ML20195C795
| ML20195C795 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/27/1986 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20195C798 | List: |
| References | |
| NUDOCS 8605300604 | |
| Download: ML20195C795 (5) | |
Text
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UNITED STATES
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COMMONWEALTH EDIS0N COMPANY DOCKET N0. 50-249 DRESDEN NllCLEAR POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.86 License No. OPR-25 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated March 31, 1986, 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 t
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 endancering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's r.egulations; 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.
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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. 86, 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.
1 FORTHENUCLEARREGUpT0l'Y COMMISSION
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. Zwolinski, Director RWR P o.iect Directorate #1 Division of BWR Licensino
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 27, 1986.
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ATTACHMENT TO LICENSE AMENDMENT NO. 86 FACILITY OPERATINr LICENSE DPR-25 DOCKET NO. 50-249 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4.2-8 3/4.7-8 3/4.7-31 3/4.2-31 l
i l
I
DRESDEN III PR-25 Am:ndmeltNo.J,
, 86 l
TABLE 3.2.1 INSIRUMENTATION THAT INITIATES PRIMARY CONTAINMENT ISOLATION FUNCTIONS MINIMUM # OF OPERABLE INST.
CHANNELS PER TRIP SYSTEM (1)
INSTRUMENTS TRIP LEVEL SETTING ACTION (3) 2 Reactor Low Creater than 144" A
Water Level above top of active fuel (8) 2 Reactor Low Creater than or equal A
Low Water to 84" above top of active fuel (8) 2 High Drywell Less than or equal A
Pressure to 2 psig (4),(5) 2 (2)
High Flow Main Less than or equal B
Steam Line to 120% of rated steam flow 2 of 4 in each High Temperature Less than or equal B
of 4 sets Main Steamline to 200*F.
Tunnel 2
High Radiation Less than or equal B
Main Steamline to 3 times full Tunnel power background (6) 2 Low Pressure Creater than or equal B
Main Steamline to 850 psis High Flow Isolation 1
Condenser Line Less than or equal C
Steamline side to 20 psi diff on steamline side.
1 Condensete Less than or equal C
Return Side to 14.8" water diff on condensate return side 2
High Flow HPCI Less than or equal D
Steamline to 150 inches of water diff. (7) 4 High Temperature Less than or equal D
HPCI Ste'amlina Area to 200*F.
Notes:
(See Next Page) 3/4.2-8
)
3840s 3845A l
DRESDEN III DPR-25 Am.nda.nt no. p, p, p, as 3.2 LIMITING CONDITION FOR OPERATION BASES (Cont'd.)
and/or bypass valves to open. With the trip set at 850 psig, inventory loss is limited so that fuel is not uncovered and peak clad temperatures are much less than 1500 degrees F; thus, there are no fission products available for release other than those in the reactor water.
(Ref. Section 11.2.3 SAR)
Two sensors on the isolation condenser supply line and two sensors on the return line are provided to detect the failure of isolation condenser line and actuate isolation action. The sensors on the supply and return sides are arranged such that any one of the four sensors can cause isolation and, to meet the single failure criteria, all sensors and instrumentation are required to be operable. The trip settings of 20 psi differential and 14.8 inches of water differential and valve closure time are such as to prevent uncovering the core or exceeding site limits. The sensors will actuate due to high flow in either direction.
The HPCI high flow and temperature ir.strumentation are provided to detect a break in the HPCI piping.
Tripping of this instrumenta-tion results in actuation of HPCI isolation valves, i.e., Group 4 valves. Tripping logic for this function is the same as that for the isolation condenser and thus all sensors are required to be operable to meet the single failure of design flow and valve closure time are such that core uncovery is prevented and fission l
product release is within limits.
The instrumentation which initiates ECCS action is arranged in a dual bus system. As for other vital instrumentation arranged in this fashion the Specification preserves the effectiveness of the system even during periods when maintenance or testing is being performed.
The control rod block functions are provided to prevent excessive control rod withdrawal so that MCPR does not go below the MCPR fuel cladding integrity safety limit.
The trip logic for this function is 1 out of n, e.g., any trip on one of the six APRM's, 8 IRM's, or 4 SRM's will result in a rod block. The minimum instrument channel requirements assure sufficient instrumentation to assure the single failure criteria are met. The minimum instrument channel requirements for the RBM may be reduced by one for a short period of time to allow for maintenance, testing or calibration. This time period is only approximately 3% of the operating time in a month and does not significantly increase the
, risk of preventing an inadvertent control rod withdrawal.
The APRM rod block function is flow biased and prevents a s}gnificant reduction in MCPR, especially during operation at B 3/4.2-31 3840a 3845A
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