ML20134K652
| ML20134K652 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/19/1985 |
| From: | Butcher E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20134K650 | List: |
| References | |
| NUDOCS 8508300339 | |
| Download: ML20134K652 (5) | |
Text
.
j## * *'**
\\
e t
NUCLEAR REGULATORY COMMISSION UNITED STATES e
WASHINGTON, D. C. 20555 OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALHOUN STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.90 License No. DPR-40 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Omaha Public Power District (thelicensee)datedJune 11, 1985, 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 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 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 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.
8508300339 e50819 yDR ADOCK 05000285 PDR
2.
Accordingly, Facility Operating License No. DPR-40 is amendedeby changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No.
DPR-40 is hereby amended to read as follows:
P B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 90, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 30 days of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Edward J.
utcher, Acting Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: August 19, 1985 l
i 6
ATTACHMENT TO LICENSE AMENDMFNT NO. 90 FACILITY OPERATING LICENSE NO. DPR-40 t
DOCKET NO. 50-285 Revise the Appendix "A" Technical Specifications as indicated below. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Pages Insert Pages 3-62 3-62 3-62a 3-62a we
~
3.0 SURVEILLANCE REQUIREMENTS 3.9 Auxiliary Feedwater System Applicability Applies to periodic testing requirements of the turbine-driveh and motor-driven auxiliary feedwater pumps.
Objective To verify the operability of the auxiliary feedwater (AFW) system and its ability to respond properly when required.
Specifications (1) The position of valves necessary to ensure auxiliary feedwater flow to the steam generators shall be verified by a monthly inspection. Anytime maintenance is performed on the auxiliary feedwater system which alters valve alignments, an operator shall check that the AFW system valves are properly aligned, to ensure AFW flow to the steam generators, and a second operator shall independently verify proper valve alignment.
(2) The operability of the motor-driven auxiliary feedwater pump and the steam turbine-driven auxiliary feedwater pump shall be confirmed at least monthly.
(3) The operability of auxiliary feedwater pumps' steam generator level regulating valves HCV-1107A, HCV-11078, HCV-1108A, HCV-11088, and auxiliary feedwater cross-tie valve HCV-1384 shall be confirmed at least every three months.
(4) The capabilities of the motor-driven and turbine-driven auxiliary l
feedwater pumps shall be verified by using local pressure j
indicators and flow indicators in the control room. The dis-charge pressure will be verified to be 40 psig above the steam generator pressure at rated steam flow.
.(5) Followingcoldshutdognandpriortoraisingthereactorcoolant I
temperature above 300 F, the motor-driven auxiliary feedwater pump shall be tested to verify the normal flow path for auxiliary feedwater to the steam generators.
(6) At least once per 18 months during shutdown by:
l a.
Verifying that each automatic valve in the flow path actuates to its correct position upon receint of each auxiliary feedwater actuation test signal.
c i
b.
Verifying that each auxiliary feedwater pump starts as designed automatically upen receipt of each auxiliary feedwater actuation test signal.
3-62 Amendment No. 49, 54, 90 l
3.0 SURVEILLANCE REQUIREMENTS 3.9 Auxiliary Feedwater System (Continued)
Basis
\\
w The valve position verifications performed monthly and following auxiliary feedwater system maintenance will confirm the avail-ability of an; auxiliary feedoater flow path to the steam generators.
The testing of the auxiliary feedwater pumps every month and after cold shutdowns will verify their operability by recirculating water to the emergency feedwater storage tank.
i Operating the regulating valves (HCV-1107A, HCV-1107B, HCV-1108A and HCV-1108B) one at a time every three months and after cold shutdowns will confirm a flow path to the steam generators and operability of the valves.
Proper functioning of the steam turbine admission valve and starting of the feedwater pump will demonstrate the integrity of the steam driven pump.
Verification of correct operation will be made both from instrumentation within the main control room and direct visual observation of the pumps.
The operability of the auxiliary feedwater system ensures ghat the reactor coolant system can be cooled down to less than 350 F from normal operating conditions in the event of a total loss of off-site power.
References (1) FSAR, Section 9.4.
(2) Technical Specification 2.5 I
~..
l l
l l
l 3-62a Amendment No. f 9, Ef, 90 l
l
_-