ML20023B639
| ML20023B639 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/19/1983 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20023B592 | List: |
| References | |
| NUDOCS 8305050228 | |
| Download: ML20023B639 (24) | |
Text
{{#Wiki_filter:* Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-4 SPECIFICATION LCO 4.4-1 TABLE 4.4-1 INSTRUMENT OPERATING REQUIREMENTS FOR PLANT PROTECTIVE SYSTEM, SCRAM MINI-MUM DEGREE PERMIS-MINIMUM 0F SIBLE TRIP OPERABLE REDUN-BYPASS NO. FUNCTIONAL UNIT SETTING CHANNELS DANCY CONDITIONS la. Manual (Con-1 0 None trol Room) Ib. Manual (Emer-
2 f) 1 None gency Board) 2.
Startup Channel s105 cps 2 1 Reactor - High Mode Switch In "RUN" 3a. Linear Channel s140% Power 2 f) 1 None - High, Chan-a) nels 3, 4, 5 3b. Linear Channel s140% Power 2 f) 1 None - High, Chan-a) nels 6, 7, 8 4. Primary Coolant Moisture High Level 567 F Dew-1 f), t) I c) None Monitor point Loop Monitor s27 F Dew-2/ Loop f), t) h) point 1/ Loop 5. Reheat Steam s1075 F a) 2 b), f) 1 None Temperature - High b) 6. Primary Coolant $50 psig 2 f), k) 1 Less Than Pressure - Low Below Nor-30% Rated mal, Load Power Programmed a) 8305050228 830419 PDR ADOCK 05000267 P PDR
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-5 SPECIFICATION LCO 4.4-1 TABLE 4.4-1 (Cont'd) MINI-MUM DEGREE PERMIS-MINIMUM OF SIBLE TRIP OPERABLE REDUN-BYPASS NO. FUNCTIONAL UNIT SETTING CHANNELS DANCY CONDITIONS 7. Primary Coolant s7.5% Above 2 f), k) 1 None Pressure - High Normal Rated, Load Programmed a) 8. Hot Reheat 235 psig 2 f) 1 Less Than Header Pressure 30% Rated - Low Power 9. Main Steam 21500 psig 2 f) 1 Less Than Pressure - Low 30% Rated Power 10. Plant Elec-d) 2 e), f) 1 None trical System - Loss 11. Two Loop
2 1
Reactor Trouble Mode Switch In " Fuel Loading" 12. High Reactor s325 F 2 f) 1 None Building Temp-4 i erature (Pipe ) Cavity) i ,.,-.,-.y., _.r ,n-,-
Fort St. Vrain 01 Technical Specifications Amendment # Page 4.4-6 SPECIFICATION LC0' 4.4-1 TABLE 4.4-2 INSTRUMENT OPERATING REQUIREMENTS FOR PLANT PROTECTIVE SYSTEM, LOOP SHUTDOWN MINI-MUM DEGREE PERMIS-MINIMUM OF SIBLE TRIP OPERABLE REDUN-BYPASS NO. FUNCTIONAL UNIT SETTING CHANNELS DANCY CONDITIONS la. Steam Pipe Rupture 59 v. dc. 2 f), s) 1 None Under PCRV, Loop 1 j) i Ib. Steam Pipe Rupture s9 v. dc. 2 f), s) 1 None Under PCRV, Loop 2 j) Ic. Steam Pipe Rupture, s9 v. dc. 2 f) 1 None North Pipe Cavity Loop 1 j) Id. Steam Pipe Rupture, s9 v. dc. 2 f) 1 None South Pipe Cavity Loop 1 j) le. Steam Pipe Rupture, 59 v. dc. 2 f) 1 None North Pipe Cavity Loop 2 j) If. Steam Pipe Rupture, 59 v. dc. 2 f) 1 None South Pipe Cavity Loop 2 j) 2a. High Pressure, Pipe s2.5" w.g. 2 f) 1 None i Cavity j) 2b. High Temperature, s130 F 2 f) 1 None Pipe Cavity j) 2c. High Pressure, Under s2.5" w.g. 2 f) 1 None PCRVj) 2d. High Temperature, s130 F 2 f) 1 None Under PCRV j) 1
s Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-7 SPECIFICATION LCO 4.4-1 TABLE 4.4-2 (Cont'd) MINI-MUM DEGREE PERMIS-MINIMUM OF SIBLE TRIP OPERABLE REDUN-BYPASS NO. _ FUNCTIONAL UNIT SETTING CHANNELS DANCY CONDITIONS 3a. Loop 1 Shutdown
2 1
None Logic 3b. Loop 2 Shutdown 2 1 None Logic 4a. Circulator 1A and 18 Circulators 2 1 None Shutdown - Loop Shut-1A and 1B down Logic Shutdown 4b. Circulator IC and ID Circulators 2 1 None Shutdown - Loop Shut-IC and ID down Logic Shutdown Sa. Steam Generator Pene-5810 psig 2 f) 1 None i tration Overpressure Loop 1 Sb. Steam Generator Pene-s810 psig 2 f) 1 None tration Overpressure l Loop 2 l 6a. High Reheat Header 55 mr/hr 2 f) 1 None Activity, Loop 1 Above Back-ground 6b. High Reheat Header 55 mr/hr 2 f) 1 None Activity, Loop 2 Above Back-ground 7a. Low Superheat Header 2800 F 2 f) 1 Less Than Temperature, Loop 1 30% Rated p) Power 7b. Low Superheat Header 2800 F 2 f) 1 Less Than Temperature, Loop 2 30% Rated p) Power 7c. High Differential s50 F 2 f) 1 None Temperature Between Loop 1 and Loop 2 p) 2 .r ,,..,w<-,._..,,,m#, ,,,, -... ~. -
Fort St.-Vrain #1 Technical Sp cifications Amendment # Page 4.4-8 SPECIFICATION LCO 4.4-1 TABLE 4.4-3 INSTRUMENT OPERATING REQUIREMENTS FOR PLANT PROTECTIVE SYSTEM, CIRCULATOR TRIP MINI-MUM DEGREE PERMIS-MINIMUM OF SIBLE TRIP OPERABLE REDUN-BYPASS NO. FUNCTIONAL UNIT SETTING CHANNELS DANCY CONDITIONS 1. Circulator Speed 1910 rpm 2 f) 1 Less Tlian - Low r) Below 30% Rated Normal As Power Programmed by Feed-water Flow 2a. Loop 1, Fixed Feed-20% of 2 f) 1 Less Than water Flow - Low Rated Full 30% Rated (Both Circulators) Load Power 2b. Loop 2, Fixed Feed-20% of 2 f) 1 Less Than water Flow - Low Rated Full 30% Rated (Both Circulators) Load Power 3. Loss of Circulator 2475 psid 2 f) 1 None Bearing Water r) 4. Circulator Pene-s810 psid 2 f) 1 None tration Trouble r) 5. Circulator Drain 25 psid 2 f) 1 None Malfunction r) 6. Circulator Speed - s11,000 rpm 2 f) 1 None High Steam r) 7. Manual 1 0 None . _ ~.. - - _
Fort St. Vrain #1 Technical Spacifications Amendment # Page 4.4-9 SPECIFICATION LCO 4.4-1 TABLE 4.4-3 (Cont'd) MINI-MUM DEGREE PERMIS-MINIMUM 0F SIBLE TRIP OPERABLE REDUN-BYPASS NO. FUNCTIONAL UNIT SETTING CHANNELS DANCY CONDITIONS 8. Circulator Seal 2 -10" H 0, 2 f) 1 Opposite 2 Malfunction r) or loop s80" H O d shutdown 2 or circu-Tator seal mal-function trip of other circu-lator in same loop. 9. Circulator Speed - 58,800 rpm 2 f)* 1* None High Water
- Minimum operable channels and minimum degree of redundancy must be maintained on at least one helium circulator per loop.
If the mini-mum number of channels and the minimum degree of redundancy are not maintained as required, reactor power shall be reduced to 50% of of rated thermal power within 12 hours.
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-10 SPECIFICATION LCO 4.4-1 TABLE 4.4-4 FOR REACTOR PROTECTIVE SYSTEM, ROD WITHDRAWAL PR0HIBIT (RWP) MINI-MUM DEGREE PERMIS-MINIMUM OF SIBLE TRIP OPERABLE REDUN-BYPASS NO. FUNCTIONAL UNIT SETTING CHANNELS DANCY CONDITIONS 1. Startup Channel - Low 22.5 cps 2 1 Above Count Rate 10 2% Rated Power 2a. Linear Channel - Low 25% m) 2 1 g) Power RWP (Channels 3, i 4, and 5) 2b. Linear Channel - Low 25% m) 2 1 g) Power RWP (Channels 6, 7, and 8) l 3a. Linear Channel - High s30% n) 2 f) 1 None Power RWP (Channels 3, 4, and 5) 3b. Linear Channel - High 530% n) 2 f) 1 None Power RWP (Channels 6, 7, and 8) I i -ws. ,-.v-v 4,-, -,,,,...y, ---,--,-mm--- -.__-y r-e--
Fort St. Vrain 01 1 Technical Specifications Amendment # Page 4.4-11 SPECIFICATION LCO 4.4.1 NOTES FOR TABLES 4.4-1 THROUGH 4.4-4 a) See Specification LSSS3.3 for trip setting. 4 b) Two thermocouples from each loop, total of four, constitute one channel. For each
- channel, two thermocouples must be operable in at least one operating loop for that channel to be considered operable.
c) With one primary coolant high level moisture monitor tripped, trips of either loop primary coolant moisture monitors will cause full scram. Hence, number of operable chaanels (1) minus minimum number required to cause scram (0) equals one, the minimum degree of j redundancy. d) Both 480 volt buses IA and IC loss of voltage for no longer than 35 seconds, e) One channel consists of one undervoltage relay from each of the two 480 volt buses (two undervoltage i relays per channel). These relays fail open which is the direction required to initiate a scram. f) The inoperable channel must be in the tripped 1 condition, unless the trip of the channel will cause i l the protective action to occur. Failure to trip the t v -, - - ~ r<w, - ~ y
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-12 i l inoperable channel requires taking corrective action l as applicable. i g) RWP bypass permitted if the bypass also causes associated single channel scram. h) Permissible Bypass Conditions: I. Any circulator buffer seal malfunction. II. Loop hot reheat header high activity. III. As stated in LC0 4.9.2. j) Items la. or Ic. or Id. accompanied by 2a., 2b., 2c., or 2d. on Table 4.4-2 are required for loop 1 shutdown. Items Ib. or Ic. or lf., accompanied by 2a., 2b., 2c., or 2d. on Table 4.4-2 are required for loop 2 shutdown. k) One operable helium circulator inlet thermocouple in 4 an operable loop is required for the channel to be considered operable. m) Low Power RWP bistable resets at 4% after reactor power initially exceeds 5%. n) Power range RWP bistables automatically reset at 10% af ter reactor power is decreased from greater than 30%. The RWP may be manually reset between 10% and 30% power. _ _ _ _ _ _ _. _ _, ~ _ _.__ _ _ __. _ - --
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-13 p) Item 7a. must be accompanied by item 7c for Loop 1 shutdown. Item 7b. must be accompanied by item 7c. for Loop 2 shutdown. r) Separate instrumentation is provided on each circulator for this functional unit. Only the affected helium circulator shall be shut down within 12 hours if the indicated requirements are not met. s) Each channel has 2 microphones running in parallel with one ultrasonic amplifier. For the channel to be considered
- operable, both microphones and the amplifier must be operable.
t) A primary coolant dew point moisture monitor shall not i be considered operable unless the following conditions are met:
- 1) Reactor Power Range Minimum Sample Flow Startup to 2%
1 scc /sec. >2% - 5% 5 sec/sec. >5% - 20% 15 scc /sec. >20% - 35% 30 sec/sec. >35% - 100% 50 scc /sec.
- 2) Minimum flow of item 1) is alarmed in the control room and the alarm is set in accordance with the power ranges specified.
d Fort St. Vrain #1 Technical Specifications. Amendment # Page 4.4-14
- 3) The-ambient temperatures indicated by both temporary thermocouples mounted on the flow sensors in penetrations B1 and 83 are less than 185 F
- 4) Fixed alarms of I scc /sec and 75 scc /sec are operable.
t Basis for Specification LCO 4.4.1 The plant protection system automatically -initiates protective functions to prevent established limits from being exceeded. In
- addition, other protective instrumentation is provided to initiate action which mitigates the consequences of accidents.
This specification provides the limiting conditions for operation necessary to preserve the effectiveness of these instrument systems. If the minimum operable channels or the minimum degrees of redundancy for each functional unit of a table cannot be met or cannot be bypassed under the stated permissible bypass conditions, the following action shall be taken: For Table 4.4-1, the reactor shall be shut down within 12 hours. For Table 4.4-2, the affected loop shall be shut down within 12 hours.
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-15 4 For Table 4.4-3, the affected helium circulator shall be shut down within 12 hours. 'For Table 4.4-4, the reactor shall be shut down within 24 hours. 4 If, within the indicated time limit, the minimum number of operable channels and the minimum degree of redundancy can be reestablished, the system is considered normal and no further action needs to be taken. The trip level settings are included in this section of ^ the specification. The bases for these settings are briefly discussed below. Additional discussions pertaining to the scram, loop shutdown and circulator trip inputs may be found in Section 7.1.2.3, 7.1.2.4, and 7.1.2.6, respectively, of the FSAR. High moisture instrumentation is discussed in Section 7.1.2.5. a) Scram Inputs Manual Scram is provided to give the operator means for emergency shutdown of the reactor independent of the automatic reactor protective system. Startup Channel-High Countrate is provided as a scram input during fuel loading and zero power operations. Linear Channel Flux-High (See Technical Specification LSSS 3.3).
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-16 ) High Reactor Moisture (See Technical Specification LSSS 3.3). High Reheat System Temperature (See Technical Specification LSSS 3.3). Low Reactor Pressure is an indication of possible helium leakage from the system. A scram is required because the reactor is in danger of being inadequately cooled which would increase the hazard associated with activity release from the PCRV. The trip is programmed with plant load (similar to the high pressure trip) to reduce the response time when the plant is at high power. The low pressure trip point is 50 psi below normal during operation betwer, 30% and 100% rated power which is lower than the pressures reached on normal transient conditions. High Primary Coolant Pressure (See Technical Specification LSSS 3.3). Low Hot Reheat Steam Pressure is an indication of either a cold reheat steam line rupture or a hot reheat steam line rupture and necessitates plant shutdown due to the potential loss of steam turbine circulator motive power. The trip point is selected to be below normal operating levels which vary over a wide range.
~ Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-17 Low Main Steam Pressure is an indication of main steam line rupture or loss of feedwater flow and necessitates plant shutdown due to potential loss of steam turbine circulator motive power. The trip point is selected to be below normal operating levels. Plant Electrical System Power Loss requires a scram to prevent any power-to-flow mismatches from occurring. A 30-second delay is provided following a power loss before the scram is initiated to allow the emergency diesel generator to start. If it does start, the scram is avoided. Two-Loop Trouble. Operation on one loop at a maximum of about 50% power may continue following the shutdown of the other loop (unless preceded by scram as in the case of high moisture.) Onset of trouble in the remaining loop (two-loop trouble) results in a scram. Trouble is defined as a signal which normally initiates a loop shutdown. Similarly, simultaneous shutdown signals to both loops result in shutdown of one of the two loops only and a reactor scram. High Temperature in the pipe cavity would indicate the presence of an undetected steam leak or the failure of the steam pipe rupture detection system to differentiate in which loop the leak had occurred and to shut the faulty loop down.
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-18 The setpoint has been set above the temperature that would be expected to occur in the pipe cavity if the steam leak were detected and the faulty loop shutdown for all steam leaks except those of major proportion or due to an offset rupture of one of the steam lines. An undetected steam leak or pipe rupture under the PCRV within the support ring would also be detectable in the pipe cavity, therefore only one set of sensors and logic is required to monitor both areas. b) Loop Shutdown Inputs Steam pipe Rupture In The Reactor Building necessitates shutdown of the leaky loop to terminate the pressure and temperature buildup within the building. Ultrasonic noise caused by escaping steam in conjuction with a pressure or temperature rise will cause the appropriate loop to shutdown. The trip of the ultrasonic detection system is set at a level which corresponds to 9 v. dc. output from the untrasonic amplifier. The pressure and temperature trips are set above normal operating building pressure and temperature levels. Shutdown of Both Circulators is a loop shutdown input which is necessary to insure proper action of the reactor protective (scram) system (through the two-
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-19 loop trouble scram) in the event of the loss of all circulators and low feedwater flow. The remaining loop shutdown inputs are equipment protection items which -are included because their malfunction could prevent a scram due to loss of the two-loop trouble scram input. a c) Circulator Shutdown Inputs All circulator shutdown inputs (except circulator speed high on water turbines) are equipment protection items which are tied to two loop trouble through the loop shutdown system. These items are included in Table 4.4-3 because a malfunction could prevent a scram due to loss of the two loop trouble scram input. Circulator speed high on water turbines is included to assure continued core cooling capability on loss of steam drive. d) Rod Withdraw Prohibit Inputs Startup Channel Countrate-Low is provided to prevent control rod withdrawal and reactor startup without adequate neutron flux indication. The trip level is selected to be above the background noise level. Linear Channel (5% Power) directs the operator's attention to either a downscale failure of a power range channel or improper positioning of the I.S.S.
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-20 Linear Channel (30% Power) is provided to prevent control rod withdrawal if reactor power. exceeds the I.S.S. limit for the " Low Power" position. Specification LCO 4.4.2 - Control Room Temperature - Limiting Condition for Operation The reactor shall not be operated at power if the control room temperature exceeds 120 F. Basis for Specification LCO 4.4.2 The limiting temperature in the control room is established to assure no over temperature condition which might cause damage to essential instrumentation and control equipment. Satisfactory operation of safety related control and, electrical equipment located in the control room for temperatures up to 120 F is discussed in FSAR Amendment No. 17, Question 7.5. Specification LCO 4.4.3 - Area Radiation Monitors - Limiting Condition for Operation At least one area radiation monitor from each group shall be operable. If any area monitor becomes inoperable, a portable monitor equipped with an alarm shall be placed in the area, and all personnel notified of the condition. J
~ ~ Fort St. Vrain #1 Technical' Specifications Amendment # Page 4.4-21 i Basis for Specification LC0 4.4.3 The grouping of area radiation monitors is such th.at each monitor in the group supplements the others in the group. The notification of personnel of any malfunction, coupled' with the provision of a portable instrument, Er a replacement, adequately ensures protection for personnel, i and detection of abnormalities. The detectors are grouped as follows: 1 e f
- Y e
[ Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-22 l l l l l GROUP NO. I DETECTOR NO. I LOCATION _l l l l l l 1 l RT-93250-1 l 4881 Refueling Machine Control Room l l l l 1 l 1 l RT-93252-1 1 4881 East Wall l l 1 I I l 1 l RT-93251-1 l 4864 Reactor Plant Exhaust Filter Room l l l l T I l 1 l RT-93252-2 1 4864 South St'airwell l l l l 1 l 2 l RT-93250-3 l 4856 Hot Service Facility l l 1 I l l 2 l RT-93251-3 l 4868 Hot Service Facility l l l l l l 3 l RT-93250-2 l 4854 East Walkway l I I I I l 3 l RT-93250-4 l 4839 East Walkway l l l l l l 3 l RT-93251-4 l 4816 Office Building l l l-1 I l 3 I RT-93252-4 l 4829 Anslytic Instrument Room l l 1 1 I l .4 l RT-93250-13 l 4791 Condensate Demineralizers l l l l l l 4 I RT-93250-5 l 4823 Main Control Room l l 1 1 I l 4 l RT-93251 l 4791 Grade Floor North l l l l l l 4 i RT-93252-6 l 4791 South Stairwell l l l l l I 5 l RT-93251-5 l 4781 East Walkway l l l l l l 5 l RT-93251-7 l 4781 Valve Operating Station - West l 1 1 I I l __ 5 l RT-93252-7 l 4781 Valve Operating Station - East l 1 l l l l 6 l RT-93250-8 l 4771 Northeast Walkway l 1 I I I l' 6 l RT-93251-8 l 4771 Radiochem Lab l l l l l l 6 l RT-93251-9 l 4740 North Stairwell l t 'l i V -{i e ir- -m.
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-23 i Specification LCO 4.4.4 - Seismic Instrumentation - Limiting Conditions for Operation The reactor shall not be operated at power unless three (3) of the six (6) seismic instruments are operable. Basis for Specification LCO 4.4.4 The monitoring provided by three (3) seismic instruments, j in the event of an earthquake, is adequate to determine the ground acceleration at the site. Specification LCO 4.4.5 - Analytical System Primary Coolant Moisture Instrumentation - Limiting Condition for Operation 4 The reactor shall not be operated between a shutdown condition and 5% power during startup unless the primary coolant is being sampled for moisture by two analytical system moisture monitors. l If only one moisture monitor is operable while increasing I l l reactor power between shutdown and 5%, a second monitor shall be made operable or the reactor shall be shut down within 12 hours. l If all of the monitors become inoperable, during the above mentioned power increase, the reactor shall be shut down i immediately. l
Fort St. Vrain #1 TGchnical Specifications Amendment # Page 4.4-24 During reactor power reduction from 5% power to shutdown conditions, at least one analytical system moisture l monitor must be in operation. If all monitors become inoperable, the reactor shall be shut down immediately. Basis for Specification LCO 4.4.5 During reactor operation, the analytical system primary coolant moisture monitor system is required below 5% reactor power for administration of LCO 4.2.11. One monitor is sufficient to detect primary coolant moisture content on a continual basis. l Two monitors will normally be in service sampling primary coolant. These monitors do not provide any automatic l action (other than an alarm function). Alternate moisture l monitors can also be placed in service sampling primary l
- coolant, such as through re-alignment of a monitor in the l
analytical system or utilization of the plant protective l system dewpoint moisture monitors placed in the " indicate" l mode. Operator action is required to take corrective action in the event of high moisture levels in the primary coolant in the shutdown to 5% reactor power range. Operator reaction time to shut down the reactor in the event of high moi s! w:'s levels in the primary coolant i system at reactor power levels of 5% or less are acceptable. As indicated in Document GA-A13677, Test and Evaluation of the Fort St. Vrain Dew Point Moisture
Fort St. Vrain #1 Technical Specifications Amendment # Page 4.4-25 Monitors System, one of the limiting parameters for determining required response times to shut the reactor down in the event of high primary coolant roisture is graphite oxidation. The allowable weight loss of the hottest fuel element in the core is 1%. At operating temperatures experienced at 5% reactor power, response times to scram the reactor to limit oxidation to 1% by weight is approximately 6700 seconds, well within the capabilities of an operator. Specification LCO 4.4.6 - Room Temperature, 480 Volt Switchgear The reactor shall not be operated at power if the 480 V switchgear room temperature exceeds 120 F. Basis for Specificaton LCO 4.4.6 The most limiting temperature in the 480 V switchgear room is 120 F. This limit is established to assure satisfactory operation of safety-related control and l electrical equipment located there during reactor power operation.
w 4 ATTACHMENT 3 EVALUATION OF THE PROPOSED LCO 4.4.5 REVISION f I , _. ~,.,... -. - -.
EVALUATION OF THE PROPOSED LCO 4.4.5 REVISION As reported in the Nuclear Regulatory Commission I & E Inspection Report 82-31, dated January 21, 1983 (G-83041), LC0 4.4.5 is worded as to address only two monitors (ME-9306 and ME-9307). There presently exists other moisture monitors capable of providing an analytical dewpoint indication. One alternate to ME-9306 (or ME-9307) is ME-9305, installed in the analytical instrumentation panel. ME-9305, normally lined-up to sample a purified helium train component effluent, can be aligned to provide an analysis of primary coolant moisture. Other alternatives to ME-9306 (or ME-9307) are the plant protective system (PPS) dewpoint moisture monitors (DPMM) operating in the " indicate" or in the after-trip of the " trip / indicate" mode. Allowing the use of alternate monitors has not increased or changed the probablility or the consequences of an accident or malfunction. An accident or malfunction of a different type has not been created, because failure of an alternate monitor is no different than a failure of a monitor normally in use. The margin of safety, as defined by the present LCO 4.4.5 and its basis, has not been reduced because the required number of operable analytical primary coolant moisture monitors has not been reduced. __- _}}