ML19309C218
| ML19309C218 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 02/20/1980 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19309C219 | List: |
| References | |
| NUDOCS 8004080310 | |
| Download: ML19309C218 (8) | |
Text
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O DPR-19 2.6 1.IlllTING CONillflON FOft OPEllATION 4.8 SUltVEILLANCE IIEQUltil:Lil:NT B.
Pressurization Temperature D.
Pressurization Temperature l'
The reactor vessel shall be vented 1.
I:cactor Vessel shcll acmperature newl and power (peration shall not be reactor cool. int picssure sh. ell be per-conducted unless the reactor vessel manently recorded at 15 minute latervals teuperature is equal to or greater uliencver the aliell scinitice;ituse is I,elow than that shown in Curve C 'of r!u'r and the reactoi wes el is not rented.
Figure 3.6.1.
Operation for hydro-static or leakage tests, during 2.
When the reactnr vessel licail liolaing minds heatup or cooldown, and with the sirer H :liscue l or l<mened H.e reactor se.-
core critical shall be conducted sci shcH sciuperature inune hasely behne only when vessel tenverature is equal ths: lica.1 Hanne shah 1.c l.es inanendy to or above that shown in the appro-recoreled.
priate curve of flg. 3.6.1.
figure 3.6.1 is effective through 6 effective 3.
h*catron Hns inonHorn anil marnples steaH full power years. At least six months I'* 3"*'^d#d '" d'e ri: actor vessel a Is.icent
'" U "' "" ""I " " U "' ""
C'" " '" iid '""*
prior to 6 effective full piuer years level. 'Itc nunutor and pample pree;: ram new curves will be sulimitted.
where possible conform to ASTil E 105 The monitors and samples 2.
The reactor vessel head bolting studs will be rernoved and tested as out-shall not be under tension unless the lined in Tablg 4.6.2 to expc 6 temperature of the vessel shell Y9 Y
insnediately below the vessel flange values of integrated neutron flux is >100"F.
that are used to determino HDTT
~
O for Figure 4.6.1.
O C.
Coolant Chemistry o
a C.
Coolant Cheraistry 1.
The reactor coolant system radioactivity conceptration in water shall not exceed 1.
- a. gipple reacjo g g la e
20 microcuries of total lodine per ml 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and analyzed for of water radio-activity.
b.
Isotopic analysis of a sample of Q
reactor coolant shall be mado at least once'per month.
h Amendment No. 44 0
l DPR-19 b) the relationship between RTHDT and ferrectic stools.- Provision has and integrated neutron flux (fluence, been made for the modification of at energies > 1: Hev), and these curves to account for the c) the fluence at the location of a change in nTtIDT as a result of i
postulated flow.
neutron embrittlement.
The initial nTrany of the main closure flange, the shell and head materials connecting to The uithdraual schedule in Table 4.6.2 is based these flanges, and connecting welds is 100F.
on the three capsule surveillance program as llowever, tho vertical electroulag wolds which defined in Section 11.C.3.a of 10 CFR SO Appendin terminate immed iately below the vessel flange The accelerated capsule (licar Coyo Top' Guide) ar n t required by Appendix 11 but will ha have an RTilDT of 400P.
Iteference Appendix F to the PSAlt.
The closure flanges and con-E#9" vessel material.
l nocting shell materials are not subject to any appreciabic neutron radiation exposure
- This surveillance program conforms,to AST:: U 105-73 "acconmended Practice for survaillance. Tests nor are the vertical electroslag seams.
The for tiuclear Reactor Ve scin" uith one c::ception.
flange area is moderately stressed by
'fi.e basa metal specimens of the vessel ucre made tensioning the head bolts.
Therefor 2, as with their longitudinal axes parallel to the is indicated in curves (a) and' (b) of Figure principle rolling direction of the vessel plate.
3.6.1, the minimum temperature of the vessel shell inmiediately below the vessel flange is estabinhed as 1000P below a pressure of 400 psig.
(400F + 600F, where 400P is the ItT f the electroslag weld and 600F is a HDT conservatium required by the ASitE Code).
Above approximately 400 psig pressure, the stresses associated with pressurization are more limiting than.the bolting stresses, a fact that is reficcted in the non-linear portion of curves (a) and (h).
Curve (c),
which defines the temperature limitations for critical core operation, was established per Section IV 2.c. of Appendix G of 10cPn50 Each of the curves,- (a), (b) and (c) de fine temperature limitations for unirradicated 93 t men.imen t fin. 44
DPR,25 3.8 IJnflTINO CONDIl'lON FOft OPEttATION 4.8 StiltVEILIANCE ItrQlllitEktHNT 8.
Pressurization Terrperature II. Pressurization Temperature 1.
The reactor' vessel shall be vented 1.
I:cactor Vessel :.hcIl temperature and and power operation shall not be reactor coulant picssure stiall bo per-conducted unless the reactor vessel manently recorded at 15 minute Intervals tenverature is equal to or greater whenever the t. hell temperatus e I:s below than that shown in Curve C of 220*F ami the reactor vessel is mit vented.
Figure 3.6.1.
Operation for hydro-Static or leakage tests, during 2.
When the reactor vessel heaal holting :. tints heatup or coolduwn, and with the are lightencil or lon ened the seactor vra.-
core critical shall be conducted sei shell temperature inunciliately beli.w only when vessel tenverature is equal the head flange shall I,e pen manently recorded.
to or above that shown in the appro.
priate curve of Fig. 3.6.1.
Fiqure 3.6.1 is ef fective through 6 ef'fective 3.
b'entron Hus monitors ami samples shan i
be instaucal in Hic reactor ves:,el ad acent i
full power years. At least six months to Hic vessel uan at nur con inid: dane prior to 6 ef fective full pmer years I"' C I-
'Ih" '"".nitor aml. ample pro;: ram new curves will be submltted.
where possible conform to AS".'il 2.
The reactor vessel head bolting studs E.185.
Tlu monitors and samples shall not be under tension unless the 9 min and M M as out-4*
~
temperature of the vessel shell m nta gig calcula W inmediately below the vessel flange values of integrated neutron flux is >100*F.
that are used to determine llDTT C.
Coolant Chemistry C.
Coolant Chemistry 1.
The reactor coolant system radioactivity 1.
a.
A samolo of reactor coolant concentration in water shall not exceed shall be taken at least every 20 microcuries of total iodine per el 96 130urs anc,1 analyzed for of water radio-activity.
b.
Isotopic analysis of a sample of reactor coolant shall be made at least once per month.
. Anendment No. 39
_ mm y
[U
- 3 m
n l
l oe,.-25 b) the relationship between RTHDT and ferrectic eteele.- Provision has and integrated neutron flux (fluence, been mado for the modification of at energies > 1.Mev), and these curves to account for the c) the fluence at the location of a change in 11T:397 as a result of postulated flow.
neutron embrittlement.
The initial IITsurr of the main closure flange, the sheti and head materials connecting to The uithdraual schedule in Tabic 4.G.2 in based these flanges, and connecting welds is 100F.
on the tlyree capuule surveillance program as
^EE ""
llowever, the vertical electroslag welds which II.
The accelerateo caosule (Ecar Core Top Guioc) terminate snaned iately below the vessel flange are not required by Asocndix !! but will be-i have an ItT gny of 40')P.
Iteference Appendix P tested to provide add'itional information on the g
to the PSAlt.
The closure flangen and con-vessel material.
necting shell materials are not subject to This surveillance procran confor:as to I.ST;i E 105-any appreciabic neutron radiation exposure, 73 "ltecoramended practice for Surveillance Testa nor are the vertical electroslag seams.
The for Iluclear Itcactor Vessels" uith onc c::ceptior..
The base metal specinens of the vessel uete made flange area is moderately stressed by with their longitudinal axes parallel to the tensioning the head bolts.
Therefore, as U
is indicated in curves (a) and (b) of Figure 3.6.1, t.he minimum temperature of the vessel shell ira:nediately below the vessel flange is estabibbed as 1000P below'a pressure of 400 psig.
(400P + 600F, where 400P is the itT of the electroslag weld and 600F is a yn.p conservatism required by the ASitC code).
Above approximately 400 psig pressure, t.he stresses associated with pressurization are more limiting than.the bolting stresses, a fact that is reflected in the non-linear portion of curves (a) and (h).
curve (c),
which defines the temperature limitations for critical core operation, was established per Section IV 2.c.
of Appendix G of 10cFit50 Pach of the curves, (a), (h) and (c) de fine temperature limitations for unirradicated nendrnent No. 39 93
QUAD-CITIES DPR-29 that shown in Figure 3.61. Operation below 220*F and the reactor vessel is for hydrostatic or !cskage tests, dunng not vented.
hestup or cooldown and with the core critical shall be conducted only when vessel temperature is equal to or
- 2. Neutron flux monitors and above that shown in the appropriate samples shall be installed curve of Figure 3.6.1.
Figure 3.6.1 in the reactor vessel adjacent is effective through 6 EFPY. At least to the vessel wall at the core ax months prior to 6 EFPY new cunes midplanc levnl.
The monitor will be submitted.
l anc3 sampic crogram shall con-form to ACI E 185-66.
The
- 2. The reactor vessel heat botting studs monitors and sampics shall be shall not be under tension unless the Icmovcc; and Ocsted in accordance ternperature of the vessel shell imme.
with the guiciclines set forth diately below the vessel riange is in ICC.e.150 Appendix H 2 100
- F.
to experimentally verify the calcu.
lated values ofintegrated neutron tiux that are used to determine the NDTT for Figure 3.6-1.
- 3. When the reactor vessel head bolting stud 3 are tightened or lossened. the reactor vessel shell temperature imme.
diately below the head riange shall be permanently recorded.
C.
Coolant Chemistry C.
Coolant Chemistry c
- 1. The steady-state radiciodine concen.
I.
a.
A sample of reactor coolant shall tration in the reactor coolant sha!! not be taken at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> exceed 5 pCi ofi 131 dose equivalent and analyzed for radioactive io-per gram of water.
dines of1131 through I.135 dur.
ing power operation. In addition.
when chimney monitors indicate an increase in radioactive gaseous effluents of 25"c or $000 pCi/see, whichever is greater, during steady state reactor operation, a reactor coolant sarnple shall be taken and analyzed for radioactive iodines.
- b. An isotopic analysis of a Teactor coolant sample shall be made at l
least once per month.
c.
Whenever the steady state ra.
diciodine concentration of prior j
operation is greater than I"o but
! css 3.6 / 4.6-2 Amendment No. 53
QUAD-CITIES DPR-29 1.
The reference nilducti!ity temperature (RTNDT) for all vessel and adjoining materials.
2.
The relationship between RTNDT and integrated neutron flux (fluence, at energies > Mev), and 3.
The fluence at the Iccation of a postulated flaw.
The initial RTNDT of the main closure flange, the sheIl and head materials connectmg to these flanges, and connecting welds is 10*F. However, the vertical e!ectroslag welds which terminate immediately below the vessel flange have an RTNDT of 40 F. Reference Appendix F to the Dresden FSAR. The closure flanges and connecting shell materiais are not subject to any apprecirile neutron radiation exposure, nor are the vertical electroslag seams. The flange area is moderately stressed by tensioning the head bolts. Therefore, as is indicated in curves (a) and (b) of Figure 3.6.1, the muumum temperature of the vessel shell immediately below the vessel flange is est:blished as 100*F below a pressure of 400 psig. (40*F + 60*F where 40*F is the RTNDT of the electroslag weld and 60*F is a conservatism required by the ASME Code). Above approxi-mately 400 psig pressure, the stresses associated with pressurization are more limiting than the bolting stresses, a fact that is reflected in the non linear portion of curves (a) and (b). Curve (c), which defines the tempera.
ture limitations for entical core operation, was established pe,r Section IV 2.c. of Appendix G of 10CFR50.
Each of the curves (a). (b) and (c) de:'me temperature limitations for unitradiated ferntic steefs. Provision has been made for the modiilcation of these curves to account for the change in RTNDT as a result f neutron embrittlement.
The withdrawal schedule in Table 4.6.2 is based on the three capsule surveillance pregram as defined in Section 11.C.3.a of 10 CFR 50 Appendix H.
The accelerated cap ule (l* car Core Top Guide) are not required by Appendix 11 but will be tested to provide additional infor=ation en the vessel mater:.al.
This survoillance progra= confor== to AST:13: 185-73 "Reco== ended Practice for Surveillance Tcsts for Nuclocr Reactor Vcscels" with one e::ce stion.
The bacc =ctal specimens of the ves:cl ware macle with tho'ir longitudinal a::es para 11cl to the principle rolling direction of the vessel plate.
D**]O *]D ~9'N c c Ju cJu-3 l
3.6/ L6-9 Amendment No. 53 l
l l
1 t
QUAD-CITIES DPR-30 that shown in Figure 3.61. Operation below 2207 and the reactor vessel is for hydrostatic or leakage tests, dunns not vented.
heatup or cooldown, and with the core entical shall be conducted only when venel temperature is equal to or abov'
- 2. Neutron flux menitors and that shown in the appropriate curve of samples shall be installed Figure 3.6.1.
Figure 3.6.1 is effective in the reactor vessel adjacent through 6 EFPY. At least sx months to the vessel wall at the core prior to 6 EFPY new curves will be midplanc 1 cycl.
The monitor submitted.
and sa:nplo progra:n chall con-form to Asri f; 185-66.
The
- 2. The reactor vessel heat bolting studs shall not be under tension unless the monitors and samples shall be removod and tested in accorciance temperature of the vessel shell imme-with the cuidelincs sct forth diately below the vessel tiange is in 10CFR50 Appendi:: 11 2 100* F.
1 to experimentally verify the alcu-lated values ofintegrated neutron flux that are used to determine the NDTT for Figure 3.6-l.
- 3. When the reactor vessel head bolting studs are tightened or lossened, the reactor vessel shell temperature imme-diately below the head 11ange shall be C
permanently recorded.
C Coolant Chemistry C Coolant Chemistry I. The steady-state radiciodine concen-
- 1. a.
A sample of reactor coolant shall tration in the reactor coolant shall not be taken at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> c
exceed $ Ci or!-13 t dose equivalent and analyzed for radioactive io-per gram of water.
dines ofI 131 through I 135 dur.
Ing power operation. In addition.
when chimney moni: ors indicate an increase in radioactive gaseous effluents of 25% or 5000 pCi/sec, whichever is greater. during steady-state reactor operation. a reactor coolant sample shall be taken and analyzed for radioactive iodines.
- b. An isotopic analysis of a reactor coolant sample shall be made at least once per month.
c.
Whenever the steady state ra.
diciodine concentration of prior operation is greater than 1% but less i
i 3.6/46-2 A=--Ant No. 50 i
l e
QUAD-CITIF.S DPR-30
- 1. The reference ru!4uctdity temperature (RTNDT) for a!! vessel and adjoining materials.
- 2. The relationship between RTNDT and integrated neutron flux (fluence,at energies >l Mev),and
- 3. The fluence at the location of a postulated flaw.
Theinitial RTNOT of the main closure flange, the shell and head materials connecting to these flanges,and con.
necting welds is 10*F. However, the vertical electroslag wesds which terminate immediately below the vessel flange have an RTNDT of 40*F. Reference Appendix F to the Dresden FSAR. The closure flanges and con.
necting shell mater:als are not subject to any apprecable neutron radiation exposure, nor are the vertical electroslag seams. The flange area is moderately stressed by tensioning the head bolts. Therefore, asis indicated in curves (a) and (b) of Figure 3.6.1, the mmimum temperature of the vessel shell immediately below the vessel flange is established as 100*F below a pressure of 400 psig. (40*F + 60*F, where 40*F is the RTNDTof electroslag weld and 60*F is a conservatism required by the ASME Code). Above approximately 400 psig pres.
sure, the stresses associated with pressunzation are more limiting than the bolting stresses, a fact that is reflected in the non4inear portion of curves (2) and (b). Carve (c), which defines the temperature limitsuons for entical core operation, was established per Section IV 2.c of A;:pendix G of 10CFR50. Each of the curves, (a),(b) and (c) define temperature limitations for unirradiated ferntic steels. Provision has been made for the rnodification of these curves to account for the change in RTNDT as a resuh of mitmn em' nnlement.
e l
The withdraual schedule in Tabic 4.6.2 is based on the three capsule survoillance pregram as defined in Section ll.C.3.a of 10 CFR 50 Appendi>: H.
The accclarated caccule (Hear Core Top Guide) a. e noc required by Appendix II but vill be tested to provide additional information on the vc= sci matcrial.
This surveillance program conforms to ASTM E 185-73 "Recc=mcnded Practice for Surveillance Tccts for Nucicar Reactor vessels" with one e:tecption.
The hace metal sFecimens of the vos:cl warc = ado with their icngicudinal a::cs carallel to the principle rolling direction of the vessel plato.
J 1
l l
a I
l 3.6/46-9 Aniendment No. 50