ML20212R531

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Proposed Tech Specs Deleting Surveillance Requirement (SR) 4.6.1.8.d.4 & Revising SRs 4.7.8.d.4 & 4.9.12.d.3 Re Min Heater Capacity.Calculations & Significant Hazards Consideration Evaluation Encl
ML20212R531
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 04/16/1987
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20212R482 List:
References
TAC-R00042, TAC-R00043, TAC-R42, TAC-R43, NUDOCS 8704270223
Download: ML20212R531 (75)


Text

t ENCLOSURE 1 PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 (TVA SQN TS 80)

Proposed changes to delete SR 4.6.1.8.d.4 (units 1 and 2) and revise SRs 4.7.8.d.4 and 4.9.12.d.3 and associated bases (units 1 and 2) of the technical specifications. A typographical error in SR 4.7.8.d.4 (unit 1) is also corrected.

List of Affected Pages Unit 1 3/4 6-14 3/4 7-20 3

3/4 9-13 B 3/4 7-5 t B 3/4 9-3 1

4 Unit 2 3/4 6-14 3/4 7-20 3/4 9-15 B 3/4 7-5 B 3/4 9-3 1

I' 8704270223 870416 i PDR ADOCK0500g7 P

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CONTAINMFMT SYSTEMS

., SURVEILLANCE REQUIREMENTS (Continued)

c. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of representa-l tive carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the Regulatory Guide 1.52, Revision 2, March 1978. -
d. At least once per 18 months by:
1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 8 inches Water
Gauge while operating the filter train at a flow rate of
4000 cfm 1 105.
2. Verifying that the filter train starts on a Phase A containment isolation Test Signal.

_ 3. Verify the operation of the filter cooling bypass valves.

4. ":r yin;; 'l:t th: i:20:r; di;;ff;;; 10 1.0 ;;; hs tu t:d

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  • f r. ====; with ^?SI '?51F1075. (

Ne [. Verifying that each system produces a. negative pressure of greater than or equal to 0.5 inches W.G. in the annulus within . R25 (1) minute af ter a start signal. , ,,

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e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the 00P when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 4000 cfm 1 10L
f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas ,

when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 4000 cfm i 10L 4

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! SEQUOYAH - UNIT 1 3/4 6-14 .

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S.wsme i PLANT SYSTEMS e SURVFittANCE RE_QUIREMENis (Continued 1 , _ . __ __ , __, ,___ ,

._ _.. __.. __ . _. . _ ..__ _ _. .__ .. I

c. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying

. within 31 days after removal that a laboratory analysis of repre-sentative carbon sample obtained in accordance with Regulatory -

Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, .

meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

d. At least once per 18 months by: .
1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the filter train at a flow rate of 9000 cfm
  • 10%.

I

2. Verifying that the filter trains st.irt on a Containment Phase A Isolation test s,ignal,; or a high radiation signal from the fuel pool radiation monitoring system or the auxiliary building
ventilation monitoring sy' stem.
3. Verifying that the system maintains the spent fuel' storage area and the ESF pump rooms at a pressure equal to or more negative than ,,

minus 1/4 inch water gage relative the outside atmosphere while maintaining a vacuum relief flow g,reater than 2000 cfm and a total

system flow of 9000 cfm i 10%. ,g ,,,,4;, jg, ,, g g.,, j,,,,g.f I w;// }; nip.la de ***13 '""*U p g #'";'** 4*'

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4. Veri f ying t hat the heaters ^4 t- 32 ^ 2." hu when tested in ,g,'" ""

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accordance with ANSI N510-1975.

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I e. After each complete or partial replacement of a HEPA filter bank by //. ef/4 9 verifying that the HEPA filter banks remove greater than or equal to i

99.95% of the DOP when they are tested in place in accordance with

! ANSI N510-1975 while operating the system at a flow rate of 9000 cfm

+ 10%. ,

l l f. After each complete or partial replacement of a charcoal adsorber .

1 bank by verifying that the charcoal adsorbers remove greater than or j equal to 99.95% of a'halogenated hydrocarbon rofrigerant test gas i when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 9000 cfm 1 10%.

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e s REFUELING OPERATIONS

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%-g , . SURVEILLANCE REQUIREMENTS (Continued) c.

Af ter every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of representa-tive carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.

d. At least once per 18 months by:
1. Verifying thbt thE pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the filter train at a flow rate of 9000 cfm i 10%. -
2. Verifying that the filter train starts on a Containment Phase A Isolation Test Signal; or a high radiation signal from the fuel pool radiation monitoring system or the auxiliary building ventilation monitoring system.

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3. Verifying that the heatersddissipate^32 _ 3.2 La when tested in accordance with ANSI N510-1975. 4"gj,4 ,

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e.

Af ter each complete or partial replacement of a HEPA filter bank by 'f"* / 'b 2# 5 V" verifying that the HEPA filter banks remove greater than or equal to Q #*

99.95% of the DOP when they are tested in place in accordance with "6 ANSI N510-1975 while operating the system at a flow rate of 9000 cfm j 10%.

f. Af ter each complete or partial replacement of a charcoal adsorber '

bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas wnen they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 9000 cfm + 10%.

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,~ PLANT SYSTEMS -

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3/4.7.8 AUXILLARY BUILDING GAS TREATMENT SYSTEM The OPERABILITY of the auxiliary building gas treatment system ensures that radioactive materials leaking from the ECCS equipment following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses. ANSI N510-1975 will be used as a procedural guide for surveillance testing. Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of-moisture on the adsorbers and HEPA filters.

3/4.7.9 SNUBBERS J' Snubbers are designed to prevent unrestrained pipe or component motion under dynamic loads as might occur during an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown. The con-sequence of an inoperable snubber is an increase in the probability of structural damage to piping or components as a result of a seismic or other event initiating dynamic loads. It is therefore required that all snubbers required to protect the prirr1ry coolant system or any other safety system or component be operable during reactor operation.

Because the snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed to replace or restore the

inoperable snubber (s) to operable status and perform an engineering evaluation on the supported component or declare the supported system inoperable and follow the appropriate limiting condition for operation statement for that system. The engineering evaluation is performed to determine whether the mode R16 of failure of the snubber has adversely affected any safety-related component or system.

Safety-related snubbers are visually inspected for overall integrity and operability. The inspection will include verification of proper orientation, adequate fluid level if applicable, and attachment of the snubber to its anchorage. The removal of insulation or the verification of torque values for threaded fasteners is not required for visual inspections.

The inspection frequency is based upon maintaining a ccustant level of snubber protection. Thus, the required inspection interval varies inversely with the observed snubber failures. The number of inoperable snubbers found during a required inspection determines the time interval for the next required inspection.

Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25 percent) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter

, inspection interval will override the previous schedule.

When the cause of the rejection of a snubber in a visual inspection is clearly established and remedial for that snubber and fog n ther, snubbers SEQUOYAH - UNIT 1 B 3/4 7-5

  • REFUELING OPERATIONS ,,

V * -

~~

BASES _

3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL PIT i

The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is consistent with the assumptions of the accident analysis.

3/4.9.12 AUXILIARY BUILDING GAS TREATMENT SYSTEM FP The limitations on the auxiliary building gas treatment system ensure that all radioactive material released from an irradiated fuel assembly will 4

be filtered through the HEPA filters and charcoal adsorber prior to discharge

' ~~ to the atmosphere. Cumulative operation of the system with the heater on for j

10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 3 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The OPERABILITY of this system and the resulting iodine emoval capacity are consistent with the assumptions of the accident analyses. NSI N510-1975 will be used as a procedural guide for surveillance testing

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j CONTAINMENT SYSTEMS i

, SURVEILLANCE REQUIREMENTS (Continued)
c. After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of representa-tive carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2, March 1978, meets the Regulatory Guide 1.52, Revision 2, March 1978.
d. At least once per 18 months by:

{

! 1. Verifying that the pressure drop across the combined HEPA ,

3 filters and charcoal adsorber banks is less than 8 inches Water Gauge while operating the filter train at a flow rate of ,

j 4000 cfm ! 10%.

2. Verifying that the filter train starts on a Phase A containment isolation Test Signal.
3. Verify the operation of the filter cooling bypass valves. ,
4. Y;rifyir.g th;t th: h::t r: di i? M IS ; '.S he h:2 50hd in ;;;; d;;;; with ^."S! ".510-1975. (

s 1 Verifying that each system produces a negative pressure of

4. greater than or equal to 0.5 inches W.G. in the annulus within R11 (1) minute af ter a start signal.  ;
e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the 00P when they are tested in place in accordance with j l

ANSI N510-1975 while operating the system at a flow rate of l t

4000 cfm 1 10%.

f. After each complete or partial replacement of a charcoal adsorber i

bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas ,

f' when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 4000 cfm 1 10%.

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I SEQUOYAH - UNIT 2 3/4 6-14 d

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PLANT SYSTEMS A

SURVEILLANCE REQUIREMENTS (Continued)

c. Af ter every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing c'riteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978.
d. At least once per 18 months by:
1. Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the filter train at a flow rate of 9000 cfm + 10L
2. Verifying that the filter trains start on a Containment Phase A Isolation test signal; or a high radiation signal from the fuel pool radiation monitoring system or the auxiliary building ventilation monitoring system.
3. Verifying that the system maintains the spent fuel storage area and the ESF pump rooms at a pressure equal to or more negative than minus 1/4 inch water gauge relative the outside atmosphere while '

maintaining a vacuum relief flow greater than 2000 cfm and a total system flow of 9000 cfm i 10L

.aut 4 ~;dI., fN relaL L~A

4. Verifying that the heatersadissipate,32As ~
3. ewn 2 L wneww, hen tested in o/' A/

accordance with ANSI N510-1975. din he. 4 /m du, .

epal 4 por p : 1

e. Af ter each complete or partial replacement of a HEPA filter bank by < d< t f &

verifying that the HEPA filter banks remove greater than or equal to 4//w, 99.95% of the DOP when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 9000 cfm + 10L

f. Af ter each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 9000 cfm + 10L I

1 SEQUOYAH - UNIT 2 3/4 7-20

O E REFUELING OPERATIONS V

SURVEILLANCE REQUIREMENTS (Continued)

c. Af ter every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of representa-tive carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978,
d. At least once per 18 months by:
1. Verifying' that ~ the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches Water Gauge while operating the filter train at a flow rate of 9000 cfm

.t 10%.

2. Verifying that the filter train starts on a Containment Phase A Isolation Test Signal; or a high radiation signal from the fuel pool radiation monitoring system or the auxiliary building ventilation monitoring system.

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3. Verifying that the heaters
  • dissipate 22"93 neau.., -b
.2 'a when tested in 4 " '" b

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accordance with ANSI N510-1975. ,p 4 <,/ 4 ,. 4 /m e.

+4. e epa / 4 70 7.

Af ter each complete 'or partial replacement of a HEPA filter bank by p,3 4 l s verifying that the HEPA filter banks remove greater than or equal to s.,4t.j 2 l 99.95% of the DOP when they are tested in place in accordance with-ANSI N510-1975 while operating the system at a flow rate of 9000 cfm ////,,,, i

+ 10%.

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f. Af ter each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas  !

when they are tested in place in accordance with ANSI N510-1975 l while operating the system at a flow rate of 9000 cfm + 10%. l l

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excu / M ,,,.h:m , , c.ya,3? <ep ,:- - d, 4 imin 4,;, M a:,de,,,, ,c4 L. A wsp A du Kn c, egua/ f 70 pa-a a,,/

pt:- -4 asL.y a: eda ,y u,,.f em su'<;y a,ud<n ny . u,,dh-,s.

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PLANT SYSTEMS i

! . BASES '

w 3/4.7.8 AUXILIARY BUILDING GAS TREATMENT SYSTEM The OPERABILITY of the auxiliary building gas treatment system ensures that radioactive materials leaking from the ECCS equipment following a LOCA are i

filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the accident analyses. ANSI N510-1975 will be used as a procedural guide for surveillance '

h f j) Jesting. , Cumulative operation of the system with the heaters on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 and,HEPA adsorbers day periodfilters. is sufficient to reduce the buildup of moisture on the 3/4.7.9 SNUBBERS i i

Snubbers are designed to prevent unrestrained pipe or component motion under dynamic loads as might occur during.an earthquake or severe transient, while allowing normal thermal motion during startup and shutdown.

of an inoperable snubber is an increase in the probability of structuralThe consequence damage initiating to piping or dynamic components as a result of a seismic or other event loads.

2 It is therefore required that all snubbers required I

be operable during reactor operation.to protect the primary coolant system or

( Because the snubber protection is required only during relatively low 2

probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed to replace or restore the inoperable snubber (s) to operable status and perform an engineering evaluation on the supported component or declare the supported system inoperable and follow the system. appropriate limiting condition for-operation statement for that The engineering evaluation is performed to determine whether the mode R2 of system.

or failure of the snubber has adversely affected any safety-related component ,

l Safety-related snubbers are visually inspected for overall integrity and operability.

adequate fluid level if applicable, and attachment of the snubber to anchorage.

The removal of insulation or the verification of torque values for threaded fasteners is not required for visual inspections.

The inspection protection. frequency is based upon maintaining a constant level of snubber observed snubber failures.Thus, the required inspection interval varies inversely with the required inspection determines the time interval for the next inspection. requiredThe Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval the required has inspection elapsed (nominal interval.time less 25 percent) may not be used to lengthen shorter inspection interval will override the previous schedule.Any inspection who g_ SEQUOYAH - UNIT 2 B 3/4 7-5 8

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d REFUELING OPERATIONS 8ASES a J 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL AND SPENT FUEL PIT The restrictions on minimum water level ensure that sufficient water depth is available to remove 99% of the assumed 10% iodine gap activity released from the rupture of an irradiated fuel assembly. The minimum water depth is 4

consistent with the assumptions of the accident analysis.

3/4.9.12 AUXLIARY 8UILDING GAS TREATMENT SYSTEM The limitations on the auxiliary butiding gas treatment system ensure that all radioactive material released from an irradiated fuel assembly will f ,ese d A be filtered through the HEPA filters and charcoal adsorber prior to discharge

- to the atmospherea Cumulative operation of the system with the' heater on for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> over a 31 day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The OPERABILITY of this system and the resulting iodine removal capacity are consistent with the assumptions of the accident analyses. ANSI N510-1975 will be used as a procedural guide for

, surveillance testing.

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SEQUOYAH - UNIT 2 B 3/4 9-3 l

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_ .._ _ _ ,_.__ n __...._. _ _ _ ._ _., _ _ . _

ENCLOSURE 2 PROPOSED TECHNICAL SPECIFICATION CHANGES SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 (TVA SQN TS 80)

Justification to delete SR 4.6.1.8.d.4 (units 1 and 2) and revise SRs i 4.7.8.d.4 and 4.9.12.d.3 and associated bases (units 1 and 2) of the technical specifications.

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Description of-channe ,

Delete surveillance requirement (SR) 4.6.1.8 d.4 (units.I and-2), and revise SRs 4.7.8.d.4 and 4.9.12.d.3 and associated bases (units 1 and 2) to reflect the minimum heater capacity required. A typographical error'in SR 4.7.8.d.4 (unit 1) is also corrected.

-Reason for Channe The Emergency Cas Treatment System (EGTS) and Auxiliary Building Gas Treatment System (ABGTS) heater requirements currently in the technical specification reflect the manufacturer's ratings of the heaters. It is our position that the technical specifications should reflect the minimum heater requirements based on plant-specific analyses. Analyses have been performed which show -

that the EGTS heaters are not required to perform a safety function and that the minimum heater output required to perform a safety function in the ABGTS is significantly less than the manufacturer's rating.

Justification for Change Both EGTS and ABGTS were constructed with heaters in the ductwork upstream of the air cleanup units. These heaters were installed to maintain the relative humidity of the airstream passing through the cleanup units to less than or equal to 70 percent.

TVA has performed a detailed calculation, EN DES Calculation TI-ECS-98, .

" Maximum Annulus Relative Humidity Resulting from a Loss of Coolant Accident  !

(LOCA) or High Energy Line Break (HELB) Inside Containment," (see l

attachment 1). The maximum relative humidity as calculated in the cited analysis in the annulus after a LOCA or HELB inside containment would be approximately 60 percent (assuming the annulus was cooled to its normal operating average temperature of 105 0 Fahrenheit). This value is lower than the upper-bound relative humidity that the duct heaters were installed to maintain. As such, the duct heaters in EGTS are not required for safety.

It is important to note that the annulus relative humidity calculation was performed assuming an annulus inleakage (from the outside environment) at a rate of.100 cfm. The offsite dose calculation for Sequoyah now assumes an annulus inleakage of 500 cfm (Sequoyah Final Safety Analysis Report [FSAR]

subsection 15.5.3). The analysis points out that this would lower the annulus relative humidity for a given temperature, as the inleakage acts to " dilute" the steam leakage from containment. Therefore, using the 500 cfm inleakage rate, it is concluded that the relative humidity in the annulus can be as low as approximately 45 percent (assuming an average annulus temperature of l 1050 Fahrenheit) after a LOCA or HELE in containment. l Another TVA calculation, EN DES Calculation TI-ECS-4, " Determination of; Requirements for the Relative Humidity Heater in the Auxiliary Building Gas -

Treatment System," was prepared to determine the heater requirements for ABGTS (see attachment 2). The analysis was performed to define realistic conditions (temperature and moisture content) for the air entering the ABGTS suction.

These realistic conditions were defined-to replace the original' calculation assumptions which were overly conservative. The resulting calculations determined that a heater capacity of 15.8 kW is required to reduce the relative humidity of the ABGTS airstream to the desired 70-perceat level based on the assumed outside air conditions.

Based on the referenced evaluations, the SR for measuring the EGTS heater output can be deleted, and the SRs for measuring the ABGTS heater output can be changed to have an acceptance criteria of greater than or equal to 18 kW (15.8 kW required plus 2.2 kW safety margin) when the recorded voltage and current (from the surveillance test) are equated to the limiting voltage value of 422 Vac. This is the limiting voltage at the ABGTS heater terminals as determined by calculation OE2-EEBCAL001, "AC Auxiliary Power System Voltage and Loading Analysis." The recorded data will be equated to the analysis minimum requirement of 18 kW by using the following formula:

Power eq = (422)2(1.73) I(recorded)/V(recorded)

The technical specifications for both EGTS and ABGTS have SRs that call for the systems to be operated with the heaters on for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, at least once every 31 days on a staggered test basis. This action is intended to reduce the buildup of moisture on the air cleanup filter banks to below acceptable limits. This ensures filter efficiency is above acceptable limits. This testing will continue to be performed at the above-stated intervals.

To ensure that the heaters are performing properly, they will continue to be tested once every 18 months to verify that they meet the manufacturer's ratings. This testing will be performed to identify heater degradation, not as a required test to satisfy technical specification surveillance.

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. i form P/A 10887 (EN DRS 1441 N DES CALCULATIONS TI-ECS-98 TITLs MAXIMUM ANNULUS RELATIVE HUMIDITY RESULTING FROM A LOSS PLANT / UNIT OF C0OLANT ACCIDENT OR HICH-ENERCY LINE BREAK INSIDE CONTAINMEMT SQN 1&2 PREPARING ORGANIZATION KEY NOUN 5 (Conesit MEDS CIS DESCRIPTORS UST)

OE/ NEB /NAL annulus, humidity, LOCA, HELB SRANCH/ PROJECT IDENTIPIERg Each time these coneutettone are 6enned, properors must ensure that the orte6nes (RO) MEDs ecosenson number es filled in.

, , Rev (for MEDS* use) MEDS accession number APPUCABLE DE31GN DOCUMENT (S) ao8 5022580153 $ NEB '85 0222 2}5 R

NA R ._

i SAR SECTIONIS) UNID SYSTEMIS)

NA NA R_

Revhion 0 Revtalon Revision Rev6sion ECN NUM8ER (Enter"N/A** if there is no ECN)

NA FREPARED CHECKED ,

susMirr DATE I q,gg, g APPROVED Ust allpases added by thh reviolon g=l, uet est peces deleted

, by this rev6eson 8

Lkt als peces chenood by thh revision STATEMENT OF PROBLEM i Upon a double-ended pump-suction break (loss of coolant accident (LOCA)) or most severe eteam line break (high-energy line break (HELB))in the containment, determine the resulting maximum relative humidity (rh) in the annulus.

ABSTRACT As a result of nonconformance report (NCR) SQNNEB8408 on Sequoyah Nuclear Plant (SQN),

an analysis was performed in order to determine the maxinum rh in the annulus following a LOCA or HELB inside containment.

The rh in the annulus is a concern since the air is processed by the emergency gas treatment system (ECTS) which contains inoisture sensitiye filtration stages.

' For the analysis, the containment environment was assumed to be at 3270F and 23.0 lb/inabs.

These are representative values during the initial phase of a LOCA/HELB cnd were assumed to be constant throughout the accident. Containment leakage into the annulus was assumed to be 1.5 cfm, continually. Also, annulus inleakage from outside g g ,u,m g goJ g f00 cfm at 770F and 100 percent th.

E75052.05 Microfilm end store calcutetion in ME DS Service Center. Microfiern and destroy, b "*'d* *ad **"a ca'cukt'oa to: J. L. Huskey ^"

W10D184 C-K

l TI-ECS-98 (Continued)

It was found that the resultant th in the annulus following a LOCA or NgLB inside containment would not exceed 60 percent, even if the annulus has cooled back down to its normal average temperature of 1050F (An additional 50 of annulus cooling would result in an th of 70 percent.)

l l

l E75052.05 NEB-Feb. 21, 1985

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sraTe.0 wouto cAuse STEAM To LEAK, FRoM coorn MMEA3T IMToTM  !

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. A bolTio4 AL ConSIDeRArioMS b CoMMOMTS -

A THt #c eovoN AM EEGTS DES IG.9 IMCoRPORATE.S l

RE L AT IVE H UMiblTY H EATE R. Sl2.E.D 70 COMTROL WE l bt!% IGM FLoWRATE OF A)R TO A max) MUM OF ~10 /o RM .

I OF tooRSE, THIS FEAWRE - 15 ADORESSED t o - N RC,

! ReoutArog.y Guion i.sa (e.o," Desico, rasrias, Ano l 1

MAinTENAuct CbTab A FoR. PosT Ac.c.ibenT ESF AT Mos.PmrRF i l

CumAuve SnreM AsR I:itTRArion AND Aosogerwu Quirs CF l Emi rms-L u. ar- WArw-Coo'EL N octEA9. i% et. PcAnts ."

fleLArave HUMi blTN IM air bTREAMs PROCESS ED D/

CA R600 F LTT RS PERMS r5 CEa_rnin AssuMP noes L
REG AR DING MPRovED DecourAMlp AT1oM E FFicl EMci E S .

SIMCE RE LATIVE HOMi0iTY is A coWCEG.M Foil lESF air CtEAMuP systehs, AMO sINCE SEouoNA H-l AjoNCobFORMAMCG REPORT (NCid) sopME1384o% ourLI M ES

'A PoTEMTI AL Foft EGTS HEATER FA) LORE , )r tuAS BEClOE D To PR.EPAAE. ThE PRECEb lM G- ANALYSl$

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........ w fA .. A//t/t f IN Twt ANNULUS OPCM AM ACC 10EMT (AND Co 45FouGM71.y TMe. max IMuk D/c R.H eMraRiMG TwE EGTS FILTER S i t: TWts. MATERS 40ERE INOPEftABLE)-

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AS suMMAS.12ED eM PAsa 9 , i r vJ AS DE t e RNMtro TYrAT TWE tex 1 MUM *4 R.R IA) THt AMMULUS D)Oot0 6E 6O*/o wiTM Tig E SPACE AT IY5 NORMAL.

i AV E R A<rE TEMPER A'n)AE o F= l o5 *F . T'H-15 REPc RE, j THE c_AReoc t LTER.'s o ecaurANA) AT7ou i

i l gf=FIC)EA3C.1 woULO Nor GE fLE DUC.f.T D G E Lo to i

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1 b IS NORT1f NOTIN6- THA T TESTS 0/= CAA&oA)

FILrsR$ )NDJCATE TitAT SUCH F*n 72DS H&E FAIALY hJGM MFFJC/EA>C/ES, EVEN Ar122U%TIVE i

l HOMIDIT)2S As WIGH As 95-X. Fuarnee ExAnisinrios)

Ol= TH/S AS(2EC.Y /5, How2 VE2, BEY CAJO T7tG SCOPE DF THIS AhRLYSIS -

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THE FoLLo*)icCr Pot 2T 1% AL.So WORTH CoM5tDEEIMG-Al R- IS Tac. 99EvioOS AMALYStS ASSUMES ouT510E l

l 1.tAtpve IcTD TWts ANNOLUS AT A RATT. OF l 10 0 C,F M . LG AT% G AfL PERSoNMEL HAVE ftEcuESTtED l l

APPR. oval Fo R. ALLoo,Me A M i Gt+E R. IML.EAWAGE RATE .

l AND SUBSEcuGMT AA)A L%ES H- M E SrtoW 4 TWC EVEM C o O C.F M I A> LtI AKAGE 90VLD DE

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lh 71t2 ANA/OL US SINCE /r /} CTS TO b / L U Y E

THE ST&Abt LEAKAGE FAQbt COA)rn/4/1EA)r.

i FotL ExAmpts, Fot2 oursice nise tsAknse w i

! Sbo CFt1 (S~T1h5S &/ LEA 722 77tRN 77tE /00 CFb1 USG3 FOA TffE PRECED)AIG- ANAL \/SI.S) Tite l E Q U R T)DA) A-T~ T M ' 00770t1 Q/= PtbE 9 ' LA)OULO GG s*

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Tit 15 PJE.SuLTIM4 500 CFM INLEAKAGE Mix 7UR.E U300LD H-Ayr!. A MOIS TU RE COMTEMT CF GGATXiS / LS UncisT

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= D.077.,.

l5(o M ^^ .

LB App 1000 g 5 I

As eisroe.s , RE.FE icR lMG- TO F IGU RE 4 3 iF 1

TWE- ANNOLUS AssOMED TMis Mo iSTD RE CONTE MT-1 ANO cootec To iYs aeg.M AL AV ER.A&E TEM P.

oF 10 5l' 3 THE ANN OLUs RE LAnVE ttuMicity Ab utb E40hL OM L1 A'5* % R W . T/ts/2ErofE, l

I i /P AA) INCRGASE /A) ANNULUS JA)LGdKA6E /S PADPOSED /\NO ACLEPTGD #*C/L ,SEQu o VAH, AS BONE ~FOR

LOA TTS BAR, 7~//E /HAX//tutt ANNOLU.S N RH UPDA)

! A ConrA/A>Mii'A>T AcctDEA)r tooOLD /LE REDUCED F/loM fo O Yo R H 70 A t.ow2R AtHochT(45%/F THG l l ,

l JNLEhKAGE /S 500 CFh) .

. . M6,c.,/ a EN DES CALCULATIONS TI-ECs - 4

$3F TETERMINATION OF REQUIREMENTS FOR THE RELATIVE HUMIDITf erne.) "'*"' ON S 1/2 I HEATER IN THE AUXILIARY BUILDING GAS TREATMENT SYSTEM san escTioats l

PREFARING ORG ANIEATION REV (FOR MEDs USE) MEDS ACCESS 80W MtfMEER EN DES-NEB A.,1.lcmE.

cOCUMENT ...lo. ..A.c, o o m ,

IDENTIFIER 5 ai 00018D0057 e NEB '800811 301 i TI-ECS-4 nl GEG-1100 W 1 Tutu CH 35 mEYNOUN.

ABGTS, Heater HVAC na t;EV no na as na FTATEMENT OP PROBt.EM DATE gfdro Determine if the relative humidity raEr^ men heater capacity is sufficient as tested by analyzing the present G. L. Askew assumptions for overly conservative casc=En conditions. . Define more realistic

  1. D/M conditions if possible to reduce M F >Jl./d* the required heater capacity.

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!@IENSNS"s'nsvi c'#2 '.^r"T".6 ABKTRACT The perfomance of the auxiliary building gas treatment system relative humidity heater was analyzed by examining several entering air conditions and the resultant relative humidity leaving the heater to detemine heater sufficiency based on a test power of 28.9 kw versus

, a rated power of 32.0 kw.

The original worst case entering air conditions of 150 Fdb and 100 percent RH were found to be overly conservative. This origingl assumption was used because the air in the fuel handling area must pass over the 150 F water surfaces of the fuel pool and transfer canal.

However, analysis showed that because of short path length and low air velocity, the heat and mass transfer were insufficient to cause either the high humidity or high temperature.

Further investigation showed that the worst entering air conditions will be caused if warm and humid outdoor air infiltrates the building and passes over the pool with a conservative minimum of 60,800 Btu /hr of sensible heat added. 41 Lbm/hr of moisture is also added to the air due to evaporation of water from the pool.

A study of several sources of weather data showed that the worst condition that might be expected to occur no more than 1 percent of the suniner hours was 72 Fdb and 100 percent RH.

This condition required a heater capacity of 15.8 kw to reduce the humidity to 70 percent.

The actual heater capacity of 28.9 kw will reduce the humidity to 60 percent.

The heater was shown to be fully adequate with an excess capacity of 83 percent.

TvA 10497 (ENDES 7 78) 'Use revision log (form TVA 10534)if more room is required

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T61E l l5 ATH Q. 10 RATEb AT 32kW BJT Ts:TO e4 Ave O k>eJ eJ T4/47 TNF AtTJAL DGAT Li?.s9A"Tiot) n" 28.9 kw ( Tr;CT br* FF#CIFsJcy PT-425 P. I ) .

P6EUI P4 ".irATw m r u T i

l DETER.M i4 E It Twe HeATvt cAPAc TTY #5 SO FC 8Ct G sJT E4 A*J ALV I'k3G DE PRES tut Act.orn e rrio*JS FO R. 09EC.LY Co t>0 F#VATAJE- Cou D ,7tonJS A/J D D E Fl*JlF M IAuft C kEAltSTC AlR. Car 3Dt Tio?JS IP lb"*Si ELG =

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.3. tie AP.,,GTS POL LS A i fl fro m T.tr. R i tutTfs /L o C~ Fury L Ptx> t., A > J P. PJ f7 L T&fst10 f*6 (L

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fttJD Cs1915 L VJA TF(L 2,E F~oG2 gpts /?//J G 77+ si DUC r .

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DRY-BULB TE' MPERATURE, T: (*F) ,

I'igure 2. Joint Values of II;gh Temperature (to 120*F) and Illgh Ilumidity Which are Equ:ill'd or Exceeded O. 1, 0. 5, 1, 5, 10, 20, :10, 4 0, 50, GO, 70,

  • and 80 Percent ser the Tim <- (Irours) of the A1ost Severe Alonth in the World's Severest Joint Iligh-Temperature, liigh-Ilumidity Environment

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  • M JHr* M Soe* Jes ow >W Meco-65 70 15 so 85 W 95 DRY-BULB TEMPERATURE, Tg (*F) , ,

Figure 2 Joint Values of Iligh Temperature (to 120 F) and Ifigh Ilumidity Which are Equ:ill6d or F.xeceded O. I, 0. 5, 1, 5, 10, 20, .10, 40, 50, GO, 70, -

and 80 Percent of the Time (flours) of tiie hiost Severe hionth in the Forld's j Severest Joint liigh-Tciuperature, liigh-!!umidity Environment  ;

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Tl/E F i r/st rJ/ ME 77/cnD Lor) C 70 EyA mrud ACTUAL 7VA ^!fA T7/ff Of779 F*oR THC 2*L%'UWe\ H  : ~/75 [33 . THG Gum m fRC OF~ 1978 AND 1979 WtiRE Vil\nitoJCD . TIIC WGR:7 CIA /GL E H&vt c'ouD/ 7/oN3 favub forz DC ~i tuu'8 A+1b DFw s'ornT w Ffl E .'

TT. 8 Vdbl 76 8 fdp 75.o Mb / 74.7fdp .

Tills wcoun tu Du c'ATC THAT Til 5 l % VALVEC GST' thA TWO CU f"All f1RE cut T E CoM LWR \/ATIVC . T//2 ttJAA 7 HfA D/]I'A CUR VE1 :; Hcst uM THAT llb */o SM C0/.tD/77o/JS 000U2 LUITH SOM G AfflC0/2/lEl E EWS-Quenci /rJ Tile ~/o 70 7 2. Fdh PAtJGE . THEREroRG 'Ple //FATFA CAP /1 CIT 4 V2I t. t. EE cat. ('ut A TSD Est*ED QM 72fdb A/JD /C to */. k'//

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=

19929 BTv/niz .

29 2 kW 7 111 '. i0 Ttir!. H E c: G (L c A PA c n-f GE Qui G GD IF THE 174 F8LTR AT seJG ouTDoog. A n tt

,. 15 pot C E7dc c E uY H r; ATB D AO :T PAtt ri t THQouGH TilfE S P AcG S Tu inE FUE L Pool A *J D C A

  • s A L. Dx.T IMLETS. HovJ E vfi G. , TH G Q E WILL BE A f.lGtJI Fic A UT HEAT LOAD CPACES Cl*X E 19 7 p C' 3

PI' CE btM G A Lo c.A orl FvFL NAuDLauG AcclDri+3T , TH E PLAeJT wLL SE ItJ A tJoa m A L opr! R ATs u G MODE. THIS 8 .'~ AT !oAD DI C Ec,TLY R 'E Duc.E 5 TH E. H E A T E (2. RECQVIGEMIIOTS APJD / o C- FUf4Tib7G. PEDLt.FS TH E B EL A TIV fC 14U ml Dll T 8FLovV '7 0 /o .

WC E UKQ. s r3 G hill corJ D s 770 r.s: a t t. L sJow BE GSTI m A TED TA gro)G 184TO AOCou O T EoTu S F t M I BL E. W ITATioG A aJ D trr1 A C; TP Air f 99 Foot e 'nlE Poot Sup F=Ac.F_ .

8

6./

GLA t-to-to

. .. . . . . ._.......L_

l 5waP CA L Cut. AT to >J " f. 4 ] 4WT 7kE FoLLN:tJ G HEAT LCADS Fo rt THE. F E ru v7 s. i .a G At?sA LlGHTC, 60 j 000 W 204 000 R w/ Hf.

Roop c,ot Ait toAr3 92 coo

2. S G oo o E70/HC

%E (to o F Co t A(L LA AD 10 A Ts2 A>JOl G'JT /ItJ D ('A /J /.D7 OE 4/06 C)

ArJU Du rl ita G Li rfCF L GFtJ r-g ATo#7 opf7a fwlosJ 7/4E tt G H T ;,; c wiLi P871,uc.c b E,fi Sco%

.'. H t7AT LoAid = 204o0c X 2 =

40300 EP/H'

(' IF iT 10, co0 0 6 RvA 7 iv.7Lv A 50u rn a i, THAT THE A l f2. I tJ F ILTPATE,' '

pt si Fu fi L M Ata bL i ta G. /1 9 E A Po# 7 tor.> o sc" THE. A u X lL t A E 't ? ulL brAJC Ds R F CT L 4 VRom T>6 'i' O.tT: s Dt' PA 7HE/L 7/1Ar) PASSI^1G THnouait ornest C P/1C E 5 Ts t 7 pJ GEou Te.wa / p r.  ; r, y ecA - Aooy3 ;florvg 79s cer.c n c. so , .. q AsoTs i . g ptovvr.

T ll EVE wlL L ptSo CE A SEtJslBL G A)vD L A TrirJ 7~ HWAT L oA D F~Ror.1 Tn ti- Pool Ar>0 C/ird L Cuf FocriFC . T3liSE H6AT Lo A D*" t.p>G R EE Celcut AT FD iM A p pi7 pa bt X P AS C'F ut i t., L E HFAT Lo A 7s ? 2 0 oo s

, ev/ n s.

Yoo n ',. ' u st. E. ADDiTb Al 9' lbm /PC

'it7rA L 4 trAT LOA D :: 402 co -+ 2 oc o *  : (psco ty v ma s **,,1s ta (2.

, ADDrio : AI Ilim /n p.

t

$ . 130 v) E /11 m it) E Tl/E El~fGcT CF T ~9 // EAT I oA/) AnO l VVDoo S 7Litz E orJ FasTSAts/G At(2 car.<>t7 w J Br>D //t~A7)ft

= -

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OuT51DE A ll2- P/?oPMe 7/f *; 13 H D - DATA i

i h - 35.9 Uw/ Km - M;-

, 'll = l 4.0 S FT S//bm- nig.

Y- 9ooo r~r 3/ MIN' 15 W = 960f) x (ao  :- 36434 lb ~ / It 14-W /4.05 i

l bh = (o O S:'o Te.,u / N e - t. s s uru//br ( sgnsiatt) anew B2434 lb- /4 A FPom "P. c H ArtT pgw co,J D 77c a >L F o /2- h = 3 5 A + t 5 2.

= 37AE

( ,

. AND W = cons.TA"T 7 9.5 F d l; AM b 6 "/o RH 4i L b~ - Hno /I4 tL Copt, a ce (L fvios tru P E 6W =

3 e 4 ,4 l b e. A r g /'g e.

o o it Ib e - H, 0 l

lbv -AIL i o,

W' ' o O l ~1 f- , Doll = .ol8I '!

,1 N o t^> C o p o e Ttc.> 9 0, A6E r'g.o m '1 P- canaT -

I I

l 1 79.5 Fdb A90 B S */o R 41

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/W A I L A E.LE 4 UA TV 6 P o w f (L- .

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t.

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br 38.7  !

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@ W - co ue A w T Coobi nog 0 L(7Avi PJ G ME

// GA 777R ,

8 9 Fc)b A 36 60*/o RH C P - c - A rt r )

l i

s cat cut Avtt Hora 7 w n, cA pac iT f WEDrD 'T.) ovwed atr_T ~7 0 %.

l g = - o; j

ha ze.7 eTu/ /6 i l

lr oar = 40.I cro/Ile l

N 3 8434 /fv/NA l e

-; .'. s e4 2+ ( 40 1 - as.1) = szaos e,ojue.

g

l i, = i s .77 tw

=

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Fycyst o gATri tt. ce ives7Y -

28.9- /5.77 _ 33*/,

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.I myx /-m=- 90 ~~

\T clul now BE C V Fr) TilAT P1 Co!JSI DWR itJG 'P//[ CFtJ:t DL C //E*A T f AND M ol".TU R E. ADDC'D TD 'TH E IlJ r lLTpAT i tJ G fi s #,. "#/E H6AW/_ l l

l CAPAGiW R EQu e ttMD H si ., P f5E d (2 GDJc.R i> Tu A Z3c.v 7 / 6 kW. '

l 'T*H *, V htl G **, 'TH E H GhTTfl. CAP /10 TTY AS W37ft) v1) o n. G W ArJ l CO I FtOf RtJT ,

h5 A VH ATT1T(L OF lO'T TEflGC T' T'IE PECu t Tw T 12 EL A T'u5 Ifurris0171 '

WITH THit Av A IL A F.',L 6 la GATTi/L C/)p/W N wit L p.o w s e c A L c u t 4 Tst ,3 We7) lout TAif a M C. C #7blT Fo12 M D D s 7/o f.s A t 564/5/64 E NE/777/JG, WG en THE r.p/W e: Ar>L 7bc2 c. .

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2. sis c:w IL.- sia (90o o ) ( (so )

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(- h o u, = 240 Twr

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@ s2 F a e. 24 o. y4 Ss.s49

& 92,15 38,?43 9 2e.34c

  • . = B2 . / 5___ F*

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7/. c. "/.

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P

=

(G 3 36 2. ) ( B2./ 5 + so) [ t + /,4o7E ( .c/ 697))

( 14.7) i/44)_

=

l4.04 F~T 3 / lbn - n/2 i TE(2 AT 5.

() oh - ( za.9) ( s 4 /2 )

(90o o ) (Go)

, z.sG(

/4 ,04 l

h. , = z =. se + 2 . sc.4 - se . gv4 arv//4 . nia E8.594 =

. 2 4 T,_.,. + . o/691 [106 I + . q94 7,,,.]

c2 sz. 2 s 4

ES.399 / 29.364 e az. s s 38 294 2 sg, gg ey

( ,, .. Tou .,. = 82 55 '

Pw .S'4735 c ,1 l

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35 l l

6Ls sz-n-79 l

--- f l

} . . . _ _ _. _ . . . . . _ -. -- A P- '4t?/?? ,)

ii

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1

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Cced 37 R>tt 77* AGt\\d 77 = (C3. E 52 ) ( B2. 35 J. 460_) [ g 4 p , goy 2 ( . c yc q,)}

(l#,7) { /11) l

= l4.C)4 /JO MA!JGV,

.. NO fur 7MTR C'940 ULM7x*JS.

THE REL A TIVE HUM!DITY LSAJttJG 7742 HR}7FL l'; 71 % IP ^10 5745 s BL6. HEAT F/ZoM T4e $ PACES /5 ADoso 7b TH E M //L .

^

, s 0A/CL USlo Al5 _ *

l. 71/F O/2/St>J /lL Accun*Pr/cd of /Sc fc/L AuD /Co% R// I: CVEHLY CotJCF2s/A TivE AND u!J Ju: 7 i f't FD , /totMFufA T/4E /-/FilTEA WA 5

/\ t'T U A L L Y BCt.45/!T VAJDrPA C/26I) F&2 771/ (2/Jb t T7o ^/ .

2 THE /> &li**. T C' k^ i

^

_. CA O:fi) &f tb si!/ D QvTC/CGK At/2.

eftNG E covo+17 /NTO Tile SPKEG n'J o V ?t1 w M t rJ7t. 711C M7 wlTIl A InisJimtJ m OF SfirJ 18L S IIVAT ADne h Filom TH E S PAG ES AND Poot tu f2 f:Acg ,

3 TitC D u T D o o tl AIA CurJ DI Tic)H sa st sC.lA WI L L. Occ ult w McWR E ' T71 AN I L cF 77tE Tiin E 15 7 2 F cfb Aub / C o % !? N .

4. D4C AD IL wlLL FF M T E C. THE HEAT 54 AT 78. 5 Pdb AMD 6 5 % R//.
5. THE AIR WI L. L. LgAug 7pf H S A 7 Fot Ar 81.S fdb AN/> bo % RH. t

. 6. w c. HsAtsrs. HAs 9 3 "/o cxcee cAPAci rf ( 15.B kW RFavi n ei> j 2 8. 9 kW Aveyt.95LE)

. . . , , . ,nas wee 6.,.+aw O & $ $i,e:;4wd,j$d?1S.*$$$ & $ $ $$h55 S-

s. .-

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l. R. V. l*cR M Ell , " VW'4LO wtDG EyrnfMrs op* Huntruin wr 7H TGMPFEATUQE' BGwWnd 96 AMb /2ca fj' A F C R L - TR 0603 ,

5 D MC IR"1 4 .

2. ACHP A G. HFtJD Ecxa f. c F' For.sDA mdAJ7 ML * , cpAirrEf. 2 3, /977 ,

.3 HO29 W WGATHWn iMTA - 3F&Lov'AH //.P. , pA rA inni>AGFM W Sfd7*Kjd y DA77\ SERVICPS ESAtxH , CPCdf of Nef72MM RE-Cov!? C 65 y / 97;ir - /971,

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0 I

APPfablY A

, CALCu L ATlodt foR Ot?/6tNA L WC2CT CASE HFA77/2.

SI F.i tJ G A S S um P7 to d s Fo /L A fEGT5 i l I

. I

! I I

e 4

i  !

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1 1

1 i

l 1

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N-e

- - - - - . - - - - - - - - - , ,- _n,ww.w_,,_,,,,,, p,_ , _,_ ,. , , .

, , , _ . ,p __

+=r _

, _APPerubix A 35' 55 E vat.u A h or AnA nver Humm TY H FATwrl Permortm Ape rt Pon *ca rd AEGT5 Fo#-

g \ 50 F DN BuL B #D leo % RH GLA t ol-2 7.

I /4 L o o* $'-1* ;

J tpostire : -

DF77tirn/A,t frQJtR *TU

! sinb tit 7Unl. infritcr>rowc of ABG75 AIR tWATTR.

xamus ;

I. 9000 c{rvs *WrMM ** HEA TE/t ^~ l$ 0 Gib ^MO h = IO* Y*

2.

h LFeditJG. H F ATFtt l' 7c*/.

2. A07vt.t HGATNg FisWF/2. 15 2 9'.4 gw ( PT- 40 2 , Tv A - 9. )

< Atcut AT 0,J :

M Me, 4 M w, M3 -

, W. , d WI ,

no L 6 *, ',, en Ar>Dorrup of wA1 , ..

, = k1g= nh

( ,

w%mrye = (h -2 h . ) M FW A ,ppAgt pu,JD 3 14 17 ) p . (., - l, nail :'Jstuf7 ATE D AIR N :, = . 2. 415 11 m . u o / lb , . b . A .

T = 20.sto Ol' . M os t,t Aif2 / lbm - D.A

h. . 2.75. 2 ew / h - c.A.

W= = So'>o M/m

' 3 t,o<ra , 262s9.o; LL_

2 o . sc, W/li- . o.A b M i

W '

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I-ENCLOSURE 3 PROPOSED TECHNICAL SPECIFICACION CHANCES SEQUOYAH NUCLEAR PLANT UNTTS 1 AND 2 (TVA SQN TS 80)

Determination of no significant hazards considerations for proposed changes to the EGTS and ABGTS relative humidity heater surveillance requirements.

i I

l l

I 4 , 3 SIGNIFICANT HAZARDS CONSIDERATIONS

1. Is the probability of an occurrence or the consequences of an accident previously evaluated in the safety analysis report significantly increased?

No. The purpose of the heators is to maintain the relative humidity of the airstream passing through the Emergency Gas Treatment System (EGTS) and Auxiliary Building Gas Treatment System (ABGTS) cleanup units to less than or equal to 70 percent. TVA analysis TI-ECS-98,

" Maximum Annulus Relative Humidity Resulting from a Loss of Coolant Accident (LOCA) or High Energy Line Break (HELB) Inside Containment,"

indicated that the relative humidity in tho annulus (EGTS suction) would remain well below 70 percent af ter a LOCA or HELB. As such, the ECTS heaters are not required for the proper operation of the system under postaccident conditions. TVA analysis TI-ECS-4,

" Determination of Requirements for the Relative Humidity Heater in the Auxiliary Building Gas Treatment System," determined that the manufacturer's rated capacity of the ABGTS heators was significantly greater than the capacity required to maintain the relativo humidity to less than or equal to 70 percent (based on the realistic conditions assumed for the outside air). Therefore, the changes to the SRs still ensure the relativo humidity of the ABGTS airstream to be less than or equal to 70 percent. In both casos, the relative humidity of the airstream before the cleanup units will be sufficiently low to ensure the efficiencies of the air cleanup units meet or exceed their assumed analysis values. As such, these changes do not significantly increase the probability of occurrence or the consequences of an accident previously evaluated in the safety analysis report.

2. Is the possibility for an accident of a new or different type than evaluated previously in the safety analysis report created?

No. The heators were installed to ensure that the rotativo humidity of the EGTS and ABGTS airstreams was loss than or equal to 70 percent before entering the cleanup units and to provido a method for periodically removing accumulated moisture from the filter banks.

The proposed changes to the SRs do not advernoly affect either of these functions. Therefore, those changes do not create the possibility for an accident of a new or different type than ovaluated previously in the safety analysis report.

3. Is the margin of safety significantly reduced?

No. The margin of safety provided by thoso heators is to ensure the sufficiently low moisturo content of the airstream through the filters to maintain filter efficiency. As thoso changes will not result in an excessive moisture content and loworod filter efficiency, there is no adverso impact on tho offsito doso calculations. Thus, there la no significant reduction in the margin of safety.

-- _ - _ _ - _ - _ _ _ - _ _ .