ML20206D974
| ML20206D974 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/14/1988 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206D979 | List: |
| References | |
| NUDOCS 8811170343 | |
| Download: ML20206D974 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20044 k*...+
CONSUMERS POWER COMPANY PALISADES PLANT DOCKET NO. 50-255 AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.115 License No. OPR-20 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applicatiens for amendment by Consumers Power Company (the licensee)datedAugust19andAugust 24, 1988, comply 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 applications, the provisions of tie Act, and the rules and regulations of the Comission; C.
There 1* reasonable assurance (1) that the activities authorized by this atendment 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 appitcable requirements have 1
been satisfied, i
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t i 2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendrent and Paragraph 3.B. of Provisional Operating License No. DPR-20 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Aspendices A and B, as revised through Aaendment No.115, are.1ereby incorporated in the license. Tne licensee shall operate the facility in accordance with the Technical Specifications.
3.
- his licenst amendment is effective as of the date of its issuance.
F09 THE NUCLEAR REGULATORY COMMISSION ajew h
^^p Theodore Quay, Acting Director Project Directortte III-1 Division of Reactor Projects - III, lY, V
& Special Projects
Attachment:
Changes to the Teciinical Specifications i
Date of Issuance: November 14, 1988 s
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O ATTACHMENT TO LICENSE AMENDMENT NO.1i5 PROVISIONAL OPERATING LICENSE NO. OPR-20 DOCKET NO. 50-255 Revise 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 3-81a 3-81a 3-81b 3-81b
' 4-ta 4-2a 4-10 4-10 1
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Table 3.17.4 (Cont'd)
Minimum Minimum Permissible Operable Degree of Bypass g
Functional Unit Channels Redundancy Conditions 3.
Pressuriser Wide Range 2 (1, p, q)
Mone Not required in
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Water Level Cold or Refuel-
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Indication ing Shutdown
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Pressuriser Code 1 per None Not Required Safety Relief Valves Valve below 375'T Position Indication (Acoustic Monitor or Temperature Indication) 10.
Power Operated Relief 1 per None Not required when Valves (Acoustic Valve PORV isolation valve Monitor or Ta'aperature is closed and its Indication) indication system is operable 11.
PORY Isolation Valves 1 per None Not required when Position Indication Valve reactor is depressurized and vented through a vent 21.3 sq.in.
12.
Subcooling Margin 1
None Not required Monitor below 515'T 13.
Auxiliary Teed Flow 1 per flow (h)
None Not required Rate Indication Control below 325'T Valve 14 Auxiliary Teedwater 2persteg) 1 Not required Actuation System generator below 325'T Sensor Channels II) 15.
Auxiliary Teedwater 2
1 Not required Actuation System below 325'T Actuation Channels II 16.
Encore Dttector I
(e)
AuxiliaryTeedwaterSystemActuationSystesSensorChannElscontainpump
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auto initiation circuitry. If two sensor channels for one steam generator are (noperable, one of the steam generator low level bistable modules in one et the inoperable channels must be in the tripped condition.
3-81a Amendment No. 67, if, 96,115
Table 3.17.4 (Cont'd)
(f)
With one Auxiliary Peedwater Actuation Systes Actuation Channel inoperable, in lieu,of the requirement of 3.17.2, provide a second licensed operator in the control room within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. With both inoperab1ra, in lieu of following the requirements of 3.17.2, star, and reintain in operation the turbine friven auxiliary feed pump.
(g)
Calculate the Quadrant Power Tilt using the encore reatings at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the encore detectors deviation alarus are inoperable.
(h)
With two flow rate indicators inoperable for a giver control valve, the control valve shall be considered inoperable arJ the requirements of 3.5.2(a) apply.
(1)
The previsions of Specification 3.0.4 are not applicable.
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(p)
With one OPERABLE Pressurizer Wide Range Water Level Channel in
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lieu of the requirement of 3.17.2, restore the inoperable channel
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to OPERABLE status within 7 days or be in at least BOT SHUTDOWN
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within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(q)
With no OPERABLE Pressuriter Wide Range Water Level Channels in
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lieu of the requirements of 3.17.2, either restore at least one
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of the inoperable channels to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />,
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or be in at least HOT SEVTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />."
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3-81b Anandment No. ff, pf, 115
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i 4.1 Basis (continued)
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For the specified one-month test interval, the average unprotected f
time is 360 hours0.00417 days <br />0.1 hours <br />5.952381e-4 weeks <br />1.3698e-4 months <br /> in case of a f ailure occurring between test intervals, thus the probability of failure of one channel between test intervals is 360 x 1.14 x 10-5 or 4.1 x 10~3 Since two l
channels must fail in order to negate the safety function the i
I probability of simultaneous failure of two-out-of-four channels is l
(4.1 x 10' ) = 6.9 x 10-8 This represents the fraction of time in which each four-channel system would have one operable and three l
inererable channels and equals 6.9 x 10'I a 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per year or 2.16 seconds / year.
These estimated are conservative and may be considered upper limits.
l Testing intervals will be adjusted as i.ppropriate ' cased on the v
4 accumulation of specific operating history.
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I The testing frequency of the process instrumentation is conside:ed i
adequate (based on experience at other conventional and nuclear y
plants on Consumers Power Company's system) to maintain the status 4
j of the instruments so as to assure safe operation. As the reactor l
protection system is not required when the plant is in a refueling i
j shutdown condition, routine testing is not required.
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Those instruments which are similar to the reactor protective system I
i instruments are tested at a stallar frequency and on the same htsis.
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Since the wide and narrow range indicators are calibrated at
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j different temperatures it is not appropriate to compare the wide
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t range instruments with the narrow range. The shift comparison
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l surveillance requirement. Table 4.1.3, item No. 7a.. is intended
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to compare the two wide range indicators with each other and the
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t two narrow range Indicators with each other.
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Amendment No. 51, 115 i
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TABU: 4.1.3 Minimum Frequencies for Checks. Calibrations and Testing of Miscellaneous Instrumentation and Controls Surveillance Channel Description Function Frequency Surveillance Method 1.
Start-Up Range a.
Check N
a.
Comparfson of both channel count rate Neutron Monitors indications when in service.
b.
Test T
b.
Internal test signals. 45 2.
Primary Rod a.
Check 5
a.
Comparison of output da a with secondary Position RPIS.
Indication b.
Check b.
Check of power dependent ipsertion limits System monitoring system.
gg) c.
Calibrate R
c.
Physically measured rod drive position used to verify system accuracy. Check rod position interlocks.
3.
Secondary Rod a.
Check 5
m.
Comparison of output data with primary RFIS.
Position Indication b.
Check M
b.
Same as 2(b) above.
II}
System c.
Calibrate R
c.
Same as 2(c) above, including out-of-sequence alarm function.
4 Area Monitors a.
Check D
a.
Normal readings observed and internal Note Process test signals used to verify instrument Monitor Surveil-operation.
lance Requirements b.
Calibrate R
b.
Exposure to known external radiation are located in source..
Tables 4.24-1 and c.
Test M
c.
Detector exposed to remote operated 4.24-2 radiation check source or integral
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electronic check source.
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5.
Emerger.cy Plan Radia-a.
Calibrate A
a.
Exposure to known radiation source.
tion Instruments b.
Test M
b.
Battery check.
6.
Environmental a.
Check M
a.
Operational check.
Monitors b.
Calibrate A
b.
Verify airflow indicator.
7.
Pressurizer Level a.
Check S
a.
Comparison of two wide and two marrow
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Instruments range ind s f xt level readings.
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b.
Calibrate R
b.
Knoun differential pressure applied to sensor.
c.
Test M
c.
Signal to meter relay adjusted with test device.
4-10 Amendment No.14 U, 38, $5,115 9
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