ML20113C531

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Proposed Tech Specs 3/4.3.3.6 Re Accident Monitoring Instrumentation
ML20113C531
Person / Time
Site: Waterford Entergy icon.png
Issue date: 06/27/1996
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20113C528 List:
References
NUDOCS 9607010320
Download: ML20113C531 (13)
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INSTRUMENTATION

'b ACCIDENT MONITORING INSTRUMENTATION l LIMITING CONDITION FOR OPERATION 3.3.3.6 Table 3.3-10 shall be OPERABLE.The accident monitoring instrumentati 1

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

a.

With the number of OPERABLE accident monitoring channels les the Required Number of Channels shown in Table 3.3-10, take the action identified in Table 3.3-10. _

b.

With the number of OPERABLE accident monitoring channels less the Minimum Channels OPERABLE requirements of Table 3.3-10

, take the action identified in Table 3.3-10.

c.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS  !

4.3.3.6 Each accident monitoring instrumentation channel shall be 1 demonstrated OPERABLE by performance of the CRANNEL CHECK and C CALIBRATION operations at the frequencies shown in Table 4.3-7 .

9607010320 960627 PDR P ADOCK 05000382 PM WATERFORD - UNIT 3 3/4 3-44 AMEN 0 MENT NO.14

I g TABLE 3.3-10 M

= ACCIDENT MONITORING INSTRUNENTATION  !

3 REQUIRED MINIMlM E NUMER OF CHANNELS

. INSTRt4ENT l CHANNELS OPERA 8LE ACTION

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E 1. Containment Pressure 2 1 29,30 r

Q 2. Reactor Coolant Outlet Temperature - THot (Wide Range) 2 1 29,30  ;

4. Reactor Coolant Pressure - Wide Range 2 1 29,30 ,
5. Pressurizer Water Level 2 1 29,30
6. Steam Generator Pressure 2/ steam generator 1/ steam generator 29,30 ,
7. Steam Generator Water Level - Narrow Range 2/ steam generator 1/ steam generator  ;

29,30

8. Steam Generator Water Level - Wide Range 1/ steam generator ** 1/ steam generator ** 29,30 w 9. Refueling Wa*er Storage Pool Water Level 2 1 29,30

) 10. Emergency Feedwater Flow Rate 1/ steam generator ** 1/ steam generator ** 29,30 t

  • ' 11. Reactor Cooling System Saturation Margin Monitor 2
12. Safety Valve Position Indicator 1 29,30 3 1/ valve 1/ valve 29,30
13. Containment Water Level (Marrow Range) 1*** 1*** 29,30
14. Containment Water Level (Wide Range) 2 1 29,30
15. Core Exit Thermocouples 4/ core quadrant 2/ core quadrant 29,30
16. Containment Isolation Valve Position Indicators
  • 1/ valve # 1/ valve # 29,30
17. Condensate Storage Pool Level 2 1 D*"
18. Reactor Vessel Level Monitoring System 2**** 1 31,32 k #If the containment isolation valve is declared inoperable and the provisions of Specification 3.6.3 are '

$ complied with, position indicators may be inoperable; otherwise, comply with the provisions of Specification 3.3.3.6.

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" Containment isolation valves governed by Specification 3.6.3 (Category 1).

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g **These corresponding instruments may be substituted for each other.

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M ***0peration may continue for up to 30 days with less than the Minimum Channels OPERA 8LE requirement.

        • A channel is eight sensors in a probe. A channel is operable if four or more sensors, one or more in the upper three and three or more in the lower five, are operable.

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l TABLE 3.3-10

! ACTION STATEMENTS ACTION 29 -

l With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-10, either restore the inoperable channel to OPERABLE status within 7 days, or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 30 -

With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE requirements of Table 3.3-10; either restore the inoperable channel (s) to OPERABLE status

! within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least H0T SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l ACTION 31 -

l With the number of OPERABLE accident monitoring channels, less i than the Required Number of Channels, either restore the system ,

to OPERABLE status within 7 days if repairs are feasible without l

shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 wTthin 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

ACTION 32 -

With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE in Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 48..

hours if repairs are feasible without shutting down or:

1.

Initiate an alternate method of monitoring the reactor vessel inventory;

2. Prepare and submit a Special Report to the Commission l

! pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and i 3. Restore the system to OPERABLE status at the next scheduled refueling.

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WATERFORD - UNIT 3 3/4 3-45a AMEN 0 MENT NO.14 l

l TABLE 4.3-7 -

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y ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

c2 CHANNEL CHANNEL i INSTRUMENT CHECK CALIBRATION C

1. Containment Pressure l @ M R u, 2. Reactor Coolant Outlet Temperature - THot (Wide Range) M R
3. Reactor Coolant Inlet Temperature -TCold (Wide Range) M R
4. Reactor Coolant Pressure - Wide Range M R
5. Pressurizer Water Level M R
6. Steam Generator Pressure M R
7. Steam Generator Water Level - Narrow Rang? M R
8. Steam Generator Water Level - Wide Range

{ M R y 9. Refueling Water Storage Pool Water Level M R

& 10. Emergency Feedwater Flow Rate M R

11. Reactor Coolant System Saturation Margin Monitor M R
12. Safety Valve Position Indicator M R
13. Containment Water Level (Narrow Range) M R
14. Containment Water Level (Wide Range) M R
15. Core Exit Thermocouples M R
16. Containment Isolation Valve Position M R i

g 17. Condensate Storage Pool Level M R E

18. Reactor Vessel Level Monitoring System M R m

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y i INSTRUMENTATION

. BASES I

i 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION 1

i The OPERABILITY of the accident monitoring instrumentation ensures that i

sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, " Instrumentation for

Light-Water-Cooled Nuclear Plants to Assess Plant Conditions During and i

Following an Accident," December 1980 and NUREG-0578, "TMI-2 Lessons Learned

Task Force Status Report and Short-Term Recommendations." Table 3.3-10 includes i Regulatory Guide 1.97 Category I key variables. The remaining Category I

! variables are included in their respective specifications.

l The Subcooled Margin Monitor (SMM), the Heated Junction Thermocouple j (HJTC), and the Core Exit Thermocouples (CET) comprise the Inadequate Core

Cooling (ICC) instrumentation required by Item II.F.2 NUREG-0737, the Post j TMI-2 Action Plan. The function of the ICC instrumentation is to enhance the i ability of the plant operator to diagnose the approach to existence of,_and 1 recovery from ICC. Additionally, they-aid in tracking reactor coolant  !

l inventory. These instruments are included in the Technical Specifications at i the request of NRC Generic Letter 83-37. These are not required by the

accident analysis, nor to bring the plant to Cold Shutdown.

In the event more than four sensors in a Reactor Vessel Level channel are

inoperable, repairs may only be possible during the next refueling outage.

This is because the sensors are accessible only after the missile shield and-reactor vessel head are removed. It is not feasible to repair a channel except during a refueling outage when the missile shield and reactor vessel head are removed to refuel the core. If only one channel is inoperable, it ~

1 should be restored to OPERABLE status in a refueling outage as soon as i

reasonably possible. If both channels are inoperable, at least one channel {

! shall be restored to OPERABLE status in the nearest refueling outage.

l I 3/4.3.3.7 CHEMICAL DETECTION SYSTEMS 5 The chemical detection systems are the chlorine and broad range toxic gas I

detection systems.

! The OPERABILITY of the chemical detection systems ensures that sufficient

! capability is available to promptly detect and initiate protective action in the event of an accidental chemical release.

The chemical detection systems provide prompt detection of toxic gas re-leases which could pose an actual threat to safety of the nuclear power plant or significantly hamper site personnel in performance of duties necessary for the safe operation of the plant.

The broad range toxic gas detection system operates on the principle of gas photoionization, and therefore, the system is sensitive to a broad range of gases." The system is therefore sensitive to both atmospheric and chemical l composition normal fluctuations affecting the Waterford 3 site. The setpoint

  • Including Amononia WATERFORD - UNIT 3 8 3/4 3-3 AMENDMENT NO. 14, 20, 49

i, INSTRUMENTATION j -

BASES i

1 for the system is thus based on testing and operating experience, and the set-

point is set at the lowest achievable IDLH gas concentration providing reliable operation and the optimum detection of toxic gases. The setpoint is therefore j

subject to change wherein necessitated by operating experience such as a result of changes in the Waterford 3 area chemical atmospheric profile. The setpoint is established and controlled by procedure.

l 3/4.3.3.8 This section deleted j 3/4.3.3.9 This section deleted i

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i WATERFORD - UNIT 3 8 3/4 3-3a AMENDMENT NO. I',20,50,104 l

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INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.6 The accident monitoring instrumentation channels shown in Table 3.3-10 shall be OPERABLE.

APPLICABILITY MODES 1, 2, and 3.

ACTION .

a. With the number of OPERABLE accident monitoring channels less than the Required Number of Channels shown in Table 3.3-10. take the action identified in Table 3.3-10.
b. With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE requirements of Table 3.3-10, take the action identified in Table 3.3-10.
c. The provisions of Specification 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.3.3.6 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in l Table 4.3-7.

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WATERFORD - UNIT 3 3/4 3-44 AMENDMENT NO. 14 l

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TABLE 3.3-10 . i ACCIDENT MONITORING INSTRUMENTATION REQUIRED MINIMUM NUMBER OF CHANNELS INSTRUMENT CHANNELS OPERABLE ACTION

1. Containment Pressure (Wide Range) Z- 1 29.30 ,
2. Containment Pressure (Wide Wide Range) 2 1 29.30_ y
33. Reactor Coolant Outlet Temperature - THot (Wide Range) 2 1 29.30
43. Reactor Coolant Inlet Temperature - TCold (Wide Range) 2 1 29.30

_54. Reactor Coolant Pressure - Wide Range 2 1 29.30 -

65. Pressurizer Water Level 2 1 29,30  :

6 Steam Generator o ressure 2/stca-'generatcr 1/ steam generator 29.30

7. Steam Generator Water Level - Narrow Range 2/ steam generator 1/ steam generator 29.30
8. Steam Generator Water Level - Wide Range ll/ steam generator **- 1/ steam generato# 29.30 t
9. Refueling Water Storage Pco! Water Level 2 1 29.30
10. E-'^rgency Feede: ter cle': Rat 0 1/ steam 00ncrato ^ 1/ steam 00ncrat0
  • 29.30
11. Reactor Cccling Syste- Saturation Marg!" Monitor 2 1 29.30
12. Safety Valve Pccition Ind!cator 1/valv0 1/ valve 29.30 ,
13. Contain ent Water Level (Narrce: Range) l' 1~ 29.30 914 Containment Water Level (Wide Range) 2 1 29.30 10M. Core Exit Thermocouples 4/ core quadrant 2/ core quadrant 29.30 1_1M. Containment Isolation Valve Position Indicators
  • 1/ valve ( N/A 1/valver 29A3 12U. Condensate Storage Pool Level 2 1 29.30 M18. Reactor Vessel Level Monitoring System ** 2**** 1 29.3131-33  !
14. Log Power Indication (Neutron Flux)*** 2 1 29.30 .

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  • /If the containment isolation valve is declared inoperable and the provisions of Specification 3.6.3 are complied with.

action requirements of this specification are not applicable. position indicators may be inoperable; ctNrcisc. cc-' ply tith the provision of Speci'ication 3.3.3.5.

Montain-'^nt inclation " Pres governed by Speci'ication 3.5.3 (Catege y 1)

    • "'c 0 corresponding instru""nt; may b^ cubstituted for cach Other i

@eration may continue for up to 20 day; ith les; than the *-tm Channels OPEP^.BLE require =nt.

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        • A channel is eight sensors in a probe. A channel is operable if four or more sensors, one or more in the upper three and three or more in the lower five, are operable.  ;
      • Channels C and D only (ENIIJI0001C and ENIIJI0001D). These instruments are also covered by Specification 3.3.1. " Reactor Protective Instrumentation."  ;

WATERFORD - UNIT 3 3/4 3-45 AMENDMENT NO. 75

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I J TABLE 3.3-10 ACTION STATEMENT ACTION 29 - With the number of OPERABLE accident monitoring channels less than the Required Number of Channels snown in Table 3.3-10, either restore the inoperable channel to OPERABLE status within 307 days, or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the following 14 days.

The report shall outline the preplanned alternate method of monitoring the cause of the inoperability, and the plans and schedule for restoring the

'a instrumentation channels to OPERABLE status.or be HOT SHUTDOW" "ith1" the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 30 - With the number of OPERABLE accident monitoring channels less than the Minimum Channels OPERABLE requirements of Table 3.3-10; either restore the inoperable channel (s) to OPERABLE status within 7 days 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT l SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 31 "ith the number of OPERAELE accident monitoring channels, ! cts than the Required Number of Channels, either restore the syster to OPEP^BLE status withir ' day 4# repairs are feasible without shutting down or preparc and submit : Special Report to the Commit:10n pursuant-to Speci'1 cation 5.9.2 w4thi" 30 days following the event out44ning the action taken, the cause of the I inoperability and th^ plant and schedule for rc toring the system to CPEPABLE status-l ACTION 312 - With the number of OPERABLE accident monitoring channels less than the l Minimum Channels OPERABLE in Table 3.3-10, either restore the inoperable channel (s) to OPERABLE status within 7 daysiS hour 4f repair; are feasible without shutting dowa cr- or prepare and submit a Special Report to the l

I Commission pursuant to Specification 6.9.2 within the following 14 days. The ,

report shall outline the preplanned alternate method of monitoring, the cause l

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! of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.

1. Iaitiat0 and alternate method of monitoring the reactor ventel invent 0ry;
2. reparc and submit a Special oeport to the Commi;; ion pursuant to Specification S.9.2 "ithin 30 days following the event Outlining the action taken, the cause of the inoperabi'ity and the plans .and schedule I fne
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3. Re: tore the system to OPERABLE status at the next scheduled refueling- l i

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,1 WATERFORD - UNIT 3 3/4 3-45a AMENDMENT NO, 14 l

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TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION

1. Containment Pressure (Wide Range). M R
2. Containment Pressure (Wide Wide Range) M R
32. Reactor Coolant Outlet Temperature - THot (Wide Range) M R
43. Reactor Coolant Inlet Temperature -TCold (Wide Range) M R

_54. Reactor Coolant Pressure - Wide Range M R

_65. Pressurizer Water Level M R

5. Ste - Generator ressure "
7. Steam Generator Water Level - Narrow Range M R
8. Steam Generator Water Level - Wide Level M R
9. Refueling L;er Storage P001 Mater Leve' " o
10. E-^rgency F^e& 2ter cl0: Rate " o
11. Reactor C0010-t Syst^- $2turation "2rgi" "^^.itor "
12. Safety Val"^ Position !ndicator " o
12. Contai^-^nt Water Level (Narr0w Range) " o 914. Containment Water Level (Wide Range) M R 10M. Core Exit Thermocouples M R 11M. Containment Isolation Valve Position M R 1217. Condensate Storage Pool Level M R 1318. Reactor Vessel level Monitoring System M R 14_. Log Power Indication (Neutron Flux) M R WATERFORD - UNIT 3 3/4 3-46 AMENDMENT NO. 14

INSTRUMENTATION BASES 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrurMtation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. The availability of accident monitoring instrumentation is important so that responses to corrective actions can be observed and the need for, and magnii#e of, further actions can be determined. These essential instruments are identified by plant specific documents addressing the recommendations of Regulatory Guide 1.97, as reauired by Supplement 1 to NUREG-0737, "TMI Action Items." ^10 capabi'ity is conti tent aith the recc=ndation: Of Regulatory Guide 1.97, "Instru entation for l Light Water C001cd Nuclear 1:nts to ^.::c:: 1:nt Condition: During and F0110w ng 4 an

^cc! dent," Dece-ber 1980 and MUREG 0578. r ! 2 Let:On: Learned T Sk Force Status R0 port and-She-t Ter- Rec 0--^ndations." Table 3.310 include: Regulatory Cuide 1.97 Category ?

key variab!00. Se re cining Cat 0gery ! variable; are included 4- thei respectiv0 cpect'ications. Table 3.3-10 includes most of the plant's RG 1.97 Type A and Category 1 l

variables. The remaining Type A/ Category 1 variables are included in their respective  !

specifications. Type A variables are included in this LC0 because they provide the i primary information required to permit the control room operator to take specific manually controlled actions, for which no automatic control is provided, that are required for safety systems to accomplish their safety functions for Design Basis Accidents (DBAs). Category 1 variables are the key variables deemed risk significant i because they are needed to: (1) Determine whether other systems imt.ortant to safety are )

performing their intended functions: (2) Provide information to the operators that will '

enable ther. to determine the potential for causing a gross breach of the barriers to radioactivity release; and (3) Provide information regarding the release of radioactive materials to allow for early indication of the need to initiate action necessary to protect the public as well as to obtain an estimate of the magnitude of any impending threat.

With the number of OPERABLE accident monitoring channels less than the Required l Number of Channels shown in Table 3.3-10, the inoperable channel should be restored to OPERABLE status within 30 days. The 30 day Completion Time is based on operating experience and takes into account the remaining OPERABLE channel (or in the case of a Function that has only one required channel, other non-Regulttory Guide 1.97 instrument channels to monitor the Function), the passive nature of the instrument (no critical automatic action is assumed to occur from these instruments), znd the low probability of an event requiring accident monitoring instrumentation during th.'s interval . If the 30 day A0T is not met, a Special Report approved by PORC is requirec' to be submitted to the NRC within the following 14 days. This report discusses the results of the root cause evaluation of the inoperability and identifies proposed restorative Actions. This Action l 1s appropriate in lieu of a shutdown requirement, given the likelihood of plant conditions that would require information provided by this instrumentation. Also, l

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aliernative Actions are identified before a loss of functional capability condition occurs.

With the number of OPERABLE accident monitoring channels less than the Minimum Channels i OPERABLE requirements of Table 3.3-10: at least one of the inoperable channels shodd be 1

restored to OPERABLE status within 7 days. The Completion Time of 7 days is based on the relatively low probability of an event requiring PAM instrumentation operation and tne availability of alternate means to obtain the required information.

WATERFORD - UNIT 3 B 3/4 3-3 AMEN 0 MENT NO. 49 l

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4 C'ntinuous o oreration with less than the Minimum Channels OPERABLE requirements is not acceptable oecause the alternate indications may not fully meet all performance '

avalification requirements applied to t.he accident monitoring instrumentation.

Therefore, requiring restoration of one inoperabie l channel limits the risk that the variable will be in a degraded condition should ao accident occur._If the 7 day requirement is not met, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to at least MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The completion time is reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without >

challenging plant systems.

TS 3/4.3.3.6 applies to the following instrumentation: ESFIP16750 A, ESFIPR6750 8 ESFIPR6755 A&B, RC ITIO122 HA, RC ITIO112 HB, RC ITIO122 CA, RC ITIO112 CB,'RC IPIO102 A,B,C,&D, RC ILIO 110 X&Y, SG ILI1113 A,B,C,&D, SG ILI1123 A,B.C,&D, SG IL11115 A2&B2, SG ,

ILI1125 A2&B2, SI ILI7145 A. SI ILR7145 B, all CET's, all Category 1 Containment Isolation Valve Position Indicators EFWILI9013 A&B, HJTC's, and ENIIJI0001 C&D.

The Subc00 led "argi- "cnitor (S""), the H0:t^d Junction Ther Occuple (HJTC), and i the C0re Exit Ther=ccuples (CET) cc pri;0 the Inadequat0 Core C0014ng (!CC) instru Ontation required by !te- !! c.? NUREG 0737, the Pc t 7"! 2 Action olen The ,

function Of th0 !CC instru-^ntation is to enhance the abi'ity of the plant Operatcr to diagnose the approach to existence of, and recovery #ron ICC. Additiona'!y, they aid in i tracking reactor coolant 4 ventory. The:0 instru=nt are included in the Technical ,

Spec 1#ication; at th0 r0;uest Of 'RC C0ncric Letter 83 37 Th0:0 are not required by the accident analysis, nor to bring the plant to Cold Shutdown

!" the event =re than four 50n:Or 4a : Re:ctor V0:Sel Level channel are i" Operable, repair may only be p0: ible during the next refueling Outage. *1 is I because the son:Or: are acc00 ible Only after the -istile chield and reactor v00:01 head l

l 3r0 re 0ved. It 1; not f02 ibl0 to repai a channel except during a ref+eling Outage ,

l when the ~15:110 shield and reactor ves 01 head are re Oved to refucl the core. If Only l I

One channel 1: inoperabl0, it should be restored to CPEP/SLE statu: 4" r0 fueling Outage l

000n : rea:Onably p00:1ble. !# both channc's are inoperable, at 10:0t 0"0 channel chal' be restored to OPEP/SLE status 4" the nearest refueling cutage.

3/4.3.3.7 CHEMICAL DETECTION SYSTEMS The chemical detection systems are the chlorine and broad range toxic gas

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detection systems,

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t The OPERABILITY of the chemical detection systems ensures that sufficient capability is available to promptly detect and initiate prcaective action in the event of an accidental chemical release.

The chemical detection systems provide prompt detection of toxic gas releases which could pose an actual threat to safety of the nuclear power plant or significantly hamper site personnel in performance of duties necessary for the safe operation of the plant.

The broad range toxic gas detection system operates on the principle of gas

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photoionization, and therefore. the system is sensitive to a broad range of gases *. The system is therefore sensitive to both atmospheric and chemical composition normal fluctuations affecting the Waterford 3 site. The setpoint for the system is thus based on 4

testing and operating experience, and the set- point is set at the lowect achievable IDLH gas concentration providing reliable operation and the optimum

! detection of toxic gases.

  • Including Ammonia WATERFORD - UNIT 3 8 3/4 3-3a AMENDMENT NO. 104

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