ML20151X043

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Proposed Tech Specs Adding Three Addl Reg Guide 1.97 Type a Category 1 Pami Variables & One Type B Category 1 Pami Variable to ITS Table 3.3.17-1, Pami
ML20151X043
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 08/31/1998
From:
FLORIDA POWER CORP.
To:
Shared Package
ML20151X038 List:
References
RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 9809160235
Download: ML20151X043 (16)


Text

. _ . _ _ _ _ . _ ____ . . _ _ _ _ _ _ .. _ _ _ _ . . _ _ _ . . . _ . . _ . _ .

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72 ATTACIIMENT B

. LICENSE AMENDMENT REQUEST #234 REVISION O Proposed ITS and ITS Bases Change Pages - Strikethrough/ Highlight F! "-:et' re;;E Text Deleted, Highligb~ted,Texj Added l

l l

i 9809160235 900831 yDR ADOCK 05000302 PDR '

PAM Instrumentation 3.3.17 SURVEILLANCE REQUIREMENTS


NOTE-------------------------------------

These SRs apply to each PAM instrumentation Function in Table 3.3.17-1.

i SURVEILLANCE FREQUENCY SR 3.3.17.1 -------------------NOTE--------------------

Not required for Function 4.

Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.  ;


NOTE-----

SR 3.3.17 -------------------NOTE-------------------- The Frequency Neutron detectors are excluded from CHANNEL for Function 12 CALIBRATION, is 18 months.

,. . . .n .n .-v . -- .n. ,


NOTE-- --- - ,--- ------s  !

-- iNot r'e,gsirid for? Fdnctions)23ian~d
c. . . .. . .. . . . .  :. . .. ,25. .n J t

c : c .------------ :-- .- :::: - :::r- ::- :

i l

Perform CHANNEL CALIBRATION. 24 months  !

y , , ,

q:

y. ,

y y ,

e ...s I hR:3.3~;17.3) , -k-----k----'-4NbTE-----.-----'--------- N'" $

4

~

D y , -

Only.r.equired for Functions;23-and 25'.;

.a f'

3

3. _ _ .
c. >

,.t,. s 1

.., A  !

3. ,

u .. ,

_ 3 ,

V. ,

m; , :d. J.> .

b@ . }' '

..I.

r s' 3

{s

. , . . . -,, .. < 1:L-

i. Perform CHANNED FUNCTIONAL TESTg , 241 months- i n

p . ,

ss

{

Crystal River Unit 3 3.3-40 Amendment No.

PAM Instrumentation 3.3.17 l

Table 3.3.17-1 (page 1 of 1)

Post Accident Monitoring Instrumentation i

CONDITIONS l REFERENCED FROM l FUNCTION REQUIRED CHANNELS REQUIRED ACTION D.1 l

1. Wide Range Neutron Flux 2 E
2. RCS Hot leg Temperature 2 E l
3. RCS Pressure (Wide Range) 2 E l
4. Reactor Coolant Inventory 2 F
5. Borated Water Storage Tank Level 2 E
6. High Pressure Injection Flow 2 per injection line E l l
7. Containment Sump Water Level (Flood Level) 2 E
8. Containment Pressure (Expected Post-Accident E 2

Range)

9. Containment Pressure (Wide Range) 2 E
10. Containment Isolation Valve Position 2 per penetration (a)(b) E
11. Containment Area Radiation (High Range) 2 F
12. Containment Hydrogen Concentration 2 E
13. Pressurizer Level 2 E 14 Steam Generator Water Level (Start-up Range) 2 per OTSG E
15. Steam Generator Water Level (Operating Range) 2 per OTSG E
16. Steam Generator Pressure 2 per OTSG E
17. Emergency Feedwater Tank Level 2 E
18. Core Exit Temperature (Backup) 3 per core quadrant E
19. Emergency Feedwater Flow 2 per OTSG E
20. Low Pressure Injection Flow 2 E
21. Degrees of Subcooling 2(d) E
22. Emergency Diesel Generator kW Indication 2(c) E f 23.I I.PI' Puni Run' 5thuC '7""~"""~""""""2""F'" T U" ' " ET *'"3i fo .. ~ f .. L. ; ' . i . , . . ., _. m ,

{24. DW-42 and DHV-43 Open Position ' 2' Er ,

t ,s c n ' d (25f.HPI. Pump Run Stat'us j _

(2( Ej j V - , , .. . . . . -

~

[266 RCS Pressure (Low Range)f 12 .i -E- 1 (a) Only one position indication is required for penetrations with one Control Room indicator.

(b) Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(c) One indicator per EDG.

(d) These two channels of subcooling margin are backed up by either of two indications of subcooling margin based on similar inputs through the Safety Parameter Display System (SPDS). At least one SPDS channel must be available to provide this backup. With both SPDS channels INOPERABLE, Condition C is applicable.

Crystal River Unit 3 3.3-41 Amendment No.

- . . ~ . . - _ . - - _ .- - -. - - ..

PAM InStrumsntation l B 3.3.17  ;

i BASES t

FUNCTION CHANNEL A CHANNEL 8

15. Steam Generator Water Level OTSG A: SP-17-LIl or OTSG A: SP-18-LIl (Operating Range) SP-17-LIR OTSG 8: SP-22-LII OTSG b: SP-21-LIl or SP-21-LIR 1

i

16. Steam Generator OTSG A: MS-106-PIl or OTSG A: MS-107-PIl or Pressure MS-106-PIR MS-107-PIR l OTSG 8: MS-110-PIl or OTSG 8: MS-111-PIl or MS-110-PIR MS-111-PIR
17. Emergency Feedwater EF-98-LIl EF-99-LII Tank Level
18. Core Exit Temperature Three detectors from each of the following groups:

(Backup) Quadrant WX: IM-2G-TE/IM-5G-TE/IM-6C-TE/IM-7F-TE Quadrant XY: IM-9E-TE/IM-10C-TE/IM-11G-TE/IM-13C-TE Quadrant YZ: IM-9H-TE/IM-10M-TE/IM-100-TE/IM-13L-TE Quadrant ZW: IM-3L-TE/IM-4N-TE/IM-6L-TE/IM-60-TE and Recorders RC-171-TR, RC-172-TR, RC-173-TR

18. Emergency Feedwater OTSG A: EF-26-FIl OTSG A: EF-26-FIl Flow OTSG 8: EF-24-FIl OTSG 8: EF-24-FIl
20. Low Pressure Injection Flow DHV-110 Hand / Auto station flow DHV-111 Hand / Auto station flow indication (DH-1-FK3-1) indication (DH-1-FK4-1)
21. Degrees of Subcooling RC-4-TI4 and RC-4-TIS and SPDS "A" or SPDS "B"
22. Emergency Diesel Generator EGDG-1A Wattmeter SSF-AH Main ECDG-1B Wattmeter SSF-AX Main kW Indication control board indicator control board indicator
m. ,-

.._.m .. , . . . . . . . . . . . , _ .......s ~,.

W m .. .

23LLPI Pump Run Status':: , ESFA-LX3-J(Red Light):or s &., . E5FB-LX3 (Red Light).orf .'.,.g JW i ESFA-MU (E5'Liaht Matrix "A")i ESFb-HU (ES Lisht Matrix1 "B")"

sm . .. < . , . , . ~ _m . , ~ . . - .. . . . . ,~. . = '  ;

24yGnanPosition*WRf-42 'and

. ~ESFA-MN3 DNV-43 (Red

' ' ( , Mp Light)h ,u n, ESFB-lut3(Red)1ght)j , R j N "k ' ~' # 4' >

j

.m . . .

, , mo i 25f;HPI huilp!tua Stiatus s4 IFEMay14:; L  % tri Puy-3C 1- J z y , i W; 4;; # ' ~ , L .. ESFA-NF7i(Aed Light)4ior R . . N ESFB-MF7.'(Red-Light)"ori gg 6W Off! ESFA-AN (E5. Light , Matrix,"A").3

,  ! "y 5;p.f ;

, , _ . +J>-~ ^' ~ ; g% y .

ESFBJAM . (E5 Light .Mstrixy"B")l-f , i 36 Mh:.

YU", Wis mney 40 4 0

%. IS:!Jgn . ~

ESFA-0917/(Red. Light)For1 ,: ' ,7 ESFB-MW7-(Red Light) ov R>.

. .L IFI % 38 Mm . . . .

i Ms

.~ '

E5FA-A3 (E5'Lisht Matris'"A")v ESFB-A3 (ES LiaktQ p &ik "B")'

wn ...:.. .z. ~, , .. . . . , . ,

ey RCN48 PIl\lp  !;'

28.j.RC5 t rt.,

P.Pessurep

+  % RC-147F11Q 7 ,a Wi

% s ,

i NOTES: For Function 18, OPERABILITY of only two detectors (and associated recorder) for any group constitutes entry into Condition A of LCO 3.3,17. Any group with only one OPERABLE detector / recorder combination constitutes entry into Condition C of LCO 3 3.17. Separate Condition entry is allowed for each group.

For Function 21, with both channels of SPDS inoperable. LCO Condition C and its associated Required Action are applicable.

For Functioni25;"0FERA81LITYlof. indication;isiroquiredfonlf forithe'one1ESielected HPI'pumplinsch channen (Continued)

Crystal River Unit 3 B 3.3-125B Amendment No.

l l

PAM Instrumentation '

B 3.3.17 i

l BASES l

LC0 230 EfLPIrP E Rus35tatss  !

(continued) l LPI* Pump;RuhlStatuslisfusied ~ byl the* operator?during' the i ECCSTPump SuctiontTransferLto-initiate the; opening,of )

i r

DNV-1113nd;;DNV-12,[the JRiggyback", valves! >

LPI[ Pump 1RuniStatuslis7a? Type?AWaHable'becaussithe opening of these; valve's stof establish la> suction; source l is:a'p1anned manualJaction (and isL ne~cessary;t6 in LOCAsjwhere the'RCS pressureLhasinot {

l maintain;HPI; decreased <to theip'ointtthat:LPI will provide linjectidri of cool ant i nto ithe l ReactorfCool ant 1 Sy' stem ' and :.when

~

s ingle; failures ?occuriwhich; resultlinaonlykleitrain I ofcLPIfbeing.availablet 24 G DNV!42Tand"DHV;43'Onen' Position 7

DHV 42 Fand DHVF 43 'OpenT P6s1 tion ,7 ths7 suctiori' Val Vei from:thefRBisumpito.thelLPIfpumps, fare used:by;the operatoreduring the ECCS; Pump Suction Transfer to initiateithe closing of?DNV-34'and:DHV-35nthensuction valvestfrom1the: 8WStetoithe;LPI; pumps?

DNV-42 Tand l DHVJ4350 pen'~ Poii t'i 6n' a re?Tysie 'ATVa r'i abl ei because the closing -of DHV-34)and-DHV-35. to'ma'nually isolatelthe BWST from,the;LPILandl85.suctioni;fs  :

necess damageary :tb; prevent > vortexing f and consequentialtolthe LPI  !

maintaining; core;andicontainment; cooling; 25 M l HPI'P M Rui Status HPI1PuinpT:RuniStathsTis7U' sed' b9f the(6peratWin l determi.ning1the total HPI flow per; pumpa LIf theitotal fl ow j decreases below; the J ai nimum : pump; flow ;11eri ts ! i l thenia'manuallactionLisitakenhto;openithe

recirculation valves ;in< order;to ' avoid; low ~flos

~

operation which could' damage';the? pump and rendefit l i noperabl el whil e si t d s bei ng i used ;to mi tigate? a ,desi gn basisjaccident?

~

HPI[ Pump?Rurf StatusTis:~a" Type 7A variable'becaUseithere

are some SBLOCAsithattwould; result in;HPIsflows of t

i this smallia magnituden Since?these acti6ns:are necessary;to"protectiequipmentithat is(necessaryfto l mi tigate ; the i accident ,ithese : areiType - A 2 va r,i abl es !

l (continued) e Crystal River Unit 3 B 3.3-138C Amendment No.

PAM Instrumentation B 3.3.17 l

! BASES LCO 26E:RCS'Prsss6re 4Loi Ranae) .

(continued)

RCS : pres s u r'e"i s ' meas u rsd : bp Tp'res su re ' t ran smi tters : wi th l af span:of 0-600 psig; . Redundant- monitoring; capability l

is providedl by:;two. trains ofninstrumentation. The

'controU rbom, indications are the: primary 3 indications bsed byLthe operator during:an: accident.;'Therefore; the~. LCO. deal s : speci fi cal.ly_withithi s1 portion . ofithe instrumentsstring; RCS" Pres sur ' e~ (Low ~ Range)T i sE cl as si fi efas[i Type " B Category livariable because nonelof,..the: actions 1taken by> theLoperator -based 'on: RCS: pressure variables qualifiescit -as:JasType A variable. . :It -is included 2jn Table 3.3s17.-1 as0 it is La' Category 1: variable (and relied on byithe operators;to. maintain RCSLpressure for several: contingency actions included in the EOPs'.'

Those" actionsr are: 1) determination thatian<ES actu'ation~of thelLPI pumpsishould.,have' occurred;E2) selecting Low--Temperature.Overpressur'e Protection

.( LTOP), 3) opening .of drop lines l to establish .Decap Heat: removal -: 4): ensure' adequate RCP:NPSH. at 1ow RCS pressure,landi5)Lensure NDTJimits..have not.been exceeded.

(continued)

Crystal River Unit 3 B 3.3-138D Amendment No.

I I

l PAM Instrumentation B 3.3.17 i

BASES SURVEILLANCE SR 3.3.17.1 (continued)

REQUIREMENTS A note to the Surveillance excludes the performance of a i

CHANNEL CHECK on Function 4. FPC requested, and was granted, exception from performing a CHANNEL CHECK on this

  • instrumentation as part of Amendment 124, dated October 17, 1989. The basis for not performing this SR is based on the design of the system. The system utilizes differential pressure (dp) measurements across vertical elevations of the hot leg and the reactor vessel when the RCPs are tripped.

Performance of the SR with the RCPs in operation provides no meaningful information, such that a CHANNEL CHECK of this Function is not required.

SR 3.3.17.2 CHANNEL CALIBRATION is a complete check of the instrument channel, including the sensor, to verify the channel responds to the measured parameter (s) within the necessary range and accuracy.

For the Containment Area Radiation instrumentation, a CHANNEL CALIBRATION consists of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr. The calibration also provides a one point check of the detector below 10 R/hr using a gamma test source (Reference NUREG 0737, Table II.F.1-3).

The 24 month Frequency is based on the results of a review of instrument drift data conducted in accordance with NRC Generic Letter 91-04. The Frequency for the hydrogen monitors is 18 months based on operating experience and was originally selected to be consistent with the typical industry fuel cycle.

A Note clarifies that the neutron detectors are not required to be tested as part of the CHANNEL CALIBRATION.

Adjustment of the detectors is unnecessary because they are passive devices and operating experience has shown them to exhibit minimal drift. Furthermore, there is no adjustment that can be made to the detectors.

A7 Note"tolthe"Su'rveillan' ceTexclude'sithe"performanceTof.'a CHANNEL 1 CALIBRATION :'on : Functions '23 ' and . 25 ; : : FPC requested l and wasigranted Fexception;from performing <a CHANNEL CALIBRATION"on ~ this instrumentation as . part of Amendment

[TBD],3 dated'[T80) . Since no adjustment of: these on-off

. indications .is possible~ performance of-.the SR providesfno meaningful 11nformationisuch;that a CHANNEL CALIBRATION of

.this?FunctionLis:not. required. Instead,'these11ndications are - subjecteditoia: CHANNEL FUNCTIONAL 1TESTias: describediin SR;i3.3.17.32 l

l (continued) i Crystal River Unit 3 8 3.3-143 Amendment No.

l PAM Instrumentation B 3.3.17 BASES i

l SURVEILLANCE SR"3f3?17'.'3 REQUIREMENTS (continued) CHANNEL" FUNCTIONAL 5 TEST"i sF for T iwi tihTc6htactif the l injection 'of;a simulated or actua1Ysignaliinto' the ~chinnel l i

l as closeitojthe sensor asipracticable ,.to verifyiOPERA8ILITY,' '

;i ncl udi ng irequi red J al a;rm and ;.tri p (functi ons t l'6f1
heFLPITPUipIRus'Stitsi![indTh(HPI t the" CHANNEL: FUNCTIONALKTEST red; verifies Lthe[Psep~ Rsh~Sfa indicating lightsfon the main contro1J board )andJthe' ES- Light nag;5 jndicators? during testingifs theipumps',already;requYredIb.i otherisurveillancezrequirements2

- TheT24'monh 7frdsihE9"iil. tias'ed Ion"p'roVidi 6g^^c6iisi sti6cy between this ! surveillance testing "and the: otherfsurveillanci

requi rement!s ;foraver_i fying ; ope rabi li tyLlottheselspeci fi c pumps 4 i REFERENCES 1. FSAR, Table 7-12.
2. Regulatory Guide 1.97, Revision 3.

l

3. NUREG-0737, 1979.  ;
4. 32-1177256-00, " Technical Basis for Reactor Vessel Level Indication System (RVLIS) Action Statement," l April 10, 1990.

I I

l Crystal River Unit 3 8 3.3-144 Amendment No.

l

FLORIDA POWER CORPORATION  ;

CRYSTAL RIVER UNIT 3 i

DOCKET NUMBER 50-302/ LICENSE NUMBER DPR-72  :

ATTACHMENT C LICENSE AMENDMENT REQUEST #234 REVISION O Proposed ITS and ITS Bases Change Pages - Revision Bars 1

l l

PAM Instrumentation 3.3.17  !

t SURVEILLANCE REQUIREMENTS


NOTE-------------------------------------

These SRs apply to each PAM instrumentation Function in Table 3.3.17-1. '

)

SURVEILLANCE FREQUENCY )

1 SR 3.3.17.1 -------------------NOTE--------------------

Not required for Function 4.

Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.


NOTE----- i SR 3.3.17.2 -------------------NOTE-------------------- The Frequency l Neutron detectors are excluded from CHANNEL for Function 12 CALIBRATION. is 18 months.


NOTE--------------------

Not required for Functions 23 and 25.  ;

Perform CHANNEL CALIBRATION. 24 months SR 3.3.17.3 -------------------NOTE--------------------

Only required for Functions 23 and 25.

Perform CHANNEL FUNCTIONAL TEST. 24 months l

l Crystal River Unit 3' 3.3-40 Amendment No.

l I:

PAM Instrumentation 3.3.17 Table 3.3.17-1 (page 1 of 1)

Post Accident Monitoring Instrumentation

, CONDITIONS REFERENCED FROM FUNCTION REQUIRED CHANNELS REQUIRED ACTION D.1

~

1. Wide Range Neutron Flux 2 E i-. 2. RCS Hot Leg Temperature 2 E

-3. RCS Pressure (Wide Range) 2 E

4. Reactor Coolant Inventory 2 F
5. . Borated Water Storage Tank Level 2 E

=

6. High Pressure Injection Flow 2 per injection line E
7. Containment Sump Water Level (Flood Level) 2 E

,8. Containment Pressure (Expected Post Accident 2 E

?

Range)

9. Containment Pressure (Wide Range) 2 E
10. Containment Isolation Valve Position 2 per penetration (s)(b) E
11. Containment Area Radiation (High Range) 2 F
12. Containment Hydrogen concentration 2 E 13.- Pressurizer Level 2 E
14. Steam Generator Water Level (Start-up Range) 2 per OTSG E
15. Steam Generator Water Level (Operating Range) 2 per OTSG E
16. Steam Generator Pressure 2 per OTSG E
17. Emergency Feedwater Tank Level 2 E a

- 18. Core Exit Temperature (Backup) .3 oer core quadrant E

19. Emergency Feedwater Flow 2 per OTSG E

, 20. Low Pressure Injection Flow 2 E

21. Degrees of Subcooling 2(d) E
22. - Emergency Diesel Generator kW Indication 2(c) E
23. LPI Pump Run Status 2 E

~24 DNV-42 and DHV 43 Open Position 2 E

25. _HPI Pupp Run Status 2 E
26. RCS Pressure (Low Range) 2 E k (a) only one position indication is required for penetrations with one Control Room indicator.

(b) ~Not required for isolation valves whose associated penetration is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(c) ' One indicator per EDG.

(d) These two channels of subcooling margin are backed up by either of two indications of subcooling margin based on similar inputs through the Safety Parameter Display System (SPDS). At least one SPDS channel must be available to provide this backup. With both SPDS chanr.els INOPERABLE, Condition C is applicable.

Crystal River. Unit 3 .3.3-41 Amendment No.

l PAM Instrumentation B 3.3.17 i

i r

BASES FUNCTION CHANNEL A CHANNEL B

15. Steam Generator Water OTSG A: SP-17-LII or OTSG A: SP-18 L11 Level (Operating Range) SP-17-LIR OTSG B: SP-22-LIl OTSG B: SP-21-L11 or SP-21-LIR
16. Steam Generator OTSG A: MS-106-P!1 or OTSG A: MS-107-P!1 or Pressure MS-106-PIR, MS-107-PIR
OTSG B
MS-110-PI1 or OTSG B: MS 111-PI1 or MS-110-PIR MS-111-PIR
17. Emergency Feedwater EF-96-L11 EF-99-L11 Tank Level l' 18. Core Exit Temperature Three detectors from each of the following groups:

- (Backup) Quadrant WK: IM 2G TE /IM-5G TE /IM-6C TE /IM-7F-TE oundrant XY: IM-9E-TE /IM-10C-TE/IM-11G TE/IM-13G-TE Ouedrant YZ: IM-9H-TE /IM-10M-TE/IM 100-TE/IM-13L-TE eundrant ZW: IM 3L-TE /IM-4N-TE /IM-6L TE /IM 60-TE and Recorders RC-171-TR, RC-172-TR, RC-173-TR

19. Emergency Feedwater OTSG A: EF-25 FI1 OTSG A: EF-26-FI1 Flow OTSG 5: EF-23-Ft1 OTSG B: EF-24-FI1
20. Low Pressure Injection DHV-110 Hand / Auto station flow DHV-111 Hand / Auto station flow Flow indication (DH-1-FK3-1) indication (DH 1*FK4-1)
21. Degrees of subcooling RC 4-T!4 and RC-4-TIS and SPDS "A" or SPDS "B"
22. Emergency Diesel EGDG-1A Wattmeter SSF-AH Main EGDG-1B Wattmeter SSF-AX Main Generator kW Indication control board indicator control board indicator
23. LPI P m p Run Status ESFA-LX3 (Red Light) or ESFB-LX3 (Red Light) or ESFA-HU (ES Light Matrix "A") ESFB-HU (ES Light Matrx "B")
24. DHV-42 and DHV-43 ESFA KN3 (Red Light) ESFB KN3 (Red Light)

Open Position

25. HP! Ptmp Run Status NPI P m p 1A: HPI Ptap 1C ESFA MF7 (Red Light) or ESFB-MF7 (Red Light) or ESFA-AH (ES Light Matrix "A") ESFB-AH (ES Light Matrix "B")

W W NPI Ptap 18: NPI Ptap 18:

ESFA-MNT (Red Light) or ESFB-MV7 (Red Light) or ESFA-AJ (ES Light Matrix "A") ESFB-AJ (ES Light Matrix "Bu)

26. RCS Pressure RC-147-P!1 RC-148-P11 (Low Range)

NOTES: For Function 18, OPERABILITY of only two detectors (and associated recorder) for any group constitutes entry into Condition A of LCO 3.3.17. Any group with only one OPERABLE detector / recorder combiration constitutes entry into Condition C of LCO 3.3.17. Separate Condition l

entry is allowed for each group.

For Function 21, with both channels of SPDS inoperable, LCO Condition C and its associated Required Action are applicable.

l-l For Function 25, OPERABILITY ci indication is required only for the one ES selected HP1 p m p in each channel.

(continued)

Crystal River Unit 3 8 3.3-125B Amendment No.

i PAM Instrumentation B 3.3.17 ,

1 BASES LC0 23. LPI Pumo Run Status (continued)

LPI Pump Run Status is used by the operator during the ECCS Pump Suction Transfer to initiate the opening of ,

DHV-11 and DHV-12, the " Piggyback" valves.

l LPI Pump Run Status is a Type A variable becaa e the opening of these valves to establish a suction source is a planned manual action and is necessary to maintain HPI in LOCAs where the RCS pressure has not l decreased to the point that LPI will provide injection of coolant into the Reactor Coolant System and when single failures occur which result in only one train of LPI being available.

24. DHV-42 and DHV-43 Open Position DHV-42 and DHV-43 Open Position, the suction valves from the RB sump to the LPI pumps, are used by the operator during the ECCS Pump Suction Transfer to initiate the closing of DHV-34 and DHV-35, the suction valves from the BWST to the LPI pumps.

DHV-42 and DHV-43 Open Position are Type A variables because the closing of DHV-34 and DHV-35 to manually isolate the BWST from the LPI and BS suction is necessary to prevent vortexing and consequential ,

damage to the LPI and BS pumps, which are required for maintaining core and containment cooling.

25. HPI Pumn Run Status HPI Fump Run Status is used by the operator in determining the total HPI flow per pump. If the total flow decreases below the minimum pump flow limits, then a manual action is taken to open the recirculation valves in order to avoid low flow operation which could damage the pump and render it inoperable while it is being used to mitigate a design basis accident.

HPI Pump Run Status is a Type A variable because there are some SBLOCAs that would result in HPI flows of this small a magnitude. Since these actions are necessary to protect equipment that is necessary to mitigate the accident, these are Type A variables.

(continued)

Crystal River Unit 3 B 3.3-138C Amendment No.

. . - . . - . _ . . _ _ - - - . ~ . . - - . - . - - . - . . . - . . - . . - -

l PAM Instrumentation B 3.3.17 ,

i BASES h

e LC0 26. RCS Pressure (Low Ranae) l (continued) ,

RCS pressure is measured by pressure transmitters with a span of 0-600 psig. Redundant monitoring capability is provided by two trains of instrumentation. The control room indications-are the primary indications ,

used by the operator during an accident. Therefore, j l the LCO deals specifically with this portion of the instrwnent string.

RCS Pressure (Low Range is classified as a Type B  ;

Category 1 variable beca)use none of the actions taken  !

by the operator based on RCS pressure variables  !

qualifies it as a Type A variable. It is-included ir.

Table 3.3.17-1 as it is a Category 1 variable and relied on by the operators to maintain RCS pressure ,

for several contingency actions included in the E0Ps.

Those actions are: 1) determination that an ES actuation of the LPI pumps should have occurred, 2) selecting Low Temperature Overpressure Protection (LTOP),3 o Heat Remov)al,pening 4) ensureof orop -lines adequate RCPtoNPSH establish at lowDecay RCS pressure, and 5) ensure NDT limits have not been exceeded.

1 t

l d

(continued) l Crystal River Unit 3 B 3.3-138D Amendment No.

J i-

PAM Instrumentation l B 3.3.17 j BASES l l

SURVEILLANCE SR 3.3.17.1 (continued)

REQUIREMENTS A note to the Surveillance excludes the performance of a CHANNEL CHECK on Function 4. FPC requested, and was granted, exception from performing a CHANNEL CHECK on this instrumentation as part of Amendment 124, dated October 17, 1989. The basis for not performing this SR is based on the design of the system. The system utilizes differential measurements across vertical elevations of the pressure hot leg and(dp)he t reactor vessel when the RCPs are tripped.

Performance of the SR with the RCPs in operation provides no meaningful Function isinformation,d.such not require that a CHANNEL CHECK of this 1 l

SR 3.3.17.2  !

CHANNEL CALIBRATION is a complete check of the instrument channel, including the sensor, to verify the channel responds to the measured parameter (s) within the necessary range and accuracy. ,

For the Containment Area Radiation instrumentation, a j CHANNEL CALIBRATION consists of an electronic calibration of the channel, not including the detector, for range decades above 10 R/hr. The calibration also provides a one point check of the detector below 10 R/hr using a gamma test i source (Reference NUREG 0737, Table II.F.1-3). i The 24 month Frequency is based on the results of a review of instrument drift data conducted in accordance with NRC Generic Letter 91-04. The Frequency for the hydrogen monitors is 18 months based on operating experience and was ,

originally selected to be consistent with the typical  !

industry fuel cycle.

A Note clarifies that the neutron detectors are not required to be tested as part of the CHANNEL CALIBRATION.

Adjustment of the detectors is unnecessary because they are passive devices and operating experience has shown them to exhibit minimal drift. Furthermore, there is no adjustment that can be made to the detectors.

A Note to the Surveillance excludes the performance of a l CHANNEL CALIBRATION on Functions 23 and 25. FPC requested, i and was granted exception from performing a CHANNEL l CALIBRATIONonthisinstrumentationaspartofAmendment i

[TBD], dated [TBD]. Since no adjustment of these on-off '

indications is possible, performance of the SR provides no meaningful information such that a CHANNEL CALIBRATION of this Function is not required. Instead these indications  ;

aresubjectedtoaCHANNELFUNCTIONALT$STasdescribedin l SR 3.3.17.3.

(conti:iued)

! Crystal River Unit 3 8 3.3-143 Amendment No.

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PAM Instrumentation l B 3.3.17 -

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!- BASES i

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SURVEILLANCE SR 3.3.17.3 ,

l REQUIREMENTS (continued) CHANNEL FUNCTIONAL TEST is, for switch contacts, the  :

injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm and trip functions.

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For the LPI Pump Run Status, and the HPI Pump Run Status, i the CHANNEL FUNCTIONAL TEST verifies the red indicating lights on the main control board and the ES Light Matrix indicators during testing of the pumps already required by r other surveillance requirements.

The 24 month frequency is based on providing consistency between this surveillance testing and the other surveillance  !

requirements for verifying operability'of these specific pumps.

REFERENCES 1. FSAR, Table 7-12, i

2. Regulatory Guide 1.97, Revision 3.  ;
3. NUREG-0737, 1979.
4. 32-1177256-00, " Technical Basis for Reactor Vessel Level Indication System (RVLIS) Action Statement,"

April 10, 1990.

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Crystal River Unit 3 B 3.3-144 Amendment No.

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