ML19344B593

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Tech Specs 4.2 Re Nuclear Instrument Power Range,Safety Channels & Waste Disposal During ATWS
ML19344B593
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 09/12/1980
From:
DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML19344B592 List:
References
NUDOCS 8010210598
Download: ML19344B593 (13)
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Text

{{#Wiki_filter:. ATTACHMENT.1 TECH. SPEC. 'PAGE, . 4.2.6.7. During operation in the nuclear instrument power range, at least three 'of nuclear channels 5, 6, 7, and 8 shall be in operation. Whenever a channel is deliberately made inoperative, its scram contacts shall be placed in the trip position. 4.2.6.8 Safety channels directly backed up by'an identical channel or channels, performing the same safety function may be bypassed for maintenance. -Safety channels in the partial-scram circuit may be bypassed for maintenance provided that the reactor shall be brought to a condition under which the channel protection is not required if the' bypass cannot be removed within 24 hours. 4.2.6.9 Both reactor forced circulation pumps shall be automatically shut down by a high reactor pressure signal or by a low reactor water level signal. Bases - The-RPTS is a diverse and. independent backup except for common current sensing loops to the normal scram system for rapid shu+down of the reactor. To protect the primary system from an ATWS event in which either MSIV closes at power, thus eliminating the main condenser' as a heat sink, the recirculation pumps must be shut down to prevent damage to the primary system. A rapid 4 shut down_ of the recirculation pumps has the effect of causing an increase in the moderator voids in the reactor core. A substantial negative reactivity results and the power and pressure surges that might otherwise occur in the most limiting transient (MSIV closure) are. substantially reduced. With the recirculation pumps shut down, the reactor power will be reduced to a steady state power level of'less than 20% (based on natural circulation through the core). 4.2.7 Waste Disposal 4.2.7.1 - All liquid waste system radioactive effluents shall be batch-sampled and analyzed prior to release. 4.2.7.2 Disposal of the radioactive gaseous waste shall be through the stack, with at least one stack blower in operation. The discharge rates shall not exceed the limits in the following chart. The maximum permissible concentra-tions (MPC in micro curies per ml) shown in this chart are for individual isotopes and mixtures listed in Column 1,. Table II, Appendix B of 10 CFR 20. s L... L841021opf

ATTACHMENT 1' -t n . TECH. SPEC. PAGE-36a - .~ ,I. TWO-BLOWER OPERATION Column 1 Column 2 Colunn 3' Maximum curies per second Curies per second to.be Type'of Activity-to be released' released, avg. ove. 1 yr. Particulate matter and ~ halogens with! half lives . longer'than 8 days 5.1 x 103 x MPC 5.1 x 10 'x MPC 2 All other radioactive isotopes 3.4 x 106 x MPC 3.4 x 105 x MPC II. ONE-BLOWER OPERATION Particulate matter and halogens with half lives ~ 2 x MPC longer than 8 days 2.4 x 103 x MPC 2.4 x 10 -All other radioactive-isotopes 1.6 x 106 x MPC 1.6 x 105 x MPC 4 9_. r t l~ l- --11'- tj s

'ATTACFIMDTIl TECH. SPEC. PAGE: - g l Channels Action Minimum Frequency 22. CRD accumulators. low gas . Test Prior to each plant startup if l l pressure scram relay test has not been performed within 30 days.. Check. pressure Weekly I' indication L

23. - Turbine stop valve.

Test Prior to each plant startup if test has not been performed f within 30 days. 24. Reactor Pressure'(RPTS) Calibration At each refueling shutdown

25. Reactor Water Level Calibration At'each refueling shutdown l

(RPTS)

  • Test shall inc1Jde tripping of the scam relays K-114.

l 5.2.16 Corrosion est coupons shall be inserted in the forced circulation l loop to evaluate tne corrosion deterioration of chromium-molybdenum piping;- L and that piping shall be replaced if-the reduction in pipe. wall thickness, as indicated by weight loss.and metallographic evaluation of the test coupons, i is greater than 0.190 inches. The replacement piping shall be stainless steel l. or shall be clad internally with stainless steel and shall meet the design L . requirements of Section 2.3.2. i

TABLE'1 - OPERATING LIMITS'- (Cont'd) ITEM N0. CONDITION CHANNEL OR SENS0R' SET I3 INT ' ACTION KEYSWITCH BYPASS PROVISIONS '18 -reactor building 'rodiation monitors 4 radiation levelt closure of ventil-none ventilation. which correspond. ation dampers exhaust to Column 2 of the limitations given in Sec. 4'.2.7.2 19 simultaneous low pressure transmitter 25-30 psig and opening'of diaphragm 12" below nomin-valve allowing water reactor pressure and water level and low water-safety channel 1 al indicated to flow directly.from level or 2 level overhead storage tank to core spray nozzles

20 simultaneous high reactor building 1 5 psig and opening of motor reactor building

. pressure. transmitter i 12" below operating valves and pressure and 1 or 2 and reactor nominal indi-start of engina driven K) - reactor low water water level safety cated level pumps of alternate -level channel 1 or 2 core spray system 21

steam safety position switches open-close none - post accident' none valves not fully on each of the indication only closed three inservice safety valves 22 high reactor 3 reactor pressure i 1350'psig or trip of both recirc-the protective function pressure or low or 3 reactor level 1 30 inches below ulation pump breakers can be. bypassed when,ever reactor water

' transmitters nominal indicated the reactor is~ shutdown level level or recirculation pump operation is required for safety reasons. h? Ei ~Pr 529 4? ?? 8 25 - n. T r.

t [ ATTACHMENT 1 i . 6.: SCHEDULE-L' Procurement 'of necessary compor.ents and detailed f hial: design has commenced; With timely 1 receipt of necessary hardware, installation is L 'schedulea during the next. refueling outage (September-October zl980). t l ~ 7. REFERENCES l s.- (1), LAC-2788:- J.EP. Madgett to A. Giambusso, Dairyland Power-Cooperative,'LACBWR, Provisional Operating License No. DPR-45, Full-Term License Application, dated October 19, 1974. (2) NRC Letter:- V. Stello to J. P. Madgett, re:

LACBWR, dated August. 31,'1976.

(3)- LAC-4270: J. P. ' Madgett-to V. Stello, Jr., Dairyland - Power Cooperative, LACBWR Provisional Operat: rg License-LNo. DPR-45, LRecirculation Pump Trip Modification, dated October 13, 1976. L (4) NRC Letter: D. L. Ziemann to J. P. Madgett, re:

LACBWR, dated May 15,-1978.

l l l l- ^ i. (. r h L h-l L. : 1

RECIRCULATION PUMP TRIP SYSTE1 --LOGIC DIAGRAM P: P P L L 7 2 3 y 2 3 .PRbhbRE PRShRE PRShbRE LkhfL LkhL Lk\\ L I I I I LbbkC LbbfC l d___ - -TRIP REMY TgLAY IP Ru I l CIRCUIT CIRCUIT BREAKER BREAKER J RjgC RgACT0R ggEL; RhCl,C 1A. G 1 FIGURE 1 A

RX: STEAM PRESS. RX - STE AM PRES S. 64-35 '307 'To TURBINE PT PT B-25 a 64-3s-son T/6 IIGM-D52-0 41-503757 o-1600 PSIG. (W/D 41-503036) M63 - ALARM P3 G4 GO3 B25% 64-35-301 REMOTE AMP POWER SUPPLY REAR i C4-35-401 PML E M ~~ MG3 M P P. S % u_ gg P33 Mr.3 Eli M64 2CH RECORDER 64-35-511 i i ~ RED GREEN \\ MC. B24-2 TO ~ RX SAFETY i i GYSTEM Reo MARROW RANGE (SCHEM. 41-50 3-213) m STEAM DUMP a O <COMTROLLER

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l CD

62. H O-M /6420-DFO RECORDE R iyt.

$ PROPOSED MODIFIC ATio ps B-25 64-35-801 v-f FIGURE 2 -..I

Rx STEAM TO TURBIME 4I-Sos 758 PT 41-503757 LT' Rx WATER LEVEL 3 g4_35.goz 50-42-306 8-54a - I PRESS.TRANS. T/6tiqM-Dsz-o 0-1600 PSI (W/D. 503823) REMOTE AliPL, 50 302 A REA R 64-35-302 PNL*E" B-54q-l } REMOTE AMP. A POWER,5UPPLY W 50- 42-403 M-s3$ ~* W 4

9. s.

x g M-63 REL. 50 7/2 W M4 INDICATIA/Q M~63 TO Rx SAFETY SCVN-L-33 SYSTEN\\ PNL SCHEM

  • E" Nyl65 PX-OHW 41-503-213)

/ g4 35_gog ~ 50-42-81I INDICATOR 5 PROPOSED Moon Fic_ATIoM

F f ~ i RX WATER LEVEL 1 r. T o 60-42-302 50-42-303 LT F-El b -l LT F-2 i b - 2 LEVEL TRANS. LEVEL TRANS. 41-503759 TA l30M-H52- 0 TA 130 M-HE2-0 . (%f/D 41-503823) (W/D 41-503$23) L 50-42-302 50-42-303 \\- F2lb-I

~ 2 l b - 2 REMOTE AMP.

REMOTE AMP. 12O V. A.C. Mo4-M-63 M-63* DdTER BLAS *1B" L-l /_- E h e.s. N M-fo3 M-GS L-lI L-22 50-42-401 S.CH.I S. CH. 2 l 50-42-802 Y lll P P F-16 l TO Rx SAFE 7Y Sfs. 41-503-232 M/65-PX-OHW (KHEM.4/f03-213 LEVEL IND. 41-5' 3-801-PtJ L "E " 0 Q /20 V A.C. NON-INTERR. BUS */ A .Q-9 120 V A.C. NON-INTERR. I20 V A.C NoN-INTERR. Bus 'B' Bus t A ~ -$ PRORDSEC) MCC)iFl CATION FIGURE 4

M63 RELAYS CIRCUIT 1 CIRCUIT 2 Lil Reactor Water Level #1 L1 L22

  1. 2 L2 L33
  2. 3 L3 P11 Reactor Pressure
  3. 1 Pi P22
  4. 2 P2
  5. 3 P

P33 3 ATWS TEST / BYPASS CIRCUlT 441 AMMUkl. < g >q 8 Si d LI i l Pi l i h)f-L2-P2 h Li Pi _ _ I l 2} Lal I La Pa l l P3 h l1l 1 A REclRC. PUMP COUTROL l lB REclRC. PUMP CONTROL i REclRC. PUMP TRIP ATWS AWMUM. i ATWS i t.sT/ BYPASS CIRCU)T

  • 2 AhlMUM J'

LEL 1_ zt i i f33 5 3 L33 .} 1.zt _ Pzs H T i Ri y Lui Ti_Il P33 I i 1 i

l A REClRC. PUMP COMTROL I

ll

18 REC.lRC.. PUMP CONTROL I

i .REclRC. PUMP 'TRI P ATW5 AMMUN. I FIC,URE 5

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U / UCT10N) ~d* CN H.h! d _ _ L6 r -- CVO \\ VALVE / y (Srn SEAL ll5VDc VAWE MW wy CVC (DISCHARGE) us _Y \\ VALVE J v $A $C GRD o

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__ PS2 (BRG OIL -- 14 PSI ( ABOVE) S __ LS [sucTioNT i cVc ~d Tis C -- CVO (VALVE / N (StI710N Hi-TEMP vAi.vE) SEAL LS [ DISCHARGE) ,1EAK0E _f 7-CVC \\ VALVE 5A

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SAME AS MA
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