ML19309F652
| ML19309F652 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 04/04/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19309F649 | List: |
| References | |
| NUDOCS 8004300255 | |
| Download: ML19309F652 (5) | |
Text
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UNITED STATES j
y y,... *,g NUCLEAR REGULATORY COMMISSION 5
E WASHINGTON, D. C. 20555 5
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PORTLAND GENERAL ELECTRIC COMPANY THE CITY OF EUGENE, OREGON PACIFIC POWER AND LIGHT COMPANY DOCKET NO. 50-344 TROJAN NUCLEAR PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.43 License No. NPF-1 1.
ihe Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Portland General Electric Company, the City of Eugene, Oregon, and Pacific Power and Light Company (the licensee) dated April 1,1980, complies with the standards 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 l
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; l
and f
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of -the Comission's regulations and all applicable requirements have bee,n satisfied.
2-2.
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. NPF-1 is herehy amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43, are hereby incorporated in the license.
The licensee shall operate :he facility in accordance with the Technical Specific.itions.
p 3.
This license anendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
, ',f(W RY 'V A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: April 4,1980 t
l
ATTACHMENT LICENSE AMENDMENT NO.43 4
FACILITY OPERATING LICENSE NO. NPF-1 i
DOCKET NO. 344
?
t Replace the following page of the Appendix "A" Technical Specifications t
with the enclosed page as indicated. The revised page is identified by Amendment number and.contains a vertical line indicating the area of The corresponding overleaf page is also provided to maintain change.
docmnent completeness.
Pace 3/4 1-21 1
4 I
t 4
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4
REACTIVITY CONTROL SYSTEMS R0D DROP flME LIMITING CONDITION FOR OPERAT fN 3.1.3.3 The individual full length (shutdown and control) rod drop time from the fully withdrawn position shall be < 2.2 seconds from beoinning of decay of stationary gripper coil voltage to dashpot entry with:
a.
T 1 550*F, and avg b.
All reactor coolant pumps operating.
APPLICABILITY: MODES 1 and 2.
ACTION:
a.
With the drop time of any full length rod determined to. exceed the above limit, restore the rod drop time to within the above limit prior to proceeding to MODE 1 or 2.
b.
With the rod drop times _within limits but determined with 3 reactor. coolant pumps operating, operation may proceed provided THERMAL POWER is restricted to < 75% of RATED THERMAL POWER.
SURVEILLANCE REQUIREMENTS 4.1.3.3 The rod drop time of full lenoth rods shall be demonstrated through measurement prior to reactor criticality:
a.
For all rods following each removal of the reactor vessel head, b.
For specifically affected individual rods following any main-tenance on or modification to the control rod drive system ~
which could affect the drop time of those specific rods, and-c.
At least once per 18 months.*
f i
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- Performance of this Surveillancy Requirement may be deferred to coincide with the scheduled refueling outage.
This extension permits operation to continue in MODES I and 2 until April 11, 1980.
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TROJAN-UNITil 3/4 1-21 Amendment No. 43
1 O
i 4
REACTIVITY CONTROL SYSTEMS SHUTOOWN ROD INSERTION LIMIT l
LIMITING CONDITION FOR OPERATION 3.1.3.4 All shutdown rods shall be fully withdrawn.
APPLICABILITY:
MODES 1* and 2*#
ACTION:
With a maximum of one shutdown rod.not fully withdrawn, except for surveillance testing pursuant to Specification 4.1.3.1.2, within one hour either:
a.
Fully withdraw the rod, or Declare the rod to be inoperable and apply Specification 3.1.3.1.
b.
SURVEILLANCE REQUIREMENTS t
4.1.3.4 Each shutdown-rod shall be determined to be fully withdrawn:
Within 15 minutes prior to withdrawal of any vads in control a.
banks A, B, C or D during an approach to reactor criticality,-
and 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 /> thereafter.
- See Special Test Exceptions 3.10.2 and 3.10.4.
- With Kef f > 1.0.
s r
c TROJAN-UNIT 1 3/4 1-22
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