ML19253A763
| ML19253A763 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, 05000234 |
| Issue date: | 08/13/1979 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19253A764 | List: |
| References | |
| NUDOCS 7909110192 | |
| Download: ML19253A763 (28) | |
Text
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UNITED STATES tf. },
e-NUCLEAR REGULATORY COMMISSION 3
g WASH WG TON, D. C. 20555
- o. - Pyf i N..v.. f COMMONWEALTH EDIS0N COMPANY DOCKET N0. 50-237 DRESDEN NUCLEAR POWER STATION UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated May 16, 1977, as supplemented by filing dated November 3, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Connission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the oublic, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No. DPR-19 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 44, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
?
/.< k W Thomas A#f ppolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 13, 1979 m.
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ATTACHMENT TO LICENSE AMENDMENT fl0. 44 FACILITY OPERATING LICEtiSE fl0. DPR-19 DOCKET NO. 50-237 Replace the following existing pages of the Technical Specifications with the attached revised pages. Changed areas on the revised pages are shown by a marginal line.
Remove Pages Insert Pages 88 88 93 93 93A 94A
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DPR-19 4.G SURVEILLANCE ItEQUlilEMr NT 3.6 LIMI FING CONDITION FOR OPERA TION B.
Pressurization Temperature B.
Pressurization Temperature 1.
Reactor Vessel shcIl temperature and 1.
The reactor vessel shall be vented and reactor coolant pressure shall be per-power operation shall not be conduct manently recorded at 15 minute intervals unless the reactor vessel temperature whenever the shell temperature is below is equal to or greater than that shown in 220*F and the reactor vessel is not vented.
Figu re 1. G. I.
2.
When the reactor vessel head bolting studs 2.
The reactor vessel head botting studs are tightened or loosened the reactor ves-shall not be under tension unicss the set shel! temperature immediately below temperature of the vessel shcIl immedi-the head flange shall be permanently ately below the vessel flange is 1120*F.
recorded.
3.
Neutron flux monitors and samples shall
{;
g be installed in the reactor vessel adjacent to the vessel wall at the core midplane p
level. The momtor and sample program shere possible conform to ASThi Q(
9 E 185.
The monitors and samples will be removed and tested as out-
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lined in Table 4.6.2 to c:< peri-fM mentally verify the calculated values of integrated neutron flu:c that are used to determine NDTT for Figure 4.6.1.
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C.
Coolant Chemistry C.
Coolant Chemistry 1.
The reactor coolant system radioactivity As e of me m&R concentration in water shall not exceed shall'bc taken at least every 20 microcuries of total iodine per ml of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and analy::ed for radio-activity, w a t e r.
b.
Isotopic analysis of a sample of O
reactor coolant shall be made 05 at least once por month.
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2,
88 Ainenduient flo. 44
DPR-19 the vessel flange have an NDT temperature of tensioning of the studs. Therefore, the mini-60*F.
The design life of the reactor vessel is mum temperature of the vessel shell immediate-10 years and the maximum fast reutron expo-ly telow the vessel flange is established as I7 sure at -10 fears is c,'culated to be 2.7 X 10 Co* F + 60* F, or 120* F.
nyt.
Numerous data are available relating integrated The NDT temperature limit curve in Figure flux and the change in nil-ductility transition
- 1. 6. I uses the " worst case" cu rve of the SA R temperature (NDTT) in various steels. The to establish the NDT temperature shift and is, most conservative data has been used in Spect-the re fo re, based on more conservative pre 3-fication 3. 0.
The integrated flux at the vessel sure data. For exampl(, the expected NDT wall is calculated from core physics data and l,',
t( mperature hift for ll.is vessel at 2.7 X 10 will be measured using flux monitors installed ns t s expecteil to be 15*F instead of the Du'F inside the vessel. The measurements of the ssumed in establishir.g Figare 1.91.
Figu re neutron flux at the vessel wall will be use.1 to c.
3
.l.6. I aldo incor;> orates a 60*1' factar of safety, check ar.d if necessary corrt et, the e ticulated llas factor is based upon the s stirements of data to determina an accurate NDTT.
the AME code and the considt ations which resulte l in thesc.cquirements. W re fore, in addition vessel material samples will be lo-the specification provides for "w orst case" cated within the vessel to monitor the affect of dat, as well as 60*F of margin to provide neutron exposure on these materials. The y
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mu rance that operation in the non-ductile samples include specimens of base metal, weld region will not occur.
zone metal, heat affected zone metal, and ca standard specimens. These samples will re-The reactor vessel head flange and the vessel ceive neutre,n exposur e more rapidly than the flange in combination with the double "0" ring vessel wall material and therefore will lead type deal are designed to provide a leak-tight the vessel in integrated neutron fhtx exposure.
seal when bolted together. When the vessel These samples will provide further as8urance head is placed on the reactor vessel, only that that the shift in NDT F used in the specification poition of the head flange near the inside of is conservative.
the tcs'el rests on the vessel flange. As the head bolts are replaced and tensioned, the The uithdraual schedule in Table 4.6.2 is based vessel head is flesed alightly to bring together on the three capsule surveillance progra2a as the entire contact surfaces adiacent to the "0" defined in Section ll.C.3.a of 10 Cn150 Appendi::
i nngs of the head and vessel flange. The clo-H.
The ace 31erated capsule (Near Core Top Guide)
C sure flanges aad connecting shell materials are not recuired by Appendix H but vill ha Ci have an NDT temperature of 10'F, and they are tested to provide cdditional information on the
/'
not subject to any appreciable neutron radia-vessel raaterial.
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tion exposu re.
Ilow ever, the vertical electro-This surveillance program conf orms to ACT:: P 135-slag seams terminating immediately below the 73 Recoramonded Practice for Surveillance Testa w
t vessel flange have an NDT temperature of for nuclear Reactor Vessels" uith onc c::ception.
W O* U, and they are moderately stressed by
'ii.e base ractal specimens of the vessel vero made with their longitudinal axes parallel to the principle rolling direction of the vessel plato.
93 Amendment flo. 44
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Tabic 4.6.2 DPR-19 Neutron Flu:< and Sa:aples Withdrawal Schedule fo:: Drcsden Unit 2 Withdraual Yea:.
Part No.
Location Comments 1977 6
Near Core Top Accelcrated Sampic Guide - 1800 1980 8
Wall - 2150 2000 7
Wall - 950 9
Wall - 2450 Standby 10 Wall - 2750 Standby D
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s tru w 9 *. A Amendment No. 44 0 7 < 7.n}
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'h NUCLEAR REGULATORY COMMISSION y*
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W ASHINGTON, D. C. 20555 5
COMMCNWEALTH EDISCN CCMPANY DOCKET NO. 50-249 DRESDEN STATION UNIT NO. 3 APENOMENT TO FACILITY OPERATING LICENSE Amendment No. 39 License No. DPR-25 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Comonwealth Edison Company (the licensee) dated May 16, 1977, as supplemented by filing dated November 3,1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by tnis amencment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of tne public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragracn 3.5 of Facility Operating License No. DPR-25 is hereby amencec to read as # allows:
3.
Tecnnical Soecifications The Tecnnical iceci#ications contained in Accendix A, as revised tnrougn Amendment No. 39, are hereoy incorporatec in the license.
The licensee shall operate the facility in accordance with the Tecnnical Specificaticns.
".!h g., c- < e u s
2-3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas d.jIppolito, C'hief Operating Reactors 3 ranch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 13, 1979 f
a,
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ATTACHMENT TO LICENSE AMEllDMEllT NO. 39 FACILITY OPERATIflG LICEllSE NO. DPR-25 DOCKET fl0. 50-249 Replace the following existing pages of the Technical Specifications with the attached revised pages. Changed areas on the revised pages are shown by a marginal line.
Remove Pages Insert Pages 88 88 93 93 93A 94A o. - r -,, -., 3 J G riim t):. e
DPR-25 3.6 LIMIl'ING CONDITION FOlt OPEIIA FION 4.G SUltV EILLANCE ItEQUillCMr'NT D.
Pressurization Temperature U.
Pressu rization Temperature 1.
The reactor vessel shall be vented and 1.
Iteactor Vessel shell temperature and reactor coolant pressure simil be per-power operation shall not be conducted manently recorded at 15 minute intervals unless the reactor vessel temperature whenever the shell temperature is below is cegual to or greater than that shown in 220*1' and the reactor vessel is not vented.
Figu re 4. G.1.
2.
.The reactor vessel head bo: ting studs 2
When the reactor vessel head botting studs shall not be under tension unless the are tightened or loosened the reactor ves-temperature of the vessel shell
<nedi-set shel' temperature immediately below the head flange shall be permanently ately below the vessel flange is
.0*F.
recorded.
3.
Neutron flux monitors and samples shall be instatted in the reactor vessel adjacent h
to the ve.,sel wall a! the core midplane level. The monitor and sample pro;; ram C ~~~3 Q where possible conform to AS T E 185.
The monitors and samples C'~~3 h will be removed and tested as out-lined in Table 4.6.2 to e:: peri-h mentally verify the calculated values of integrated neutron flux p'
that are used F.o determine UDTT for Figure 4,6.1.
C.
Coolant Chemutry C.
Coolant Chemistry 1.
The reactor coolant system radioactivity 1.
a.
A sample of reactor coolant concentration in water shall not exceed shall be uaken at leas every 20 microcuries of total lod.me per ml of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and analyzed for radio-activity.
w at e r.
g b.
Isotopic analysis of a sample of f.f reactor coolant shall be made 3) at least once per month.
'J 88 Amendment No. 39
DPR-25 the vessel flange have an NDT temperature of tensioning of the studs. Therefore, the mini-6 0
- 1'.
The design life of the reactor venel is mum temperature of the vessel shell immediate-10 u ars and the maximum fast neutron expo-ly below the vessel flange is established as I7 sur'e at -10 years is calculated to be 2.7 X 10 60* F + 60* F, or 120* F.
nyt.
Numerous data are available relating intt grated
'll e NDT t(mperature limit curve in Figure flux and the change in nil-ductility transition 1.6. I uses the " worst case" curve of the SAR temperature (NDTT) in various steels. T he to establish the NDT temperature shift and is, most conservative data has beer. used in Speci-t he re fo re, based on more conservative pres-fication 3. G.
The integrated flu at the v-el soi e data. For examp!c, the espected NDT uali is calculated from core physics data and temperature shif t for this vessel at 2.7 N 10 will be measured using flux monitors installed I7 m i is especte.1 to be 15*r instead of the 90'F inside the vessel. The measurements of th" awomed in establishmg Figure 1.G;1.
Figure neut ron flux at the vessel w all will be use.I to
- a. o.1 also meorporates a Go*F factor of safety.
check av.d if necewary correct, the cateulated
'I his factor is based upon the requirements of data to determine an accurate NDTT.
t he A:Oll. code and the consideratians w hicn resulted m these requirements. The re fo re, in addition, vessel material samples will be lo-the specibeation provides for "wordt case" cateil within the vessel to mor.i:or the affect of u
data as w ell as bu'F of margin to provide r.ent ron esposure on tl.ede mee r.als. The C
ar u rance that operation in the non-ductile samples include specimens of base metal, ucld h
region u ill not occur.
zone metal, heat affected zor.e metal, and standard specimens. These samp'es will re-The reactor vessel head flange and the vessel ceive neutron exposure raore rap.dly than the flange in combination with the double "0" ring sessel wall material and therefere will lead type seal are designed to provide a leak-tight the vessel ir. integrated neu;ron f!ux exposure.
seal u hen bolted together. When the vessel These samples uill provide for:hcr assurance t ~~~~3 head is placed on the reactor vessel, only that that the shift in NDT F used in tae specification U
portion of the head flange near the insule of is conservatise.
the vessel rest 3 on the vessel flange, As the head hedts are r< placed and tensioned, the The uithdraual schedcle in Table 4.6.2 is bcscd vessel head is flesed sbghtly to bring together on the three capsule surveillance progra:a as the ent.re contact surfaces adiacent to the "0" defined in Section ll.C.3.a of 10 CFR 50 c.p,aendix rmgs of the he:ul and veeccl flange. The clo-II.
The accelerated capsule (near Core Top Guido) sure flanges and cannecting shell materials are not recuired by ?.ppendix II but will be p]
have an SDT temper. eire of 10*F, and they are tested to provide additional information on the f
4, not st.bject td any af Jiable neutron radia-vessel material.
tion exposure. H r, the vertical electro-
)
This surveillance program conf orms, to I.ST.. n 105-slag seams terma, immediately belo.v the 73 " Recommended Practice for Surveillance Testa e 4\\
vessel flange have...i SDT temperature of for Nuclear Reactor Vessels" uith one enccptior..
60*F, and they are moderately stressed by The base metal speci-.cns of the vessel uere made with their longitudinal axes parallel to tha principle rolling direction of the vessel plate.
Amendment No. 39 93
DPR-25 C.
Coqljut Chemistiv - A radioactivity cor. centra-t tion limit of 20 oCi/ml total indine can be reached if the c.ascous efilu. nts are near the li: nit as set foi th in.Specificalion 3. 8.C.1 or there is a failure or a prolont;cd shutdown of the cleanup demine ali/cr. In the event of a sica:n line ru pt u re, outside the drywe:1, the resultant radiolo;;ical dose at the site boundary wouhl be about 10 rent to the thyroid. This <iose was caletalated on the basis of a total iodine activity lwsit of 20 pCi/ int, meteorology corresponding
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6' 93A Amendment No. 39
Tabic 4.6.2 DPR-25 Neutron Flux and Samples Withdraual Schedule for Dresden Unit 3 Withdraual Year Part No.
Location Conur.c nt s 1979 16 Near Core Top Accclcrated Sample Cuide - 1800 1981 18 Wall - 2150 2001 17 Wall - 950 19 Wall - 2450 Standby 20 Uall - 2750 Standby 9'. A Amendment No. 39 i
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UNITED STATES 3'
,4 NUCLEAR REGULATORY COMMISSION 3,N L j WASHINGTON, D. C. 20555 Y+.4f E
%.% y CCMMCNWEALTH EDISON COMPANY AND ICWA ILLINDIS GAS AND ELECTRIC COMPANY COCKET NO. 50-254 QUAD CITIES NUCLEAR POWER STATION UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. DPR-29 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Comonwealth Edison Company (the licensee) dated May 16, 1977, as supplemented by filing dated November 3,1978, complies with the standards and requirements of the Atcmic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 3.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be
- onducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comen defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as incicated in the attachment to this license amend-ment, and paragraph 3.3 of Facility Ccerating License No. DPR-29 is hereby amenced to read as follows:
S.
Technical Scecifications The Technical Scecifications.cntainec in Accencices A and 3, as revised througn Amendmen-No. 53, are nereby incorcoratec in the license.
The licensee s1all ocerate the facility in accorcance witn :ne Tecnnical Spacifications.
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. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION A
h 2wS.,
Thomas
/Ippulito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 13, 1979 Q;cor-v u ve...p
ATTACHMENT TO LICENSE AMENDMENT fl0. 53 FACILITY OPERATING LICENSE NO. DPR-29 DOCKET N0. 50-254 Replace the following existing pages of the Technical Specifications with the attached revised pages. Changed areas on the revised pages are shown by a marginal line.
Remove Pages Insert Pages 3.6/4.6-2 3.6/4.6-2 3.6/4.6-9 3.6/4.6-9 3.6/4.6-9A 3.6/4.6-21A g*
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QUAD.clTIES CPR-29 k'
that shown in Figure 3 6-l. The reac-belove 2207 and 'ne reactor vessel is tor vessel shall not be pressurized not ventei above 250 psig untess the reactor ves.
- 2. Neutron flux rnonitors and set temperature is equal to nr ereater sampics shall be installed than 190' F w hen fuct is ir. tite reactor in the reactor vessel adjacent.
vessel.
to the vesrel wall at the core 2.
For isothermal inservice hydrostatic midplane lovcil.
The monitor tests, full test pressures shall be per.
and sampic program shall con-missible on the venel above the limit.
form to ASTM E 185-66.
The monitors and semples shall be ing pressuriration temperature as removcci and tested in accordan shown in Firure 3.6-1. Fer isothermal inservice hydrostatic tests conducted with.:he guiaelines set forth in 10CFR50 Arpen lix H between 140' F and the limiting pres.
surization temperature shown in Fig-ure 3.6-1, test pressures shall be lim-
, te experim ntally s erify the calcu-ited to 1/2 of the vessel operating lated values ofinte.7. rated neutten 'lus presst.re (500 psig).
that are used to determine the ND1T for Figure 3.6-l.
- 3. The reactor vessel heat botting studs
- 3. When the reactor vessel head bolting shall not be under tension unicss the studs are tightened or lossencJ. the temperature of the vessel shell imme-reactor sessci shcIl temperature imme-diately below the vessel flan 6: is diately below the head flange shall be 2 100' F.
permanently recorded.
C C.
Coolant Cl.emistry C.
Coolant Chemistry A sample of reactor coolant shall 1.
The steady-state radioindine concen-1.
a.
tration in the reactor coolant shall not he taken at lent ev.ry 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> exceed 5 pCiofl 131 dose cqinvalent and anslyzed for radioactive io-per gram of water.
dines ofI-131 through I 135 dur-ing power operatioa. In addition, when chimne) monitors indicate an increase in radio.ctive gaseous effluents of ?$^o* or 5000 pCi/sec.
I D' whichever is greater, during l
steady-state reactor operation, a i
i reactor coolant sampic shall bc I $
yl[, "-
taken and analyzed fer radioactive iodines.
- b. An isotopic analysis of a reactor coolant samp!e shall be made at least once per month.
c.
Whenever the steady-state ra-dioindine concentration of prior operation is greater than 19 but less than 10 7o of Specifice. tion 3.6.C.I a sample of re.u tot coolant shall be taken within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of
. r m, 4 -V.. i ant r-r
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Amendment No. 53 3.6/46-2 m.m q o-e
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DPR-29 a Jd_ dla 1 a
n' region shifts to higher temperatures when the thickness of the specimen tested is increased (si effect).
Accordingly, a conservatise reactor vessel pressurization temperature as a function of fast neutron exposere is presented H Figure 3.6-1 to cover ' worst-caw hmits required during reactor power operation. This curse is based c.a an initial S DlT of the s essel shell electrostag welds adjace of 40' F plus 100' F to assure an adequate fracture touchnea for small thnLnew material plus a 5 mar $ n to account for the hickness effect of heavy seuion steel to give 100' F mmimem temperature i
nst. At that time, the from initial operation to the time w hen the neutron Duence excceds 5 x IOS mit imum temperature will increase steaddv as the neutron Ouence increases based on the Norst cas curve relating the change in transition temperature to neutron Duence shown in Figure 4.2 2 of the For temperatures below the limiting pressuritatior, temperature, the vess:1 presure will be lim psig during reactor startup and shutdown operationt The total stress level mcludinc hoop transient thermal stress in the reactor vessel during startup and shutdown operation for internal prenures of 250 psig is approximately the same as the reactor veuel hoop strew incurred during isothe
- u. internal pressure of 500 psig. Therefore during isottermal hydrostatic tests at hydrostatic testing &
500 psig, the pressurization temperature may be below the curve shown in Fi ure 3.6-1 but a E
140' F.
The reactor vessel head Dange and the vessel Gange in combination with the double 0 ring type seal are designed to pros rde a leakught seal w hen bolted topther. When the vesf ri head is placcd on the re vessel, only that portion of the head fiante near the inside of the sessel rests an the vcuel Gange. A head bolts are rep ated 2nd temioned, the vessel head is Resed sli; htly to hung together the entire cont.nt i
surfaces adjacent to the 0 rings c f the heau and seuel flange The slosure Ganges ard tonnect.ng sh materials have an NDTT of 10' F, and they are not subject to any appreciable neutron radiation
(..
exposure. However, the vertical electroslag seams terminating immediately below the vessel 11a an NDTT of 40' F.and they are moderately stressed by tensioning of the studs Therefore, the nurnmun temperature of the vessel shellimmediately oclow the vesselllange is established 45 40' F + 60* F 100
- F.
Numerous data are availabic reiring integrated flux and the change in NDTT ;n various steels 1he mc.st conservative data has been used.n Specif.tation ?.6. The integrated flux at the vessel wall is calculated from core physics data and will be measured using flux monitors installed insid the vessel The measurements of the neutron ilux at thc sessel wall will be es:d to check and if necenary correct the esteulated data to determine an accurate NDTT.
In addition, vessel material samples will be located within the sessel to monit. r the effect of neutron exposure on these materials. The samples include specimens of base metal, wc!d zona metal zone metal, and standard specimens.These samples will receive neutron esposure ntore r.ipidly th.in the vessel wall material and wdl therefore lead the vessel in integrated neutron tius exposure. The.e samples will provide further assurance that the shift in NDTT used in the speci5 cation is conservative.
The withdrawal schedule in Table 4.6.2 is baced on the three capsule surveillance prograra as defined in Section ll.C.3.a of 10 CFR 50 Appendix H.
The acccicrated capsule (Ucar Core Top Guide) are not rcriuired by Appendix 11 but will be tested to provide additional information on the veccel material.
This surveillance progra_n conforms to ASTM E 185-73 " Recommended Practice for Surveillance Tests for Nuclcar Reactor Vecccls" with one e::ception.
The base metal specimenu of the ves cl were made with their longitudinal a::cs parallel to the principle rolling direction of the vesccl plate.
3.6/4.6-9 Amendment No. 53 q ~. m.,
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QUAD-CITIES DPR-29 C.
Coolant Chemistry A steady state radiciodine concentration limit of 5 pCi of1131 dose equivaient per gram of water in the reactor coolant system can be reached if the grou radio.tetivity in the gaseous (t?luents are near the limit as set forth in Specification 3 8.C.1 or there is a failure or piolonged shutdown af the ci, anup demineralizer. In the event of a steamline rupture outs;de the drywell, the NRC sta:T calculations show the resultant radiological dose at the site boundary to be less than 30 rem to the thyroid. Thii dose was Ci of f-131 do.e equivalent per gram calculated on the basis of the radiciodine concentration limit of 5 s
of water, atmospheric ditTusion from an elevated release at 30 meters under fumigation conditions for Pasquill Type F, I meter per second wind speed, and a steamfit.c infation vahe ciosure time of 5 (s.
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3.6/4.6-9A Amendment No. 53 o ;c n.
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DPR-29 Table 4.6.2 I
Revised Withdrawal Schedule for Quad-cities Unit 1 Withdrawal Year Part No.
Location __
Comments 1982 8
Wall - 2150 2002 7
Wall -
950 9
Wall - 2450 Standby 5
Wall -
650 Standby 0
10 Wall - 275 Standby 1981 4
Near Core Top Guide -
900 1984 6
Near Core Top Guide - 1800
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3.6/4.6-21A Amendment No. 53 g.,_,,,
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UNITED STATES f
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'k NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 gv f COMMCNWEALTH EDISON COMPANY AND IOWA-ILLINDIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES STATION UNIT N0. 2 AMENCMENT TO FACILITY OPERATING LICENSE Amendment No. 50 License No. OPR-30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for a
.1dment by the Commonwealth Edison Company (the licensee) dated May 16, 1977, as supplemented by filing dated November 3, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; 3.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comisison; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amend-ment, and paragrapn 3.3 of Facility Ocerating License No. DPR-30 is hereby amended to read as follows:
3.
Technical Scecifications a pendices A and The Technical Specifications contained in c
3, as revised through Amencment No. 50, are hereby incorporated in the license.
The licensee shall operate the facility in accorcance with the Technical Specifications.
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- 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 9,<'~'t U honds d[.,VIppolito, Chief Operating Reactors Branch #3 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
August 13, 1979 a -, n m a..
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ATTACHMENT TO LICENSE AMENOMENT NO. 50 s.
FACILITY OPERATING LICENSE NO. DPR-30 DOCKET N0. 50-265 Replace the following existing pages of the Technical Specifications with the attached revised pages. Changed areas on the revised pages are shown by a marginal line.
Remove Pages Insert Pages 3.6/4.6-2 3.6/4.6-2 3.6/4.6-9 3.6/4.6-9 3.6/4.6-9A 3.6/4.6-21A a_,....,.
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QU AD-Cl fil'S DPR-30 that shown in Figure 3 61. The reac-below 220'F and the reactor sessel is tor vessel shall not bc pressurized not vented.
above 250 psig unless the reactor ses-
- 2. Neutron flux monitors and set temperature is equal to or cicater samples shall be installed than 190' F when fuelis in the reactor in the reactor vessel adjacent vessel.
to the vessel wall at the core 2.
For isotherma' inservice hydrostatic midplano level.
The monitor tests, full test pressures shall be per-and campic program shall con-missible on the vessel above the limit-form to AST 1 1; 185-66.
The monitors and samples shall be ing pressurization temperature as removed and tested in accordar.1 shown in Fqure 3.6-1. For isothctmal inservice bsdrostatic tests conducted with the guidelines set forth in 10C1'n50 Appendi:: II between 140' F and the li:niting pres-surization temperature shown in Fig-ure 3.61, test pressures shall be lim-
, to experim,ntally verify the calcu-ited to 1/2 of the vessel operating lated salues ofintegrated neutren aus that are used to Jetermine the ND'IT pressure (500 psig).
for Fig.ure 3.6 l.
- 3. The reactor vessel heat behing studs
- 3. When the reactor vessel head bolting
- hall not be under tension unless the studs are tightened or louened, the temperature of the vessel shell imme-reactor sessel shell temperature imme-diately below the vessel flange is crateiv below the head flange shall be 2 100' F.
perm.nently recorded C.
Coolant Chemistry C.
Coolant Chemistry A sample of reactor coolant shall
- 1. The steady-state radiciodine concen-1.
a.
tration in the reactor coo! ant shall not be taken at leau cvery 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> exceed 5 Ci of I 131 dose equivalent and analyicd for radioactive io-per gram of water.
dines of I-131 through I-135 dur-ing power operatica. In addition, when chimne) monitc,rs indicate an increase in radio;.ctive pseous effluents of 25~c. or 5000 Ci/sec, whichever is greater, during steady state reactor operation, a g
reactor coc,! ant sample shall be D h taken and analyzed for radioactive U
- b. An isotopic analysis of a reactor g
Q coolant samp!e shah be made at U
least once per inonth.
c.
Whenever the steady-state ra-diciodine concentration of prior operation is gicater than !"c but less than 10% of Specif; cation 3.6 C.I. a sample of textor coolant shall be taken within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of any tr'-
e e to, W uni 0 e
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3.6 / 4.6-2 Amendment No. 50 9 <
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S, n) U m J W m region shifts to higher temperatures when the thickness of the specimen tested is increased (site s.
effect ).
Accordingly, a conservative reactor vessel pressurization temperature as a function of fat neutron exposure is presented in Figure 3.61 to covcr ' worst-ccse* limits required during reactor pcwer operation. This curve is based r.a an initial ND'lT of the veuel shell cicctrushg w ela adjacent to the of 40' F plw 100' F to assure an adequate fracture toughnee for small thict.nsss materul plus a 50' margin to account for the :hickness eTect of heavy section stee! to give 190* F minimum temperature nvt. At that time, the from initial operation m the time when the neutron fluence exceeds 5 x IOS mir.imum temperature will inercase steadily as the neutron fluence increases based on the 'aorst case' curve relating the change in transitton temperature to neutron fluence shown in Ficure 4.2-2 of the SA For ternperatures below the limiting pressurization temperature, the vesst! pressure will be lirn.te psig during reactor startup and shutdown operations. The total rtress level including hoop s transient thermal stress in the reactor vcue! durm; startup and shutdow n operation for internal pressures of 250 psig is approximately the same n the reactor vessel hoop stress incurred daring isotherm hydrostatic testing at an internal pressure of.%0 psig. Therefore during isothermal hydrostatic tests.it 500 psig, the pressuriration temperature ntay be below the curve shown in Figure 3 61 but above 140' F.
'ne reactor sessel head flange and the vessel f%ge in enmhination with the double Oqing typ scal are designed to provide a IcaLtight seal w hen bolted together. When the vessel head is placed on the reactor vessel only that portion of the head fiange near the mside of the seuct rests an the vcuct flange. As the head bolts are replaced 2nd tensioned.the venel head is flexcd shchtly to bang together the entire cont.a t surfaces adjacent to the 0-rings (,f the heaw and seuct flange. The 61osure flanges and conr.cct;ng shell materials have an NDTT of 10' F. and they are not auhject to a ty appreciable neutron radiation exposure. However, the vert cal electroslag seams terminating immediately below the veswl llan i
("
an NDTTof 40' F.and thcy are moderately stressed by tensioning of the studs.Therefore, the nummum temperature of the vessel shellimniediately below the vessel flange is established as 40
- F + 60* F 100* F.
Numerous data are available rela:ing integt ated flux and the change in NDTT :n various steels The most conservative data Fas been used in Specification 3.6. The integrated flut at the ve: sci wall is calculated from core physics data and will be measured using flux monitors installed msid the scoc! The measurements of the neutron flux at the vessel wall will be es:ci to check and if necewary corrett the ci!culated data to determanc an accurate NDTT.
In addition vessel material samples will be located within the senel to moniter the e!!ect of neutron netal, wc!d zona metal heat afreeted exposure on these materiah. The sampics include specimens of bas:
zone metal, and standard specimens. These sample > wdl receive neutron esposure more rapidly than the vessel wall material and will therefore lead the vewel in i0tegrated neutron flux exposure. 'I hc.e sample 3 will provide further assurance that the shift in NDTT used in the specirication is conservative.
The withdrawal schedule in Table 4.6.2 is based on the three capsule surveillance program as defined in Section ll.C.3.a of 10 CFR 50 Appendix II.
The accclerated caocule (idear Core Too Guide) a.e not recuired by Appendix II but vill be tected to -
provide additional information on the vessel material.
This surveillance program conforms to AST.11 E 185-73 "Recorame nded Practice for Surveillance Tcntc for Nuclear Reactor Vecccls" with one exception.
The bac ractal specimens of the vescel were raade with their longitudinal a::cc parallel to the principle rolling direction of the vessel plate.
3.6/4.6-9 e,. n.M, a..~
Amendment No. 30 i
QUAD-CITIES DPR-30 C.
Coolant Chemistry A steady-state radiciodine concentration limit of 5 Ci ofI 131 dose equivalent per gram of water in the reactor coolant system can be reached if th gross radioactivity in the gaseous efIluents are near the limit as set forth in Specification 3 S.C.I or there is a failure or piolonged shutdown of the cle.inup demineralizer. In the event of a steamline rupture out>ide the drywell. the NRC stafrcalculations show the resultant radiological dose at the site boundary to be less than 30 rem to the thyroid. This dose was calculated on the basis of the radiciodine concentration limit of 5 pCi of!-131 dose equivalent per gra 1 of water, atmospheric dithsion from an elevated release at 30 meters under fumigation conditions for Pasquill Type F. I meter per second wind speed. and a steamlinc isolation valve closure time of 5 (t
seconds.
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3.6/4.6-9A Amendment No. 50
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DPR-30 Table 4.6.2 Revised Withdrawal Schedule for Quad-cities Unit 2 Withdrawal Year Part No.
Location Comments 1982 18 Wall - 2150 2002 17 Wall -
950 19 Wall - 2450 Standby 15 Wall -
650 Standby 0
Standby 20 Wall - 275 1980 14 Near Core Top Guidt. -
00 190s 16 Near Core Top Guide - 1800 3.6/4.6-21A Amendment No. 50 n.. c
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