ML17191B470
| ML17191B470 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 10/01/1999 |
| From: | Anthony Mendiola NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17191B471 | List: |
| References | |
| NUDOCS 9910120179 | |
| Download: ML17191B470 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 COMMONWEAL TH EDISON COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 174 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 20, 1999, as supplemented by letters dated September 8, September 16, and September 20, 1999, 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 (i) that the activities authorized by this amendment can be conducted without endangering the health and sat ety 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 sat ety of the public; and E.
The issuance of this amendment is in accordance with 1 O 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 2.C.(2) of Facility Operating License No. DPR-19 is hereby amended to read as follows:
9910120179 991001 PDR APOCK 05000237 P
PDR.'
.- (2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 174, 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.
Attachment:
Changes to the Technical Specifications Date of Issuance:
Oc to her 1, 1999 FOR THE NUCLEAR REGULATORY COMMISSION
, nthony J. Mendiola, Chief, Section 2 reject Directorate Ill ivision of Licensing Project Management Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 COMMONWEAL TH EDISON COMPANY DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 1 70 License No. DPR-25
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated May 20, 1999, as supplemented by letters dated September 8, September 16, and September 20, 1999, 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 (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, ana (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-25 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 1 70, 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.
Attachment:
Changes to the Technical Specifications Date of Issuance:
October l, 1999 thony J. Mendiola, Chief, Section 2 reject Directorate Ill Division of Licensing Pr.oject Management
. Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NOS. 174 AND 170 FACILITY OPERATING LICENSE NOS. DPR-19 AND DPR-25 DOCKET NOS. 50-237 AND 50-249 Revise the Appendix "A" Technical Specifications by replacing the pages identified below with the enclosed pages. The revised pages are identified by amendment number and contain a vertical line indicating the area of change.
REMOVE INSERT 3/4.8-1 3/4.8-1 3/4.8-3 3/4.8-3 83/4.8-1 83/4.8-1
PLANT SYSTEMS 3.8 - LIMITING CONDITIONS FOR OPERATION A. Containment Cooling Service Water System 1. Containment Cooling Two independent containment cooling service water (CCSW) subsystems, with each subsystem comprised of:
- a.
Two OPERABLE CCSW pumps, and
- b.
An OPERABLE flow path capable of taking suction from the ultimate heat sink and transferring the water:
- 1) Through one LPCI heat exchanger, and separately,
- 2)
To the associated safety related equipment, shall be OPERABLE, and
- 2.
Control Room Emergency Ventilation (CREVS) Refrigeration Control Unit (RCU) support One Unit 2 CCSW pump and flow path shall be OPERABLE.
APPLICABILITY:
For Containment Cooling, OPERATIONAL MODE(s) 1, 2, and 3.
For CREVS RCU support, OPERATIONAL MODE(s) 1, 2, 3 and *.
CCSW 3/4.8.A 4.8 - SURVEILLANCE REQUIREMENTS A. Containment Cooling Service Water System Each of the required CCSW subsystem shall be demonstrated OPERABLE at least once per 31 days by verifying that each valve, manual or power operated, in the flow path that is not locked, sealed or otherwise secured in position, is in its correct position.
- J When handling irradiated fuel in the Secondary Containment, during CORE AL TERATION(s). and operations with a potential for dr~ining the reactor vessel.
DRESDEN - UNITS 2 & 3 3/4.8-1 Amendment Nos.174 and 170
l PLANT SYSTEMS 3.B - LIMITING CONDITIONS FOR OPERATION
- 2.
In OPERATIONAL MODE(s) 1,2,3 and
- with the CCSW pump or flow path which is associated with the safety related equipment required OPERABLE by Specification 3.8.D inoperable, declare the associated safety related equipment inoperable and take the ACTION required by Specification 3.8.D.
CCSW 3/4.8.A 4.8 - SURVEILLANCE REQUIREMENTS 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 3/4.8-3 Amendment Nos. 174 and 170
PLANT SYSTEMS B 3/4.8 BASES 3/4.8.A Containment Cooling Service Water System The containment cooling service water system, with the ultimate heat sink, provides sufficient cooling capacity for continued operation of the containment cooling system and of other safety-related equipment (e.g., CCSW keep-fill, the control room emergency ventilation system refrigeration unit which can be supplied by any single Unit 2 CCSW pump), during normal and accident conditions. The redundant cooling capacity of the system, assuming a single failure, is consistent with the assumptions used in the safety analysis to keep the accident conditions within acceptable limits. Since only two of the four pumps is required to provide the necessary cooling capacity, a thirty day repair period is allowed for one pump out of service. OPERABILITY of this system is also dependent upon special measures for protection from flooding in the condenser pit area.
3/4.8.B Diesel Generator Cooling Water System The diesel generator cooling water system, with the ultimate heat sink, provides sufficient cooling capacity for continued op.eration of the diesel generators during normal and accident conditions. The cooling capacity of the system is consistent with the assumptions used in the safety analysis to keep the accident conditions within acceptable limits.
3/4.8.C Ultimate Heat Sink The canals provide an ultimate heat sink with sufficient cooling capacity to either provide normal cooldown of the units, or to mitigate the effects of accident conditions within acceptable limits for one unit while conducting a normal cooldown on the other unit.
3/4.8.D Control Room Emergency Ventilation System The control room emergency filtration system maintains habitable conditions for operations personnel during and following all design basis accident conditions. This system, in conjunction with control room design, is based on limiting the radiation exposure to personnel occupying the room to five rem or less whole body, or its equivalent.
The frequency of tests and sample analysis is necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. The control room emergency filtration system in-place testing procedures are established utilizing applicable sections of ANSI N510-1980 standard.
Operation of,the system with the heaters OPERABLE for ten hours a month is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The charcoal adsorber efficiency test procedures allow for the removal of one representative sample cartridge and testing in accordance with the guidelines of ASTM-D-3803-89. T'1e 1c:r.-;;;a iG * *~ast two inches in diameter and has a length equivalent to the thickness of the bed. If the iodine removal efficiency DRESDEN - UNITS 2 & 3 B 3/4.8-1 Amendment Nos. 174 and 170