ML20076L203

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Proposed Changes to Tech Specs,Enchancing Clarity or Providing Consistency W/Plant Design & Operation
ML20076L203
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 07/11/1983
From:
MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20076L183 List:
References
NUDOCS 8307190079
Download: ML20076L203 (40)
v • d • e


Text

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INSERT FOR PAGE 3/4 4-5

~#~: Initial opening of 1B21-F051B is at 1103 1 15 psig due to low-low set

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' REACTOR COOLANT SYSTEM

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3/4.4.2 SAFETY VALVES SAFETY / RELIEF VALVES e

LIMITING C00eITION FOR OPERATION 3.4'.2.1 of the following safety / relief valves, the safety valve function of at least 7 valves and the relief valve function of at least 6 valves other than l

those satisfying the safety valve function requirement shall be OPERABLE with the specified lift settings:

Ihaber of Valves Function Setpoint* (psia)+45-8 Safety 1165 t 15.6F51 2

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6 Safety 1180 2.Ii.Spsi 6

Safety 1190 2it.9es:

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1 Relief 1103 1 IT est 10 Relief 1113 1 r p :

9 Relief 1123115 psf e

APPLICABILITY: OPERATIONAL C00eITIONS 1, 2 and 3.

ACTION:-

and/or relief valve function of one or more of the above With the safety / relief valves inoperable, be in at least HDT SHUTDOWN e.

required safety within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOW within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, With one or more safety / relief valves stuck open, provided that suppression l

b.

pool average water temperature is less than 105*F, close the stuck open relief valve (s); if unable to close the open velve(s) within 2 minutes or if suppression pool average water temperature is 105*F or greater, place the reactor mode switch in the Shutdown position.

With one or more safety / relief tail-pipe pressure switches inoperable, restore the inoperable switch (es) to OPERABLE status within 7 days or be c.

in at least HDT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOW within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREDENTS 4.4.2.1.1 The tail-pipe pressure switch for each safety / relief valve shall be demonstrated OPERABLE with the setpoint verified to be 30 2 5 psig by l

performance of a:

CHAISIEL FUNCTIONAL TEST at least once per 31 days, and a a.

CHANNEL CALIBRATION at least once per 18 months.**

b.

The relief valve function pressure actuation instrumentation shall 4.4.2.1.2 i

be demonstrated OPERABLE by performance of a:

f' CHAletEL FUNCTIONAL TEST, including calibration of the trip unit, at M se

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least once per 31 days.

I CHANNEL CALIBRATION, LOGIC SYSTEM FUIICTIONAL TEST and steulated b.

4 automatic operation of the entire system at least once per 18 months.

mne lift setting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.

    • The provisions of Specification 4.0.4 are not applicable prov m

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Technical Specification 4.1.3.1.4.a. page 3/4 1-5.

SUBJECT:

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(DISCUSSION:

._ Specification 4.1.3.1.4.a requires the scram discharge volume to be determined OPERABLE by demonstrating the scram discharge volume drain and vent valves OPERABLE when control rods are scram tested from a normal control rod configuration of less than or. equal to 50% R0D DENSITY at least once per 18 months.

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Specification 4.0.4 requires the. Surveillance Requirements asscciated with the Limiting Condition for Operation to have been performed within the' required surveillance interval prior

'to entry into OPERATIONAL CONDITION 2.- Since the referenced i

surveillance cannot be performed prior-to entry into

-OPERATIONAL-CONDITION 2, the following change is requested.

The proposed technical specification change adds a note to the i

. bottom of page 3/4 1-5 to read as follows:

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"*The provisions of Specification.4.0.4 are not applicable l

provided the surveillance requirement is performed during the first orderly. shutdown and~no later than the next scheduled refueling outage after reaching less than.or-equal to.50% rod density in OPERATIONAL CONDITIONS l'or 2."

JUSTIFICATION: EntryLinto OPERATIONAL CONDITIONS 1 or 2 requires the 18 month surveillance' requirement be completed on the scram discharge volume as ' stated in Specification '4.1.3.1.4.a.

However, this specification requires a normal' control rod configuration.of less than or equal to.50% ROD DENSITY.' - There are times when:

l' the plant may.not'be placed into OPERATIONAL CONDITIONS:1 or 2.

J for intervals exceeding 18 months. ;This' change-to the technical specification will allow entry into 0PERATIONAL CONDITIONS 1 or 2 as long as the testing required by:

Specification 4.1.3.1.4.a is performed within'18 months.after-entering OPERATIONAL CONDITION 1 or 2.'

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.SIGNIFICANT HAZARDS CONSIDERATION:

The proposed. change relaxes the. provisions of Specification 4.0.4~ so that ' the plant conditions necessary to satisfy the

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intent of1 Technical Specification 4.1.3.1.4.a.can'be' achieved..

The Standard Technica1TSpecifications in several areas indicates it-isfac'c'eptable'to relax the' pro' visions' of-Specification 4.0.4 so'that an~0PERATIONAL-CONDITION-can be-

-entered to achieve the plant-conditions'necessary.to satisfy the intent of surveillance. requirements. Therefore this' change.

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b to the Technical Specification does not involve a significant

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-reduction in a margin of safety. Additionally, as this change' allows for the satisfaction of the intent of the surveillance, neither a significant increase in the probability or consequences of an accident previously evaluated nor the possibility of'a new or different kind of accident from any accident previously evaluated is involved. Therefore, this proposed change to the Technical Specifications does not involve any significant hazards considerations.

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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.1.3.1.'4 The scram discharge volume shall be detemined OPERA 8LE by

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demonstrating:

The scram discharge volume drair, and vent valves OPERABLE, een l

a control rods are scram tested from a normal control rod configuration of less than or equal to 50% R00 DENSITY at least once per 18 months, by verifying that the drain and vent valves:

1.

Close within 30 seconds after receipt of a signal for control rods to scram, and 2.

Open when th pICScramsignalisreset.

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b.

Proper level sensor response by performance of a CHANNEL FUNCTIONAL TEST of the scram discharge volume scram and control rod block level instrumentation at least once per 31 days.

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SUBJECT:

Technical Specification Tables 3.3.2-1, 3.6.4-1, 3.6.6.2-1 and Technical Specification 3/4.6.4 pages 3/4 3-10, 3/4 3-12 through 14,~3/4'6-1, 3/4 6-27, 3/4 6-29 through 3/4 6-35, 3/4 6-37 through. 3/4 6-42,-3/4.6-44, 3/4 6-48 through 3/4 6-52.

DISCUSSION:

'The changes to Table 3.3.2-1 include the following:

f 1.

. Delete valve group 5 and 9 from item 1.b, Drywell Prescure-High and 1.d, Manual Initiation. Delete valve group 5 from items 2.a and 2.h, Reactor Vessel Water Level-Low Low' Low, Level 1 and Manual Initiation.

2.

Add valve group 9 to 5.b, RCIC Steam Supply Pressure -

Low.

3.

Add new note (k) to 6.d, Reactor Vessel (RHR Cut-in Permissive) Pressure - High, to 6.e Drywell. Pressure -

High and to the b'ottom of page 3/4 3-14.

Note (k) ~ states:

Valves E12-F037A and E12-F037B are closed by high drywell pressure. All other group 3 valves are closed by high reactor pressure.

4.

Add new note (m) to 5.b, page 3/4 3-14, RCIC Steam Supply Pressure-Low to reflect that-valve group 9 must receive a

' concurrent drywell pressure-high signal to isolate.

Specification 4.6.1.1 is changed to exempt isolation valves located in the steam tunnel from the requirements of surveillance.4.6.1.1.b by modifying the ** footnote on page 3/4

'6-1.

Specification 3.6.4 is changed to ensure consistency between Tables 3.3.2-1 and 3.6.4-1.

The proposed change is to add a

'9"Lto the Applicability statement and a footnote to the bottom oof page 3/4 6-27.

This note'will require the isolation valves listed on Table 3.6.4-1 to be OPERABLE when the corresponding actuation instrumentation is required to be OPERABLE per Table 3.3.2-1.

Yable 3.6.4-1 lists the Containment and Drywel'. Isolation Valves in four sections. Section 1 contains the~ Automatic Isolation Valves which are those valves that receive an automatic isolation signal from: Table 3.3.2-1 instrumentation and are' located on the Containment'or Erywell penetrations.

The valvesfincluded in Section 2 are Manual ~ Isolation-valves which receive a remote manual signal from a handswitch and are located on the Containment or Drywell Penetrations.

Some of the' valves in Section'2 may receive automatic signals, but not automatic isolation signals,from instrumentation in Table 3.3.2-1.

Some of these valves will still be considered as automatic isolation valves for the purpose of meetingL specifications'4.6.1.1.b and 4.6.2.1.a'since they receive low reactor level ~ and high drywell pressure automatic -isolation

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signals from ECCS instrumentation. The valves included in Section 3 are those which do not receive isolation signals from instrumentation listed in Table 3.3.2-1 and do not utilize a remote manual handswitch. Section 3 includes check valves, local manual. operated valves and power operated valves that do not utilize a handswitch. Section 4 of Table 3.6.4-1 contains test connection valves. The changes to Table 3.6.4-1 fall into the following categories:

1.

Correction of maximum isolaticn times 2.-

Correction of valve group assignments 3.

Penetration number corrections.

4.

Addition of new valves 5.

-Addition to and correction of present footnotes 6.

Placement of valves in proper section'of the table.

7.

Correction of typographical error.

Table 3.6.6.2-1 contains a list of secondary containment ventilation system automatic isolation dampers and valves.

Section "a" of the table lists dampers with their associated

-maximum isolation times. -Section "b"~ lists valves and their associated maximum isolation times. The changes-to Table 3.6.6.2-1 fall into the following categories:

1.

Correction of typographical errors 2.

Correction of maximum isolation times 3.

Addition of dampers A more detailed description of the changes to Tables 3.6.4-1 and 3.6.6.2-1 is provided below in the justification section.

JUSTIFICATION: The changes to Table 3.3.2-1 are proposed to correct previous ommissions and to more accurately describe the signals that operate valve groups. The changes to items 1.b, 1.d, ' 2.a. and 2.h delete valve groups 5 and 9 because these valve groups received an isolation signal from ECCS rather than a containment isolation signal. Valve group 9 is added to 5.b, RCIC Steam Supply Pressure - Low, along with footnote (m) to clarify that group 9 valves must receive a concurrent drywell pressure signal to isolate, since this signal closes group 9 valves. Note '(k) is added to 6.d and 6.e valve groups and to, the bottom of page 3/4 3-14.

Note- (k) clarifies that valves E12-F037A and E12-F037B are closed by high drywell pressure and i-all other group 3-valves are closed by high reactor pressure.

The proposed changes to specification 3.6.1.1 will exempt.from survillance 4.6.1.1.b primary containment isolation valves located in the steam tunnel which are locked closed. The harsh environment and high radiation in the steam tunnel would preclude visual verification of these valves during normal operation as ' required by surveillance 4.6.1.1.b.

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c The. proposed change to. Specification 3.6.4 is made to require s

'the~ containment and drywell isolation valves to be OPERABLE wben their corresponding actuation instrumentation in Table 3.3.2-1 is required to be OPERABLE. This chr'ge provides consistency between the Instrumentation and the Containment Systems Sections of the Technical Specifications.

The changes-to Table 3.6.4-1 are justified.as follows:-

1.

'All proposed valve closing time changes except E12-F024A-A c

and E12-F024B-B were derived by applying margins to previo'us test' data. These margins were obtained from ASME Section XI which states that valves closing faster than 10 seconds are allowed a 50% change in closing speed and valves closing slower than-10 seconds are allowed a 25%

change in speed before increased surveillance is required.

To determine the maximum closing time for the valves, a factor of two times the allowable from previous test closure to next test closure (based on the 50% and 25%

values) was added to the stroke' times obtained from previous test data. For example:-

A valve for which previous test data indicates a 20 second closing time would have a 5 second (25%) from previous' test to next test Allowable Value. Two times the Allowable Value (or 10 seconds) would then be added to the tested closing time of 20 seconds to give the maximum closing time for the valve of 30 seconds.

The closing times for E12-F024A-A and E12-F024B-B were reduced from 93 seconds to 90 seconds.- The analytical value of 90 seconds is used in FSAR accident analysis and

-is thus-' required. These valves have been tested and found to close in less than 80 seconds,-well below their analytical time requirements.

The present maximum closure times in the table have no consistent basis and use values from design or purchase specification values. The~ proposed Technical Specification changes will provide a' consistent basis.for the maximum isolation times and will provide a realistic measure of valve performance through both the Technical Specification'and ASME Section XI testing.

2.

E12-F023-B is-corrected to read E12-F023-A.

S E12-F042A A'and E12-F042B-B have been moved from Section 1 3..

to Section 2.

These valves do not receive an automatic ~

isolation signal from instrumentation listed'in Table-4

=3.3.2-1.- The automatic signal received'for closing these G34spl8

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- valves is a " containment spray" signal. ~These valves.

U would close on a " containment spray" signal to divert the

- RHR water to theLeontainment spray header. These valves

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may be operated by a remote handswitch.

4. -

E12-F028A-A'and E12-F028B-B.have been moved from Section 1 to Section 2.' These valves do not receive an automatic I

isolation signal-from instrumentation listed Table -

~3.3.2-1.

The automatic signal for closing these valves is

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'a LOCA signal. If these valves were open during testing, and a LOCA signal was received, they would close, allowing' the RHR. water to go to the RPV rather.than the containment spray. header These valves may be operated by a remote handswitch.-

5 5.

E12-F024A-A, E12-F024B-B, E12-F011A-A, E12-F011B-B,-

E12-F021-B, E22-F023-C, and E21-F012-A have been moved-from Section 1 to Section 2.

These valves are'RHR, LPCS or HPCS test return line valves and do not receive a L

direct automatic isolation signal.to close on low reactor L

water level (level 1) or high drywell pressure signals.

These' valves receive their isolation closure-signals through the-Load Shed and Sequencing Panel and ECCS system

-signals.

L6.-

E12-F290A-A and E12-F290B-B have been moved from Section 1 to Section 3.

These valves-do not receive an automatic isolation signal from instrumentation listed Table 3.3.2-1.

This signal was removed by design change which was. submitted for approval in' licensing submittal PCOL-83/11. These valves close when the Feedwater Leakage Control-System is in operation or when the associated RHR jockey pump is not running.. These valves do not have a handswitch for remote. operation.

. 7.

E22-F023-C, E51-F031-A. and E21-F012-A should_have

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supercript (d). The. superscripts for these valves were-

-apparently omitted.

8; P44-F076-A, P44-F077-B, and P44-F074-B are moved frons

'Section 2.b to Section 1.b.s These valves receive 7

automatic isolation signals,. group 6,ufrom instrumentation

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listed in Table 3.3.2-1.

9.. 'E61-F003B-B, E61-F003A-A, E61-F005A-A, E61-F0058-B, and E61-F007. have been moved from-Section-1 to Section 2.-

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,T ese va ves receive low reactor water level (Level 11) and :

.high.drywell pressure automatic isolation 1 signals from

-ECCS,'not from the instrumentation. listed ~in Table 3.3.2-1.

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10. E61-F020 is being added to the table. This valve was inadvertently left off the table. It receives automatic l

isolation signals from ECCS, not from the instrumentation listed in Table 3.3.2-1.

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11. G33-F253 has the wrong valve group identified. This is a group 8 valve, not group 10.

12.' E12-YO275 should be E12-F027B-B. This change makes the valve identification consistent with the rest of the table.

13. E12-F042C-B - The superscript (e) is being changed to superscript'(c). This is apparently a typographical error. The valve will be tested per (c) as are other r

valves with similar piping configurations. This footnote describes the type of leak test required.

14..E12-F064B-B is being moved from Section 3 to Section 2.

This is a minimum flow valve and serves the same function as E12-F064A-A which is already in Section 2.

The valve has a handswitch for remote manual operation.

' 15. P41-F159A-A - Th'e superscript (e) is being changed to

. superscript (c). This le apparently a typographical error. The valve will be tested per (c) as is P41-F159B-B. This footnote describes the type of leak test required.

16. B33eF204 and B33-F205 are being moved to Section 3.b.

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These valves are local manually operated valves.

17. In Section 3 of the table Cont. Leak Rate System

. penetration 40(I)(0) is being moved to page 3/4 6-39 to correct the order of penetration listing.

18. ' Penetration numbers for M61-F015,.M61-F019, M61-F017, and E12-F236 are corrected ' from outboard -(0) to Inboard (1).

Penetration numbers for M61-F014, M61-F018,~and M61-F016 1

are corrected from Inboard (I) to Outboard (0).

19. M61-F021 and M61-F020 are being added to the table. These valves were inadvertently left off.the table.

'20.

E51-F258 should be penetration #29(0)

E51-F257'should be. penetration #29(0)

.Thesc' changes constitute correction of errors.

~21.

. Penetration numbers:for E12-F056A and E12-F056B are corrected from Gutboard. (O) to Inboard (I).

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22. Change footnotes on page 3/4 6-29 as follows:

a.

Change (f) to read: Hydrostatically sealed by feedwater leakage control system. Type C test results not required to be included when determining the combined leakage rate.

10 CFR 50 Appendix J~III.C.3 allows deletion of this leakage from the combined leakage rate.

b.

Add footnote (g)to read: Normally closed or locked closed manual valves may be opened on an intermittent basis under administrative control.

This footnote applies to sections, 2, 3, and 4 of Table 3.6.4-1.

The addition of this footnote will enhance operational flexibility and provide control of valve position.

The changes'to Table 3.6.6.2-1 are justified as follows:

1.

Under dampers in Section a, the following changes are proposed and justification provided:

a.

Add Q1M41-F007, Q1M41-F008, Q1M41-F036, and QlM41-F037. These dampers were inadvertently 1

omitted from the table.

b.

All closing times in Table 3.6.6.2-1.a are based on accident analysis in Chapter 15 of the FSAR which used a 4 second closing time. This change will make the damper closing times consistent with the FSAR.

2.

The maximum isolation time for valves in Section b, was. determined using the same approach as in Table-3.6.4-1, discussed above.-

SIGNIFICANT HAZARDS CONSIDERATION:

The proposed changes fall into the following major categories:

1.

Corrections-2.

Additions to'the tables.

3.

Changes to ensure consistency'in-the Technical

' Specifications between Tables 3.3.2-1 and 3.6.4-1.

Valveisolationtimes(exceptforE12-F024A-AandEi2-F024B-B) c

- presently do not have a consistent basis. Some are from design' or purchase specifications. The proposed change will make the basis for maximum isolation times: consistent and. follow ASME Section XI requires.ents..The closing times for E12-F024A-A and

.l E12-F024B-B were reduced to correspond to their'-

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analytical closing times used in FSAR accident analysis. The changes to the footnotes on page 3/4 6-29 are proposed to follow 10CFR50 Appendix J.III.C.3 requiremente and to add administrative control to manually operated valves. The closing times for dampers listed in 3.6.6.2-1.a are based on Chapter 15. FSAR requirements.

The changes proposed constitute administrative changes, corrections of errors or imposition of more stringent requirements. These changes do not introduce a significant reduction in margin of safety and they do not involve a significant increase in the probability or consequences of an accident previously evaluated nor does it create the possibility of a new or different kind of accident from any accident previously evaluated. Thus, no significant hazards considerations are involved.

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l-TABLE 3.3.2-1 l

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E ISOLATION ACTUATION INSTRUMENTATION l

o VALVE GROUPS MINIMUM APPLICABLE i

G OPERATED BY OPERABLE CHANNELS OPERATIONAL g

TRIP FUNCTION SIGNAL (a) PER TRIP SYSTEM (b)

CONDITION ACTION Q

1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level-Low Low, Level 2 6, 7, 8, 10(c)(d) 2 1, 2, 3 and #

20 b.

Drywell Pressure - High

+,6,7,gc)(d) 2 1,2,3 20 2 ')

1, 2, 3 and

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c.

Containment and Drywell 7

Ventilation Exhau I glA Radiation - High Nigh im ig M

(cXd) g d.

Manual Initiation

-5, 6, 7, 8, 4, 10 2?;ra";

1, 2, 3 and *#

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MAIN STEAM LINE ISOLATION w4 a.

Reactor Vessel Water Level-g Low Low Low, Level 1 1, 2 1,2,3 20 l

b.

Main Steam Line Radiation - High 1, 10(f) 2/'in:

1,2,3 23 p

c.

Main Steam Line N

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Pressure - Low 1

1/n; 1

24 m

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Main Steam Line 9) 23 P* Mk 4

Flow - High 1

1, e.

Condenser Vacuum - Low 1

2 1, 2W*

23 4 f.

Main Steam Line Tunnel y$4 Temperature - High 1

2 1,2,3 23 "M (o@s y >#

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Main Steam Line Tunnel A Temp.- High 1

2 1,2,3 23 h.

Manual Initiation 1, +; 10 1, 2, 3 22 WD "l'

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I TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION IIISTRISENTATICII 3

VALVE GROUPS MINIMUM APPLICABLE

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OPERATE 0 RY OPERABLE CNAISELS OPERATIONAL Q

g TRIP Ft31CT1011 SIGIIAL (a) PER TRIP SYSTEN (?)

COISITION ACTION E

5.

MACTOR CORE ISOLATICII COOLING SYSTEM 150LAT1001 a.

KIC Steam Line Flow - High 4

1 1,2,3 27 g

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KIC Steam Supply 4 9(m)

Pressure - Low 1

1,2,3 27 l

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c.

KIC Turbine Exhaust Diaphrop Pressure - High 4

2 1,2,3 27 d.

KIC Equipment Room Ambient

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Temperature - High 4

1 1,2,3 27 w

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KIC Equipment Room & Temp.

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- High 4

1 1,2,3 27 p

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Main Steam Line Tunnel Ambient Temperature - High 4 1

1,2,3 27 2.

g.

Main Steam Line Tunnel a Temp. - High 4

1 1,2,3 27 D

h.

Main Steam Line Tunnel fp' Temperature Timer 4

1 1,2,3 27 w w*

1.

NIR Equipment Room Ambient us g o

Temperature - High 4

1[roce*

1, 2, 3 27 g

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M Equipment Room a Temp. -

liigh 4

1/F* **

1, 2, 3 27 m

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WE/RCIC Ste'am Line Flow -

. High 4

1 1,2,3 27 M$

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Manual Initiation 4 II) 1hehe-1,2,3 26 4 lad un g h

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TABLE 3.3.2-1 (Continued)

ISOLATION ACTUAT10N INSimlNLMIATION E

VALVE GROUPS MINIMUM APPLICABLE G

OP[RAIED BY OPERABLE CHANNELS OPERAll0NAL a

TRIP FUNCTION SIGNAL (a) PER TRIP SYST[N (b)

CONDITION ACTION 5*

6.

RHR SYSTEM ISOLATION e

l a.

MR Equipment Room Ami,aent 1[ rap %

1, 2, 3 28 Temperature - High 3

b.

MR Equipment Room a 1/re 1, 2, 3 28 Temp. - High 3

c.

Reactor Vessel Water Level - Low, Level 3 3

2 1, 2, 3 28 d.

Reactor Vessel (RHR Cut-in 3(g}

Pemissive) Pressure - High 2

1, 2, 3 28 w0 3(K)

  • 4 2

1, 2, 3 28 l

e.

Drywell Pressure - High M

f.

Manual Initiation 3, 4

2. 2.';r-;

1, 2, 3 26 g

h oy1 N

Mocs'

  • w.=

NW M

ms ktw w

np0 v*%~

O y@u" W

~

4*

Mob

~

I 2O, Mg331, sag INSTSLSENTATION TABLE 3.3.2-1 (Continued) 59 392 436 4 '

l ISOLATION ACTUATION INSTRLSENTATION 12d,72,1 I

ACTIGN l

Se in at least NOT SNUTOOW within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in ACTION 20 -

within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Close the affected system isolation valve (s) within e N hou l

ACTION 21 -

In OPERATIONAL CO M ITION 1, 2, or 3, he in at toast NOT er:

SWT00W within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD 5WT g}'

a.

I P" m* "Y within the following 24 homes.

In Operational Condution 8 suspend RE ALTERATIONS, 4

I ontainment and b.

handling of irradiated fuel in the operations with a potential for draining the reactor vessel.

Restore the manual initiation function to OPERABL 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 NOT SNUTOOWN within the I ACTION 22 I1#4 and in COLD 5 NUT 00WN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

g Be in at least STARTUP with the associated isolat within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> or be in at least NOT $ NUT 00m within 12 lf d ACTION 23 I$

and in COLD $ NUT 00WN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

i 3 Se in at least STARTUP within 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

, I $

ACTION 24 Establish SECOWARY CONTAlf9ENT INTEGRITY with the staney ga ACTION 25 f.f,y treatment system operating within one hour.

Restore the manual initiation function to OPERABLE statu 5

within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isola u

ACTION 26 l{%

4,

Close the affected system isolation valves within one hour

j.3 J a

./ ACTION 27 and declare the affacted system inoperable.

e+

./

Lock the affected system isolation valves closed within one hour

(

.*, ACTION 28 l 4 g{r lare the affected system inoperable.

ag

$31 getone,ry oc sasawde,cy 3

g g,,,

  1. l$*

When handling irradiated fuel in thehtontainment and during CORE I)e..

ALTERATIONS and operations with a potential for draining the ref l

4Y*

9 During CORE ALTERATIONS and operations with a potential for d b

Og g a g} f See Specification 3.6.4 Table 3.6.4-1 for valves in each valve group.

reactor vessel.

. g + (a)

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for f j EI (b) a required surveillance without placing the trip sys 19 l

8

  1. t is monitoring that parameter.

Wj Also actuates the staney gas treatment system.

d)~ Also actuates the control room emergency filtration syste lpM]d((c) l g

=" R v'm._

!& Q ' Ais. T i ~ais i bi s h s i s s dica G 4 u =~pJp r veD_AchanneftsOPERABLE1f2of4instrumentaintha chD ' Also actuates secondary containment ventilation isolatten M

INS 8fT JE p Adv.A Aa %Jby G s Tr he.A $sh a & s,.Vth s, A** tarC1sses only NW

  • ~t r'dgYalv@3-F004ff541mdj33#ul g

valves per Table 3.6.6.2-1.

4

  • G f

(1) ggs-g ge.*.ws.t h W.h.g. g h wA. K. W.v,q3. %

g g) um:ee_

= -

l

~~

O.$

e g g

l

k. 97,203,261,360,381,

.) N l.

\\( Sos,.) 72o, 72.L 3/4.6 CONTAINMENT SYSTEMS 6

3/4.6.1 PRIMARY CONTAINMENT PRIMARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR OPERATION l

3.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be maintained.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.

ACTION:

Without PRIMARY CONTAINMENT INTEGRITY, restore PRIMARY CONTAINMENT INTEGRITY within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in at least 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY shall be demonstrated:

a.

After each closing of each penetration subject to Type B testing, except the containment air locks, if opened following Type A or B test, by leak rate testing the equipment hatch seals with oas at Pa,

+

11.5 psig, and verifying that when the measured leakage ra.e for these seals is added to the leakage rates determined pursuant to Surveillance Requirement 4.6.1.2.d for all other Type B and C penetrations, the combined leakage rate is less than or equal to 0.60 La.

b.

At least once per 31 days by verifying that all containment penetrations ** 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 position, except as provided in Table 3.6.4-1 of Specification 3.6.4.

c.

By verifying each containment air lock OPERABLE per Specification 3.6.1.3.

d.

By verifying the suppression pool OPERABLE per Specification 3.6.3.1.

"See Special Test Exception 3.10.1

    • Except valves, blind flanges, and deactivated automatic valves which are located inside the containmen W drvwell and are locked, sealed or otherwise f-secured in the closed positio W These penetrations shall be verified closed during each COLD SHUTDOWN except such verification need not be performed more often than once per 92 days.

oP SYes.% tuavvah y

GRAND GULF-UNIT 1 3/4 6-1

InseAT A )h w w

.DISEkT" TD PAcru 3/q 3-gy vaevem

/%SZV s.las u re.

n ay 9 4' Th s.

loses codeo.sar Gusad wko c.n ee d.n M a r vacvw"

I be m s. u o ll 1La.

is balow t'yfa n-lf satyelo 76 all.w opas.;>,9 J er= =~

vs==.T-v s kuTJews. o r for vsa a r-e-A SIV 's Tk

  • p^~~a ~*J byrus wlll La ve~** nd w A <*~

s farr y.

e. a. sar vaevu-avu Js rt. a s.;y cary,:.cr:

l 2

TNSEAT &

one ans,sumsnr nave isr uess,-

Ehc4

-rso r sysre n ausr

\\ % S ve n ts L u n a OPERhBLE IN osoeA fo A.

THt res O PEitAsts.

c.H Ad#O 5, 7o Ibs c.. r4 s t o e n.a4 T+.se e r " C. )

at E I2-Fo 3 7A / El 2-Fo 576 A M c' as*o5 VAL (k) %tve s A s.s. oT Hen Gnavy KtGH ORYkstLs Psgss u n g.

Agg ca..sde 6Y HICH ACAc T84 P Ress und.

RCI.C. o vv 8o^s.o VAtues. A couaunacar (A ) Ct.oses o u s.y

!s' RE Q UIR6~D fCK

%CTC.

sM'T'A T*ou SIG NAl-lsoLATION To occ uK.

(%)

YN Ve Stoop 9 ('equ;res a. Concurreah d(f tJe.\\\\

so\\ mtg, g,y R. s s ;cj ad, pre s. so m s.g e m.( %
4. GbNs-17,2o33 261,36o, Ja1,3M, 340,312,436,444, sos, 7zo,121.

j l

u -,,., _ _

3 381 310 39D $3S 444>S*S 1to,721) 4, (GGN5-17,tOS,2C2> 36Op3 61 2

2 J

2 s

CONTAINMENT SYSTEMS 3/4.6.4 CONTAINMENT AND ORYWELL ISOLATION VALVES LIMITING CON 0! TION FOR OPERATION 3.6.4 The containment and drywell isolation valves shown in Table 3.6.4-1 shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.4-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2.aad 3, o.ucs :#.

ACTION:

With one or more of the containment or drywell isolation valves shown in Table 3.6.4-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

a.

Restore the inoperable valve (s) to OPERABLE status, or b.

Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position,* or c.

Isolate each affected penetration by use of at least one closed manual valve or blind flange."

Otherwise, be in at least 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 /> and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

t

" Isolation valves closed to satisfy these requirements may be reopened on an intermittent basis under administrative controls.

M [yos,rrec# VALVES SHowd 8M "TA t t.6 3.6.4 - 1 AAS As.so Mapymeo 1 o ne OPERABLE WHgN "T)e at A A S t o CsA"ree ACTuA rtoA/ /Nf7MuwgM-TA7to w sa mse vissa To as CPEAA!5LE iN "Th e s.a 7. 3 g -1, GRAND GULF-UNIT 1 3/4 6-27

l 4 (i;GN5-97,to3,2(,1,360,781,399,370,312,f34A, So5,72a,732) l TABLE 3.6.4-1 CONTAINMENT AND ORWELL ISOLATION VALVES MAXIMLM -

ISOLATION TIME PENETRATION I

l SYSTEM AND VALVE GROUP,I (Seconds)

NUMBER VALVE NUMBER 1.

Automatic Isolation valves i

a.

Containment Main Steam Lines 521-F028A 5(0) 1 5

Main Steam Lines 521-F022A 5(I) 1 5

Main Steam Lines 821-F067A-A 5(0) 1

  1. 9 Main Steam Lines 821-F0288 6(0) 1 5

Main Steam Lines 821-F0228 6(I) 1 5

Main Steam Lines 821-F0678-A 6(0) 1

  1. 7 Main Steam Lines 821-F028C 7(0) 1 5

Main Steam Lines 821-F022C 7(I) 1 5

Main Steam Lines 521-F067C-A 7(0) 1

,F 9 Main Steam Lines 821-F0280 8(0) 1 5

Main Steam Lines 821-F0220 8(I) 1 5#9 Main Steam Lines 821-F0670-A 8(0) 1 RHR Reactor E12-F005-A 14(0)(C) 3 40 Shutdown Ccoling Suction RHR Reactor E12-F009-8 14(I)(c) 3 40 Shutdown Cooling Suction Steam Supply to E51-F063-8 17(I) 4 X27 RHR and RCIC Turbine Steam Supply to E51-F064-A 17(0) 4 X27 RHR and RCIC Turbine Steam Supply to E51-F076-8 17(I) 4 R / dr RHR and RCIC Turbine (MriGenhHR to E12-F023 18(0)C*)

3 M 9Y (I

N' nesa spray Main Steam Line 821-F019-A 19(0) 1

,3r20 Drains Main Steam Line 821-F016-8 19(I) 1 M20 Drains 01 7000A A 20' '.)f *)

"O

{;..p M......

n (a) 5ee Specification 3.3.2. Table 3.3.2-1, for isolation signal (s) that operates each valve group.

(b) Hydrostatically tested to ASME Section XI criteria.

11.5 psig.

Hydrostatically tested with water at P's,ystem to 1.10 P,, 12.65 psig.

(c)

Hydrostatically tested by pressurizing (d)

(e) Hydrostatically tested during system functional tests.

(f) Hyd ally sealed by feedwater leakage control system. Type C viredd. be id M.J sen 5&.e 4 & t %.c.$'s (s) p"est t

dgjft.ty"<*o..,.

.a..

at anAnd a b.% g e.4.ci. g"" e.

. m

-ev e- +c.5-

    • 5 Ir 1

4 A (GG N 5-17; E os,2 s 2, 3so,3 e 4 sef;. s 4 392,435;444, SAS,720, 72J)

TABLE 3.6.4-1 (Continued)

CONTAINMENT AND ORYWELL ISOLATION VALVES

~

MAXIMUM ISOLATION TIE

$YSTEM AND PENETRATION VALVE GROUP *)

(Seconds)

I VALVE NUMER NUMBER Containment (Continued) ima n..i Ene.nym E12-70;R A 20(G 5

70 "A" 6 ;JO!

RHR Heat Exchanger E12-F037A-A 20(I)(c) 3

,6V 7M "A" to LPCI

.e; et.e,.;;7 10 T0200 0 21(!)(e) g

.~.

%;[;;;$5 55E.ec.;e.-

ElbT00000 01(!)(C}

O

?!

";" h L":

RHR Heat Exchanger E12-F0378-8 21(I)(C) 3

.65 7V "B" to LPCI

%;; "A" in Lin

!!:-TO:t".- A 22(0)Id) 5 M 0.;;. T.;l

%:: "A" i n t Line 512-7011A-A

!!(0)(d) 5

P -

t 0;;. Psi

%:: "A" Te.. M r 01: T200" ^

20(0)(d) 0 0

NI),

^; I;;. ?;;?

m "g"r;in c.;=

4 : p :7_ g

<(e)(d) a s

o t.

g W

27(0)(d)

"700 int Lim E22-T0:3-0 RCIC Pump Suction E51-F031-A 28(0) 4 2 56 RCIC Turbine E51-F077-A 29(0)(C) 9 3 26 Exhaust g

LP00 int Lin 5 1-T012-A (0) 5

=

Cont. Purge and M41-F011 34(0) 7 4

Vent Air Supply Cont Purge and M41-F012 34(I) 7 4

Vent Air Supply Cont. Purge and M41-F034 35(I) 7 4

and Vent Air Exh.

i Cont Purge and M41-F035 35(0) 7 4

and Vent Air Exh.

Plant Service P44-F070-8 36(I) 6 F33 Water Return Plant Service P44-F069-A 36(0) 6

.34 33 Water Return Plant Service P44-F053-A 37(0) 6

.M 33 Water Supply Chilled Water P71-F150 38(0) 6 3F 12 Supply Chilled Water P71-F148 39(0) 6 M 12 Return l

l i

i GRAND GULF-UNIT 1 3/4 6-30 1

1

.~...,......

2 0 3 ' ' A> $#' G A> O')

'E 436 04 S*5 72*> 721) 4,((,6ns-1Tp 2

2 2

3 2

2 TABLE 3.6.4-1 (Continued)

CONTAINMENT AND ORYWELL ISOLATION VALVES HAXIMUM SYSTEM AND PENETRATION ISOLATION TIME VALVE NUMBER NUMBER VALVE GROUP (,)

(Seconds)

Containment (Continued)

Chilled Water P71-F149 39(I) 6 E /2.

Return Service Air P52-F105 41(0) 6

  1. 6 Supply Inst. Air Supply PS3-F001 42(0) 6 A6 RWCU to Main G33-F034-A 43(0) 8 E3l Condenser RWCU to Main G33-F028-B 43(I) 8 E3I Condenser RWCU Backwash to G36<F106 49(I) 6 R ll C/U Phase Sep. Tank RWCU Backwash to G36-F101 49(0) 6 R ll C/U Phase Sep. Tank Drywell & Cont.

P45-F067 50(I) 6

  1. 7 Equip. Drain Sump Disch.

Drywell & Cont.

P45-F068 50(0) 6

  1. 7 Equip. Drain Sump Disch.

Drywell & Cont.

P45-F061 51(I) 6 A7 Floor Drain Sump Disch.

Drywell & Cont.

P45-F062 51(0) 6

  1. 7 Floor Orain Sump Disch, Condensate Supply P11-F075 56(0) 6 J6 9 FPC & CU to Upper G41-F028-A 57(0) 6 A4 51 Cont. Pool Upper Cont. Pool G41-F029-A 58(0) 6
  1. SI to Fuel Pool Drain Tank Upper Cont Pool G41-F044-B 58(I) 6
  1. 37 to Fuel Pool l

Drain Tank -

Aux. Bldg. Fir.

P45-F273-A 60(0) 6 EM and Equip. Orn.

Tks. to Supp. Pool Aux. Bldg. Fir.

P45-F274-B 60(0) 6

)!r32.

l and Equip. Orn.

l Tks. to Supp. Pool GRAND GULF-UNIT 1 3/4 6-31

    • > 301 309) 370 312,43G,444,505s ?2o,711) 4,,(GNM5-17 205 2G1 2

2 2

2 2

TABLE 3.6.4-1 (Continued)

CONTAINMENT AND ORYWELL ISOLATION VALVES HAXIMUM SYSTEM AND PENETRATION ISOLATION. TIME VALVE NUM8ER HUMBER VALVE GROUP (a)

(Seconds)

Containment (Continued)

Comb. Gas Control E61-F009 65(0) 7 4

Cont. Purge (Outside Air Supply)

Comb. Gas Control E61-F010 65(I) 7 4

Cont. Purge (Outside Air Supply)

Purge Rad.

E61-F056 66(I) 7 4

Detector Purge Rad.

E61-F057 66(0) 7 4

Detector

"",". _ " ", ".. _ Tu : Li,,;

"12 "0200 C7'0' 5

^

n__,

,.,,m e )-

...l"n,7 C J m..._

re,,.

.m..

.,m bbt' 57(0)N 5

0 512-F2?CS-S Refueling Water P11-F130 69(0)(c) 6 A'8 Transf. Pump Suction Refueling Water P11-F131 69(0)(c) 6 AI Transf. Pump Suction Instr. Air to ADS P53-F003-A 70(0) 6 4

RCIC Turbine Exh.

E51-F078-B 75(0) 9

  1. /0 Vacuum Breaker RWCU to Feedwater G33-F040-B 83(I) 8 Jtf42 RWCU to Feedwater G33-F039-A 83(0) 8 K #2 Chemical Waste P45-F098 84(I) 6 7I Sump Discharge Chemical Waste P45-F099 84(0) 6

/I Sump Discharge Supp. Pool Clean-P60-F009-A 85(0) 6

/I up Return Supp. Pool Clean-P60-F010-B 85(0) 6 (I

up Return Domin. Water P21-F017-A 86(0) 6 gli Supply to Cont.

Demin. Water P21-F018-B 86(I) 6

)tf/9 Supply to Cont.

RWCU Pump Suetion G33-F001-B 87(I) 8

% 41 GRAND GULF-UNIT 1 3/4 6-32

4, (GGN s-17, to 5, L 61, 360, 501 361 310s M2 436s444 5*S) lE*> Y21) j 0

2 3

2 TA8LE 3.6.4-1 (Continued)

CONTAINMENT AND ORYWELL ISOLATION VALVES HAXIMUM SYSTEM AND PENETRATION ISOLATION. TIME VALVE NUMBER NUMBER VALVE GROUP (,)

(Seconds)

Containment (Continued)

RWCU Pump Suction G33-F252-A 87(I) 8 J6 #Z RWCU Pump Suction G33-F004-A 87(0) 8

,3g 42.

RWCU Pump Disch.

G33-F053-B 88(I) 8

)( 22 RWCU Pump Disch.

G33-F054-A 88(0) 8 3t" 32 b.

Drywell Instrument Air P53-F007-B 327(0) 6

/7 RWCU Pump Suction G33-F250-A 337(I) 8 g#2 RWCU Pump Suction G33-F251-B 337(0) _

8 g 42.

" Combustible Gas E61-F0038-8 338(0)

M[

Lsco.TC

' Con nevt To CombuktibleGas E61-F003A-A 339(0)

I

~)#ki <

rass Con.

g 6-37 Combustible Gas E61-F005A-A 340(0)

[I M

CombhtibleGas E61-F005B-B 340(0)

[f N

C stible Gas E61-F007 341(0)

'M kom Con.

J Drywell Air Purge M41-F015 345(I) 7 4

Supply l

Drywell Air Purge M41-F013 345(0) 7 4

Supply i

Drywell Air Purge M41-F016 347(I) 7 4

4 Exhaust Drywell Air Purge M41-F017 347(0) 7 4

Exhaust i

Equipment Drains P45-F009 348(I) 6

/6 Equipment Drains P45-F010 348(0) 6

/6 Floor Drains P45-F003 349(I) 6

/6 Floor Orains P45-F004 349(0) 6

/ 6e Service Air PS2-F195-B 363(0) 6

)6/ 6 l

Chemical Sump P45-F096-A 364(I) 6 gi Disch.

Chemical Sump P45-F097-B 364(0) 6

/T Disch.

RWCU to Heat G33-F253 366(0)

)68

)6Yi Exch.

Reactor Water B33-F019 465(I) 10 M 3h Sample Line Reactor Water B33-F020 465(0) 10 S&f43h Sample Line GRAND GULF-UNIT 1 3/4 6-33

.\\

..(CG Qs,--47, to 5, t 61,360, 3 81, 3e9, 3 fo, 312, 43Gy444,505,72o,7g1) resect n

( p V4 6-55)

N 4 Seevite W.ler P44 -Fo74 -A 3 31 (I)

(,

32 fa.+w e a l

Plu t S.,ec.. W.J.<

P44-Fe77 - 8 33tCo) 4 32 l

h iuen Pl.h Sere: e W fer P 44 - F074-S 33Z(0) 6 32

\\

6"FF 1 1

I Tu seek B

(p 3/4 6.- 37)

Com.bst.kle Go.s E'61 - Foto JV/(o)

Cou.

i I'*J N N $3'2 W #*0 W#}

2 h,((e(p 3043 47,203 261,36O 30L b

2 2

9 p

2 TABLE 3.6.4-1 (Continued)

CONTAINMENT AND DRYWELL ISOLATION VALVES SYSTEM AND PENETRATION VALVE NUMBER NUMBER l

2.

Manual Isolation valves 4) a.

Containment Main Steam Lines E32-F001A-A 5(0)

Main Steam Lines E32-F001E-A 6(0)

Main Steam Lines E32-F001J-A 7(0)

Main Steam Lines E32-F001N-A 8(0)

Feedwater Inlet B21-F065A-A 9(0)(D)

Feedwater Inlet B21-F065B-A 10(0)(D)

RHR Pump "A" E12-F004A-A 11(0)(d)

Suction RHR Pump "B" E12-F004B-B 12(0)(d)

Suction RHR Pump "C" E12-F004C-B 13(0)(d)

RHR bd E5 A~** LPC4)

~

El2-F04& A-A Zo(1J Suction g

RHR Heat Ex. " A" E12-F027A-A 20(0)IC)

  • N W W Nr spray N 3 M " #

21(0)(D)

E n.- Folt' A-A 2c(1) to LPCI C

RHR Heat Ex. "B" E12-F0278-6 to LPCI e

RHR Pump "C" to E12-F042C-B 22(0)(/)

Et h.+ Ev. "g* +. LKg' It W 23(0)(d) y) Elt-Fo42.5-5bem wh LPCI RHR " A" Test Line E12-F064A-A U(.I.i}

RHR "C" Test Line E12-F064C-B 24(0)(d) l( E17.-Fo2r 5-5 To Suppr. Pool

}

To Suppr. Pool g

,,g,,

r L'o n 25(0)fg gyff, p,, j g j 2_f o 2,94.j

(

HPCS Suction E22-F015-C HPCS Discharge E22-F004-C 26(0) a.S Co)cs)

HPCS Test Line E22-F012-C 27(

s 4

      • 'F# ## #~A RCIC Turbine Exh.

E51-F068-A 29(0)(d) I I"//'

i LPCS Pump Suction E21-F001-A 30(0)(C) 3 Co)")

LPCS Pump E21-F005-A 31(0)

NHM C 7 'r L LP low E21-F011-A

_32(0)(d)

, gf g CRD Pump C11-F083-A

' 33(0) g)

Discharge CCW Supply P42-F066-A 44(0)

PHPct re r d u e.

E22-fotJ-c CCW Retura P42-F067-A 45(0)

L~27(o) O CCW Return P42-F068-B 45(I)(d)

LPCS Test L.. E2.1-for:4 c

RCIC Pump E51-F019-A 46(0) 31(o) <d}

Discharge Min. Flow i

Reactor Recire.

B33-F128-B 47(I)

Post Accident Sampling GRAND GULF-UNIT 1 3/4 6-34 l

o-. a --

055120 ill)

Q (QMS-47,2Oh 261,560 3DL 364 310 392 436 9

p 2

2 9

2 444p 2

2 TABLE 3.6.4-1 (Continued)

CONTAINMENT AND ORYWELL ISOLATION VALVES SYSTEM AND PENETRATION VALVE NUMBER NUMBER Containment (Continued)

Reactor Recire.

B33-F127-A 47(0)

Post Accident 67(o)(d Sampling Vent Header to E12-F073B-B 48(0)(d)

E 12 - Fo64 5-5 Supp. Pool RHR "C" Relief E12-F346-B 71B(0)

(kHW "B " Test Lka To t Su pr i

S" W 0 *I NI2 ~ Y# " 9'

& Post-Acc.

(

4 7 (0)

RHR "A"

E12-F073A-A 77(0)(d) 8H R 8 Test-L T*

Reactor Recire.

B33-F126-B 81(I)

(& 7(o) @

Accident Sampling Reactor Recire.

B33-F125-A 81(0)

Accident Sampling C

SSW Supply "A" P41-F159A-A 89(0) g SSW Return "A" P41-F168A-A 90(1)(C) 90(0)((C)

SSW Return "A" P41-F160A-A 91(I)(C)

SSW Return "B" P41-F168B-B 91(0)(c)

SSW Return "B" P41-F160B-B 92(0) C)

SSW Supply "B" P41-F159B-B Drywell Press.

M71-F593-A 101C(0)

Inst.

Drywell Press.

M71-F591A-A 101F(0)

Inst.

Drywell Press.

M71-F591B-B 102D(0)

Inst.

Ctmt. Press. Inst. M71-F592A-A 103D(0)

Ctat. Press. Inst. M71-F592B-B 104D(0)

E61-F595C 106A(0)

Drywell H2 Analyzer Sample E61-F595D 106A(I)

Drywell H2 Analyzer Sample Drywell Hz Ana-E61-F597C 106B(0) lyzer Sample Ret.

Drywell H Ana-E61-F5970 106B(I) lyzer Sample Ret.

Ctat. H E61-F596C 105A(0)

Analyzer Sample Ctat. H E61-F5960 105A(I)

Analyzer Sample Ctat. H Analyzer E61-F598C 106E(0)

Sample Ret.

Ctat. H Analyzer E61-F5980

-106E(I)

Sample Ret.

GRAND GULF-UNIT 1 3/4 6-35 O

--Q

l' H.1) 4., (GGN5-97,20 5, t.GL,560s 381 309 390 31Ds 436>444 '*** T20 3

3 2

2 TABLE 3.6.4-1 (Continued)

CONTAINNENT AND ORYWELL ISOLATION VALVES SYSTEM AND PENETRATION VALVE NUMER NUISER b.

Drvwell Cont. Cooling P42-F114-8 329(0)

Water Inlet Cont. Cooling P42-F116-A 330(I)

Water Outlet Cont. Cooling P42-F117-8 330(0)

Water Outlet Ph t u ;. " t:r

"'"-T07:

31(:)

Retem-P h:t 5:. ":t:r

""-F077-5

1(^)

.n b""

.. D _.

m_.__

..., s

.m

...s.,

Supph-

. n c:t:=t:The

-r: '
(:)

ru.ru r C Fa*

PA6s a/4 6-33 m

-GenneeMon 4

3.

Other Isolation Valves @

l a.

Containment Fuel Transfer F11-E015 4(I)

Tube i

Cont. Leak Rrte NA 40(I)(0)

Sys.

9(I)((f)

Feedwater Inlet 821-F010A 9(0) f)

Feedwater Inlet B21-F032A 10(I)((f)

Feedwater Inlet B21-F0108 f)

Feedwater Inlet B21-F0328 10(0)(d) 11(0)Il)12(0)I )

RHR "A" Suetion E12-F017A RHR "B" Suction E12*-F0178 RHR "C" Suction E12-F017C 13(0)(*)

RHR Shutdown E12-F308 14(1)

Cooling Suction Q4 AGE 4 RHR Head E51-F066 18(I)(g)

? A I

Spray E',2 be 3 4G44 4 RHR Head

& l-F344 18(I)(g) 3y w

l Spray RNR Heat Ex. "A" E12-F044A 20(I)(g) to LPCI RHR Heat Ex. "A" E12-F025A 20(I)I*)

to LPCI RHR Heat Ex. "A" E12-F107A 20(I)I*)

1 to LPCI RNR Heat Ex. "B" E12-F0258 21(I)IC) to LPCI RHR Heat Ex. "B" E12-F0448 21(1)I")

to LPCI RHR Heat Ex. "B" E12-F107B 21(I)IC) to LPCI GRAND GULF-UNIT 1 3/4 6-37

' k. {GCN5 -17, to5, t61,sto, Set,369, Sto,392,4 sS, +4+, sos,72o,7y TABLE 3.6.4-1 (Continued)

CONTAIMENT AM ORWELL ISOLATION VALVES PENETRATION SYSTEM AM NUMER VALVE NUMER Containment (Continued) 22(0)(*)

RHR Heat Ex. "C" E12-F234 to LPCI RHR Puep "C" to E12-F041C-8 22(I)

LPCI 23(0)(,)

RHR Pump "A" Test E12-F259 Line to Suppe.

Pool 23(0)(')

RHR Puse "A" Test E12-F261 Line to Suppr.

Pool 23(0)(*)

RHR Pump "A" Test E12-F227 Line to Suppr.

Pool 23(0)I')

RP Pump "A" Test E12-F262 Line to Suppr.

l 23(0)(e)

R H R *A"Tn+ t N e h g 5-pre. N\\

240)(d RH

" A" Test E12-F228 E.t1-FI'io A-A Line to Suppr.

Pool 23(0)(C)

RHR Pump "A" Test E12-F338 Line to Suppr.

Pool 23(0)(CI RHR Pump "A" Test E12-F339 Line to Suppr.

9001 23(0)I')

RHR Pump "A" Test E12-F260 Line to Suppr.

Pool 24(0)N)

RHR Pump "C" Test E12-F280 i

Line to Suppr.

l Pool 24(0)(')

RHR Pump "C" Test E12-F281 Line to Suppr.

25(0)((d) 9001 HPCS Suction E22-F014 C) 26(I)fCl HPCS Discharge E22-F005 t

26(I) g HPCS Discharge E22-F218 HPCS Discharge E22-F201 26(I)(d)

HPCS Test Line E22-F035 27(0)(,)

HPCS Test Line E22-F302 27(0)(,)

HPCS Test Line E22-F301 27(0)(d)

LPCS Pump E21-F031 30(0)

Suction 31(I)(*)

LPCS 81scharge E21-F006 LPCS Discharge E21-F200 31(I)

LPCS Discharge E21-F207 31(I)(,)

LPCS Test Line E21-F217 32(0)I,I LPCS Test Line E21-F218 32(0) 3/4 6-38 GRAM GULF-UNIT 1

4. '(GGNs-97, to3, 26.1,56 c., 382, 3BT, 390, 312, 436, 4%,505,720,721)

TABLE 3.6.4-1 (Continued)

CONTAINMENT AND ORYWELL ISOLATION VALVES SYSTEM AND PENETRATION VALVE NUMBER NUMBER Containment (Continued)

CRD Pump C11-F122 33(I)

Discharge PSW Supply P44-F043 37(I) 4:----- h,. gT.Lu k RJe. fs Plant Chilled P71-F151 38(I) y Water Supply q

p ay,,) 9o(2)(c)

Service Air P52-F122 41(I)

L Supply Instr. Air Supply P53-F002 42(I)

CCW Supply P42-F035 44(I)(,)

RCIC Disch.

E51-F251 46(0)

' Min. Flow RCIC Disch.

E51-F252 46(0)(')

Min. Flow RHR Heat Ex. "B" E12-F055B 48(0)(d)

Relief Vent Header RHR Heat Ex. "B" E12-F103B 48(0)(d)

Relief Vent Header RHR Heat Ex. "B" E12-F104B 48(0)(d)

Relief Vent Header Refueling Wtr.

G41-F053 54(0)

Stg. Tk. to Upper Ctmt. Pool Refueling Wtr.

G41-F201 54(I)

Stg. Tk. to Upper Ctmt. Pool Condensate Supply P11-F004 56(I)

FPC & CU to Upper G41-F040 57(I)

Cont. Pool Stby. Liquid C41-F151 61(I)

Control Sys.

Mix. Tk.

(future use)

Stby. Liquid C41-F150 61(0)

Control Sys.

Mix. Tk.

"ll e;t 12-TOM" C7(ON 4,6ee RHR Pump "B" Test E12-F276 67(0)(')

Li'e n

RHR Pump "B" Test E12-F277 67(0)(')

Line l

RHR Pump "B" Test E12-F212 67(0)(')

l Line GRAND GULF-UNIT 1 3/4 6-39

gg S-y, t.os, t 6 i 3%., 381, 3 81, 310, 312, 43 f, 44+, 505, 720, 72.t) p 4

TABLE 3.6.4-1 (Continued)

CONTAIHMENT AND ORYWELL ISOLATION VALVES SYSTEM AND PENETRATIO!!

VALVE NUMBER NUMBER Containment (Continued)

RHR Pump "B" Test E12-F213 67(0)(')

Line RHR Pump "B" Test E12-F249 67(0)(')

RH mp "B" Test E12-F250 67(0)(')

{

p"}

RHR Pump "B" Test E12-F334 67 E 17. - F Z.90 5-8 4.7(o)

Line

=

RHR Pump "B" Test E12-E335 67(0)(c)

' Line Inst. Air to ADS P53-F006 70(I) (d)

LPCS Relief Valve E21-F018 71A(0)

Vent Header RHR Pump "C" E12-F025C 715(0)(d)

Relief Valve Vent Header RHR Shutdown E12-F036 73(0)(d)

Vent Header RHR Shutdown E12-F005 76B(0)(d)

Suction Relief Valve Disch.

RHR Heat Ex. "A" E12-F055A 77(0)(d)

Relief Vent Header RHR Heat Ex. "A" E12-F103A 77(0)(d)

Relief Vent Header RHR Heat Ex. "A" E12-F104A 77(0)(d)

Relief Vent Header Cont. Leak Rate NA 82(I)

Sys.

SSW "A" Supply P41-F169A B9(I)(c)

SSW "B" Supply P41-F169B 92(I)(c)

Ctat. Leak Rate M61-F015 110AS). (_I)

Test Inst.

Ctat. Leak Rate M61-F014 110At Q (0 )

Test Inst.

Ctat. Leak Rate M61-F019 110CtQ(1)

Test Inst.

Ctet. Leak Rate M61-F018 110Cl%(0)

Te'st Inst.

Ctat. Leak Rate M61-F017 110FlQ(I)

Test Inst.

Ctat. Leak Rate M61-F016 110F N (,0)

Test Inst.

GRAND GULF-UNIT 1 3/4 6-40

NT0 NYS)$US $AA)# 0 YEO ISA) k,(&GH5~17, t03 2$$)NS0j3Ob 001s 2

3 3

S y

TABLE 3.6.4-1 (Continued)

CONTAINf1ENT AND ORYWELL ISOLATION VALVES SYSTEM AND PENETRATION VALVE NUMBER nut 1BER b.

Drywell LPCI "A" E12-F041A 313(I) i 314(I) (I) l LPCI "B" E12-F041B 314Nhk LPCI "B" E12-F236 CRD to Recire.

B33-F013A 326(I)

Pump A Seals CRD to Recire.

B33-F017A 326(0)

Pump A Seals Instrument Air P53-F008 327(I)

Standby Liquid C41-F007 328(I)

Control Standby Liquid C41-F006 328(0)

Control Co Co P42-F115 329(I) g,e,g c

,,y p g,,(, g,M, Plant Service P44-F075 332(I) 633-FZ04 333(.N Water Supply F

C oNJ end* Eldk b*dd*

CRD to Recire.

B33-F013B 346(I)

Pump B Seals I g 33. p lo r 33 3 (C)

CRD to Recire.

B33-F017B 346(I) b Pump B Seals Service Air P52-F196 363(I)

BLIND FLANGES Containment NA 343 Leak Rate System

(,,y, l.u kpora. M6l~Fo2.l

+3 Th (L)

\\

Ta rT Tnsr.

GnT bak Bara

/Wf /--fs2p 431rA (o)

TssT Inst i

GRAND GULF-UNIT 1 3/4 6-41

.~

300 33A 369 0f*2 S*0 72O T22) 393 436 Wy g ggN$ ) 7,20S 265p 2

2 2

2 p

2 y

p TABLE 3.6.4-1 (Continued)

CONTAINMENT AND DRYWELL ISOLATION VALVES SYSTEM AND PENETRATION VALVE NUMBER NUMBER TestConnectionsh 4.

a.

Containment Main Steam T/C B21-F025A 5(0)

Main Steam T/C B21-F025B 6(0)

Main Steam T/C B21-F025C 7(0)

Main Steam T/C B21-F0250 8(0)(f)

Feedwater T/C B21-F030A 9(0)(f)

Feedwater T/C B21-F063A 9(0) (f)

Feedwater T/C B21-F063B 10(0)(f)

Feedwater T/C B21-F030B 10(0)(c)

RHR Shutdown Cool.

E12-F002 14(0)

Suction T/C

  • { A, RCIC Steam Line

-F072 17(0) w T/C et r-RHR to Head MF342 18(0)(C) 8 1

W t Spray T/C y

it RHR to Head F061 18(0)(c) g g, Spray T/C 22(0)(C)

C)

LPCI "C" T/C E12-F056C 23(0)(

RHR "A" Pump E12-F322 Test Line T/C RHR "A" Pump E12-F336 23(0)(c)

Test Line T/C RHR "A" Pump E12-F349 23(0)(C)

Test Line T/C RHR "A" Pump E12-F303 23(0)(c)

Test Line T/C RHR "A" Pump E12-F310 23(0)(C)

Test Line T/C RHR "A" Pump E12-F348 23(0)(c)

Test Line T/C l,

RHR"C" Pump E12-F311 24(0)(c)

Test Line T/C

. RHR"C" Pump E12-F304 24(0)(C)

Test Line T/C HPCS Discharge T/C E22-F021 26(0)(c) 27(0)((c)

HPCS Test Line T/C E22-F303 27(0) c)

HPCS Test Line T/C E22-F304 RCIC Turbine E51-F258 29 )((0)(C)

Exhaust T/C l

RCIC Turbine E51-F257 29 ff(0)(C)

Exhaust T/C LPCS'T/C E21-5013 31(0)(C)

LPCS Test Line E21-F222 32(0)(c)

T/C LPCS Test Line E21-F221 32(0)(*)

T/C GRAND GULF-UNIT 1 3/4 6-42

7 3 3 9e> 3 s % 't 3 63'iv4,ros31*i>1Q l(C G:N S - 9 3, 2 o), '1 t ',3 4 0, 3 s I > 3 %9 i

?

TABLE 3.6.4-1 (Continued)

CONTAlleqENT AND DRYWELL ISOLATION VALVES SYSTEM AW PENETRATION f

VALVE NLSSER -

NUMER I-ntinued)

.E itNR "B" Test Line E12-F350 67(0)(c)

T/C RHR "B" Test Line E12-F312 67(0)(c)

T/C RHR "B" Test Line E12-F305 67(0)(c)

T/C Refueling Water

$11-F425 69(0)(c)

Transf. Pump Suction T/C Refueling Water P11-F132 69(0)(c)

Transf. Pump Suction T/C i

Inst. Air to ADS P53-F043 70(0)

T/C Cont. Leak Rate M61-F010 82(I)

T/C RWCU To Feedwater G33-F055 83(0)

T/C Suppr. Pool P60-F011 85(0)

Cleanup T/C Suppr. Pool P60-F034 85(0)

Cleanup T/C RWCU Pump Suction G33-F002 87(0)

T/C RWCU Pump G33-F061 88(0)

Discharge T/C

)

SSW T/C P41-F163A 89(0)

)

SSW T/C P41-F1638 92(0) b.

Drywell

.LPCI "A" T/C E12-F056A 313(4PfU) l LPCI "B" T/C E12-F0568 314(4FrCO l

Intrument Air T/C P53-F493 327(0)

SLCS T/C C41-F026 328(0)

Service Air T/C F52-F476 363(0)

Reactor Sample B33-F021 465(0)

T/C l

l l

GRAND GULF-UNIT 1-3/4 6-44

4g[g;Ns-97,205, 26 t SGOs 5bl 361,310,392,43GM,505, 720, yjg y

y TABLE 3.6.6.2-1 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DA!1PERS/ VALVES MAXIMUM ISOLATION TIME DAMPER / VALVE FUNCTION (Number)

(Seconds) a.

Dampers Auxiliary Building Ventilation Supply Damper (Q1T41F006)

F4 Auxiliary Building Ventilation Supply Damper (Q1T41F007)

  1. 4 Fuel Handling Area Ventilation Exhaust Oamper (QlT42F003) g4 Fuel Handling Area Ventilation Exhaust Damper (Q1T42F004) yV F el N dlin Area Ventilation Supply Damper h

42p01

  1. 4 o

'*1 Handlin Area Ventilation Supply Damper 1

y g Q1T42g012

  1. 4 y

I

\\P Fuel Pool Sweep Ventilation. Supply Damper (Q1T42F019)

  1. 4 Fuel Pool Sweep Ventilation Supply Damper (QlT42F020) f4 4

C. J tum.~f i bryw O\\ b w Ve~ hI A q

su ppy h.my ar- (.c i m 4 i roo 7) c ouk.e.A t by wa\\ Ar.

V,./: 1.J:m 4

6*rrly D**y e (tM M H Feof) c..~ t~. meuf 4 Detwe.a sem %);l /:,a q

I nK ostd9.c La\\M9svoQ c..+.--

  • t %( 4 w *~+:Id =

9 Es,. Jtw.c

.einevo3%

l GRAND GULF-UNIT 1 3/4 6-48

j A(GG N.S - 97, 203, 2G 1, 3Co, S8L,19V, 3 fo 312, +3G, 444 s

TABLE 3.6.6.2-1 (Continued) 7Faj 721 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION MAXIMUM ISOLATION TIME (Seconds)

VALVE FUNCTION (Number) b.

Valves Plant Chilled Water System Aux. Bldg. Isol. Valve

  1. /Y (P71-F306) i Plant Chilled Water System Aux. B1dg. Isol. Valve MI/4 (P71-F304)

Plant Chilled Water System Aux. Bldg. Isol. Valve

/7

)

(P71-F302)

Plant Chilled Water System Aux. Bldg. Isol. Valve-

/

7 1P71-F300) i Plant Chilled Water System Aux. Bldg. Isol. Valve

//4 (P71-F307)

Plant Chilled Water System Aux. Bldg. Isol. Valve

/ /8/

(P71-F305)

Plant Chilled Water System Aux. Bldg. Isol.. Valve

/

'l (P71-F303)

Plant Chilled Water System Aux. Bldg. Isol. Valve

(

7 (P71-F301)

Service Air System Aux. Bldg. Isol Valve

/ f (P52-F221A)

Service Air System Aux. Bldg. Isol. Valve (P52-F160A) fk Service Air System Aux. Bldg. Isol. Valve

/ ~[g (P52-F2218)

Service Air System Aux. Bldg. Isol. Valve (P52-F1608)

/(p Instrument Air System Aux. Bldg. Isol. Valve

/7 (P53-F026A)

Instrument Air System Aux. Bldg. Isol. Valve

/7 (P53-F0268)

FKC Filt-Demin System Backwash Aux. B1dg. Isol.

/h Valve (G46-F253) l GRAND GULF-UNIT 1 3/4 6-49 L

4Ss,444,Sog,)

'4,fGGNs-17, toS, LG1,56o,301,581,310, s92, 72ej 721 j TABLE 3.6.6.2-1 (Continued)

SECONDARY CONTAINMENT VENTILATION SYSTEM MAXIMIM ISOLATION TIME (Seconds)

VALVE FUNCTION (Number)

Valves (Continued)

RWCU Backwash RCVG Tk. Aux. Bldg. Isol. Valve

)df 12-(G36-F108)

RWCU Backwash RCVG Tk. Aux. Bldg. Isol. Valve pd /2.

(G36-F109)

Nuclear Boiler System Aux. Bldg. Isol. Valve

)drli (521-F113)

Nuclear Boiler System Aux. Bldg. Isol. Valve 36 il (B21-F114) 3 lZ 6

RWCU Aux. Bldg. Isol. Valve (G33-F235)

)df 12 RWCU Aux. Bldg. Isol. Valve (G33-F234)

)df / Z SPCU Aux. Bldg. Isol. Valve (P60-F003) 3df 12 SPCU Aux. Bldg. Isol. Valve (P60-F004)

)df 12 SPCU Aux. Bldg. Isol. Valve (P60-F007)

[I 2-SPCU Aux. Bldg. Isol. Valve (P60-F008)

Fire Protection System Aux. Bldg. Isol. Valve yG (P64-F282A)

Fire Protection System Aux. Bldg. Isol. Valve f6 l

5 (P64-F283A)

Fire Protection System Aux. Bldg. Isol. Valve

/h (P64-F332A)

Fire Protection System Aux. Bldg. Isol. Valve gh (P64-F2828)

Fire Protection System Aux. Bldg. Isol. Valve

/k (P64-F2838)

Fire Protecti6n System Aux. Bldg. Isol. Valve

/ [p (P64-F3325)

Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve

/ /3 (P11-F062) 3/4 6-50 GRAND GULF-UNIT 1

  • QNGN$- 9 7, 205,26 t,160s 3 81,399 390, 436M, 505, 72o, 721) 3 TABLE 3.6.6.2-1 (Continued)

SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS / VALVES MAXIMUM ISOLATION TIME VALVE FUNCTION (Number)

(Seconds)

Valves (Continued)

Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F064)

/7 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F066)

/7 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F047)

/7 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F063)

//3 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F065)

/7 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F067)

/7 Cond. & Refuel Water Transfer Aux. Bldg. Isol. Valve (P11-F061) y7 Floor and Equipment Orains System Aux. Bldg. Isol. Valve (P45-F158)

/ 13 Floor ar.d Equipment Drains System Aux. Bldg. Isol. Valve (P45-F160) f 13 Floor and Equipment Drains System Aux. Bldg. Isol. Valve (P45-F163)

/ (a Floor and Equipment Drains System Aux. Bldg. Isol. Valve (P45-F159)

/ /3 Floor and Equipment Orains System Aux. Bldg. Isol. Valve (P45-F161)

/ /3 Makeup Water Treatment Sys. Aux. Bldg. Isol. Valve (P21-F024) g / Z.

Domestic Water System Aux. Bldg. Isol. Valve (P66-F029A)

/ (a PSW Aux. Bldg. Isol. Valve (P4a-F121) g /30 GRAND GULF-UNIT 1 3/4 6-51

s $4+,503 720,721)

' '4$(

NS-97, tos,2GL,360,381e 3Ms 310s 393s 436 3

TABLE 3.6.6.2-1 (Continued)

SECONDARY CONTAINMENT VENTILATION SYSTEM AUT0ftATIC ISOLATION DAMPERS / VALVES MAXIMUM ISOLATION TIME VALVE FUNCTION (Number)

(Seconds)

Valves (Continued)

PSW Aux. Bldg. Isol. Valve (P44-F122) j94 PSW Aux. Bldg. Isol. Valve (P44-F117) jg9 PSW Aux Bldg. Isol. Valve (P44-F118) jg9 PSW Aux. Bldg. Isol. Valve (P44-F120) jyg PSW Aux. Bldg. 1501. Valve (P44-F123)

W jf PSW Aux. Bldg. Isol. Valve (P44-F116) jp9 PSW Aux. Bldg. Isol. Valve (P44-F119) joy RHR "A" Loop Discharge To Liquid Radwaste Valve (E12-F203)

GRAND GULF-UNIT 1 3/4 6-52

- -..

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