocumentec.
(C.3-66) h 22.
Stresses in puno flanges should ce verifiec to te witnir allowable limits.
(C.3-69) 23.
Qualification of cable trays and interaction of trays witn supports snould be accressed.
(C.3-S0) 24 Allowacle limits for welds based on fielc sa cles snuule ce usec in cualification of trays succorted by superstrut.
y (C.3-90) 25.
Total lateral forces, total resistance to slicing anc f act:-
of safety against sliding of intake structure sr.oulc ce fuli:.
evaluated.
(C.3-86) 2 Enc' m re 5
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26.
Additional analyses of buried diesel fuel oil tanks snoulc"ce performed (analyses with refineo mesn and witncut ceconvolution, partially filled tan (, exmamination of properties).
(C.3-99) h 27.
Control circuits for isolation valves in steam supply line for m) 7 turbine driven auxiliary feedwater pump should be classified as safety-related.
(C.4-11).
28.
Auxiliary relay for automatic closure of redundant steam generator blowdown isolation valves should meet Westingnouse requirements.
(C.4-12) h 29.
Censideration of jet impingement loads in design and cualifi-cation of all safety-related piping and equipment snould ce clearly demonstrated.
(C.4-29) 30.
It should be clearly indicated that rupture restraints insice' A
and outside containment have been properly designed anc V
installed.
(C.4-31) 2 Y.
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Diablo Canyon'SER Supplement 18 Requirements of Further Documentation Containment Annulus Structure C.3-9 ITR-51 h
Containment Interior Structure C.3-13 ITR-54 Containment Exterior Shell C.3-17 ITR-54 4.
Auxiliary Building C.3-22 ITR-55 5.
Fuel Handling Building C.3-26 ITR-57 6.
Intake Structure C-3-28 ITR-58 7.
Turbine Building C-3-37 ITR-56 b@
Large Bore Piping C-3.48 ITR-59 Berc h h Large e Piping Supports
^C-3-48 ITR 60 Small Bore Piping C.3-58 ITR-61
')( h Small Bore Piping Supports C.3-58 ITR-60 12.
Mechanical Equipment and Supports C-3-70 ITR-67 13.
HVAC Equipment C.3-73 ITR-31 & 63 p h Raceways, Tubing & Supports C.3-76/77 ITR-63 C.3-80.
15.
Soils-Intake Structure t,. -83 ITR-13 16.
Soils Intake Structure Boring
- -85 ITR-39 Capacity 17.
Shake Table Testing C.3-89 ITR-67 Main Control Board C.3-91 V TLC.e 'svec$
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1 08/31/83 1
DIABLO CANTON SUP iS REQUIR 1.5 Ttg vircc C
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Diablo Canyon SER Supplement 18 I
Action Items a
1.
PG&E will perform a startup test of AFWS runout control system to confirm dynamic stability.
(C.4-3) 3
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2.
PG&E will delete fram design drawing steam trap in steam supply line for turbine driven pump of AFWS.
(C.4-5) 3.
PG&E will revise FSAR to reflect acceptability of as-built conditions regarding separation and color coding of electrical circuits fo.AFWS.
(C.4-8)
N 4.
PG&E will correct table in environmental qualification report with respect to ficw transmitters and flow control valves in AFWS.
(C.4-12) 5.
PG&E will conduct analyses to determine qualified life of motor capacitor for steam generator 'cor. trol valves.
(C.4-12) 6.
PG&E will amend FSAR to indicate that pipe breaks are not postulated in steam supply line to turbine criven pump of AFWS.
(C.4-16) 08/31/83 1
DIASLO CANYON SUF 18 ACT ITEM
E
'7.
PGLE will amend FSAR to ' include all changes for equipmen-qualification (CRVPS and AFWS) that resulted^from reanalysis of pipe break environments within containment.
(C.4-16) a 8.
PG&E will revise FSAR licensing commitments regarding needs for protective shields for AFWS and CRVPS components against 4
effects of moderate energy line breaks.
-(C.4-17) 9.
Staff will confirm that any modifications required in safety-related systems with respect to pressure / temperature rating and power-operated valve ~ operability are implemented.
(C.4-26) 10.
PG&E will verify assumptions regarding closing / opening of coors in their continuing pressure-temperature reanalysis.
(C.4-27) 11.
PG&E will make modifications as necessary based on results of pressure-temperature reanalysis (C.4-27).
12.
Staff will evaluate PG&E results of reanalysis with respect to environmental qualification of equipment.
(C.4-27) l.
E 08/31/83 2
DIABLO CANYON SUP 18 ACT ITEM
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