ML20138D165
| ML20138D165 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/25/1997 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20138D172 | List: |
| References | |
| NUDOCS 9705010050 | |
| Download: ML20138D165 (8) | |
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COMMONWEALTH EDIS0N COMPANY i
DOCKET NO. 50-237 1
DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.158 License No. DPR-19 1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated April 14, 1997, as supplemented on April 17, April 22, and April 24, 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; l
B.
The facility will operate in conformity with the application, the i
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 l
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; i
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable l
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 l
paragraph 2.C.(2) of Facility Operating License No. DPR-19 is hereby l
amended to read as follows:
9705010050 970425
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PDR ADOCK 05000237 P
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(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 158, 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 shall be implemented within 30 days.
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Joh F. Stang, Senior Project Manager P'oject Directorate III-2 r
Division of Reactor Projects - III/IV l
Office of Nuclear Reactor Regulation l
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Attachment:
Changes to the Technical Specifications i
l Date of Issuance: April 25, 1997 l
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WASHINGTON. D.C. 2065M21 1
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COMMONWEALTH EDIS0N COMPANY l
DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 153 License No. DPR-25 I
1.
The Nuclear Regulatory Commission (the Commission) has found that:
l A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated April 14, 1997, as supplemented on April 17, April 22, and April 24, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the j
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 I
provisions of the Act and the rules and regulations of the l
Commission; 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; i
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 witt 10 CFR Part 51 of the Commission's regulations and all applwable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-l cations as indicated in the attachment to this license amendment and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
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Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 153, are hereby incorporated in the license. The licensee shall operate the facility in accordance j
with the Technical Specifications.
l 3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
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johnF.Stang,SeniorProjectManager Pr"oject Directorate III-2 Division of Reactor Projects - III/IV l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications 1
Date of Issuance:
April 25,1997 l
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ATTACHMENT TO LICENSE AMENDMENT NOS.158 AND 153 FACILITY OPERATING LICENSE NO. DPR-19 AND DPR-25 DOCKET NOS. 50-237 AND 50-249 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 I
indicating the area of change.
REMOVE INSERT 3/4.7-23 3/4.7-23
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3/4.7-24 3/4.7-24
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CONTAINMENT SYSTEMS SBGT 3/4.7.P s
37 7_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 heaters operating.
ACTION:
2.
At least once per 18 months or (1) 1.
With one standby gas treatment after any structural maintenance on the subsystem inoperable, restore the HEPA filter or ch1rcoal adsorber inoperable subsystem to OPERABLE housings, or (2) following painting, fire status within 7 days, or:
or chemical release in any ventilation zone communicating with the a.
In OPERATIONAL MODE (s) 1,2 or subsystem by:
3, be in at least HOT SHUTDOWN 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 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 i
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.S.c in the secondary containment, and C.5.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 cfm draining the reactor vessel. The 110 %.
provisions,of Specification 3.0.C are not applicable.
b.
Verifying within 31 days after removal that a laboratory analysis 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 methyliodide penetration SHUTDOWN within the following of < 2.5%, when tested at 30oC 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 l
l When handling irradiated fuelin the secondary containrnent, during CORE ALTERATION (s), and operations with a potential for draining the reactor vessel.
DRESDEN - UNITS 2 & 3 3/4.7-23 Amendment Nos. 158, 153 l
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i CONTAINMENT SYSTEMS SBGT 3/4.7.P
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3.7 - LIMITING CONDITIONS FOR OPERATION 4.7 - SURVEILLANCE REQUIREMENTS l
3.
With both standby gas treatment c.
Verifying a subsystem flow rate of subsystems inoperable in 4000 cfm *10% during system 1
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 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-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.
analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of i
l 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.
Verifying 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 l
rata of 4000 cfm *10%.
l b.
Verifying that the filter train starts I
and isolation dampers open on each of the following test signals:
- 1) Manual initiation from the control room, and l
- 2) Simulated automatic initiation i
signal.
c.
Verifying that the heaters dissipate i
30 *3 kw when tested in l
accordance with ANSI N510-1989.
l This reading shallinclude the l
appropriate correction for variations in voltage.
When handling irradiated fuel in the secondary containment, during CORE ALTERATION (s), and operations with a potential for draining the reactor vessel.
DRESDEN - UNITS 2 & 3 3/4.7-24 Amendment Nos.158,153
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, CONTAINMENT 5.2 5.0 DESIGN FEATURES l
l L2 CONTAINMENT l
Confiauration l
5.2.A The primary containment is a steellined concrete structure consisting of a drywell and l
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 j
drywell has a minimum free air volume of 158,236 cubic feet. The suppression
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- chamber has an air region of 116,300 to 112,800 cubic feet and a water region of 116,300 to 119,800 cubic feet.
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Desian Temoerature and Pressure 5.2.B The primary containment is designed and shall be maintained for:
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1.
Maximum internal pressure:
62 psig.
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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 4,500,000 cubic feet.
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DRESDEN - UNITS 2 & 3 54 Amendment Nos. 158, 153
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