ML20079D681
| ML20079D681 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/10/1991 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079D682 | List: |
| References | |
| TAC-80547, NUDOCS 9107240052 | |
| Download: ML20079D681 (5) | |
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UNITED STATES s.S,, 7)! i NUCLEAR REGULATORY COMMISSION k e6
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- lTLAh,T,1,C"C)T7IlltTEll'tDh)AhT DOCKET t10.,,50,,2J8 PEACH LOTT0ft ATOMIC POWER STATION, UNIT _NO. 3 AMftlDMENT TO FACILITY CPERATitlG LICENSE Amendment No. 166 License No. DPR-56 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et.
al. (the licensee) dated June 14, 1991, complies with the standards arid 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, tne 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, 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 iridicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. DPR-56 is hereby amended to read as follows:
9107240052 910710 PDR ADOCK 05000277 P
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. (2) Te,c_hnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.166, are hereby incorporated in tre license.
PECO shall operate the facility in accordance with this Technical Specifications.
3.
This license amendment is effective as oi its date of issuance.
FOR THE flVCLEAR REGULATORY C0t411SS10fl Walter R. Butler, Director Project Directorate 1-2 Division of Reactor Projects - 1/11
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 10, 1991
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ATTACHMENT TO l_I.C.E.N.S.E..AliENOME.N.T..N.O.
166 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO 50 278 Replace the following pages of the Appendix A Technical Specifications with l
the enclosed pages.
The revised areas are indicated by marginal lines.
REMOVE INSERT 101 101 102 102 l
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i Unit 3 PDAPS i-LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3.A.;eactivity Limitations 4.3.A Reactivity Limitations (Cont'd)
(Cont'd) f.
Inoperablecontrolrodssha1120 positioned such that specific 9 tion 3.3.A.1 is met. 'In addition, during reactor power operation, no more than' one control rod in any 5 x 5 array may be inoperable (at least 4 operable control rods must separate any 2 inoperable ones).
If this Specification cannot be met the reactor shall not be started, or if at power, the reactor shall be brought to a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
8.
Control Rods B.
Control Rods 1.
Each control rod shall be 1.
The coupling integrity shall coupled to its drive or be verified for each withdrawn completely inserted and the control rod as follows:
control rod directional control valves disarmed
- a. When a rod is withdrawn electrically except as in the first time after each 3.3.B.1.a.
This requirement refueling outage or after does not apply in the refuel maintenance, observe discernible condition when the reactor response of the nuclear is vented. Two control
-instrumentation and rod rod drives may be removed position iadication for as long-as Specification 3.3.A.1 the " full-in" and " full-out" is met, position. However, for initiel rods when response is not
- a. For control rod 38-23, for discernible, subsequent the remainder of cycle 8 (to exercising of these rods after be completed before 10/30/91).
the reactor is above the Rod Worth Minimizer low power setpoint if coupling cannot be shall be performed to verify accomplished, the uncoupled control instrumentation response, rod may be withdrawn when > 10%
of rated thermal power
- b. When the rod is' fully
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only if all the following withdrawn the first time conditions are satisfied:
after each refueling outage or-after maintenance observe
- 1) no other uncoupled control that the drive does not go rod is withdrawn; to the overtravel position.
- 2) the uncoupled control rod may not be withdrawn past notch position 46.
~ Amendment No. 16, 43, 153, 166
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Unit 3 PBAPS LIMITING CONDITIONS FOR OPERATION SURVElllANCE REQUIREMENTS 3.3.8ControlRods(Cont'd.)
4.3.8 Control Rods (Cont'd.)
During each refueling outage c.
and after control rod maintenance, observe that the drive does not go to the overtravel position, d.
When repositioning the uncoupled control rod, per Specification
'3.3.B.1.a the uncoupled control rod's position shall be verified to have followed the control rod drive by neutron instrumentation (LPRM or TIP).
If the control blade cannot be verified to have followed the drive out to its final position, then the rod shall be completely inserted and the control rod directional control valves disarmed electrically.
- 2. The control-rod drive housing 2.
The control rod drive housing support system shall be in support system shall be in-place during reactor power spected after reassembly and operation or when the reactor the results of the Inspection coolant system is pressurized recorded.
above atmospheric pressure
.with fuel in the reactor vessel, unless all control rods are fully inserted and Specificat Mn 3.3. A.1. is met.
3.a. DELETED 3.a. DELETED
- b. The Rod Worth. Minimizer b.1. Prior to the start of (RWM) low power setpoint control rod withdrawal is greater than or equal to towards criticality and 10% of rated power. Whenever prior to attaining the the reactor is in the startup Rod Worth Minimizer low or run modes with thermal power setpoint during rod power less than or equal to insertion at shutdown, the theRodWorthMinimizer(RWM)
Rod Worth Minimizer (RWM) low-power setpoint the shall be demonstrated to Rod Worth Minimizer shall be
.be operable by the l
operable except as follows:
following checks:
- 1. With the RWM inoperable after the
- a. The RWM computer on
. first 12 control rods are fully line diagnostic test.
withdrawn, operation may continue shall be successfully provided that control rod movement performed..
and compliance with the prescribed control-rod pattern are verified
- b. Prior to the start by a second licensed operator or of control rod withdrawal technically qualified member of the only, proper annunciation station technical staff.
l' of the selection error of at least one out-of-sequence control rod in a fully inserted group shall be verified.
Amendment No. 33, 43, 0 3, 166
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