ML20135E181
| ML20135E181 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/04/1997 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20135E182 | List: |
| References | |
| NUDOCS 9703060334 | |
| Download: ML20135E181 (7) | |
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1 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30886 4001 o%...../
COMMONWEALTH EDIS0N COMPANY DOCKET NO. 50-237 DRESDEN NUCLEAR POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.154 License No. DPR-19 3
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for' amendment by the Comonwealth Edison Company (the licensee) dated December 6, 1996, complies with the standards i
and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attacament to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-19 is hereby amended to read as follows:
1 i
ER188ME88llg7 P
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1 l
(2)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 154, 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 60 days.,
FOR THE NUCLEAR REGULATORY COMMISSION J
C V
ohn F. Stang, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: March 4, 1997 J
p lEr UNITED STATES
)p j
NUCLEAR REGULATORY COMMISSION I &
WASHINGTON, D.C. 206 6 0001
%...../
COMMONWEALTH EDISON COMPANY l
DOCKET NO. 50-249 DRESDEN NUCLEAR POWER STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE 1
Amendment No.149 License No. DPR-25 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Comonwealth Edison Company (the licensee) dated December 6, 1996, complias 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 Comission; 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; 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 Specifi-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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2 B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 149, 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 60 days.
j FOR THE NUCLEAR REGULATORY COMMISSION John F. Stang, Project Manager Project Directorate III-2 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical 1
Specifications l
i Date of Issuance: March 4, 1997 l
J
ATTACHMENT TO LICENSE AMENDMENT NOS.154 AND 149 FACILITY OPERATING LICENSE NOS. 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 number and contain marginal lines indicating the area of change.
REMOVE INSERT 1-9 1-9 1
3/4.10-1 3/4.10-1 l
I l
Definitior.s 1.0 TABLE 1-2 OPERATIONAL MODES MODE SWITCH AVERAGE REACTOR MODE 4
POSITIONS COOLANT TEMPERATURE
- 1. POWER OPERATION Run Any temperature 2.STARTUP Startup/ Hot Standby Any temperature
- 3. HOT SHUTDOWN Shutdown'"'
> 212'F
- 4. COLD SHUTDOWN Shutd own**'
s 212*F
- 5. REFUELINGid Shutdown or Refuel*
s 140 F i
TABLE NOTATIONS (a) The reactor mode switch may be placed in the Run, Startup/ Hot Standby, or Refuel position to test the switch interlock functions provided the control rods are verified to remain fully inserted by a second licensed operator or other technically qualified individual.
j (b) The reactor mode switch may be placed in the Refuel position while a single control rod drive.
is being removed from the reactor pressure vessel per Specification 3.10.l.
(c) Fuel in the reactor vessel with one or more vessel head closure bolts less than fully tensioned or with the head removed.
(d) See Special Test Exceptions 3.12.A and 3.12.B.
(e) The reactor mode switch may be placed in the Refuel position while a single control rod is being moved provided the one-rod-out interlock is OPERABLE.
(f) When there is no fuel in the reactor vessel, the reactor is considered not to be in any OPERATIONAL MODE. The reactor mode switch may then be in any position or may be
. inoperable, j
DRESDEN - UNITS 2 & 3 1-9 Amendment Nos. 154 & 149
i REFUELING OPERATIONS Moda Switch 3/4.10.A
,1 3.10 - LIMITING CONDITIONS FOR OPERATION 4.10 - SURVEILLANCE REQUIREMENTS l
A.
Reactor Mode Switch A.
Reactor Mode Switch i
The reactor mode switch shall be 1.
The reactor mode switch shall be
)
OPERABLE and locked in the Shutdown or verified to be locked in the Shutdown Refuel position. When the reactor mode or Refuel position as specified:
j a
j switch is locked in the Refuel position:
a.
Within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to:
f 1.
A control rod shall not be withdrawn j
unless the Refuel position one-rod-out 1.
Beginning CORE interlock is' OPERABLE.
ALTERATION (s), and j
~ w j
j 2.
CCRE ALTERATION (s) shall not be 2.
Resuming CORE l
performed using equipment associated ALTERATION (s) when the 1
with a Refuel position interlock unless reactor mode switch has been i
l at least the following associated Refuel unlocked.
position interlocks are OPERABLE for b.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
]
such equipment.
3 l
a.
All rods in.
2.
Each of the required reactor mode b.
Refuel platform position.
switch Refuel position interlocks'*
c.
Refuel platform hQts fuel-loaded, shall be demonstrated OPERABLE by d.
Fuel grapple postpon.
performance of a CHANNEL FUNCTIONAL TEST within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
!l prior to the start of and at least once j
1 APPLICABILITY:
per 7 days during control rod withdrawal or CORE ALTERATION (s),
i OPERATIONAL MODE (s) 3,4 and as applicable.
5 '6'.
3.
Each of the required reactor mode switch Refuel position interlocksia that ACTION:
is affected shall be demonstrated OPERABLE by performance of a 1.
With the reactor mode switch not CHANNEL FUNCTIONAL TEST prior to locked in the Shutdown or Refuel resuming control rod withdrawal or position as specified, suspend CORE ALTERATION (s) and lock the reactor mode switch in the Shutdown or Refuel position.
When the reactor mode switch is in the Refuel position.
a b
See Special Test Exceptions 3.12.A and 3.12.B.
The reactor shall be maintained in OPERATIONAL MODE 5 whenever fuel is in the reactor vessel with c
vessel head closure bolts less than fully tensioned or with the head removed.
The reactor mode switch may be placed in the Run or Startup/ Hot Standby position to test the switch d
interlock functions provided that all control rods are verified to remain fully inserted by a second licensed operator or other technically qualified individual.
DRESDEN - UNITS 2 & 3 3/4.10-1 Amendment Nos. 154 & 149