Text

Proposed Tech Specs Re Containment Leak Testing & Containment Isolation Valve Table
	ML20133H043
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/29/1985
From:	; PORTLAND GENERAL ELECTRIC CO.
To:	;
Shared Package
ML20133H024	List: ML20133H022; ML20133H034; ML20133H043;
References
	NUDOCS 8508090165
	Download: ML20133H043 (23)
	v • d • e

r LCA 124

. Attachment 1 Page 1 of 21 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity . . . . ............ 3/46-1 Containment Leakage . . . . . . . . . . . . . . . . . 3/4 6-2 Containment Air Locks . . . . . . . . . . . . . . . . 3/4 6-5 Internal Pressure . . . . . . . . . . . . . . . . . . 3/4 6-6 Air Temperature . . . . . . . . . . . . . . . . . . . 3/4 6-7 Containment Structural Integrity. . . . . . . . . . . 3/4 6-8 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray Systems . . . . . . . . . . . . . . 3/4 6-10 Spray Additive System . . . . . . . . . . . . . . . . 3/4 6-12 Containment Cooling System. . . . . . . . . . . . . . 3/4 6-14 3/4.6.3 CONTAINMENT ISOLATION VALVES. . . . . . . . . . . . . 3/4 6-15 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers. . . . . . . . . . . . . . . . . . 3/4 6-23 Electric Hydrogen Recombiners . . . . . . . . . . . . 3/4 6-24 Hydrogen Vent System. . . . . . . . . . . . . . . . . 3/4 6-26 Hydrogen Mixing System. . . . . . . . . . . . . . . . 3/4 6-28 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety Valves . . . . . . . . . . . . . . . . . . . . 3/4 7-1 Auxiliary Feedwater System. . . . . . . . . . . . . . 3/4 7-5 Secondary Water Chemistry . . . . . . . . . . . . . . 3/4 7-7 Condensate Storage Tank . . . . . . . . . . . . . . . 3/4

8 Activity. . . . . . . . . . . . . . . . . . . . . . . 3/4 7-9 Main Steam Line Isolation Valves. . . . . . . . . . . 3/4 7-11 TROJAN-UNIT 1 VI 8500090165 850729 PDR ADOCK 05000344 P PDR

F LCA 124

- Attachment 1 Page 2 of 21 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT i CONTAINMENT INTEGRITY LIMITING CON 0! TION FOR OPERATION 3.6.1.1 Primary CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION Without primary CONTAINMENT INTEGRITY, restore CONTAINMENT INTEGRITY within one hour or be in COLD SHU100WN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

SURVEILLANCE REQUIREMENTS 4.6.1.1 Primary CONTAINMENT INTEGRITY shall be demonstrated:

a. At least once per 31 days by verifying that:

1. All penetrations (except those portions located inside containment) not capable of being closed by OPERABLE containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic valves secured in their positions, except as provided in Specification 3.6.3.1, l and

2. All equipment hatches are closed and sealed.

b. By verifying that each containment air lock is OPERABLE per Specification 3.6.1.3.

c. By verifying that valves, blind flanges, and deactivated automatic valves which are located inside the containment are verified closed during each COLD SHUTDOWN except that such verification need not be performed more often than once per 92 days.

1 TROJAN-UNIT 1 3/46-1 Amendment No.

LCA 124 Attachment 1 Page 3 of 21 CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a.- An overall integrated leakage rate of:

1. sta (defined as 0.10 percent by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at Pa, 60 psig), or

2. SLt (defined as 0.07 percent by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at a reduced pressure of P t 30 psig).

b. A combined leakage rate of 10.60 La for all penetrations and valves subject to Type B and C tests (except for airlocks which have leakage rates specified by Specification 3.6.1.3) when -

pressurized to Pa*

, APPLICA8ILITY: MODES 1, 2, 3 and 4.

ACTION: .

With either: (a) the measured overall integrated containment leakage rate exceeding 0.75 La or 0.75 L t, as applicable, or (b) with the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 La, restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and

provisions of ANSI N45.4-1972:

a. Three Type A tests (Overall Integrated Containment Leakage ,

l Rate) shall be conducted at 40 1 10 month intervals'during '

shutdown at either Pa (60 psig) or at Pt (30 psig) during each 10-year service period. The third test of each set shall be conducted during the shutdown for the 10-year plant inservice !

inspection. i l

I i

TROJAN-UNIT 1 3/4 6-2 Amendment No.

l

)

LCA 124 Attachment 1 Page 4 of 21 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) {

b. If any periodic Type A test fails to meet either .75 La or .75 Lt .

the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet either .75 La or .75 L t , a Type A test shall be per-formed at least every 18 months until two consecutive Type A tests meet either .75 La or .75 Lt at which time the above i test schedule may be resumed.

c. The ' accuracy of each Type A test shall be verified by a supple-mental test which:

1. Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 La or 0.25 Lt-

2. Has a minimum duration of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following a stabiliza-

-tion period of at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

3. R'equires the induced leakage rate from the containment during the supplemental test to be approximately equal to the maximum allowable leakage rate at Pa (60 psig) or Pt (30 psig).

d. Type B penetration tests shall be conducted with gas at a mini-mum pressure of Pa (60 psig) at intervals no greater than 24 i months except for tests involving the air locks which are tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.

l e. Penetrations subject to Type B testing (except air locks), which have been opened following the last Type A or B test, shall be Type 8(te'sted prior to entering Mode 4 from Mode 5.

f. Type C penetration tests shall be conducted with gas at a minimum pressure of Pa (60 psig) each refueling outage, but in no case at intervals greater than 24 months for all valves listed in Table 3.6-1 that are not specifically excluded.

l l

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TROJAN-UNIT I 3/4 6-3 Amendment No. 23, 9

LCA 124 Attachment 1 Page 5 of 21 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

g. In addition to the requirements of f. above, the Containment +

purge supply and exhaust valves shall be verified OPERABLE at least once per 9 months by performing a Type C leakage rate test. In addition, prior to entering Mode 4 from Mode 5, these valves shall be verified OPERABLE, if they have been cycled in Modes 5 or 6, by performing a leakage rate test. The leakage rate for the Containment purge supply and exhaust valves shall be compared to their previously measured leakage rate to detect excessive valve degradation.

h. All test leakage rates shall be calculated using observed data converted to absolute values. Error analyses shall be per- l formed to determine the inaccuracy of the measured leakage rates.

l l

I 1

l TROJAN-UNIT 1 3/4 6-4 Amendment No.

l

LCA 124 I

. Attachment 1 Page 6 of 21 CONTAINMENT SYSTEMS

< 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment isolation valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Table 3.6-1.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one or more of the isolation valve (s) specified in Table 3.6-1 inoperable, either:

a. Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or

b. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at l least one deactivated automatic valve secured in the isolation position, or

c. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one closed manual valve or blind flange, or

d. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS l 4.6.3.1.1 'The isolation valves specified in Table 3.6-1 shall be demon-strated OPERABLE prior to returning the valve to service af ter maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and, if applicable, verification of isolation time.

4.6.3.1.2 Each automatic containment isolation valve specified in l l Table 3.6-l 'shall be demonstrated OPERABLE during the COLD SHUTDOWN l or REFUELING MODE at least once per 18 months by:

L

a. Verifying that on a containment isolation test signal, each automatic isolation valve actuates to its isolation position. l l

TROJAN-UNIT 1 3/4 6-15 Amendment No. 7#,

LCA 124 Attachment 1 Page 7 of 21 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. Verifying that on a Containment Ventilation isolation signal, each Containment purge and hydrogen vent supply and exhaust valve actuates to its isolation position.

c. Verifying that upon a Containment High Radiation signal, each Containment purge and hydrogen vent supply and exhaust valve actuates to its isolation position.

4.6.3.1.3 The isolation time of each automatic Containment isolation l valve of Table 3.6-1 shall be determined to be within its limits when tested pursuant to Specification 4.0.5.

4.6.3.1.4 Containment purge supply and exhaust valves shall be verified to be inoperable (electric power or air supplies removed from their respective operators) every 31 days while in Operating Modes 1 through 4.

4.6.3.1.5 The Containment purge supply and exhaust valves shall not be cycled af ter the leakage rate testing performed prior to entering Mode 4 from Mode 5 per Requirement 4.6.1.2.g except as necessary to perform repairs following an unsuccessful leakage rate test during operation in Modes 1 through 4.

I l

l f

l TROJAN-UNIT 1 3/4 6-16 Amendment No. 28, 7#, 77 L . . .

i

~

h TABLE 3.6 s:

z CONTAINMENT ISOLATION VALVES E

_., TESTABLE DURING ISOLATION TIME VALVE NUMBER FUNCTION PLANT OPERATION (seconds)

A. Automatic Containment Isolation' Valves l MO 5658* PRZ steam sample - Inside yes 10 CV 5659* PRZ steam sample - Outside yes 10 MO 5656* PRZ water sample - Inside yes 10 CV 5657* PRZ water sample - Outside yes 10 MO 5653* Reactor Coolant Loop Sample - Inside yes 10 MO 5654* Reactor Coolant Loop Sample - Inside yes 10

, CV 5655* Reactor Coolant Loop Sample - Outside yes 10 l MO 5651A* Accumulator "A" Sample - Inside yes 10

) R MO 5651B* Accumulator "B" Sample - Inside yes 10

MO 5651C* Accumulator "C" Sample - Inside yes 10

? MO 5651D* Accumulator "D" Sample - Inside yes 10 CV 5652* Accumulators' Sample - Outside yes 10 MO 5674 Containment atmosphere sample l

supply - inside yes 10 MO 5675 Containment atmosphere sample

supply - outside yes 10 MO 5672 Containment atmosphere sample return - inside yes 10 MO 5676 Containment atmosphere sample return - outside yes 10 MO 5671 Containment atmosphere sample supply - outside yes 10 y 3 ,_

k MO 5673 Containment atmosphere sample ,g g g a return - inside yes 10 to g ,

8 MO 5663 Containment atmosphere sample co g ,N g return - outside yes 10 o,, g 2 CV 8026 Pressurizer relief tank gas y c+

P analyzer - inside yes 10 --

^

F I

TABLE 3.6-1 .

N CONTAINMENT ISOLATION VALVES s:

? +

E TESTA 8LE DURING ISOLATION TIME Q VALVE NUN 8ER FUNCTION PLANT OPERATION (seconds) ,

A. Automatic Containment Isolation Valves (Continued) l CV 8025 Pressurizer relief tank gas analyzer - outside yes 10 MO 5660 RCDT gas analyzer - inside yes 10 CV 5661 RCDT gas analyzer - outside yes 10 i CV 4000 RCDT Np supply - outside yes 10 MO 4005 RCDT discharge - inside yes 10 ;

CV 4006 RCDT discharge - outside yes 10 ,

CV 8028 Pressurizer relief tank '

t' makeup - outside yes 10

MO 5677 Containment atmosphere sample

? supply - outside yes 10

$ MO 5678 Containment atmosphere sample return - outside yes 10 CV 8033 Pressurizer relief tank N2 supply - outside yes 10 CV 8880 Accumulator N2 supply - outside yes 10 M0 4300 Gas collection header - inside yes 10 CV 4301 Gas collection header - outside yes 10 MO 10016 Chilled water supply - inside yes 5 CV 10015 Chilled water supply - outside yes 3 MO 10013 Chilled water return - inside yes 5 CV 10014 Chilled water return - outside yes 3 MO 4180 Containment sump discharge -

> inside yes 10 gg l

o.

CV 4181 Containment sump discharge -

outside yes 10 eg>

, g. g 8 CV 8871 SIS test line - inside yes 10 oga <

5 CV 8964 SIS test line - outside yes 10 *g CV 8888 SIS test line - outside yes 10 ro, m

g TABLE 3.6-1 -

C3 j' '

CONTAINMENT ISOLATION VALVES N

El TESTABLE DURING ISOLATION TIME s VALVE NUMBER FUNCTION PLANT OPERATION (seconds) 4 A. Automatic Containment Isolation Valves (Continued)

CV 8149A CVCS letdown - inside yes 10 CV 8149B CVCS letdown - inside yes 10 CV 8149C CVCS letdown - inside yes 10 CV 8152 CVCS letdown - outside yes 10 MO 8112 RC Pump seal water return -

inside no 10 4 MO 8100 RC Pump seal water return -

outside no 10 SV 5642 Containment atmosphere sample

}{ supply drain - inside yes 3 en i

j, SV 5643 Containment atmosphere sample u> supply drain - inside yes 3

- SV 5679 Containment atmosphere sample return - inside yes 3 MO 8105#9 CVCS charging - outside yes 10 l

, CV 4470 Service air supply - outside yes 10 j CV 4471 Instrument air supply - outside no 10 SV 6991* 93-ft airlock test line - outside yes 3

SV 6992* 93-f t airlock test line - outside yes 3

B. Automatic Containment Ventilation Isolation Valves I

![ MO 10002** Containment purge supply - inside no 5 ;? 3;;-

g CV 10001** Containment purge supply - outside no 3 'g g 3=

4 g MO 10003** Containment purge exhaust - inside no 5 _, pr ;3 g CV 10004** Containment purge exhaust - outside no 3 og* ,

_, MO 10005*** Hydrogen vent supply - outside yes 5 o, l? ,

! ,o MO 10006*** Hydrogen vent supply - outside yes 5 n, _,

i t

w TABLE 3.6-1 '

8 .

, 5;; CONTAINMENT ISOLATION VALVES T

E

-Z TESTABLE DURING ISOLATION TIME

- VALVE NUMBER' FUNCTION PLANT OPERATION (seconds) l B. Automatic Containment Ventilation Isolation Valves (Continued) l

'l MO 10011*** Hydrogen vent exhaust - outside yes 5 j MO 10012*** Hydrogen vent exhaust - outside yes 5 ,

MO 10007*** Hydrogen vent supply - inside yes 5 MO 10008*** Hydrogen vent supply - inside yes 5 MO 10009*** Hydrogen vent exhaust - inside yes 5 MO 10010*** Hydrogen vent exhaust - inside yes 5 C. Non-Automatic Power Operated Isolation Valves M

MO 3291# CCW train "A" supply - outside no N.A.

? MO 3292# CCW train "A" discharge - outside no N.A.

1 E$ MO 3346# CCW train "B" supply - outside no N.A.

MO 3290# CCW train "B" discharge - outside no N.A.

MO 2053A# Containment Spray Pump A

discharge - outside yes N . A .-

~

. M0 20538# Containment Spray Pump B j discharge - outside yes N.A.

RHR normal suction inside N.A.

~

MO 8701#$ no I CV 8825# RHR hot leg recirculation - inside no N.A.

MO 8703# RHR hot leg recirculation - outside no N.A.

j MO 8835# SIS discharge line - outside no N.A.

(cold leg)

MO 8809A# RHR pump "A" discharge - outside no N.A. o w r-

[

s MO 88098# RHR pump "B" discharge - outside no N.A. E$9

, [

a MO 2069A# Sump _ Recirculation Train "A" inside yes N.A. $h

-sa

M0 20698# Sump Recirculation Train "B" -

o$

E inside yes N.A. ] ",

4 i

TABLE 3.6-1 ~

IE! '

O CONTAINNENT ISOLATION VALVES 5 TESTABLE DURING ISOLATION TINE

[ VALVE NUNBER FUNCTION PLANT OPERATION (seconds)

C. Non-Automatic Power Operated Isolation Valves (Continued)

CV 8843# BIT Discharge - inside no- N.A.

N0'8802A# SIS discharge Train "A" -

outside no N.A.

NO 88028# SIS discharge Train "B" -

outside no N.A.

D. Manual Valves g g 8090A* (RCS) Deadweight Tester - outside N.A. N.A.

8090B* (RCS) Deadweight Tester - outside N.A. N.A.

p SF080 Refueling cavity recirculation -

n>

inside N.A. N.A.

Sf046 Refueling cavity recirculation -

outside N.A. N.A.

SF073 Refueling cavity drain - inside N.A. N.A.

SF074 Refueling cavity drain - outside N.A. N.A.

SF063 Refueling cavity skimming - inside N.A. N.A.

SF062 Refueling cavity skimming - outside N.A. N.A.

ND059 Demin water washdown - outside N.A. N.A.

10610A ILRT Instrument Line - outside N.A. N.A.

106108 ILRT Instrument Line - inside N.A. N.A.

10611A ILRT Instrument Line - outside N.A. N.A.

106118 ILRT Instrument Line - inside N.A. N.A.

[h LD001* 45-ft airlock test line - outside N.A. N.A.

[ N.A.

g LD003* 45-ft airlock test line - outside- N.A. m g _,

C5%

l @

N b-e-

i

F

_g TABLE 3.6-1 ,

8 CONTAINMENT ISOLATION VALVES g;

Y E- TESTABLE DURING ISOLATION TIME

(( VALVE NUMBER- FUNCTION PLANT OPERATION (seconds)

E. Check Valves l 8047 PRT N2 Supply - inside no N.A.

8046 PMU Water to PRT - inside no N.A. l 8180 RCP Seal Water Rtrn. - inside- no N.A.

8968 Np to Accumulators - inside no N.A.

' Check valve Demin. Water to Washdown (3" HCB-3) ~ Sta. - inside no N.A.

g

]; Check valve RCDT,N 2 Supply - inside no N.A.

m (l" GBB-1)

Check valve downstream Service Air - inside no N.A.

A3 na of CV 4470~

Check valve downstream Instrument Air - inside no N.A.

of CV 4471 F. Relief Valves l

PSV-8117 CVCS Letdown - inside_ no N.A.

PSV-8708# RHR Pump Suction - inside no N.A.

jf

May be opened on an intermittent basis under administrative control.

@ ** The Containment purge supply and exhaust valves shall be made inoperable (electric power or air supplies gt removed from their respective operators) during Modes 1 through 4. 2P ?? E-

- - The Hydrogen vent supply and exhaust valves shall be normally closed, and opened only when and for the # ET **

@ _ [? ;G r+ duration of time actually necessary.

y # Not subject to Type C leakage tests. "' 8 **

9 Closes on an SIS signal only. 95%

$ May be open during Mode 4. gg

LCA 124

, Attachment 1 l Page 14 of 21 CONTAINMENT SYSTEMS 3/4.6.4 COMBUSTIBLE GAS CONTROL HYDROGEN ANALYZERS LIMITING CONDITION FOR OPERATION 3.6.4.1 Two independent containment hydrogen analyzers shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With one hydrogen analyzer inoperable, restore the inoperable analyzer to OPERABLE status within 30 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With both hydrogen analyzers inoperable, restore at least one monitor to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.4.1 Each hydrogen analyzer shall be demonstrated OPERABLE at least once per 92 days on a STAGGERED TEST BASIS by performing a CHJ.NNEL CALIBRATION using sample gases containing:

a. One volume percent hydrogen, balance nitrogen, and

b. Four volume percent hydrogen, balance nitrogen.

TROJAN-UNIT 1 3/4 6-23 Amendment No. 93 l

. _ , . - p -- . , . , -, ,_ , - . , - - , ,,

LCA 124

.- Attachment 1 Page 15 of 21 CONTAINMENT SYSTEMS ELECTRIC HYDROGEN RECOMBINERS - W LIMITING CONDITION FOR OPERATION 3.6.4.2 Two independent containment hydrogen recombiner systems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTION:

With one hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.4.2 ' Each hydrogen recombiner system shall be demonstrated OPERABLE:

a. At least once per 6 months by verifying during a recombiner system functional test that the minimum heater sheath temperature increases to 2700*F within 90 minutes and is maintained for at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

b. - At least once per 18 months by:

1. Performing a CHANNEL CALIBRATION of all recombiner instru-mentation and control circuits.

2. Verifying through a visual examination that there is no evidence of abnornal conditions within the recombiners (ie, loose wiring or structural connections, deposits of foreign materials, etc).

3. Verifying during a recombiner system functional test that the heater sheath temperature increases to 21200'F within 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months and is maintained for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

TROJAN-UNIT 1 3/4 6-24 l

LCA 124 y Attachment 1 Page 16 of 21 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

4. Verifying the integrity of all heater electrical circuits by performing a continuity and resistance to ground test immediately following the above required functional test.

The resistance to ground for any heater phase shall be

>10,000 ohms.

d '

,=

TROJAN-UNIT 1 3/4 6-25

LCA 124 Attachment 1 )

Page 17 of 21 1 CONTAINMENT SYSTEMS HYDROGEN VENT SYSTEM LIMITING CONDITION FOR OPERATION 3.6.4.3 At least one containment hydrogen vent system shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.

APPLICABILITY: MODES 1 and 2.

ACTION:-

With no containment hydrogen vent system OPERABLE, restore at least one hydrogen vent system to OPERABLE status within 30 days or be in HOT STANDBY within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.4.3 The above required hydrogen vent system shall be demonstrated OPERABLE:

a. At least once per 31 days by initiating flow through the HEPA filter and charcoal adsorber train and verifying that the vent system operates for at least 15 minutes.

- b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:

1. Verifying that the charcoal adsorbers remove 1 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the vent system at a flow rate of 140 cfm i 10%.

2. Verifying that the HEPA filter banks remove 2 99% the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the vent system at a flow rate of 140 cfm i 10%.

3. Verifying within 31 days after removal that a laboratory analysis of a carbon sample from at least one test canister demonstrates a removal efficiency of 2 90% for radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130*C, 95% R.H.).

TROJAN-UNIT 1 3/4 6-26 Amendment No. 19 l

LCA 124 r.' Attachment 1 Page 18 of 21 CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

4. Verifying a system flow rate of 140 cfm 10% during system operation when tested in accordance with ANSI N510-1975.

c. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 days after removal that a laboratory analysis of a carbon sample obtained from a test canister demonstrates a removal efficiency of 2 90% of radioactive methyl iodide when the sample is tested in accordance with ANSI N510-1975 (130*C, 95% R.H.).

d. At least once per 18 months by verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 10 inches Water Gauge while operating the vent system at a flow rate of 140 cfm 10%.

e. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filters remove 2 99% of the DOP when they are tested in-place in accordance with ANSI N510-1975 while operating the vent system at a flow rate of 140 cfm 1-10%.

f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in-place in accordance with ANSI-1975 while operating the vent system at a flow rate of 140 cfm 10%.

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TROJAN-UNIT 1 3/4 6-27 Amendment No.19, l i

[

l LCA 124 2- A22achment 1 Page 19 of 21 CONTAINMENT SYSTEMS HYDROGEN MIXING SYSTEM LIMITING CONDITION FOR OPERATION 3.6.4.4 Two independent hydrogen mixing systems shall be OPERABLE. l APPLICABILITY: MODES 1 and 2.

ACTION:

With one hydrogen mixing system inoperable, restore the inoperable system to 0?ERABLE status within 30 days or be in HOT STANDBY within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.6.4.4 Each hydrogen mixing system shall be demonstrated OPERABLE:

a. At least once per 92 days on a STAGGERED TEST BASIS by:

1. Verifying that the system can be started on operator action in the control room, and

2. Verifying that the system operates for at least 15 minutes,

b. At least once per 18 months by verifying a system flow rate of 2500 250 cfm.

l L

TROJAN-UNIT 1 3/4 6-28 Amendment No. 98 l

t LCA 124 Attachment 1 Page 20 of 21 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths-and associated leak rates assumed in the accident analyses.

This restriction, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.

3/4.6.1.2 CONTAINMENT LEAKAGE

- The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the.value assumed in the accident analyses at the peak accident pressure, Pa. As an added conservatism, the measured overall integrated leakage rate is further limited to 50.75 La during performance of the periodic test to account for possible degradation of the containment leakage barriers between leakage tests.

The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50.

The containment purge supply and exhaust valves have resilient seat material which may-be subject to leakage past the seats. For this reason

. leakage rate testing on these valves is performed at least once per 9 months. In addition, leakage rate testing is performed prior to entering Mode 4 from Mode 5, provided the purge valves have been cycled while in Modes 5 or 6.

3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leakage rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leakage rate. Surveillance testing of the air lock seals provides assurance that the overall air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

l-TROJAN-UNIT 1 B 3/4 6-1 Amendment No. 73 1

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LCA 124

. Attachment 1 Page 21 of 21 3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment. Containment isolation within the time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.

The containment purge supply and exhaust valves are maintained shut with their power supplies removed during Operating Modes 1-4, since they have not been qualified under Design Basis Accident LOCA conditions.

Because the plant is in an inherently safer condition with containment ventilation valves shut, hydrogen vent supply and exhaust valves are normally shut and opened only when and for the duration of time actually necessary.

Table 3.6-1 does not list containment isolation valves which are:

1. Excluded f rom 10 CFR 50, Appendix J, Type C tests, and

2. Are not required to be functionally tested for containment isolation purposes.

Listing of these valves would not serve a useful purpose since none of the surveillance requirements would apply. These valves are Check Valves 8368A/B/C/D, 807c , 8381, and 8815.

3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. Either recombiner unit or the purge system is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water and

3) corrosion of metals within containment. These hydrogen control systems are consistent with the recommendations of Regulatory Guide 1.7, " Control of Combustible Gas Concentrations in Containment Following a LOCA", March 1971.

The hydrogen mixing systems are provided to ensure adequate mixing of the containment atmosphere following a LOCA. This mixing action will prevent localized accumulations of hydrogen from exceeding the flammable limit.

TROJAN-UNIT 1 B 3/4 6-4 Amendment No.

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1 July 29, 1985 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN: Mr. E. J. Butcher, Jr., Acting Chief Operating Reactors Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Conunission Washington DC 20555

Dear Sir:

License Change Application 124 Attached are three signed originals and 40 conformed copies of License Change Application 124 requesting amendment of Operating License NPF-1.

A check for $150 is attached in accordance with 10 CFR 170.

PGE has transmitted a copy of this request to the Oregon Department of Energy in accordance with 10 CFR 50.91.

Also attached is one signed copy of a certificate of Service for License Change Application 124 to the chief executive of the county in which the facility is located and the Director of the State of Oregon, Department of Energy.

Sincerely, n -2 Bart D. Withers Vice President Nuclear Attachments c: Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. Robert L. King Chairman of County Commissioners 121 S W Salmon Street. Portland, Oregon 97204

Ebrt D Wmers Vce Presdert July 29, 1985 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN: Mr. E. J. Butcher, Jr. , Acting Chief operating Reactors Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Conunission Washington DC 20555

Dear Sir:

License Chante Application 124 Attached are three signed originals and 40 conformed copies of License Change Application 124 requesting amendment of operating License NPF-1.

A check for $150 is attached in accordance with 10 CFR 170.

PGE has transmitted a copy of this request to the Oregon Department of Energy in accordance with 10 CFR 50.91.

Also attached is one signed copy of a certificate of Service for License Change Application 124 to the chief executive of the county in which the facility is located and the Director of the State of Oregon, Department of Energy.

Sincerely, L MM l Bart D. Withers Vice President Nuclear Attachments j c: Mr. Lynn Frank, Director l State of Oregon Department of Energy Mr. Robert L. King Chairman of County Comunissioners 121 S.W Salmon Street Portard. Oregon 97204 )

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ML20133H043

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Dear Sir:

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