ML19350D130
| ML19350D130 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 03/27/1981 |
| From: | Crutchfield D, Ippolito T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19350D131 | List: |
| References | |
| NUDOCS 8104130465 | |
| Download: ML19350D130 (16) | |
Text
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q UNITED STATES 8i NUCLEAR REGULATORY COMMISSION h,'b)l /
n WASHING TON, D. C. 20665 Q*....
COMMONWEALTH EDISON COMPANY DOCKET NO. 50-237 DRESDEN STATION UNIT NO. 2 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 57 License No. DPR-19 1.
The Nuc1 car Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated May 22, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conmission's rules and regulations set forth in 10 CFR Chaptdr 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 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 ininical to the connon 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.
0104130 s
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. 2.
Accor_dingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional 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.57, are hereby incorporated in the license. The licensee shall operate the fac.ility in accordance with the Technical Specifications.
't 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k,
Dennis M. Crutchfield hief Operating Reactors Br nch #5 4
l Division of Licensing i
Attachment:
Changes to the Technical 4
Specifications Date of Issuance: March 27,1981 f
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ATTACHMENT TO LICENSE AMENDMENT NO. 57 PROVISIONAL OPERATING LICENSE NO. bPR-19 DOCKET NO. 50-237 Revise the Appendix "A" Technical Specifications by removing Page 89 and replacing it with the attached revised Page 89.
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3.6 ' LDitTING CONDITION FOR OPERATION 4.6 SURVE!LLANCE REQUIRDIENT l
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2, During startups and at steaming rates 2.
The 'rcactor cooland wn't' r shall not-below 100,000 pounds per hour, a o
exceed the folloutng limits with,steitming sample of reactor coolant shall be takes rates tuas than 100.000 pounds per hour overy four hours and analyzed for con-except as specified in 3.G.C.3:
ductivity and chloride content.
Coluluctivity 2 pmho/cm S.
a.
With steaming rates greater Chloride ton 0.1 ppm than or equal to 100,000 puunds per hour, a reactor coolant 3.
For reactor startups the maximum value sampic shall be taken at 1 cast for conductivity shall not exceed 10 pmho/
every S0 hours and 'when the
- cm amt the maximum value for chtgride continuous conductivity monitors Ion concentration shall not exceed 9 1 ppm, indicate abnormal conductivity for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after placing the (other than short-term spikes),
reactor in the power operating condition.
and analyzed for conductivity and chloride ton content.
1.
Except as specified in 3.G.C.3 above, the reactor coolant water shall not exceed b.
When the continuous conductivity the following limits with steaming rates monitor is inoperable, a reactot greater than or equal to 100,000 pounds coolant sampic should he taken per hour, at least daily 4hd analyzed for conductivity and chloride ion Comiuctivity 5 pmho/cm
- content, Chloride ton 0.5 ' ppm s-,
5.
If Specification 3.6.C.1, 3.6.C.2, 3.fl.C.3 or 3.6.C.4 is not met, an orderly shutdown shall be lattiated.
D.
Coolant Leakage
. D.
Coolant Lenkage Reactor coolant system leakage shall be l
Any time Irradiated Asel is in the reactor checked by the sump and al'r sampling vessel and reactor coolant temperature is-system.
Sump flow monitoring and above 212'F, reactor coolant leakago into fecording shall bo performed once the primary containment from unidentified per shift.
Air sampling shall be sources shall not exceed 5 gpm. In addition, the total reactor coolant system leakage into performed once per day
- thu prlinary containment shall nut exceed an ui si. i s dia.ia u...in s..... na. ot i>=... 4, 89 Amendment No. If, 57
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UNITED STATES
[N NUCLEAR REGULATORY COMMISSION g
E WASHINGTON, D. C. 20555
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COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 DRESDEN STATION UNIT NO. 3 AMENDMENT TO FACILITY nPERATING LICENSE Amendment No. 50 License No. DPR-25 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated May 22, 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 confomity 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 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' 2.
Accordingly, the license is amended hy changes to the Technical Specifications as' indicated in the attachment to this license amendment and Paragraph 3.B of Facility Operating License No.
DPR-25 is herehy amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 50, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications...
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Q&
Thomas K."Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: March 27,1981 i
J ATTACHMENT T0 LICENSE AMENDMENT NO. 50 FACILITY OPERATING LICENSE NO. DPR-25 DOCKET NO. 50-249
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Revise the Appendix "A" Technical Specifications by removing Page 89 and replacing it with the attached revised Page 89.
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3.6 LI!!! TING CONDITION F0lt OPERATION 4.6 SURVEILLANCE REQUIREMENT 2.
The 'rcactor' coolant water shall not 2.
During startups and at steaming rates exceed the following limits with, steaming below 100,000 pounds per hour, a rates loss than 100,000 pounds per hour sample of reactor coolant shall be taken~
except as specified in 3.ti.C.3:
every four houra and analyzed for con-ductivity and chloride e,ontent.
Conductivity 2 pmho/cm Chloride ton
- 0. I ppm 3.
a.
With s. teaming rates greater than or equal to 100,000 pounds 3.'
For reactor startups the maximum value per hour, a reactor coolant for comiuctivity shall not exceed 10 pmho/
sample shall be taken at least cm and the maximum value for chloride every 06 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and when the ~
lon concentrallon shall not exceed 0.1 ppm, continuous conductivity monitors for the first 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> after placing the indicate abnormal conductivity reactor in the power operating condition, (other than short-term spikes) and analyzed for conductivity 4.
Except as spec! fled in 3.G.C.3 above, and chloride ton content.
the reactor coolant water shall not~ excecd the following limits with steaming rates b.
When the continuous conductivity i
grenier than or equal to 100,000 pounds monitor is inoperable, a reactor per hour.
coolant sample should be taken at least daily 4hd analyzed for Comiuctivity 5 p mho/cm conductivity and chloride ton Chlorido Ion O'.5 ppm content.
i 5.
If Specification 3.6.C.1, 3.6.C.2, 3.6.C.3 or 3.6.C.4 la not met, an orderly shutdown shall be initiated.
.g D.
Coolant Leakage D.
Coolant Leakage Any time Irradiated fuel is in the reactor Resetor coolant system leakage shall be
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vessel and reactor coolant temperature is checked by the sump and alr sampling above 212*F reactor coolant leakago into system.
Sunnp flow monitoring and the primary containment from unidentified recording shall be performed once sources shall not exceed 5 gpm. In addition, per shift.
Air sampling shall be f
the total reactor coolant system leakago into perforsned once per day
- 1 the primary cimtninment shall not exceed
- a m.....
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u..n.iii to... o.....ot i,.... 4, 89 Amendment No. 50
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UNITED STATES y ) )"r. g (,g NUCLEAR REGULATORY COMMISSION
'9g WASHINGTON, D. C. 20555 g-
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l COMMONWEALTH EDISON COMPANY AND IOWA ILLINOIS GAS D ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES STATION UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 65 License No. DPR-29 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated llay 22, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (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 Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (!i) 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; l
and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements l
have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-l ifications as indicated in the attachment to this license amendment l
and paragraph 3.8 of Facility License No. DPR-29 is hereby amended l
to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.65, are hereby incorporated in the ifcense.
The licensee shall operate the facility in accordance with the Technical Specifications.
.-2 3.
This license amendment is effective as of the date of its issuance.
t FOR THE NUCLEAR REGULATORY COMMISSION
/)
n Thomas'N. Ippolito, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications
- Date of Issuance: March 27,1981
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ATTACHMENT TO LICENSE AMENDMENT No. 65 i
FACILITY OPERATING LICENSE NO. DPR-29 DOCKET NO. 50-254 i
Revise Appendix A Technical Specifications by removing page 3.6/4.6-3 and replacing with the enclosed page.
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QUAD-CITIES i
DPR-29 thrcugh I 135.
- d. Whenever the steady-state ra.
diciodine concentration of prior operation is greater than 10% of Specification 3.6.Cl, a sample of reactor coolant shall be taken prior to any reactor startup and ana-lyzed for radioactive iodines of I 131 through I.135 as well as the coolant sample and analyses re-quired by Speci6 cation 4.6.Cl.c above.
- 2. The reactor coolant water shall not 2.
During startups and at steaming rates exceed the following limits with below 100,000 lb/hr, a sample of reac-steaming rates less than 100.000 lb/hr for coolant shall be taken every 4 except as specined in Specification hours and analyzed for conductivity 3.6.C3:
and chloride content.
conductivity 2 pmho/cm chloride ion 0.1 ppm
- 3. For reactor startups, the maximum 3,
a.
With steaming rates greater than value for conductivity shall not esceed or equal to 100.000 lb/hr, a reac-10 pmho/cm, and the maximum-tor coolant sample shall be taken value for chloride ion concentration at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and when shall not exceed 0.1 ppm for the drst the continuous conductivity moni-24 hours aner placing the reaCfJr in tors Indicate abnormal conductiv-the power operating condition.
icy (other than short term spikes)
- 4. Except as specined in Specincation and an-lyzed for conductivity and 3.6.C3 above, the reactor coolant
- hloride ion content.
water shall not exceed the fo!!owing
- b. When the continuous conductivity limits with steaming rates greater than monitor is inoperable, a reactor or equal to 100,000 lb/hr:
coolant sample should be taken at conductivity 10 mho/cm I'*** daily and analyzed for con-ductivity and chloride son chloride ion 1.0 ppm content.
- 5. If Specideation 3.6.C l, 3.6.C2, 3.6.C3, or 3.6.C4 is not met. an or-derly shutdown shall be initiated.
D. Coo!act Leakage D. Coolant Leakage
- 1. Any time irradiated fuelis in the reac-Reactor coolant system leakage shall 'be lor vessel and reactor coolant tempera-checked by the sump and air sampling system, ture is above 212
- F, reactor coolant Sump flow monitoring and recording leakage into the primary containment shall be performed once per shift.
from unidentified sous es shall not Air sampling shall be performed exceed 5 gpm. In addition the total once per day.
reactor coolant system leakage into the i
primary containment shall not exceed 25 gpm.
3.6/ 4.6-3 Amendment No. 65
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION a
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- Y WASHINGTON. D. C. 2MH
/
COMMONWEALTH EDISON COMPANY AND IOWA ILL}NOIS GAS D ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES STATION UNIT NO.2 AMENDMENT TTO FACILITY OPERATING LICENSE Amendment No. 59 License No. DPR 30 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated !!ay 22, 1978, complies with the standards and requirements of the Atomic Energy Act of 1954, as anended (the 1
Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, t
the provisions of the Act, and the rules and. regulations of the Commission; C.
There is reasonable assurance (1) 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 tbs 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 Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this i fcense amendment and paragraph 3.8 of Facility License No. DPR-30 is hereby amended to read as follows:
B.
Technical Specifications i
The Technical Specifications contained in Appendices A and 1
l B, as revised through Amendment No. 59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
/,
. 3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C0lHISSION hf74 Thomas A. Ippolito, Chief Operating Reactors Branch #2
)
Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 27,1981 1
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o ATTACHMENT TO LICENSE AMENDMENT NO. 59 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 Revise Appendix A Technical Specifications by removing page 3.6/4.6-3 and replacing with the enclosed page, i
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QUAD-CITIES DPR-30 thr'ough I I35.
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- d. Whencver the steady state ts-l, diciodine concentration of prior operation is grehter dan 10% of Specincation 3.6.C.I. a sample of reactor coolant shall be taken prior to any reactor startup and ans.
lyzed for radioactive lodines of 1131 through I.135 as weil as the coolant sample and analyses re.
quired by Specincatio t 4.6.C.I.c.
above.
- 2. The reactor coolant water shall not
- 2. During startups and at steaming rates exceed the following limits with below 100,000 lb/hr. a sampic orreac.
steaming rates less than 100.000 lb/hr for coolant shall be taken every 4 except as specided in Specification hours and analyzed for conouctivity 3.6.C.3:
and chloride content.
conductivity 2 pmho/cm chloride ion 0.1 ppm
- 3. For reactor startups, the maximum 3.
a.
With steaming rates greater than value for conductivity shall not exceed or equal to 100.000 lb/hr, a reac.
10 pmho/cm, and the maximum tor coolant sample shall be taken value for chloride ion concentration at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and when shall not exceed 0.1 ppm for the Arst the continuous conductivity mon!.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> aner placing the reactor in tors indicate abnormal conductiv.
the power operating condition.
ity (other than short term spikes) analyzed for conhetivity and,
an 4.
Eacept as speciAed in SpeciAcation c ride ion content.
l 3.6.C.3 above, the reactor coolant water shall not exceed the following
- b. When the continuous conductivity limits with steaming rates greater than monitor is inoperable, a reactor or equal to 100.000 lb/hr:
coolant sample should be taken at conductivity 10 mho/cm least daily and analyzed br con-ductivity and chloride son chloride ion I.0 ppm content.
- 5. If Specincation 3.6.C. I.
3.6.C.2, 3.6.C.3, or 3.6.C.4 is not met. an or.
der *y shutdown shall be initiated.
t D. Coslant tankage D. Coolant I4akage
- 1. Any time irradiated fuelis in the reac-Reactor coolant system leakage shall be tor vessel and reactor coolant tempera.
checked by the sump and air sampling system.
ture' is above 212' F, reactor coolant Sump flow monitoring and recording leakage into the primary containment shall be performed once per shift.
from unidentined sources shall not Air sampling shall be performed i
etceed 5 spm. In addidon. the total l
reactor coolant system leakage into the once per day.
i primary containment shall not exceed 25 gpm.
3.6/44-3 Amendment No. 59