ML19345E388
| ML19345E388 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/09/1965 |
| From: | Doan R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Wall H CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| Shared Package | |
| ML19345E389 | List: |
| References | |
| NUDOCS 8101150833 | |
| Download: ML19345E388 (8) | |
Text
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UNITED STATEE C
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ATOMIC ENERGY COMMISSION R&PRSB Reading 3
I WASHINGTON. D.C. 20545 DRL Reading
, Originator: HSteele _
s o,,, d' bec: H. J. McAlduff,' OR00 g, g gy S. G. Case i
m ev ar"' '
H. Shapar Docket No. 50-155 L. Kornblii.h (2) i E. Trenenel R. Huard G. Page P. Travelstead 7
N. Stoner-Consumers P.swer Company Change.No. 7 1945 Parr. ell Road D. Skovholt Jacxson, Michigan C. Henderson Attention:
Mr. H. - R. Wall Vice President
!~
Gentlemen:
4 The Consumers Power Company, by letter dated March 26, 1964, as supplemented by letter dated May 21, 1964, and telegram dated.
,[
. July 13, 1964, has requested changes in the Technical Specificatione of License No. DPR-6, dated May 1,1964, for the Big Rock Point reactor. The-requested changes would modify the Technical Specifica-tions in accordance with 40 items enumerated in the e.bove referenced application.
j This request has been designated Proposed Change No. -7 and has been reviewed in accordance with the provisions of Section 50.59 of the Commission's regulations. We.have found that the proposed change does not present significant hazards considerations not described or implicit in the hazards summary report and there is reasonable assur-ance that the health and safety of the public will not be endangered.
A copy of the related safety evaluation is enclosed.
.l-Accordingly, pursuant to Section 50.59,10 CFR 50, the Technical Specificaticas of Operating License No. DPR-6 are changed as set j
forth in Attachment A to this letter.
Sincerely yours, Original Signed by R.L. Dom R. L. Doan, Director Division of Reactor Licensing j
l
Enclosures:
j 1.
Attachment A to Change No. 7 2.
AEC Safety Evaluation f
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ATTACHMENT A CONSUMERS POWER COMPANY CHANCES TO TECHNICAL SPECIFICATIONS CH ANGE NO, 7 (1) Item 1 - Delete the present Section 1.2, " DEFINITIONS", and substitute the following:
"1.2 DEFINITIONS Various provisions of these Technical Specifications set forth limita-tions and restrictions which depend upon modes of operation. The following modes of operation are defined to clarify the intent of such provisions, and are not the same as, nor should they be confused with, the positions of the mode selector switch described in Sectt.on 6.1.3.
1.2.1 Power Operation - is any operation other than shutdown or cold shutdown with the reactor vessel closure bolted in place.
1.2.2 Core Alteration - is any completed planned sequence of movements or core components resulting in either a net change in the con-figuration of the reactor core or a net gain in core reactivity.
1.2.3 Refueling Operation - is any operation with any of the reactor vessel closures open during which a cere alteration, or other operation which might increase core reactivity, is in progress.
1.2.4 Ma_ior Refueline - is any refueling operation with the head of f during which four or more fuel bundles are added, exchanged or repositioned in the reactor core.
1.2.5 Shutdown - is any reactor condition meeting the following re-quirements:
(a) All or all but one of the control rods are fully inserted in the reactor core; and (b) Primary system coolant water temperature is less than 212*.F.
1.2.6 Cold Shutdown - is a reactor condition involving no fuel in the core, or a reactor condition meeting the following requirements:
(a) All of the control rods are fully inserted in the core and withdrawal prevented by meacs of the keylock selector switch, the key to which is in the possession of the Shift Supervisor; and
1 )
1 (b) The reactor coolant system is at atmospheric pressure; and (c) The core shutdown reactivity control margin requirement has been verified in the manner set forth in Section 5.2.2(b)."
(2) Item 2 - Change the first sentence of Section 3.0, " REACTOR CONTAINNENT", to read as follows; i
" Reactor containment shall consist of an externally insulated spherical steel vessel, hereinafter referred to as the containment sphere."
(3)
Item 3 - In Section 3.4.3(c), change the closing tine for " Main Steam Drain (Ho 7065) from "7.5" to "60" seconds."
(4)
Item 4 - Change Section 3.5.2(c) to read ai follows:
"The proper operation of the automatic valves and associated controls of the spray system shall normally be functionally tested during each major refueling shutdown, but not less frequently than once every 12 months."
(5) Item 5 - Change Section 3.6, "CONTAINNENT REQUIREMENTS", to read as follows:
"Containmant sphere integrity shall be maintained during power operation refueling operation, shutdown and cold shutdown conditions except as speciflod by a system of procedures and controls to be established fuc occaP'.sns when containnent must be breached during cold shutdown."
(6) l~ em 7 - In Section 4.1.3, change the last sentence of the first paragraph c
to read as follews:
"A removable shield plug of a thickness 4 fett, 6-1/2 inches, consisting of 4 feet, 4 inches of concrete and 2-1/2 inches of lead, shall close the opening above the top of the reactor."
(7)
Item 8 - In Section 4.2.1(a), change the second paragraph to read as follows:
"The reactor safety system and related circuits are fed from four 120-volt a-c buses. Each of two buses is supplied from a dif ferent 480-volt system through its own motor-generator set.
Each motor-generator is equipped with a flywheel to sustain operation' during momentary power system disturbances.
The third bus is supplied from the 125-volt d-c system through a static inverter which supplies power to Nautron Monitoring Channel No. 3.
The fourth bus is supplied from the 125-volt d-c system through a motor-genera-tor set which supplies power to the control rod position indicating system.
The 125-volt d-c battery system also furnishes power for other critical services including:
Liquid Poisor tystem Controls Motor-Operate, <.utomatic Containment Sphere Isolation Valves Containment Sphere Ventilation System Isolation Valves Emergency Condenser Drain Valves Safety System Annunciators Emergency Lighting Swit chgear"
)
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4 (8)
Item 9 - In the third paragraph of Section 4.2 10, change the second sentence to read as follows:
"During turbine start-up and shutdown, and for short periods of time during normal operation, operation on speed control shall be permitted.
During such operation, the turbine load limiter shall be set to limit turbine output to correspond to the planned teactor output."
(9)
Iten 10 - In section 5.1.4, change the secord itera in the left-hand column, "Available Quantity of Solution, Gallons," to read "Poisen Tank Capacity, Gallons."
(10)
Item 11 - (a) In Section 5.1.4, change the fourth item, " Initial injection Cas Pressure, Psia 2080", to read a: follows:
"Initin! Injection Cas Pressure, Psia Condition Pressure
!! cad of f 500 licad On - Relief Valve Settir.gr 1250 1470 1500 1800 1750 2080" (b) Delete Section 5.2 in its entirety and redesignate Section 5.3 as Section 5.2.
(11)
Item 14 - Change the first sentence of the second paragraph of Section 5.3.2(s) to read as follows:
"The following tests shall be performed during each major refueling shutdown and at least once every-six months during periods of power operation."
(12)
Item 15 - Chang the last paragraph of Section 5.3.2(a) to read as follows:
"Insertio.. c' aa.h drive over its entire stroke with reduced hydraulic system press are to determine that drive friction is normal."
(13)
Item 16 -In Section 5.3.2(b), change the third paragraph to read as follows:
"During power operation, if reactivity and control rod motion data indicate a possible loss of poison from a control rod, the reactor shall be shut down and, if any corrective action is necessary, shall remain in shutdown condition until such corrective action has been taken".
(14)
Item 17 - In Section 5.3.2(d), insert the words "to be utilized" between the words " rod" and "shall" in the first line of the subparagraph entitled
",Rytine Coupling Intecrity Checks."
m m
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n (15) Item 18 - Change Section 5.3.2(e) to read as follows: -
" Control Rod Exercisinc DurinP. Sustained Power Operation -
At least once each day during sustained power operation, the operator shall exercise each control rod that is not at that time fully inserted in the core."
(16) Item 19 - Change the first parsgraph of Section 5.3.4 to read as follows:
"During initial los.'fr.g of a core, the moderator temperature and void coefficients shall 1 e measured.
(17)
Item 20 - Change (a) and (b) of Section 5.3.4 and eliminate paragraph (c) to read as follows:
"S.2,4 Reactivity Coe f ficient s a) The power coefficient shall meet the following requirement at all times during the reactivity life of the core: The control
' red movement required to produce a given power change with the reactor pressure constant and the reactor water at saturation temperature with this pressure shall always infer a negative power coefficient.
b) The moderator temperature coef ficient, over the reactivity life of the core, (inferred from critical control rod position) during uniform heating of the core shall be limited such that isalwayslessthanoned$kfa/K,gf the potential maximum A K added by heating the moderator r.
(18)
Item 21 - Change Section 5.3.5(a) to read as follows:
"All rods
- shall be fully inserted during the reactivity addition. In order co verify the core shutdown margin of 0.3% AKeff/K with the most valuabic rod completely withdrawn, the procedure outikned in f
Section 5.2.2(b) shall be utilized before and af ter any core alteration which may result in a net gain in core reactivity. During the reactivity addition, suberiticality checks, consisting of withdrawal of one control rod in the vicinicy of the component change, shall be made at the intervals indicated in Section 5.2.5(b)."
- " Removal of a control rod from the core by means other than normal control rod drive movement shall require that the four fuel bundles surrounding the control rod first be unloaded and that the control rod be properly reinstalled and checked out prior to reinsertion of the fuel bundles."
1 l (19) Item 22 - In the first sentence of Section 6.1.2.1, substitute the words e
"five deacdes above source level, without moving detectors, (approximately 10-9 to 10-4 -of rated power)" for the words " rated power."
(.'0)
In Section 6.1.2.2 change the first and last sentences to read as follows:
" Channel 4 and 5 provij% to rated power for the 84 bundle core."
e logarithmic neutron flux level and period information from approximately 10-
"The detectors shall be gamma cogensated ion chambers with a design sensitivity of at least 2.2 x 10-14 ampe res /nv."
(21) Item 24 - Change the first and -last sentence of Section 6.1.2.3 to read as follows:
4
" Channels 1, 2 and 3 shall provide linear neutron flux level information from approximately 10-7% tc 125% rated power for the 84 fuel bundle core."
"The detectors shall be gamma comgensated ion chambers with a design sensitivity of at least 2.2 x 10-amperes /nv. The amplifier output shall be connected to the reactor safety system."
(22) Item 26 - Change Section 6.1.2.5, " NEUTRON MONITORING RANGE SWITCH", to read
' as follows:
"The range switches on the three power level instruments contain resitor-capacitor feedback circuit combinations which can be switched to provide nine decades of overlapping power level indication. The unit also contains interlock contacts used in conjunction with the upscale-downscale trip units of the piccammeters."
(23) Item 27 - In Section 6.1.3 dbange the second sentence of the introductory paragraph to read as follows:
"A key-lock reactor mode switch shall be provided, having ' Shutdown',
' Re fuel', ' Bypass Dump Tank' and ' Run' positions."
l Also, under the tabt.lation of functions, delete the pos. tion ' Start-Up' and i
its trip function 'None (e)." Add the reference "(e)" to the trip function for "Run".
i (24) Item 28 - Change Section 6.1.5(a) to read as follows:
"Except as otherwise provided in these Technical Specifications, the reactor safety system shall be operable during power operation as indicated in Section 6.1.2.
This system shall be functionally tested during each major refueling" shutdown, but not less frequently than once every 12 months, and in addition shall be teste' not less frequently than once a month using the switches provided to simulate sensor trips."
(25)
Item 29 - Change Section 6.1.5(b) to read as follows:
"The core apray system and emergency condenser control initiation sensors shall be functional?y tested not less frequently than once every 12 months."
4
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. 1 (26)
Item 30 - In Section 6.1.5(d), change the second sentence to read as follows:
"For reactor operation above approximately 5% of rated p5wer, the logariths neutron flux level information and period scram protection are not required (see Section 6.1.2)."
(27) Item 31 - Change Section 6.1.5(h) to read as follows:
" Minimum nuclear instrumentation in operation during shutdown operation shall be the same as that required for refueling operation, except that only one start-up range monitor shall be required."
(28)
Item 32 - Substitute the following for the last sentence in Section 6.2.2:
" Permissive circuits shall be-functionally tested not less frequently than once every 12 months. However, the refueling interlocks will be functionally tested prior to each major refueling."
(29)
Item 33 - In the parenthetical phrases in Sections 6.3.2(a) and (b), delete
", and monorial crane "
(30)
Item 34 - In thg last sentence oj the second paragraph of Section 6.4.l(a),
substitute "10-to 10" for "10-to 100", and change the last paragraph to read as follows:
"A trip circuit in the air ejector of f-gas monitor shall have an alarm which shall annunciate in the control room. The air ejector off-gas monitor trip circuit shall also initiate action of a time-delay switch, which in' turn shall trip the off-gas shutof f valve closed after a pre-selected delay adjustable up to 15 minutes.
(Off-gas average holdup time is about 30 minutes.) Alarm and trip settings shall be as specified in Section
- 6. 4. 3(a)."
In the fourteenth line of Section 6.4.1(b), substitute "10-4 to 10" for the "10-3 to 100."
(31) Item 35 - In the eleventh line of Section 6.4.3(a) and in the eighth line of Section 6.4.3(b), substitute "5 curies" for "10 curies."
(32)
Item 36 - In Section 6.4.3(e), substitute the following for the last two sentences in the second paragraph:
"The films at each station shall be replaced and analyzed at least monthly."
Also, change the last two sentences of the third paragraph to read as follows:
"One film at each station shall be replaced and analyzed at least every two weeks. The second film shall be replaced and analyzed monthly."
i
. l (33) Item 37 - In the last sentence of Section 6.4.3(f),
. _ _ ut e "on ce e ve ry three months" for " monthly."
(34) Item 39 - In Section 7.0, "0PERATING PROCEDURES", change the introductory paragraph to read as follows:
"This section describes those basic operating principles and procedural safeguards which have a potential ef fect on safety. Operating principles and procedures are presented for normal and emergency operation of the plant, for Phase II testing within the Research and Development Program, and for operational testing of the nuclear safeguards systems of the plant."
(35) Item 40 - In the first line of Section 7.2.3, delete the words " Review of."
(36) Item 41 - In the second sentence of Section 7.3.2(1), delete the phrase
" and the reactor reaches rated pressure,".
(37) Item 42 - Change Section 7.4(a) to read as follows:
" Detailed written procedures shall be available prior to each refueling operation."
(38) Item 43 - Change the second paragraph of Section 7.4(b), to read as follows:
" Fuel shall be replaced according to the following sequence (i)
Removal of selected bundles from core and transfer to spent fuel storage.
(ii) Reshuffling of remaining bundles in core as desired.
(iii)
Insertion of new bundles in vacant positians as desired. Shutdown margin verifications and suberiticality checks shall be made as required by Section 5.2.5."
(39)
Item 44 - Change the second paragraph of Section 7.4(c), to read as follows:
"No additional instrumentation need be placed within the core lattice if the out-of-core instrumentation produces a significant response to the suberiticality check in the region to be altered.
If this criterion I
cannot be met, a low-level neutron detector, measuring neutron flux, shall be located near the region to be altered."
(40)
Item 45 - Change Section 7.5.7, to read as followe r "It shall be permissible to remove a centrol rod drive from the corc when the reactor is in the shutdown xenon free condition and the mode selector switch is locked on the " shutdown" or ' Bypass Dump Tank" position while the drive is r~ moved. The core shutdown margin of 0.3% /iK gf/Keff e
with the strongest r d out of the core shall have been met prior to the drive removal; and, in addition, the equipment shall be properly tagged. The control rod drive that was removed shall without delay be replaced by a spare drive or the original drive shall be reinstalled."
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