ML20041F420
| ML20041F420 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 03/08/1982 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20041F411 | List: |
| References | |
| NUDOCS 8203160482 | |
| Download: ML20041F420 (9) | |
Text
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= UNITED STATES
+/
.y y jt) e,( j'g. g NUCLEAR REGULATORY COMMISSION g *-
M, E
W AsHINGTON, D. C. 20555 8
c N...../
CONSUMERS POWER COMPANY l
DOCKET NO. 50-155 BIG ROCK POINT PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 51 License No. DPR-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The applications for amendment by Consumers Power Company. (the,
lic'ensee) dated October 3,1980 and October 27, 1981, comply 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 w'ith the applications, 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 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.
1 i
8203160482 820308 PDR ADOCK 05000155 P
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. DPR-6 is hereby amended to read as follows:
(2). Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 51, are hereby incor-porated 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 3,[-
Dennis M. Crutchfield, Cp'ef-Operating Reactors Branch #5 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
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ATTACHMENT TO LICENSE AMEN 9 MENT N0.51 FACILITY OPERATING LICENSE NO. DPR-6 DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages include the cap-tiened amendment number and marginal lines indicating the area of change.
PAGES 5-16 5-16a*
7-9a**
11-1 8 11 11-20 l
- This page is included for pagination purposes only. There are no changes to the provisions contained thereon.
- A wording error, which occurred during the issuance of a previo'us amend-ment, is corrected.
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~
l 5.2.2 (Cont'd)
(1)
It 'is -detennined by the investigation that any mal-function which has occurred neither impairs the ability to control-the reactor nor indicates the imminent im-pairment of the performance of additional components of the control rod system.
(2) The operating hydraulic water to the defective. control rod has been tagged and valved out to prevent withdrawal of the control rod after an attempt has been made to in-sert the control rod.
(3).The core shutdown margin requirement (described in ('b) above) can be met with the remaining operable control rods.
Evaluation of this requirement shall'be based on previous experimental measurements.
(g) Minimum Accuracy of Rod Position Indicatino System
.The control rod drive positions itself in 23 discrete positions over its travel. The position indicating system is of a digital readout design and indicates the drive position over a range of 1.5 inches for each position of the drive.
Control rods shall not be allowed to remain in position where the indication is not operable.
If all indication for a partic-ular control rod is lost, the rod shall not be moved until the indication has been restored, except for scram.
(h)
Operation of the Scram Dunc Tank Valves and Hich Level Alarm The scram dump tank vsnt (CV/NCil) and drain (CV/NCl2) valves shall be (1) verified open at least once per 31. days, and (2) cycled through at least one ccmplete cycle of full' travel once per quarter.
These valves may be closed inter.-
mittently for testing under administrative controls ~. At every refueling outage, the valves shall be tested to close within 20 seconds of receipt of a scram signal and the scram dump tank high level alarm shall be verified operable at a level of 10 + 1/2 inch below the tank centerline.
An unexplained high Tevel alarm shall require immediate investi-gation and if not cdrrected, subsequent insertior of all or all but one control rod drive within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
5-16
i 5.2.3 Licuid poison System The liquid poison system shall be available for operation at all times during refueling and power operatio.n. The reactor shall be shutdown in any situation where the poison solution tank level drops below an equivalent of 850 gallons 19 weight percent sodium pentaborate or where the poison solution storage temperature drops to less than 5'F above saturation temperature. The maximum allow-able concentration shall be 30 weight percent of sodium pentaborate.
The minimum worth of the liquid poison system (based on normal water level) shall be 25%Akeff.
Components of the system shall be checked at one to two month intervals for proper operation except for actuation of the injection valves.
The liquid poison system shall be used at any time when subcriticality cannot be assured by the normal shutdown mechanism.
Injecticn shall be i
continued until a minimum shutdown margin of 0.014L keff/keff is assured in the most reactive core.
The reactor shall not be operated after poison has been injected until the boron con-centration in the re' actor water has been reduced to 100 ppm or less.
One squib primer'and trigger assembly from the equalizing line shall be removed and test-fired at least every 12 months.
Thes'e shall be tested on an alternate basis ensuring valve replacement every two years.
One squib primer and trigger assembly from the remaining five units shall be removed and test-fired at least every 12 months.
These shall be tested on an alternate basis ensuring valve replacement every five years.
The tests shall consist of monitoring of the input firing current and shearing of the integral inlet cup.*
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'The surveillance testing identified in this Specification (which becomes due during February,1977, 'and would require a reactor shutdown) may be accomplished during the next shutdown of sufficient time duration to allow the testing.
However, the testing must be accomplished prior to startup following the next refueling outage.
Change'No. 33 5-16a Amendment No. A1,51 y
- - ~ -.
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4
7.6 (Contd)
7 Channel comparison check One month or less Section 6.4.3 of reactor level indi-catino instruments ~in the Reactor Bepressuri -
ing System 1
Calibration of reactor At each major Section 6.4.2 level incicating refueling shutdown instruments in the l
reactor Depressuiz-
.ing System Steamdrumsafetyvaive One month or less Section 4.1.2 position monitor check Calibration of steam drum At each major refueling
. Section t.cl.2 safety valve position shutdown menitors High Radiation Trip At each major refueling Section 6.4.2.
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Closure of the Contain-shutdown ment Ventilation Isola-tion Valves d
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11.3.5.3 (MLRC[NCY_fgM(R SOUliCLS (Contd) 11.4.5.3 EMERGENCY TDWT R SotmCf.S (Contd) 8.
Du ring react or pownr opora tion, the 2.
Monthly - -
138 kV line may he ont of service inr repair for porlods tip to throo ( 3)
(a) Test start diesel generator and operate at least EM fire pasap as days.
a load to 480 V _8us 28 u,or et least 20 minutes.
9.
If Specification A.8 le not met, a normal orderly shutdown shall be ini-tlated within one (1) hour and tlin (h) Verify that the cell voltage is reactor shall be shut down a s described 22.0 volts and specific gravity Is in Section 1.2.5la) within twntve (12)
>l.2 of each call of the station hours and shut' down as described in fia t te ry; and verify that the cell Section 1.2.5(n) and (b) within thn voltage is 26.0 volts and specific following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, gravity is 21.2 on each cell of the RDS batteries.
O.
During power and ref unl ing opera tions, the 2400 volt hus undervoltago components shall bo (c) Test operate the rod position motor operable or placed in the tripped condition, genera tor set.
oxcept during the monthly channel f ur.c t i ona l testing period.
(d) perform a channni functional test of the 2400 volt bus undervoltage trip system.
3.
Weekly -
(e) the electrolyte level of each RDS hattery pliot cell and the station hattery pilot cell is between the minians and maximuse level Indication marks.
(b) the plint cell specific gravity for RDS and. station batterles corrected to
( 71)*l, is 21.2.
(c) Ihn station battery pilot cell voltage is ?2.0 volts.
The RDS bettery pilot -
cell voltage is 26.0 volts.
(d) The ove ra l l batte:y voltage is 1125 volts f or the station battery and the RDS battories.
('e ) Test start the diesel generotor and run for wa rm-up period.
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