ML20070J525
| ML20070J525 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/29/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Vermont Yankee |
| Shared Package | |
| ML20069C510 | List: |
| References | |
| DPR-28-A-073 NUDOCS 8212280007 | |
| Download: ML20070J525 (7) | |
Text
R %.
-ll V } ':
L..
Q; _ sf% _'_.,
_r.__ _ _ _. ;.,.[_.. ; ;
.7,'
- L. _
L,,,._ _ f '- l,, Q : __,_ _ ; <" *.. :
_.'M ymy,1 UNITED STATES g,
g g
NUCLEAR REGULATORY COMMISSION 1 y wiSHINGTON, D. C. 20555
\\...../
VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 VERMONT YANKEE NUCLEAR POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. DPR-28 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Vermont Yankee Nuclear Power Corporation (the licensee) dated October 5,1981 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 in 10 CFR Chapter,J,;
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 conduc:ed without endangering the health and safety of the public and (ii) that such activities will be conducted in compiiance with the Commission's reguiations; D.
The issuar a of this amendment will not be inimical to the comon defense and security or to the health and safety of the publir.,
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.
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-28 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 73 are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
~T212280007 821129 PDR ADOCK 05000271 p
_PDR
-2 3.
This. license amendm5nt is effective as of the date of issuance.
FOR THE NOCL AR REGULATORY COMMISSION M
Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
. Changes to the Technical Specificctions Date of Issuance: November 29, 1982 e
f e
d
't er
. 8 9
e a-.,
y 7..
34 e-ruw-
,tw.r rwwew
- yeg 9
w-rmwv=
- -w'i4 gm-w
r v.
'[. fA -
g ATTACHMENT:TO LICENSE AMENDMENT NO. 73
~ FACILITY' OPERATING LICENSE NO.~~DPR-28 DOCKET NO. 50-271
~
Revise the Technical Specifications as follows:
REMOVE INSERT 47-47
-48
'48
~71 71 77:
77 6
e-1 1
4
..__.,...,.-,,...,..,....._..,__,--_,._..._...-..._._-.....I
VYNPS TABLE 3.2.5 CONTROL ROD BLOCK INSTRUMENTATION
~*
Mini =um Number Oparable Instrument Modes in Which Function Channels per Trip Must be Operable 5
System' (Note 1)
Trip Function Refuel Startup Run Trip' Setting Startup Range Monitor 5
2 a.
Upscale (Note 2)
X X
15 x 10 cps (Note'3) 2 b.
Detector not fully inserted X
X Intermediate Range Monitor 2
a.
Upscale X
X 1108/125 full scale 2
b.
Downscale (Note 4)
X X
3,5/125 full scale 2
c.
Detector not fully inserted X
_ X Average Power Range Monitor 2
a.
Upscale (flow bias)
X 10.66W+42%(Note 5)
(Nate 6) 2 b.
Downscale
.X
>2/125 full l scale -
Rod Block Monitor (Note 6) 1 a.
Upscale (flow bias)(Note 7)
X 10.66W+N (Note 5) 1 b.
Downscale (Note 7)
X 3,2/125 full scale 1
Trip System Logic X
X X
~
1 Scram Discharge Volume (Note 9)
X X
X 112 gallons 47 Amendment No. 64 73
N,
VYNPS TABLE 3.2.5 NOTES 1.
There shall be two operable or tripped trip systems for each function in the required operating mode.
If the minimum. number of operable Instruments are not available for one of the two trip systems, this condition may exist for up to seven days provided that during the time the operable system is functionally tested immediately and daily thereafter; if the' condition lasts longer than seven days, the system shall be tripped.
If the minimum number of instrumcnt channels are not available for both trip systems, the systems shall be tripped.
2.
One of these trips may be bypassed. The SRM function may be bypassed in the higher IRM ranges
" 3 when the IRM upscale rod block is operable.
3.
This function may be bypassed when count rate is >100 cps or when all IRM range switches are above Position 2.
4.
'sM downscale may be bypassed when it is on its lowest scale.
6 5.
"W" is percent rated drive flow where 100% rated drive flow is that' flow equivalent to 48 x 10 lbs/hr core flow.
Refer to L.C.O. 3.ll.C for acceptable values for N.
6.
The minimum number of operable instrument channels may be reduced by one for maintenance and/or testing for periods not in excess of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in any 30-day period.
7.
The trip may be bypassed when the reactor power is <30% of rated. An RBM channel will be considered inoperable if there are less than half the total number of normal inputs from any LPRM level.
8.
For special stability tests, the.APRM rod block shall be <0.66W + 75% for the duration of testing.
9.
Note (1) is not applicable to this function. There shall be one operable or operating trip system for this function.
48 Amendment No. 64 73 i
Q
w VYNPS 4.3 LIMITING CONDITIONS FOR OPERATION 4.3 SURVEILLANCE REQUIREMENTS 5.
Control rods shall not be withdrawn for startup 5.
Prior to control rod withdrawal for startup or or refueling unless at least two source range during refueling, verification shall be made that channels have an observed count rate greater than at least two source range channels have an or equal to three counts per second.
observed count rate of at least three counts per second.
6.
During operation with limiting control rod patterns either:
6.
When a limiting control rod pattern ' exists, an 1
instrument functional test of the RBM shall he (e) Both RBM channels shall be operable; or performed prior to withdrawal of the designated rod (s) and daily thereafter.
(b) Control rod withdrawal shall be blocked; or 7.
The scram discharge volume drain and vent valves (c) The operating power level shall be limited shall be verified.open at.least once per month.
so that the MCPR will remain above the fuel These valves may be closed intermittently for cladding integrity saf ety limit assuming a testing under administrative control.
single error that resuls in complete withdrawal of any single operable control rod.
F 4
O O
i 4
71 1
Amendment No. 61 73 8
-r
-..-._.n.a-ae-
._-4.-
4 z
g_
e e4 6
beh-'
L
'-+4 f*
d-m-+e a
I i
VYNPS 5.
The Source Range Monitor (SRM) system has no scram functions.
It does provide the operator with a visual l
indication of neutron level. The consequences of reactivity accidents are a function of the' initial neutron,
flux. The requirement of at least three counts per second assures that any transient, should it occur, begins at or above the initial value of 10-8 of rated power used in the anlyses of transients f rom cold conditions. One operable SRM channel is adequate to monitor the approach to criticality, therefore, two operable SRM's are specified for added conservatism.
6.
The Rod Block Monitor (RBM) is designed to automatically prevent fuel damage in the event of erroneous rod withdrawal f rom locations of high power density during high power level operation. During reactor-operation with certain limiting control rod patterns, the withdrawal of a designated single. control rod could resul t in one or' more fuel rods with MCPR less than the feel cladding integrity saf ety limit..During use of such patterns,'It'{s judged that testing of the RBM system prior to withdrawal of such rods will provide added assurance that improper withdrawal does not occur.
it. ls the responsibility of the Nuclear Engineer' to" identify these limiting patterns and the designated rods either when the patterns are initially established or as they develop due to the occurrence of inoperable control. rods.
7.
Periodic verification that the Scram Discharge Volume (SDV) drain and vent valves are maintained in the open i
position provides assurance that the SDV will be available to accept the water displaced from the' control rod.
I drives in the event of a scram.
?
3 4
1 g.
1 77.
{
Amendment No. 61 73 4
1
~