ML20137F752
| ML20137F752 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/27/1997 |
| From: | Capra R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137F758 | List: |
| References | |
| NUDOCS 9704010202 | |
| Download: ML20137F752 (8) | |
Text
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p.Merugk UNITED STATES g
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001
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COMMONWEALTH EDISON COMPANY m
MIDAMERICAN ENERGY COMPANY DOCKET NO. 50-254 DVAD CITIES NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No. 175 License No. DPR-29 1..
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 26, 1997, as supplemented March 27, 1997, 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 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 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 Commission'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 amendment, and paragraph 3.B. of Facility Operating License No. DPR-29 is hereby amended to read as follows:
9704010202 970327 PDR ADOCK 05000254 P
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B.
Technical Specifications t
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 175, 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 and j
shall be implemented immediately.
l FOR THE NUCLEAR REGULATORY COMMISSION
^
Robeat A. Capra, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications i
Date of Issuance: March 27, 1997 1
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1 UNITED STATES s
j NUCLEAR REGULATORY COMMISSION i
2 WASHINGTON, D.C. 3066H001 COMMONWEALTH EDISON COMPANY AND MIDAMERICAN ENERGY COMPANY l
DOCKET NO. 50-265 OllAD CITIES NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 171 License No. DPR-30 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Comonwealth Edison Company (the licensee) dated March 26, 1997, as supplemented March 27, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's
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rules and regulations set forth in 10 CFR Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the l
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 the Comission's regulations; j
l D.
The issuance of this amendment will nct be inimical to the common i
defense and security or to the health ui safety of the public-I and j
E.
The issuance of this amendment is in accordance with 10 CFR l
Part 51 of the Commission's regulations and all applicable j
requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-30 is hereby amended to read as follows:
r
B.
Technical Soecifications The Technical Specifications contained in A>pendices A and B, as revised through Amendment No.171, are here)y 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 and shall be implemented immediately.
FOR THE NUCLEAR REGULATORY COMMISSION M'
Robert A. Capra, Director Project Directorate III-2 Division of Reactor Projects - III/IV Office of N.xlear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: brch 27,1997
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ATTACHMENT TO LICENSE AMENDMENT NOS. 175 AND 171 FACILITY OPERATING LICENSE NOS. DPR-29 AND DPR-30 DOCKET NOS. 50-254 AND 50-265 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment numbers and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4.7-24 3/4.7-24 3/4.7-25 3/4.7-25 5.4 5.4 i
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CONTAINMENT SYSTEMS SBGT 3/4.7.P 1
-3.7 - LIMITING CONDITIONS FOR OPERATION 4.7 - SURVEILLANCE REQUIREMENTS P.
Standby _ Gas Treatment System P.
Standby Gas Treatment System Two independent standby gas treatment Each standby gas treatment subsystem subsystems shall be OPERABLE.
shall be demonstrated OPERABLE:
1.
At least once per 31 days by initiating, APPLICABILITY:
from the control room, flow through the HEPA filters and charcoal adsorbers OPERATIONAL MODE (s) 1,2,3 and *.
and verifying that the subsystem operates for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with the i
heaters operating.
ACTION:
2.
At least once per 18 months or (1) i 1.
With one standby gas treatment after any structural maintenance on the I
subsystem inoperable, restore the HEPA filter or charcoal adsorber
[
inoperable subsystem to OPERABLE housings, or (2) following painting, fire i
status within 7 days, or:
or chemical release in any ventilation zone communicating with the j
a.
In OPERATIONAL MODE (s) 1,2 or subsystem by:
l 3, be in at least HOT SHUTDOWN i
within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in a.
Verifying that the subsystem i
COLD SHUTDOWN within the satisfies the in-place penetration following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and bypass leakage testing acceptance criteria of < 1 % and b.
In OPERATIONAL MODE *,
uses the test procedure guidance in suspend handling of irradiated fuel Regulatory Positions C.5.a, C.5.c in the secondary containment, and C.S.d of Regulatory Guide CORE ALTERATION (s), and 1.52, Revision 2, March 1978, and operations with a potential for the system flow rate is 4000 cfin draining the reactor vessel. The i10 %.
i provisions of Specification 3.0.C are not applicable, b.
Verifying within 31 days after removal that a laboratory analysis j
2.
With both standby gas treatment of a representative carbon sample subsystems inoperable in obtained in accordance with OPERATIONAL MODE (s) 1,2 or 3, Regulatory Position C.6.b of restore at least one subsystem to Regulatory Guide 1.52, Revision 2, OPERABLE status within one hour, or March 1978, meets the laboratory be in at least HOT SHUTDOWN within testing criteria of ASTM-D-3803-the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD 89, for a methyl iodide penetration SHUTDOWN within the following of < 2.5%, when tested at 30*C l
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
and 70% relative humidity; and i
When handling irradiated fuelin the secondary containment, during CORE ALTERATION (s), and operations with a potential for draining the reactor vessel.
QUAD CITIES - UNITS 1 & 2 3/4.7-24 Amendment Nos.175 & 171
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CONTAINMENT SYSTEMS S8GT 3/4.7.P 3.7 - LIMITING CONDITIONS FOR OPERATION 4.7 - SURVEILLANCE REQUIREMENTS 3.
With both standby gas treatment c.
Verifying a subsystem flow rate of
)
subsystems inoperable in 4000 cfm 110% during system i
OPERATIONAL MODE *, suspend operation when tested in handling of irradiated fuelin the accordance with ANSI N510-1980.
secondary containment, CORE ALTERATION (s), and operations with a 3.
After every 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> of charcoal potential for draining the reactor vessel.
adsorber operation by verifying within The provisions of Specification 3.0.C 31 days after removal that a laboratory are not applicable.
analysir of a representative carbon sample obtained in accordance with i
Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, l
meets the laboratory testing criteria of ASTM-D-3803-89, for a methyl iodide penetration of <2.5%, when tested at l
30*C and 70% relative humidity.
4.
At least once per 18 months by:
a.
Verifyiig that the pressure drop across the combined HEPA filters and charcoal adsorber banks is
<6 inches water gauge while operating the filter train at a flow rate of 4000 cfm i10%.
b.
Verifying that the filter train starts j
and isolation dampers open on each of the following test signals:
- 1) Manual initiation from the i
control room, and
- 2) Simulated automatic initiation i
signal.
c.
Verifying that the heaters dissipate 30 i3 kw when tested in accordance with ANSI N510-1589.
This reading shallinclude the appropriate correction for variations in voltage.
When handling irradiated fuelin the secondary containment. during CORE ALTERATION (s), and operations with a potential for draining the reactor vessel.
QUAD CITIES - UNITS 1 & 2 3/4.7-25 Amendment Nos. 175 & 171
CONTAINMENT 5.2
' 5.0 DESIGN FEATURES w
52 CONTAINMENT Confiouration 5.2.A The primary containment is a steellined concrete structure consisting of a drywell and suppression chamber. The drywell is a steel structure composed of a sphericallower portion, a cylindrical middle portion, and a hemispherical top head. The drywell is attached to the suppression chamber through a series of downcomer vents. The drywell has a rninimum free air volume of 158,236 cubic feet. The suppression chamber has an air region of 120,800 to 117,300 cubic feet and a water region of 111,500 to 115,000 cubic feet.
Desian Temoerature and Pressure 5.2.8 The primary containment is designed and shall be maintained for:
1.
Maximum internal pressure:
56 psig.
2.
Maximum internal temperature: drywell 281'F.
suppression pool 281*F.
- 3.. Maximum external pressure:
drywell 2 psig.
suppression pool 1 psig.
5.2.C The secondary containment consists of the Reactor Building and a portion of the main steam tunnel and has a minimum free volume of 4,716,000 cubic feet.
l QUAD CITIES - UNITS 1 & 2 54 Amendment Nos. 175 & 171