ML20004F869
| ML20004F869 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/12/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004F870 | List: |
| References | |
| NUDOCS 8106260070 | |
| Download: ML20004F869 (10) | |
Text
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d UNITED STATES 8g g
NUCLEAP REGULATORY COMMISSION
- . E WASHINGTON, D. C. 20555 o.7
%, *. + *f CONSUMERS POUER COMPANY DOCKET NO. 50-255 PA:ISADES PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 66 License No. OPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensec) dated May 26, 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 I; B.
The facility will operate in conformity with the i iplication, the provisions of the Act, and the rules and regulations of the "ommission; C.
There is reasonable assurance (i) that the activities authorized 1,y this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activitihs 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.
8106260070s, l
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2.
Accordingly, the' license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.8 of Provisional Operating License
.No. DPR-20 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B (Environmental Protection Plan), as revised through Amendment No. 66, 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.
FOR THE NUCLEAR REGULATORY COMMISSION hN
/g y
Dennis M. Crutchfield, Ch ef Operating Reactors Branch #5 Division of Licensing Attachments:
Changes to the Technical Specifications Date of Issuance:
June 12,1981
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.. ATTACHMENT TO LICENSE' AMENDMENT NO. 66_
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PROVISIONAL OPERATING LICENSE-NO. DPR-20 DOCKET NO. 50-255 IRevise Appendix A Technical Specifications by removing the following pages.and by inserting the enclosed'pages. The revised pages contain the captioned amendment number and marginal lines indicating the area of change.
REMOVE INSERT 4.3 4.3 4.4 4.4 4.6 4.6 4.11 4.11 4.29 4.29 4
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i TABLE la.l.1 Minimum Frequencies for Checks, Calibrations and Testing of Heactor
- Protective System {$)
^L Surveillance Channel Description Function Frequeury Surveillance Method Comparison of four-power channel readings, S
a.
Check.g 1.
Power Hange Unrety Channels a.
g b.
Check '
D b.
Channel adjustment to agree with heat balance calculation. Hepeat whenever lux-T power compara alarms.
M(2)
Internal test signal.
c.
Test-c.
d.
Calibrate H
d.
Channel alignment through measurement /
adjustment of internal test points.
Comparison of both wide-range readings.
2.
Wide-Range logarithmic a.
Check S
a.
Neutron Monitors b.
Test P
b.
Internal test signal.
Comparison of four separate total flow 3.
Henctor Coolant Flow a.
Check S
a.
I"d1C"tl "8-Calibrate (6)
H b.
Kncun differential pressure applied to b.
r-O t'
mens rs.
){g)
M(2)
B1 stable trip tester.
c.
Test c.
[
h.
Thermal Margin / Low a.
Check:
S a.
Check:
s Pressurizer Pressure (1) Temperature (1) Comparison of four separate calculated Input trip pressure set point indications.
(2) Pressure (2) Comparison or four pressurizer pressure Input indications. (Same as 5(a) below.)
di b.
Calibrate H
b.
Calibrate:
(1) Temperature (1) Known resistance substituted for RTD
{
Input coincident with known pressure input.
(2) Pressure (2) Part of 5(b) below.
'"E" M(2)
Distable trip' tester. (1)(4) c.
Test c.
5 Ilich-Prescurizer Pressure a.
Check S
a.
Comparison of four separate pressure -
indications.
b.
Calibrate' H
b.
Known pressure applied to sensors.
B1 stable trip tester.II) c.
Test M
c.
g'OM
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--~-
.e S
TABLE h l.1 Minimum Frequencies fe Checks, Calibrations and Testing of Reactor Protective Systemg) (Cont.d),
Surveillance Channel Descript. ion Func t. ion Frequency Surveillance Method
- 6..St.etun Generator bevel n.
Check S
a.
Comparison of four level indications per i
gene rat.or.
b.
Calibrate H
b.
Known differential pressure applied to.
sens rs.
c.
Test.
M(2)
Distable trip tester.g) c.
7 Stenute Generator Pressure a.
Check S.
a.
Comparisons of four pressure indications per generator.
b.
Cali brut,e H
b.
Known pressure applie o sensors.
l M(2)
Distable t. rip tester.1 c.
Test c.
11.
Containment Pressure a.
".. librate H
n.
Known pressure applied to sensors, M(2) b.
Test.
b.
Simulate pressure swit.ch act. ion.
i 9
Loss of Load 3,
n.
- Test, P
a.
Manually trip turbine auto stop oil relays.
-f:
10.
M:inual Trips a.
Test P
a.
Manually t.est. both ci rcuits.
11.
stenctor Protectinn System a.
Test.
M a.
Internal test circuits.
logic thil ts 4
I Hot.e a:
(1) The bistable trip tester injects a signal into the bistable and provides a precision readout, of the t.r i p se t, po i n t..
$g (2) Al1 mont.hly tests wilI be done on only one of four channels at. a t.ime to prevent, reactor trip.
I a.g (j) Adjust, the nuclear gain pot, on the AT cabinet, unt.il readout agrees with heat balance calculations.
(h) Trip sett.ing for operating pinnp combinnt.icn only. Se t t.i ngs for other than operating pump combinat. ions
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y must, be tested during rout.ine monthly testing performed when shut down and within four hours after resmning operation wit.h a di fferent, pump combination if the set.t.ing for t. hat, combination has not been t.est.ed within the presions month.
(S) It is not necessary t.o perform the speci fled testing during prolonged periods in the regueling shut.down condition.
I f t.his occurs, omitted test.ing will be performed prior to returning t.he plant. l.o service.
l (6) The 1981 surveillance function may be deferred until the end of the 1981 refueling outage.
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TABLE 1.1.2 4
Minimum Frequencies for Checks, Calibrations and Testing of Engineered Safety Fcut.ure Instrumentat. ion Controls Surveillance Channel Descriptfor Func t. lon Frequency Surveillance Method 1.
Inw-Prcr.sure SIS Init.f ation a.
Check S
a.
Comparison of four separate pressure indications.
Channels Test.{g)p)
H b.
Signal to met.er relay adjust with test b.
device to verify SIS actuation logic.
c.
Test H
c.
Signal to meter relay adjusted with test device.
2.
Iow-Pressure SIS Signal Block a.
Test H
a.
Part, of 1(b) above.
Permissive and Aut.o Heset.
3 SIS Act.uation Helays u.
Test 4
s.
Simulation of SIS 2/14 logic trip using I
built-in testing system. Both " standby power" and "no standby power" circuits t
will be tested for left and right chan-nels. Test, will veri fy functioning of initiation circuits of all equipment normally operated by SIS signals.
b.
Test H
b.
Complete automatic test initiat.ed by g-same method as Item 1(b) and including
'D all normal automat.ic operations.
1 Cont.ainment, liigh-Pressure a.
Calibrate H
a.
Known pressure applied to sensors.
4
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Channels b.
Test.
H b.
Simulation of CllP 2/1 logic trip to 4
verify actuation logic for SIS, con-tainment is lati n and containment spray M(2)
Pressure switch operation simulated by g
c.
Test.
c.
opening or shorting terminals or pres-sure applied t.o the switch.
5 Containment, 'llie:h Hadiettion u.
Check D
a.
Comparison of four separate radiation Channels level indications, b.
Cal ibrat.e H
b.
Exposure to known external radiation source.
TABLE h.l.2 Minimum Frequencies for checks, Calibrations and Tect.ing of Eng.neered Unrety Feat.ure Inst.rumentat. ion Cont.rols (Contd)
Surveillance Channel Deuc ri pt.lon Func t. ion Frequency Surveillance Method 13.
Su rely inject.lon Tank ievel a.
Check S
a.
Verify that level and pressure indica-und Pressure Inst.ruments
- t. ion is between independent high high/
low alarms for level and pressure.
b.
Calibrate H
b.
Known pressure and different.ial pres-sure applied to pressure and level sensors.
14.
Iloric Acid Tank Level Svitcher.
u.
Test.
H a.
Pump tank below low-level alarm point to veri fy switch operat. ion.
t$.
II.oric Acid lleat. Tracing System n.
Check D
n.
Observe temperature recorders for proper readings.
f 16.
Check S
a.
Compare four independent pressure indi-n>
Ci rc ui t.n ca t. ions.
t ts. Test.{3)
H b.
Signal to meter relay adjusted wit.h test, device to verify MSIV circuit. logic.
17.
SilM Tank Tempernt.ure n.
Check H
a.
Compare independent t.emperat,ure readout.s.
g In.licat.lon and blurma b.
Ca li brat.e H
h.
Known resistance applied t.o indicating loop.
a.g 18.
Low-Pressure Safety Inject. ion n.
Check P
a.
Observe valve is open with air supply 3
Flow ' Control Valve CV-3006 isolated.
g 19.
Sarety inject. ion liot.t.le a.
Check P
a.
Ensure each valve open by observing valve Icolat. ion Valves position indicat. ion and valve itself.
Then lock open breakers (at. MCC-9) and control power (key switch in control room).
20.
Sa fety inject. ion Minirlow n.
Check P
a.
Valves CV-3027, 3056 Verify valves open and HS-3027 and 3056 positioned to maintain them open.
Notes:
(1) Calibration of t.he sensors is perrormed during calibration of Item S(b). Table 1 '.1.1.
4 (2) Att monthly t.ests will be done on only one channel at, a t.ine t.o prevent, protect. ion system actuat. ion.
(3) Calibration of the sensors is performed during calibrat. inn of Item 7(b), Table la.l.1.
(4) The 1981 surveillance function raay be deferred until the end of the 1981 refueling outage.
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Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controla (Contd) h nr+
2:
P Surveillance Chunnel liescription Function Frequency Surveillance Method u
5' Verify proper operation of all rod drive 8.
Control Hod Drive System a.
Test R
a.
control system interlocks, using minulated Interlocks signals where necessary.
g m.
b.
Test P
b.
Same as 8(a) above, if not done within three months.
m m
9.
Flux-AT Power Comparator u.
Calibrate R
a.
Use almulated signals.
b.
Test M
b.
Internal Leut algnal.
10.
Calorimetric Instrumentation a.
Calibrate H
a.
Known differential pressure applied to feed-water flow senuora.
11.
Containment building fiumidity a.
Test R
a.
Expose sensor to high humidity atmosphere.
Detectors
,k)12. Interlocks - Isolation Valves n.
Calibrate R
a.
Known pressure applied to sensor.
6*
on Suntdown: Coolle.g !.!ne Known differential pressure applied to 13.
Servlee Water Break Detector m.
Test R
a.
in Coiituinment sensors.
14.
Control Itoom Ventilation a.
Test R
a.
Check damper operation for DBA mode with 113-1801 and isolation signal.
b.
Test R
b.
Check control room for positive pressure.
l (1)
Item 2.c will only be performed on 7 rods (1 per bank). The During the 1978 refueling outage, secondary rod position surveillance (Item 3.c) will be performed in entirety. Additionally, a 20" rod poAltion check (comparing prtmary indication to uecondary indication) will be If the primary and secondary indications vary more than 2" f rom each conducted on each rod.
other, corrective action will be taken to restore the proper tolerances.
(2)The 1981 surveillance function may be deferred until the end of the 1981 refueling outage.
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CO:: TAIT:MFl*T TESTS (Contd)
~ k.5 (3) Visual inspection shall be made for excessive leakage from
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components of the system. Any. si6nificant leakage shall be measured by collection and veighing or by another equivalent method.
b.
Acceptance Criterion The maximum allowable leakage from the recirculation heat rc= oval systems' cceponents (which include valve stems, flanges and pump seals) shall not exceed 0.2 gallon per minute under the normal hydrostatic head from the SIRW tank (approximately hh psig).
c.
Corrective Action Repairs shall be made as required to maintain leakage within the acceptance criterion of h.5.3.b.
d.
Test Frequency Tests of the recirculation heat removal system shall be conducted at intervals not to exceed twelve months.
e.
The 1981 recirculation heat removal system test may be deferred until the end of the 1981 refueling outage.
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h.S.h Surveillance for Prestressing System a.
Tenden inspection shall be accomplished in accordance with the following schedule:
1 1.
One year after initial structural integrity test.
2.
Three years after initial structural integrity test.
3.
Five years after initial structural integrity test.
h.
At five-year intervals thereafter for the life of the plant.
b.
Surveillance tendons for the one-year inspection shall be the nine designated surveillance tendons plus V-10h and V-200.
In addition,15 vertical tendons shall be tested for lift-off forces only.
c.
For the three-year inspection, the surveillcnce tendons shal]
consist of the 11 tendons inspected during the one -/ car test plus an additional 10 vertical tendor.s to be tested for lift-off force only. The additional 10 tendons shall be selected from tendons other than those tendons tested for lift-off force during the one-year inspection.
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4-29 Amendment No jf, 66 9
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h.T EMERGENCY FOUER SYSTE4 PERIODIC TESTS (Contd) b.
Every three months, the specific gravity of each cell, the temperature reading of every fifth cell, the height of electrolyte, and the amount of water added shall be measured and recorded.
-k.T.3 Emergency Lichting The correct functioning of the emer6ency 11 sir. ting system shall be verified at least once each year.
The 1981 veriff eation may be deferred until the end of the 1981 refueling outage.
Basis The emergency power system provides power requirements for the engineered safety features in the event of a DBA. Each of the two diesel generators is capable of supplying minimum required safeguards equipment from independent buses.
This redundancy is a factor in establishing testing intervals.
The monthly tests specified above vill demonstrate operability and load capacity of the diesel generator. The fuel supply and various controls are continuously monitored and alarmed for abnormal conditions. Starting on complete loss of off-site power vill be verified by simulated loss-of-power tests at approximately yearly intervals (during refueling shutdowns).
Considering system redundancy, the specified testing intervals for the station batteries should be adequate to detect and correct any malfunction before it can result in system malfunction. Batteries will deteriorate with time, but precipitous failure is extremely unlikely. The surveillance specified is that which has been emonstrated over the years to provide an indication of a cell beccming unserviceable long before it fails.
References (1) FSAR, Section 8.4.1.
(2) FSAR, Section 8.5 2.2.
,4-43 Amendment No. 66
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