ML20046A827
| ML20046A827 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 07/15/1993 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20046A828 | List: |
| References | |
| NUDOCS 9307300110 | |
| Download: ML20046A827 (7) | |
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'o UNITED STATES' Ly 3 1 ' NUCLEAR REGULATORY;COMM4SION I
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f I ,o q r i F ILLINDIS POWER COMPANY. ET Al. ' DOCKET-NO. 50-461 CLINTON POWER STATION. UNIT N01 1. 4 AMENDMENT TO FACILITY OPERATING LICENSE lq ' Amendment. No. 78 m License No. NPF,. 1. The Nuclear Regulatory Commission (the Commission) has 'foundithat: 1 .A. The application for amendment by Illinois Power Company *-(IP),:.and.? Soyland Power Cooperative, Inc. (the licensees) dated April 16,' 1992, complies with the standards and requirements of:the Atomic; Energy Act of 1954, as amended'(the Act), and the Commission's= rules and regulathns set.forth in:10 CFR Chapter;I; B. The facility will operate in conformity with:the1 application,--the provisions.of the Act, and the rules and regulations; of. the. Commission; C. There is reasonable assurance.(i)'that the activities authorized: l by this amendment can be conducted withoutu endangeri_ng the health I and ~ safety of the public, and. (ii) Lthat;such' activities"will be : q 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- .i 4 -E. The issuance of this amendment 1s.in accordance with 10 CFR- [ 4 Part 51 of the Commission's regulations:and all applicable ?! requirements have been satisfied. 2. Accordingly, the license is amended by changes totthe Technical'Specifi-cations as indicated in the attachment to this license, amendment, Land paragraph 2.C.(2) of Facility Operating. License No'.' NPF-62 is.hereby d , amended to read asifollowst-l '
- Illinois Power Company is authorized to act as agent for Soyland Power ~
4 s Cooper'ative, Inc. and has exclusive responsibility and control?over; thel physical construction, operation and maintenance.of the facility. }i i .u I 9307300110 930715W N ' PDR' ' ADOCK- 05000461
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._v r T, q 1 (2). Technical Specificitions and Environmental Protection Plan ~ .The Tech' ical ~ Specifications contained in Appendix A and the i n Environmental'_ Protection Plan contained'in Appendix B, :as revised l -through' Amendment No. 78, are hereby incorporated:into:this' ~ license. Illinois Power Company shal1< operate.the facility in. ' I accordance with_the Technical Specifications and the Environmental: Protection ~ Pl an.- 1 I - 3. This license amendment'_is effective as of its date 'of issuance. FORTHENUCLEAR'REGULATORYCOMNISSION a h James E. Dyer, Director: l Project' Directorate III-2' -Division of Reactor Projects. III/IV/V-- ~ ~ Office of Nuclear Reactor Regulation-
Attachment:
' Changes to the Technical 1 Specifications 'j 1 Date of Issuance: July 15,' 1993 a [j r; -,. i m -t f fi 7 y V Y. : > 0 r ; 1 2 i N fi[t -{ .j 5 a +- +
W i j ATTACHMENT TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. NPF-62 DOCKET NO. 50-461 i Replace the following pages of the Appendix "A" Technical Specifications with i the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change..The corresponding overleaf pages, as indicated by asterisks, are provided to maintain document completeness. Remove Paoes Insert Paoes 3/4 1-21 3/4 1-21 B 3/4 1-3* B 3/4 1-3* B 3/4 1-4 B 3/4 1-4 B 3/4 1-5 B 3/4 1 : i h 'I a 'l
1 m LCW ..KYEL -- 3Y DFLOW -uw avr - z9 u e p g ..................u.' a oW wn A: -i v> .................na e = ks; s u m s O h @z 5 A, r GO r x wF a< u s C ""~ i sn wux 32 awa=w ~w CONCENTRATCH. @o = A vag '\\ so n s z o x' w o 's,, ,g .s I b 9 374 d37 je r .o .a 3000 3500 4000 4600 8000 5500 NET TANK VOLUME (gallons) Figure 3.1.5-1 Weight Percent Sodium Pentaborate Solution as a Function of Net Tank Volume CLINTON - UNIT 1 3/4 1-21 Amendment No. 78
J 'l -REACTIVITY CONTROL SYSTEMS
- 1 BASES 3/4.1.3 CONTROL RODS (Continued)
CORE ALTERATIONS that could have affected the control rod cogling integrity._ j The subsequent check is perfonned as a backup to the initial; demonstration' i In order to ensure that the control rod. patterns can be followed and therefore that other parameters are within their limits, the control rod position indica-~ tion system must be OPERABLE. The controi rod housing Jupport restricts the outward movement of-a control rod l ~ to less than 3 inches in the event of. a housing failure.. The amount of rod reactivity which couldlbe added by this small amount of rod withdrawal'is less than a normal withdrawal increment and will not contribute to any damage to the primary coolant system. The support is not required when there is-no pressure to att as a driving. force to rapidly eject a drive housing. q' The required surveillance intervals are adequate to determine that the rods are ~ l OPERABLE and not so frequent as to cause excessive wear on the system components. 3/4.1.4 CONTROL ROD PROGRAM CONTROLS 1 The rod withdrawal limiter system input power signal;orginates from the first stage turbine pressure. signal indicates a core power level which is less than'theWhen operating with t Consequently, near the low power setpoint and high power setrue core power,. tpoint of the rod pattern control system, the potential exists for nonconservative~ control rod withdrawals. Therefore, when operating at a sufficiently high' power level, there is a small probability of violating fuel Safety Limits during'a licensing ~. jj basis rod withdrawal error transient. To ensure that fuel Safety Limits are'- not violated, this specification prohibits control rod withdrawal when a biased power signal exists and. core power exceeds the;specified 'evel. Control rod withdrawal and insertion sequences are established to assure that the maximum-insequence individual control rod or '.:ontrol rod ' segments which 'are withdrawn at any time during the fuel cycle cald not be ' worth enough' to result in'a peak fuel enthalpy greater than 280 cal /ge in the kvent' of a control rods drop accident. ~ The specified sequences are characterized by homogeneous, scat-tered patterns of-control rod withdrawal. WhenLTHERMAL POWER'is greater than 20% of RATED THERMAL POWER, there.is no possible rod worth which,-if dropped at _ j the design rate of'the ' velocity _ limiter, could result-in a peak enthalpy off 280. cal /gm. Thus requiring the RPCS to be OPERA 8LE when THERMAL POWER _is less-than or equal to 20% of RATED THERMAL POWER provides adequate control. _ j The RPCS provide automatic supervision to assure that out-of-sequence rods will' not be withdrawn or inserted. a i CLINTON - UNIT 1 8 3/4 1-3 l c
m REACTIVITY CONTROL SYSTEMS BASES ' 3/4.1.4 CONTROL R0D PROGRAM CONTROLS (Continued) The analysis of the rod drop accident is presented in Section 15.4 of the USAR and the techniques of the analysis are presented in a. topical report, ' Reference 1, and two supplements, References 2 and 3. The RPCS is also designed to automatically prevent fuel damage in the event of erroneous rod withdrawal from locations of high power density during higher power operation. A dual channel system is provided that, above the low power setpoint, restricts the withdrawal distances of all non-peripheral control rods. This restriction is greatest at highest power levels. 3/4.1.5 STANDBY LIOUID CONTROL SYSTEM The standby liquid control system provides a backup capability for bringing the reactor from full power to a cold, xenon-free shutdown, assuming that the withdrawn control rods remain fixed in the rated power pattern. To meet this' objective it is necessary to inject a quantity of sodium pentaborate solution which produces a concentration of 660 ppm in-the reactor core and other piping-systems connected to'the reactor vessel. To allow for potential leakage and imperfect mixing this concentration is increased by 25%. The required concentration is achieved by having a minimum available quantity of 3574 gallons of sodium pentaborate solution containing a minimum of 4246 lbs. of sodium pentaborate. This quantity of solution is a net-amount which'is above the storage tank level instrument zero. (The instrument zero is based on ensuring sufficient net positive suction head and includes additional. margin to preclude air entrainment in the pump suction piping due to vortexing during two-pump operation.) The pumping rate of 41.2 gpm per pump provides' a negative reactivity injection rate over the permissible pentaborate solution volume range, which adequately compensates'for the positive reactivity effects due to temperature and xenon during shutdown. The temperature requirement is. necessary to ensure that the sodium pentaborate remains in solution. -The sodium pentaborate solution is required to be maintained within the boundaries of Figure 3.1.5-1. - The boundaries of this figure are based on system design limits. Maintaining the sodium pentaborate solution'within the boundaries of Figure 3.1.5-1 ensures sufficient solution is available to bring the reactor to shutdown in accordance'with the' system design basis. With redundant pumps and explosive. injection valves and with a highly-reliable control rod scram system, operation of the reactor is permitted to continue for short periods of time with the system inoperable or for longer periods ofz time with one of.the redundant components inoperable. 4 1. C. J. Paone, R. C. Stirn and J.- A. Woolley, " Rod Drop Accident Analysis for Large BWR's," G. E. Topical Report NED0-10527, March 1972 2. C. J. Paone, R. C. Stirn and R. M. Young, Supplement I to NED0-10527, July 1972 3. J. M. Haun, C. J. Paone and R. C. Stirn, Addendum 2, " Exposed Cores," Supplement 2 to NE00-10527, January 1973 CLINTON - UNIT 1 B 3/4 1-4 Amendment No. 78
' REACTIVITY CONTROL SYSTEMS ' BASES 3/4.1.5 STANDBY-L10VID CONTROL SYSTEM (Continued) Surveillance requirements are established'on a frequency that assures a high ~ reliability of the system. Once the solution is established, sodium penta-borate concentration will not vary unless more sodium pentaborate or water is added, thus a check on the temperature and volume once each 24 hours assures-that the solution is available for use. Replacement of the explosive charges in the valves at regular intervals will' assure that these valves will not fail because of deterioration of.the charges. l i:- .I i i F CLINTON - UNIT 1 B 3/4-1-5 Amendment No.' 78 j d =}}