ML20141M190

Proposed Tech Specs Re Surveillance Requirements for Lco. Response to Request for Addl Info on Subj Encl

ML20141M190
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	03/27/1992
From:	PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20141M186	List: ML20141M184 ML20141M188 ML20141M190
References
NUDOCS 9204020078
Download: ML20141M190 (43)

Text

_ _ _ _ _ _ .

4 1CA 186. Itev.1 Attactunent B 37 hues ,i REV IS E1LILCllMLCALE ECl f1CATIONJAG ES Revised Page.Nuubers 3/4 0-2 Inserts 1 and 2 ,

3/4 1-11 3/4 1-13 3/4 1-15 3/4 1-19 3/te 1 20 .

3/4 1-21 3/4 3-2 3/4 3-12 l 3/4 3-16 3/4 3-17 3/4 4-3 3/4 4-14 3/4 4-16 3/4 4.-19

-3/4 7-5 3/4 7 6 3/4 7-14 e 3/4 7-16 3/4 7-24 3/4 8-5 V4 8-7 3/4 8-10 3/4 8-13 B 3/4 0-1 Insert 3 (4 pages)

B 3/4 0-2 B 3/4 0-4 B 3/4 0-5 Insert 4 (3 pages) q ,-

5 SAB/kih 5872W,0392 9204020078 920327 {

PDR ADOCK 05000344

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3/4.0 l'0PLICABILITY ,

SURVE 1.t ANC E_ _RrCUIREME NT S 4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other coaditions specified for individual Limiting Conditions fr.r Operation unless othervise stated in an individual Surveillance Reauirement.

4.3.2 Each Surveillance Requirement shall be perforrted within the specified surveillance inter,a1 with a maximum allowable extension not to exceed 25 A gi percent of the specified surveillance interval.

4. 0. 3 Perfermance of a Surve'.11ance Requirement witlifn the specTTI W Hr7 Inscu interval shall constitute compliance with OPERABIl!TY requirements for a

> Limiting Condition for Operation and associated ACTION statements unless 6 otherwise required by the specification. Surveillance Requirements do act have to be perfor.med on inoperable equipment.

4.0.4 Entry into an Or'ERATIONAL MODE cr other specif:ed applicability condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Concition for Operation have been performed within the I na cM

,, stated surveillance interval or as otherwise specified.

c.  :

The provisions of Specification 4.0. '+ are not applicable to the performance of surveillance activities associated wiu, 're protection techr. cal C specifications 4. 3. 3. 7.1, 4. 3. 3. 7. 2, 4. 7. 8.1.1, 4. 7. 8.1. E , 4. 7,0.1. 3, 4. 7. 8. 3 6nd 4.7.9 until the completion of the initial surveillance interval associated with each specification.

4.0.5 Surveillance Recuirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as tollows:

a. Inservice inspection of ASME Code Clas3 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as re vired by 10 CFR 50, Section 50.55a(g), except where specific wri,' rn relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

TROJAN-UNIT 1 3/4 0-2 Amendment No. 61 774 tamu.u_J4v4443-

+

Innert 1 4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2. shall constitute noncompliance with the OPERABILITY requiremente fot a Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Survalliance Requirement has not been perfernid. The A0 TION Jequirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the completion of the surveillance when the allowable outage time limits of the ACTION tesairements are less than 2'4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Survelliance Requirements do not s4vp to be performed on inoperable equipment.

Insert 2 This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

DAB /kth p 6320W.0391-

. l

RE AC11VITY CONTROL SYST[MS ,

QARGINGPUMP*SHUTOOWN 11MITINGCONDITIONFOROPERATION 3.1.2.3 At least one chi.rging pump

• in the boron injection flow path / h,3 required by Specification 3.1.2.1 shall ba OPERABLE and capable of being powered from an OPERA 3LE-emercency bus.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no charging pump OPERABLE, suspend all operations involving t0gf ALTERATIONS or positive reactivity changes until one charging pump is restored to OPERABLE status.

The provisions of Specifica don 3.0.4 are not applicable.

SURVi]LLANCE REQUIREMENTS 4.1.2.3 The above required charging puep shall be demonstrated OPERABLE by verifying. that on recirculation flow, each pump develops a differen-tial pressure' of >2400 psid when tested pursuant to Specification 4.0.5.

Charging pump CDerability must be consistent with Specification 3.5.3.2. l/(hg l

TROJAN-UNIT 1 3/4 1-11 Amendment No. 74,7??,779 r aruarr41r4Ma--

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

REACT!Y!TY COWTROL SYSTEMS i

BORIC ACID TRANSFER PUMPS - SHUT 00VN ,

LIMIT!WG CORDIT!0W FOR OPERATIOM .

3.1.2.5 At least one beric acid transfer pump shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if only the ,

flow path through the boric acid transfer pump of Specification 3.1.2.la 4 is OPERABLE.

APPLICABILITY: MODES 5 and 6.

7 ACTION:

- k'ith no boric acid transfer pump CPERABLE as required to cemplete the flow path of Spe:1fication 3.1.2.la, suspend all operations involving i

i i

CORE ALTERAT1065 'or positive reactivity changes until at least one beric acid transfer pump is restored to OPERABLE status. ,

h I The provisions of Specification 3.0.4 are not applicable.

i SURVEILLANCE REQUIREMENTS __

1 4.1.2.5 The above required boric acid transfar pump shall be demon-strated OPERABit by verifying, that on recirculation flow, the pump j()g i

develers a discharge pressure of 3105 psig when tested pursuant to

' Specification 4.0.5. ,

j 4

F 4

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1 TRDJ AH-UNIT 1 3/4 1-13 Amendment No. $hl

-Jur.e 10, 1992

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, -Her fT-4930-2 t R{ ACTIVITY CONH OL LY,1TD Q BORATED WATER SOURCES - SHUTOOWN i

k1MIT1rG CON 01T10N FOR 0 FRAT 10N 3.1.2.7 As a minimum, one of the following borated water sources shall be  !

OPERABLE:

a. A boric acid storage system with: /b i

1. A minimum contained volune of 10,000 gallons. ,

2, Between 7,000 and 7,700 ppm of boron, and

3. A minimum solution temperature of 65'F

. h. The refueling water storage tank with:

1. A minimum contained volume of 102,000 gallons. .-

2. Between 2,000 and 2,500 ppm of boron, and

3. t. minimum solution temperature of 37'F.

APPLICABILIT1: MODES $ AND 6 ACTION

. With no corated water sources OPERABLE, suspend all operations involving CORE ' ALTERATIONS or posithe reactivity changes until at least one borated water source is restored to OPERABLE states.

Tlte provisions of Specifica tion 3. 0.4 are not applicable.

}URVEILLANCE REQUIREMEN15 4.1.2.7 The above-required borated water source tha11 be demonstrated .

ODERABLE:

a. At least once per ? days by:

1. Verifying the boron concentration of the water,

2. Verifying the water level of the tank, and

3. Verifying the boric acid storage tank solution temperature whnn it 'is the source of borated water

b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when it is the source of borated water and the outside ambient air temperature is (.37'F.

TROJAN-UNIT 1 3/4 1-15 Amendment No. 58, 95, TV4/ t

, -Ma rc h-42,-1986-<

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

R[ ACTIVITY CONTROL $YSTEMS LIMITING CONDITPJN FOR OPERATION ACTION 4 - POWER OPERATION may continue provided that within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either:

1. The rod is restored to OPERABLE status within the above alignment requirements, or

2. The rod is declared inoperable and the SHUT 00WN MARGIN requirement of Specification 1.1.1.1 is satisfied. POWER OPERATION may then continue provided that:

a) An analysis of the potential ejected rod wort.% is performed within 3gdays and the rod worth is de'er-mined to be-$ 0.974 ak at 7ero power and $ 0.21%

Ak at RATED THERMAL POWER for the remainder of th(

fuel cycle, and b) The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 l is determined at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and l

c) The THE4 MAL POWER level is reduced to 5 75% of RATED i THERMAL POWER WITHIN one hour and within the next

! 4 hourt the high neutron flux trip sotpoint is reduced l to 1 85% of RATED THERMAL POWER, er i

d) The remainder of the rods in the group with the 1 inoperable rod are aligned to within i 12 steps of l the inoperable rod within orie hour while maintaining '

the rod sequence and insertion limits of Figures 3.1-1 i and 3.1-2; the THERMAL POWER level shall be restricted l pursuant to Specification 3.1.3.5 during subsequent i l operation.

l SURVEILLANCE REQUIREMENTS  !

The position of each rod 'shall be determined to be wihin the 4.1.3.1,1 group demand limit by verifying the individual rod positions at ieast once l/ b l per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except during time intervals wher, the Rod Position Deviation i Monitor is inoperable, then verify the group positions at leas' once per i 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. l l 4.1.3.1.2 Each rod not fully inserted shall be determined to be OPEPABLE by l/ h movement of at least 10 steps in any one direction at least once per 31 days.

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TROJAS'-UNIT 1 3/4 1-19 Amendment No. 70, YV5/ I

-May--2,, ..m, i

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_, ',0,{aCT1V17Y CONTR0( $YSTEMS 70$1710W IN0fCAT00 CHANNELS ttu1T1WG CONDITION FOR OPEtaTION 3.1.3.2 Control rod position indication system for control ant shutdoo rods and the demand position indication system shall be OPERA 8LE and l capable of detemining the control rod positionsp, .112 steps.

ApattCABit1TY: MODE $ 1 and 2.

A,$ TION:

4. With a noximum of one rod position indicator per group inoperable either:

1 1

i

1. Detemine the position of the non-indicating rod (s) indirectly I by the mvable incore detectors at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and immediately after any motion of the non-indicating rM which l exceeds 24 steps in one direction since the last detemination of the rod's position, or  !

2. Reduce THERMAL PowtR TO < 50% of iU.TED THERXAL PCh1R within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. l

b. With a maximus of one demand position indicator per bant inoperable either: ,

1 i

1. Verify that all rod position indicators for the af f ected bank are OPERABLE ard that the most withdrawn rad and the least withdrawn rod of the bank arv within a maximus of 12 steps of tach other at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or i

2. Reduce THERMAL PatR to < 50% of EATED THIRMAL PCWER within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

c. Tite provisions of Specification 3.0.4 a.te not applicabic.  ;

$URVEllLANCE RE0utaExtwTs 4.1.3.2 fach rod position indicator shall be detemined to be OPERABLE l by verifying the dermand position indication systate and the rod position indication systes agree within 10 steps at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> except l/[I during time intervals when the Rod Position Deviation Monitor is inoperable.

then cowart'the desand position indication systefe and the rod position indication system ht least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

TROJAN-UNIT 1 3/4 1-20 Amendment No. 72. JJ/ ,

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, S.EACT!V!TY CD CROL SY!T N S .

l 300 0D.0e '!*E ,

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i t L!MIT!MG CON 01TtCM FOR OPERATION l

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3.1.3.3 The individual full length (shutdown end centrol) r:d dre.9 time frem the fully withdrawn positien shall be 1 2.2 seconds frem beginning l cf decay of stationary gripper ceil veltage to dashpot entry with:

a. T,yg 1 550'F and

b. All reac:or coolant pumps operating, d '

AceLICABillW: MODES 1 and 2.

ACTICH: .

a. With the drop time of any full length red detemined te exceed the above limit, restere the red drop time to within the acove limit prier to proceeding to MODE 1 or 2.

b. With the red drop times within limits but determined with 3

, 7 reactor coolant cu ps operating, operatien may proceed provided

\ THERMAL 70WER is' restricted to 1 75t of RATED THETML 70WER.

SURVEILLANCE REOUIREMENTS 4.1.3.3 The red dree time of full lennth reds sna11 be d eenstrated threugh measurement prior to rea. tor criticality:

l a. Fcr all rods following each remeval of the re. actor vestel head,

b. Fer specifically affected individual rads fc11 ewing any main-tenance en er modification to the centrol red drive-system which coulc affect the drop time of these specific rods, ar.d

c. At least once per 18 months x

'Perfemance of inis Surveillarce Recuirement e.ay be deferred to coincide with the scheduled refueling cutage. This extensien cermits cceration to continue in MODES 1 and 2 until April 11, 1980.

I TROJAN-UN:71 3/4 1-21 Men:: ment No. '3 April 4. 1980 t

TABLE 3.3-1 ,

i

.. s -REACTOR TRIP SYSTEM INSTRUMENTATION I g-

$ MINIMUM

/,PPLICABLE "I~ TOTAL NO. CliANNE LS ' CliANt!ELS E FitNCTIONAL UNIT OF OfANNELS 'TO TRIP OPIRABLE MODES ACTION w 1. fanuai Reactor Trip 2 1 . 1, 2 11 I  ;

2 1 7 3*, 4 * , 5* 10 .

2. Power Range, Neutron Flux A. High Setpoint 4 2 3 1 2 28 b B. Low Setroint 4 2 3 IIII,2 28 A3h !

l 3. Power Range, Neutron Flux 4 2 3 1, 2 28 /

High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 28 l 3f\ '

!!igh Negative Rate

5. Intermediate Range, Neutron Flex 2 1 2 188#, 2 3 l 4

{ ,

Y 6. Source Range, Neutron Flux i A. Startup 2 1 2 288 .

B. Shutdown 2 1 2 3*, 4*, 5* {10 k 13 \ l C. Shutdown 2 0 1 3,4,5 57

7. Overtemperature AT  ;

Four Loop Operation 4 2 3 1, 2 68 j I Three Loop Operation 4 1** 3 1, 2 8 j

8. Overpower aT  !

Four Loop Operation 4 2 3 1, 2 68 l gg Three Loop Operatton 4 1** 3 1, 2 3  ;

9. Pressurizer Pressure - Low 4 2 3 1* 68 l ,

n en

/\

j - 5 10. Pressurizer Pressure - High 4 2 3 1, 2 68 l /13I\ !

11. Pressurizer Water Level - High 3 2 2  !* bi l \ j r .  ;

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t

. _ _ . .m _ - . . _ __ .. . . _ _ -- ._ . _ _ _ . _ _ . . .

l TABLE 4.3-1 (Cont _j_nued )

1 NOTATION With the reactor trip system breakers closed and the control red drive system capable of rod withdrawal. 1 l

1. The provisions of Specification 4.0.4 are net applicable. 1 l

1. When below the P-6 setpoint, i

t## When below the P-10 setpoint.

)

y When above the F-7 setpoint. l (1) - If not perf emed in previous 31 days.

(2) - Heat balance only, above 15% of RATED THERHAL POWIR. Adjust I l channtl if absolute dif f erence is >25. The provioicn 3 of Specification l l 4.0.4 are not applicable to entry into MODE 2 or 1. l (3)

' - Compare intore tu excore axial imbalance above 15% of RATED l THERMAL POWER. Recalibrate if absolute dif f erence >3 percent. .The pr ovision s of Spe:ification 4.0.4 are not applicable 20 entry rnto MdDE t or (4) . Neutron detectors may be excluded from CHANhEL CALIBRATION. I. '

l (5) - With the high voltage setting veHed, as recorm> ended by the l manuf acturer, an initial diariminator bias curve shall be measured for each detector. Subsequent discriminator bias curver 3 .

shall be obtained, evaluated, and compared to the initial curves.

(6) - Incore-Excore Calibration. The provision 4 of Specification 4.0.4 i

cre not applicabic to entsy into MODE 2 or 1.

(7) - Each train tested every other month.

l (8) - Setpoint verification is not apolicabic.

(9) + See Specification 3/4.9.2 for audio and visual requirements in MODE 6.

(10) - The reactor trip breakers shall be tested using the Automatic Trip Logic trip signal.

(11) - lach channel shall be tested at least every 92 days on a STAGGERED TEST BASIS.

(12) - The surveillance f requency and/or MODES specified f or these channels in Table 4.3-2 are more restrictive and, therefore, applicable.

(13) - The CSAhNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the '

Manual Reactor Trip Function. The test snall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

TROJAN-UNIT 1 3/4 3-12 Amendment No. 737, 737 ///

-June 20, 1986-

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! 81fAHQ3 COOL ANT SY$ TEM i M TY VAlv Q - SHUTpp g LIMITtNG CONDITION FOR.DPERAT109 __ ---

' 3.4.2 A minimum of one pressurizer code safety vsive shall be OP(RABLE with a lif t setting of 2486 PSIG (12%).

l

. APPL 10 ABIL17Y: MODL5 4 and 5.

6C7103:

a, l-lith no pressurizer code safety valve OPERABLE, imediately suspend all operations involving positive reactivity changes and place an OPERABLE j RHR loop into operation in the shutdown cooling mode. 1

b. In the event a saf'Ity valve fdils or is found inoperable, a Special i

Report shall tie prepared and submitted to the Comission pursuant to Specification 6.9.2 within 30 deys. The report shall vescribe the circumstsnces surrounding the f ailure, including the cause, if known.

l c. Tise provisions o f Specification 3.0,4 are no t appticab(c. l JURVC1LLANCCf,[001REMrNTS _ . .

l . _ _ . _

4.4.? The pressuriter code saf ety valve shall be demonstrated OPERABLE J per Surveillance Requirement 4.4.3. l l

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l TROJAN-UNIT 1 3/4 4-3 Amendment No 57. I.W I

-septembe r-1ri90F

--* ~ ~ ~-" ~ ~ - "~ ~ ~ ' ' ' ~' '

REACTORCOOLANTSYST9j OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.6.2 Reactor Coolant System leakage shall be limited to:

a. ho PRESSUFI BOUNDARY LEAKAGE, L 1 GPM UNIDEN11FIED LEAKAGE,

c. 400 gallens per day (gpd) total primary-to-secondary leakage through all stu m generators and 130 gpd through any one steam generator, h

d. 10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System,

e. 20 GPM total CCNTh0LLED LEAKAGE from all Reactor Coolant Pumps and 6 GPM CONTROLLED LEAKAGE from any one Reactor Coolant Pump at a Reactor Coolant System pressure of 2230 1 20 psig, .

f. Leakage at specified in Table 3.4.6-1 for each Reactor Coolant System Pressure Isolation Valve identified in Table 3.4.6-1, APPLI'ASILITY: MODES 1, 2, 3 and 4.

ACTION:

a. With any PRESSURE BOUNDARY LEAKAGE, be in COLD SHUT 00WN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />,

b. With ariy 3eactor Coolaat System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactr.r Ceolant System Pressure Isolation Valves, reduce the leakage rate u vithin limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in COLD SHUTOCWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

c. With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, reactor operation may continue, provided that at least two valves in each high pressure line having a nonfunctional valve are in, and re'nain in, the mode corresponding to the isolated condition. (Note, however, that this may lead to further ACTION requirements for the individual systems involved.)

Manual valves shall be locked in the closed position; motor operated valv>2s shall be placed in the closed position and the power supplies deenergized. Whenever it,tegrity of u pressure isolation valve listed in Table 3.4.6-1 cannot be demonstrated, the integrity of the remaining valvr in each high pressure line having a leaking valve shall be determined and recorded daily. In addition, the position of the other closed valve located in the high pressure piping shall be recorded daily. The provisions of Spccification 3.0.4' arc not applicable.

If the provisions above cannot be met, reduce vulve leakage to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in COLD SHUT 00WN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

1ROJAN-UNIT 1 3/4 4-14 Amendment N0. 17W

-februe ry+-4992-

l 4

^ REACTOR COOLANT SYSTEM l

CHEMISTRY

)

LIMITING CONDITION FOR OPERATION l

^

3.4.7 The Reactor Coolant System chemistry shall be maintained within the limits specified in Table 3.4-1. '

APPLICABILITY: At all times, i ACTION:

H0 DES 1, 2, 3 and 4

a. With any one or more chemistry parameter in excess of its Steady State Limit but within its Transient Limit, restore the Parameter to within its Steady State Limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or ,

be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.  !

l b. With any one or more chemistry parameter in excess of its

- Transient Limit, be in COLD SHUTOOWN within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, i

\ >

At all other times. l With the concentration of either chloride or fluoride in the Reactor l l

Coolant System in excess of its Steady State Limit for more than 24 (

hours or in excess of its Transient Limit, reduce the pressurizer

, pressure to 1500 psig, if applicable, and perfonn an analysis to '

l'

- determine the effects of the out-of-limit condition on the. structural integrity of.the Reactor Coolant System; detennine that the Reactor _

Coolant System remains acceptable for continued operations ririor to

' increasing the pressurizer pressure above 500 psig or prior to proceeding to MODE 4. The ProV4adone of Spec 4ficad on 3.0.4 are not applicabic.  ?

SURVEILLANCE REQUI_R,EMENTS _ _ ,

4.4.7 The Reactor Coolant System cht<nistry shall be determined to be within the limits by analysis of those parameters at the frequencies '

.specified in Table 4.4-3.  !

TROJAN - UNIT 1 3/4 4-16  ;

._ u . - . _ _ _ _.._-.._.- _ , . . _ _ _ . - . _ . _ . , _ _ . _ _ , _ _ , _

REACTOR C1QLANT SYSTJJ SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION _,,,

3.4.8 The specific activity of the primary coolant shall be limited to:

a. 5 1.0 pCi/ gram DOSE EQU! VALENT I-131, and

b. $ 100/f vCi/gra'n.

APPLICABILITY: MODES 1, 2, 3, 4 and 5 ACTION:

MODES 1, 2 and 3*

a. With the specific activity of the primary coolant > 1.0 sci / gram DOSE EQUIVALENT l-131 but within the allowable limit (below and to the lef t of the line) shown on Figure 3.4-1, operation may continue for up to 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. The provisions of Specification 3.0.4 are not applicable,

b. With the specific activity of the primary coolant > 1.0 vCi/ gram 4

OOSE EQUIVALENT l-131 f or more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous tirne interval or exceeding the limit line shown on Figure 3.4-1, be in H01 STANDBY with Tavg < 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />,

c. With the specific activity of the ~imary coolant > 100/f uti/ gram, be in HOT STANDBY with Tavg < 500*r within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

MODES 1.- 2,-3, 4 and 5

a. With the specific activity of the primary coolant > 1.0 pCi/ gram DOSE EQUIVALENT I-131 or > 100/[ uti/ gram, perfom the sampling and analysis requirements of item 44 of Table 4.4-4 until the specific activity of the prinry coolant is restored to within its limits. .The results of the analysis shall be submitted in the /\

Annual Report and include the information required in (._lH Specification 6.9.1.5.d.

b. The ptovisions v6 Specificaflon 3.0.J ate not appficable.

}_UR.V,EILLANCE RE0VIREMENTS ove/ded the mec!!!c adj,gitu is 5.100/0 904/

giam 4.4.0 The specific activity of the primary coolant shall be determined to be within the limits by perfor1 nance of the sampling and analysis program of Table 4.4-4

• With Tavg 1 50F F.

TRO.1AN-UNIT 1 3/4 4-19 Amendment No. JJ0, Y W

-JulT-&r*496fr o

4 EL@T Sn1LM A EltlARY f_f,[0WA1[R SYSlfM Ll.!!1.LI.M QJN0lilAN_FOR OPLRATION _ ,

3.7.1.2 At. least two ir. dependent steam generator auxiliary f eedwater pumps and associated flow paths shall be OPLRABLE with:

a. One feedwater pump capable of being powered by an OPERABLE diesel with 1450 gallons of feel in its day tank,-and

b. One feedwater pump p pable of being powered from an OPERABLE steam supply system.

6PPLICAM(U1: H0 DES 1, 2 and 3..

ACTION!

a. With one or the above auxiliary feedwater pumps inoperable, restore the--inoper6ble pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTOOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. With both of the above auxiliary feedwater pumps inoperable, be in at least H01 SIANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in H01 Shul 00WN within the following 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s-if the electric auxiliary feedwater pump is OPERABLE.

c. With no auxiliary f eedwater pumps OPERABLE, intnedtately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible. Reduce power to 35 percent of rated thermal power within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. When one pump is restored, enter ACTION staten.ent a. or b above as appropriate.

$URV[lLLANCE REju!RENLN15 _ _

4.7.1.2.1 Each safety-related auxiliary feedwater pump shall be demonstrated OPEPABLE:

a. At least once per 31 days by verifying that each valve (manual..

_ power-operated or automatic) in the flow p1th that is not-locked, sealed. or otherwise secured in position, is in its correct position,

b. By verifying that the diesel-driven pump starts and develops a dis-charge-pressure of t 1580 psig at I?00 RPM engine spced on recircu-lation flow when tested pursuant to Specification 4,0.5.

c. By verifying that the steam turbine-driven pump starts and develops a discharge pressure of t 1500 psig at 4560 RPM cn recirculation flow a (when tested pursuant to Specification 4.0.$) when the secondary steam pressure is > 800 psig. Pump OPERABIL11Y may be determined 1ROJAN-UNIl 1 3/4 7-5 Amendment No. H . H , 93-Septeraber 5,1984 .

P.LANT SYSTEMS MLR1Elu.ASPl.R1QUIREMF11,Sl(ontinued) e ._,,

at lower pressures in MODES 2 or 3 by verifying that the steam turbine-driven pump starts and develops a discharge pressure nf 11470 psig on recirculation flow (when testey)'fursuant to Specification 4.0.5) when the secondary steam pressure is > 275 psigt however OPr.RABILITY AT 4560 RPM shall be within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after secondary steam pressura is increased above 800 psig. The provisions of Specificative 4. 0.4 are no t applicable f or entrti into

d. At least once per la months, during shutdown, by: M0PE 3-

1. Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection test signal.

2. Verifying that each pump starts autonatically upon receipt of each auxiliary f eedwater actuation test s '.gnal in Table 4.3-2.

e. 'By verifying that each power operated (excluding automatic) valve in the flow path is OPERARLE when tested pursuant te Specification 4.0.5.

3 4.7.1.2.2 The auxiliary feedwater pump diesel shall be demonstrated OPERABLE:

a. At least once per 31 days by:

1. Verifying the fuel level in its day tink, and

2. Verifying that a sample of diesel fuel from its fuel tank is within the acceptable limits specified in lable 1 of ASIM D975-70 when checked for viscosity, water and sediment,

b. /,t letst once per 18 months during shutdown by:

1. Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service, and

2. Verifying the diesel and pump operate for E 60 minutes.

4.7.1.2.3 The electric auxiliary feedwater pump shall be demonstrated OPERABLE by verifying that the pump starts and develops-a discharge pressure of & 1580 psig on recirculation flow within the previous 92 days of entering Action item b, of 3.7.1.2.

TROJAN-UNIT-1 3/4 7-6 Amendment No. 39, 88, 7#, //

-Septembee-67-4984~

i 1

4 9'

PLANT SYS1 EMS COMPONENT CQ0 LING WATER SYSTEM LIMITING CONDITION F0R OPERATION _

3.7.3.' At least one component cooling water (CCW) train capable of supply-ing cooling water to equipment needed in MODES 5 and 6 shall be OPERADLE. d cra

. APPLICABillTY.: MODES 5 and 6.

ACTION:

With less than the required number of CCW trains OPERABLE, declare A supported equipment inoperable. Tite provi4Lona of Spec <ficatLen 3.0.1 are not applicable.

g SURVEILLANCE REQUIREMENTS 4.7.3.2 At least one CCW train shall be demonstrated OPERABLE by verifying d1L that necessary components (the portion necessary to support equipment which

-is required to te OPERABLE in the applicable MODES above) are OPERABLE when tested pursuant to Specification 4.0.5.

TROJAN-UNIT 1 3/4 7-14 Amendment No 74, 77K, 7#1 l'5%'

- Mey-11,-1990-

BANT SYSTEMS ERVICE WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.4.2 At least one service water train capable of supplying cooling water to equipment needed in MODES 5 and 6 shall be OPERABLE.

APPLICajillT_Y: MODES 5 and 6.

ACTION:

With less .,han the required nun 6er of service water trains OPERABLE, declare supported equipment inoperable. The prov44iona cf Specification 3.0.4 are not applicabic.

SURVEILL ANCE RE0tf1REMENTS ,,,

4.7.4.2 At least one sersce water train shall be demonstrated OPERABLE by verifying that necessary ccaponents (the portion ner.essary to support equipment which is required to be OPERABLE in the applicable MODES above) are OPERABLE when tested pursuant to Specification 4.0.5.

i l

TRO,lAN-UWli 1 3/4 7-16 Amendment No. 7#, Yl4/

-Wreh-14r-+MO I

i

~

I

. l PUM SY5ms LIMITING COMDITION FOR OPERATICN (C:ntinucd1 c) In writing within 14 days fellcwing the event, cut-lining the acticn tak.an, tu cause of the inc;en-bility and t e plans and schedule fer restering t::e systen ts OPEMSLE suus.

3. Tite provisions o f Specifica.tlon 3,0,4 are no t applicabic. ~

4 SLT/En1ANC:E REC 1JtTPOT3 _

t

4. 7. 8.1.1 The fin suppressien water syst.a:s shall be da=::nstra:ad CPERABLE,:  !

a. l At len: encs per 31 days en a STAGGT.3ED I'dIT EASIS by surting each p=:p and cperatins it for at leut 15 minutas. .

b.

At least enca per 31 days. by verifying that ea:h valve (=anual, pcwe.- c;erstad er au*-' tic), in the flew pac, is in its )

4 cernet ;csitien. '

c. At leut enca per 12 cenths by perfer::anca of a sy:ta= flush.

u d.

' At least enca per 12 =cnths by cycling eacn tasuble valve in the flew path t'.rcugh a: leu ene c=cleta cycle of fall travel.

e. At least encs per la =caths by parfer=ing a syste funettenal tas nich includes threughcut si=ulatad its c;ersting sequenca,aut:.:stic and: ac=ation of :ne s/ sus I

A

1. Verifying that each aut =a:1c valve in the ficw satt {ss i ac=atas ta its "c:rree. pesitten :n a tast sfinal,

2. Verifying that each pu=p davele;s at leu: 20C0 g;:s at a systm head of 17.5 psig.

3. Cycling each valve in the flew path that is net tastable during plant c;eraticn thr ugh at ler:: cne c=pleta cycle of full t: tvel, and 4.

Verifying :::at each high pressun ;t=:n starts (saquentially) u mainuin the fin sut;:n.121cn naur sy:u= pressure L 00 1 ;s 19 .

TK0JA% WIT 1 3/4 7-24 /cend=an: Nc. M

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

i

f. LLC,1R10AL 2 &lR SYSTEMS

}f0TbOWN

U31 TING CONDITIO_N FOR OPERATION

3. 0.1. ? As a minimum, the following A.C. electrical power sources sh.911 be OPERABLC:

4

a. One circuit betweer, the of fsite transmission network and the

. onsito ESF Eltetrical System and a

b. One diesel generator set with:

1. - Two diesels driving a common ger.erator,

2. Day tanks containing a minimum of 1370 gallons of fuel, 3 ., A fuel storage system containing a minimum of 33,000 i

gallons of fuel, and f

. 4. A fuel transfer pump.

APDLICAB1LiTI: MODES 5 and 6.

q ALQOd:

t With less than the above minitrum required A.C. electrical power sourets OPERABLE, suspend all operation; involving COPE ALTERATIONS or positive j reactivity changes until the minimum required A.C. electrical power 3

sources are restored to OPERABLE status.

The p1ovision.s of Specifica tion 5,0, .I are no t applicable.

4

$URVf!LLANCE RlQUIREMENTS , , _

r 4 . 8.1. 2 The above required A.C. electrical pher soerces shC1 be demonstrated OPERABLE by the performance of each of tha surveillance Requirefaents of 4.8.1.1.1 and 4.0.1.1.2 except for recuirement 4 4.8 1.1,2.a.6.

(

4 TROJAN-UNIT 1 3/4 8-5 4

- * *- v-- ar- -t - * ~ -- 7 ---

w

___._ _ __.___ _ . . . _ ~ . _ _ . __. _ _. _ . _ . . _ _ __ _ . _ _ _ _ .

ELECTRICAL POWJ_R SYSTEMS A.C. 0!STRlBUTION - SHUTDOWN LIMITING ColqlJlpN FOR OPERATION 3.8.2.2 As a minimum, the following A.C. electrical busses shall be /\

OPTRABLE and energized:

lM 1 - 4160 volt Emergency Bus 1 - 480 volt Emergency Bus 2 - 120 volt A.C. Pref erred Instrument Busses (Vital Dusses) l APPLICABILITY: MODES S and 6. l ACTION: -

With any of the above required electrical busses not energized in the required manner, irneo eately suspend all operations involving CORE A ALTERATIONS, positive reactivity changes, or movement of irradiated f uel.

Initiate *orrectiva action to energize the required electrical busses in {Q' the specified manner. Within B hours, depressurize and vent the RCS through a >3.40 square-inch vent.

The prov1sions r f Specifica tion 3. 0. .I a 't e. no t appli c a bl e .  ;

SURVEllt.ANCE RE0Vit EMENTS u

4.8.2.2 The specified A.C. busses shall be detenr.ined OPERABLE and /\

energized at least once per 7 days by verifying correct breaker l /132.

alignment and indicated power availability. .

il TROJAN-UNIT 1 3/4 8-7 ivnendment No. f37

-M y-4G r-lML -

i ELECTRIC AL POWER $YSTEMS 0,C. 015TRIBUT10N - $ HUT 00WN LlH1 TING CONDITION FOR OPERATION __ ,

3.8.2.4 As a minimum, the following D.C. electrical equipment and bus shall be energized and OPERABLE:

1 - 125-volt 0.C. bus, and 1 - 125 volt battery bank and at least one charger associated with the above O.C. bus.

APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above complement of 0.C. equipment and bus OPERABLE, immediately suspend all operations involving CORE ALTERATIONS, positive reacti<ity ct.anges, or movement of irradiated f"*1. Initiate corrective ,

action to energize the recuired electrical bus, battery bank, and as:ociated charger in the specified manner. Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, depressurize and vent the RCS through a 13.40 square-inch vent.

The provisions of Specification 3. 0. 4 a re not applicable.

IMRyEllLANCE RE0VIREMENTS 4.8.2.4.1 The above required 125-volt 0.C. bus shall be determined OPERABLE and energized at least once per 1 days by verifying indicated power availability.

i 4.8.2.4.2 The above required 125-volt battery bank and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.

l l TROJAN-UNIT 1 3/4 8-10 AmendmentNo.2)f7

-July 30, 1987

.__r_ _ . . . _ . _ . _ _ _ . . _ - _ _ _ . _ _ . _ . _ _ _ . .._ ___._ _.._. .~ _. . _ . _ . _ . _

TABLE 3.8 1 (Continued)

TABLE NOTATION

' Required when E3F equiprent is required to be operable.

ACTION STATEMENTS ACTION 1 - With the number of OPERAELE channels one less than the Total Number of Channels, operation may proceed provided both of the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within one hour.

b. The Minimum Channels OPERABLE requirement is met; hcwever, one additionki channel may be bypassed 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 surveillance testing per Specification 4.8.3 The p'tovisions of Specification 5. 0. 4 a re no t applicalle, TP.CJAN-UNIT 1 3/4 S-13 Amen:: ment No. ((

-A pril-14r49&4-

3/4.0 _APPt!CABILITY BASES , _ . _ __ _ _ _

/

The specifications of this section provide the general requirements applicable to each of the Limiting Conditions for Operation and Surveil-lance Requirements within Section 3/4.

3.0.1 This specification defines the applicability of each sp ification in terms of defined OPERATIONAL M00FS or other specified conditiop and is provided to delineate specifically when each specification is li:able. -

3.0.2 This specification defines those conditions necepsary to constitute compliance with the terms of an individual Limi)ing Cendition for Operation and associated ACTION requirerrant.

/

3.0.3 This specification delineates the ACTION be taken for circumstances nut directly provided for in the ACTI statements and whose occurrence would violate the intent of the y ecification. For exarcple, Specification 3.5.1 callt for each Rea for Coolant System accumulator to be OPERABLE and provides expli ACTION requirements when one accumulator is inoperable. Under terms of Specification 3.0.3, if more than one accumulator is inoperabl within i hour measures must be initiated to place the unit in at least and in at least HOT SHUT 00WN within th following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. As a further T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> -h \

example, Specification 3.6.2.1 requir s two Containment Spray Systems to be OPERABLE and provides explicit I.CTID requirements if one spray system is inoperable: Under the terms of Spfcification 3.0.3, if botn of the required Containment $ pray Systems are ip6perable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> measures must be initiated to place the unit i at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, [-3(

in at least HOT SHUTDOWN wi in the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in at least COLO /\

SHUTDOWN in the next 24 hop 5. It is assumed that the unit is brought to the l /13h required MODE within thegequired times by promptly initiating and carrying out the appropriate ACTIO tatement.

3.0.4 This spe'cification provides that entry into an OPERABLE MODE or other specifie 4pplicability condition must be made with (a) the full complement of r uired systems, equipment or components OPERABtE and (b) all other paramet s as specified in the Limitin!1 Conditions for Operation being met withcut egard for allowable deviations and out of service provisions contair.ed the ACTION statements.

T intent of this. provision is to insure that facility opteration is not J itiated with either required equipment or systems inoperable-or ot er specified limits being exceeded.

Replace with insert 3 TROJAN 'INIT 1 B 3/4 0-1 Araendment No. 53, 77/

Apr41 22, 1 %7.-

l

______ - - - )

I o e tt 3 $ closure 3 to Generic 'Letter 87-09

\

3/4 LIMITING CONDITIONS FOR OPEpATION AND SURVEILLANCE REQUIREMENTS - 4.0 APPUCABILITY u this enclosDFFTrbVfdeFFivTsiid~Pases 'oflilFspecifWatEnsT#

u Sactions 3.0 and 4.0.2 IAM3 ,

Specification 3.0.1 through 3.0.4 establish the general requireme.nts applicsble to Limiting conoitions for opuation. These requirements are based on the requirements for Limiting Conditions for bperation stated in the Code of Federal Regulations,10 CFR 50.36(c)(2):

"Limitine conditions for operation are the lowest functional capability or performance levels of equipment reovired for safe operation of the i facility. When a limiting condition for operation of a nuclear reactoi is not met, the licensee shall shut down the rnector or follow any remedial action  ;

pemitted by the techaicai . specification until the condition can te met."

h Specification 3.0.1 estchlien the Applicability statement within each 3

inoivioual specification as the requirement for when (i.e., in which

, OPERATIONAL MODES or other specified conditions) confomance. tc the Limitira Conditions for Operation is required for safe operation of N.:e facility. The ACTION requirements establish those remedial measures that must be taken within specified tine limits when the requirements of a Limiting Condition for Operation are not met.

There are two basic #3es of ACTION requirements. The first specifies the remedial measures that permit continued operation of the facility which is not ,

further restricted by the time limits cf the ACTION requirements. In this 3 case, confomance to the ACTION requirements provides an acceptath level of I safety for unlimited continued operation as long as the ACTION recuirements continue to be met. The second type of ACTION requirement specifies a time limit in which confomance to the conditions of the Limiting Condition for -

Operation must be met. This tie liait is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits. If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in a MODE or condition in which the specification no longer applies. It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system (s) or component (s) from service in lieu of other alternatives that would not result in redundmt systems or components being inoparable. ,

j Tha/specified time limits of the ACTION requirements are applicable from the I point in time it is identified that a Limiting Cobdition for Operation is not l met. The time limits of the ACTION requirements are also applicable when a l system or component is renoved from service for surveillance testing or investigation of operational problems. Individual specifications may include a specified time limit for the empletion of a Surveillance Requirement when equipment is removed from . service. In this case, the allowable cutage time

! -NR ':TS- B 3/4Wr--

l I

l- ,

l d

3/4.0 AHL: LABILITY, Inoett 3 (centinned)

• BASES (Cen't) limits of the ACTION requiremer.ts are. applicable when this limit ' expires if the surveillance has not been completed. When a shutdown is required to comply with ACTION reouirements, the plant may have entered a MODE in which a new specification becomes applicable. In this cese, the time limits of the ACTION requirements would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

Seecifjcatien 3.0.2 establishes that noncompliance with a specification exists 1 when the reouirements of the Limiting Cono-tion for Operation are not met and the associated AC110N requirements have not been imp 1mented within the specified time interval.

The purpose cf this specifiestion is to clarify trat (I) implementation of the ALTIch requiremnts within the specified tirse interval conetitutes conpliance with a specification end (2) completion of the remedial messures of the MTION requirements is not required when compliance with a Limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

Spe-ification 3.0.3 emblishes the shutdown ACTION requirements that must be imp 1mented when a Limiting Condition for Operation is not met and the cundition is not specifically addressed by the associated ACTION requirentents.

The purpose of this specification is to delineate the time limits for placing '

the unit in a safa shutdova MODE when plant o>eration cannot be maintained within the limitt for sate operation defined ay the Limiting Conditions for Operation and its ACTION requirements. It is not intended to be used as an

, operational convenience which pennits (routir.e) voluntary removal of redundant systems or components from Jervice in lieu of other alternatives that would not result in redundant syctems or components being inoperable. One hour is allowed to prepare for an crderly shutdown before initiating a change in plant

• operation. This time permits the operator to coordinate the reduction in electrical generat%n with the load dispatcher to ensure the stability and availability of tne electrical grid. The time limits specified to reach lower MODES of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimun reoutred .

equipment is OPERABLE. This reduces thennal stresses on cociponents of the 4 primary coolant system and the potential for a plent upset that could challenge safety systems under conditions for which this specification applies.

If remedial measures penr.itt'ng limited continwd operation of th? facility under the provisions of the ACTION requirements are completed, the shutdown r a may be termir;atad. The time limits of the ACTION requirements are applicable from the point in time there was a failure to m3et e Limiting Condition for Operation. Therefore, the shutdown may be terminated if the ACTION t requirements have been met or the time limits of the ACTION requirements have not expired, thus providing en allowhnce for the ccepletion of the required actions.

Ph" STS 0 3/4d+-

3/4.0 APPLICABILITY Insett 3 (continued)

BASES (Con'tl The time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br /> for the plant to be in

• the COLD SHUTDOWN MODE when a shutdown is required during the POWER MODE of operation. If the plant ic in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower PODE of operation ap-plies. However, if a lower MODE of operation is reached in less time than allowed, the total alluable time to reach COLD SHUTDOWN or other applicable MODE, is not reduced. For example, if HOT STANDBY is reached in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the (

time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> because the total time to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />.

Therefore, if remedial measures are completed that would pervit a return to POWER operation, a penalty is not incurred by having to reach a lower MODE of ~

operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one

~ 7 tion results in entry into a MODE or condicion of operation for

~Mr. meification in which the reovirements of the Limiting Condition for Opet are not met. If the new specification becomes applicable in less te -t  : pecified, the difference may be added to the allowable outage time

, -t <

he second specification. However, the allowable outage tine limits

( equirements for a higher MODE of operation my not be used to extend o '

- ale outage time that is applicable when a Limiting Condition for y' is not met in a lower MODE of operation.

The shutdown requirements of Specification 3.0.3 dh not apply in MODES S and 6, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Y 1

4

l i n s c ot !. Icentinued)

Changes to BASES for TS 3.0.4 Snecification 3.0.4 establishes limitations on MODE changes when a Limiting Condition for Operation is not met. It precludes placing the facility in a higher MODE of operation when the requirements for a Limiting Condition for Operation are not met. The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified lit /.ts. Complianca with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an accept-a>1e level of safety for continued optiation IDE without regard to the status of the plant before or after a~ MODE change. In these cases, exceptions to the provisions of Specification 3.0,4 are stated in individual specifications.

Therefore, entry into an OPERATIONAL MODE or other specifita condition may be made in accordance with the provisions of the ACTION requirements when an exception to the provisiens of Soecification 3.0.4 is stated in an individual specification, An exception to the provisions of this specification should not, newever, be interpreted as endorsing the failure to exercise good practice in restoring systems or comoonents to OPERABLE status before plant startup, When a shutdown is required to comply the ACTION requirements, the provisions of Scecification 3.0.4 to not acply because they would delay placing the facility in a lower MODE of operation, o

P L

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, __ J

3/4.0 APPLlCABillTY BASES (Continued)

Exceptions to this provision have been provided f oi a-limited number of specifications when startup with inoperable equipment would not affect T

plant safety. These exceptions are stated in the ACTION statements of the a'propriate g specifications. __

3.0.5 This specification delineates what additional conditions must be satisfied to permit operation to continue, consistent with the ACTION statements for power sources, when a normal or emergency power source is not OPERABLE. It specifically prohibits operation when one division is inoperable bt:cause its normal or emergency power source is inoperable and a system, subsystem, train, component or device in another division is inoperable for another reason.

l The provisions of this specificction permit the ACTION statements associ-l ated with individual systems, subsystems, trains, components, or devices

to be consistent with the ACTION stataments of the associated electrical L power source. It allows operation to be governed by the time limits of l-the ACTION statement associoteu with the limiting Condition for Operation for the normal or emergency power source, not the individual ACTION state-L ments for each system, subsystem, train, component or-device that is determined to be inoperable solely because of tr.f inoperability of its normal or emergency power source.

'- For example, Specification 3.8.1.1 requires in part that two emergency f diesel generators be OPERABLE. The ACTION statement provides for a 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> out-of-service time when one emergency diesel generator is not OPERABLE. If tne definition of OPERABLE were applied without considera-tion of Specificatien 3.0.5, all systems, subsystems, trains, components i

and devices supplied by the inoperable emergency power source would also l be inoperabit. This would dictate invoking the applicable ACTION state-l- ments for each of the applicable Limiting Conditions for Operation.

! However, the provisions of Specification 3.0.5 permit the time limits

! for continued operation to be consistent with the ACTION statement for-l the inoperable emergency diesel generator instead, provided the other l specified conditions are satisfied. In this case, this would mean that L t.ie corresponding Mrmal power source must be OPERABLE, and all redundant systems, subsystems, trains, components, and devices must be OPERABLE, or otherwise satisfy-Specification 3.0.5 (i.e., be capable of performing their design function and have at least one normal or one emergency power source OPERABLE). If they are not satisfied, shutdown is required l- in accordance with this specification.

As a f urther example, Specification 3.8.1.1 requires in part that two L

"physicallv independer.t circuits between the off site transmission network TROJAN-UNIT 1 B 3/4 0-2 Amensment No. [I Ot s bcr 1L, 1000-

~

a

1 i f

APPLICABILITV Replace dele ted s ec tions tei th appnop1ia te s ec tion s ficm in s cit 4.

4.0.1 This specification provides that surveillance activities ne essary to insure the Limiting Conditions for Operation are met an performed

, during the OPERATIONAL MODES or other condition m . ch the Limiting Conditions for Operation are appliS21+ rovisions for additional surveillance activiti be7Erformed without regard to the applicable OPERATIONAL ther conditions are provided in the individual

.Sune ' ance Requirements. .

Specification 4.0.2 establishes the limit for which the specified time i interval for Surveillance Requirements may be extended. It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that

may be suitable for conducting the surveillance; e.g., transient conditions cr other ongoing surveillance or maintenance activities. It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified witn an 18 month

, surveillance interval. It is not intended that this prevision be used repeatedly as a cor.venience to extend surveillance intervals beyond that 7s ,

specified for surveillances that are not performed during refueling outages.

The limitation cf Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. This provision i: sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval, i

4.0.3 The provisions of this specification set forth the criteriajof determination Cor.ditions for of compliance with the OPERABILITY recuirements of thejilniting Operation.

,~

Under this criteria, equipment, systejm 4 r components are assumed to be OPERABLE if the associated surve T ance

! activities have been satisfactorily performed within the s fied time

interval. Nothing in this provision is to be construe defining equipment,

systems or components OPERABLE, when such items are und or known to be inoperable although still meeting the Surveillanc(fRequirements.

l 4.0.4 This specification ensures t' the surveillance activities l associated with a Limiting Condition er Operation have been performed within i

the specified time interval prior entry into an OPERATIONAL M005 or other applicable condition. The in t of this provision is to ensure that t

surveillance activities ha # been satisfactorily demonstrated on a current basis as required to m3e(the OPERABILITY requirements of the Limiting L. Cordition for 0peraytk6n.

under t . terms of this specification, for example, during initial plant startup ollowing extended plant outages, the applicable surveillance actijv' es must be peric <med within the stated surveillance interval prior to

;JringorreturningthissystemorequipmentintoOPERABLEstatus ,

i

l. TROJAN-UNIT 1 B 3/4 04 Amendment No. 57 3 f7//

,;me-1+r 4994

4 APPLICABILITY

• Replace witit inpc.tt 4 BASES 4.0.5 This specification ensures that inservice inspection :f ASME Code Class 1, 2 and 3 components and inservice testing of A$hE Co Class 1, 2 and 3 pumps and valves will be perfomed in accorcar>ce,eewi th a periodically updated version of Section XI of tne ASME Sc/i (r and Pressure Vessel Code and Accenda as required by 10 CFR 50.La. Relief from any of the above requirements has Qeen provided in ritinc ey ne '

Commission anc is not n part of-:nese Tecnnical Speci# cations:

This specification includes a elarification f :ne frecuencias for perfoming the inservice inspection and tee ,ing activities requireo by Section XI of the ASME Boiler and Pressur Vessel Coce and applicable Adcenca. This clarification is proviceo

• ensure consistency in sur-veillance intervals throughout these Te nical Specifications anc to remove any amoiguities relative to in frequencies for performing the A required inservice inspection anc + sting activities.

'Jncer the terns of this sp6cification, the more restrictive recuir%

ments of the Technical Spectficatir.,ns take prececence over the ASME Boiler and Pressure YesseV& ode and applicable Addenct.. For example, One requirements of Specifi (tion 4.0.4 to perferm surveillance activities prier to entry into CPERATIONAL MODE or other specified coplicabil.ity c.:ncition takes pre edence over the ASME Boiler anc Pressure Vessel Coce provision which Adows pumps to be tested up to one week after return to normal cperati . And for example, tne Tecnnical Specification cefini-tion of OPE? OLE does not grant a grace period before a .cevice that is not capab of_ performing its specified function is ceclared inoperable and tak precedence over the ASME Boiler and Pressure Yessel Code prov' on wnien allows a valve to. be incacaole of performing its speci-fi function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cefore being ceclared inopersole, i

i u

i 1

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TRCdAN-dNIT 1 3 3/4 0- 5 A ent.en: n. //

-Mey 0, 1901 l L

3/4.0 $PPLICABILITY Inicit 4 I

BASES (Con't)

~

When a shutdown is required to canply wTtTACTION requ1rements, the provtsions of Specification 3.0.4 do not apply because they would delay placing the

.& facility in a lower MODE of operation.

Soecifications 4.0.1 throuch 4.0.5 establish the general requirements applicable to Surveillance RecuirementJ. These requirements are based on the Surveillan::e Requirements stated in the Code of Federal Reculations, 10 CFR 50.36(c)(3):

" Surveillance "eqJirements are requirements elating to test, calibra-tion, or inspection to ensure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions of operatice will be met."

Soecification 4.0.1 establishes the requirement that surveillances must be performec curing the OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditiens for Operation apply unless otherwise stated in an individual Surveillance Requirement. The purpose of this speci-fication is to en:ure that surveillances are performed to verify the opera-tional status of systems and components and that parametecs are within speci-fied limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONA'. MODE for which the recuirements of the associated Limiting Condition for Operatier1*do not apply unless otherwise

, specified. The Surveillance Requirements associated with a Special Test Exception are only applicable when the Special Test Exception is used as an allowable exception to the recuirements of a specification.

Soecification 4.0.2 establishes the conditions under which the specified time interval for 3urveillance Requirements may be extended. Item a. pemits an allowable extensien of the nomal surveillance interval to facilitate surveillance scheduling and consideration of plant operatin may not be suitable for conducting the surveillance; e.g., gtransient conditions that conditions or other ongoing surveillance or maintenance activities. Item b. limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of f.-f Specification 4.0.2 are based on engineering judgment and the recognition that the tes? probable result of any particular surveillance being perfomed is the ver.?i m ica of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through surveillance activitfes is not significantly degraded beyond that obtained frte the specified surveillance interval.

Soecification 4.0.3 establishes the failure to perform a Surveillance Requirement witnin the allowed surveillance interval, defined by the provisions of Soecification 4.0.2, as a condition that constitutes a failure to meet the OPEPMILITY requirements for a Limiting Ccndition for Operation. Under the

Ioeit 4 heontinuedj 3/4.0 APPLICABILITY i

BASES (Con't) provisions o'f this specification, systems and components are assumed to be ORERABLE when Surveillance Requirements have been satisfactorily perfortned within the specified time interval. However, nothing in this provision'is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements. This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completta within the allowed surveillance interval and that thh time limits of the ACTION requirements apply from the point in time it is identified that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable autage time limits of the ACTION requirements restores comoliance with the requirements of Specification 4.0.3. I!cwever, this does rot negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a limiting Condition for Operation that is subiect to enforcement action. Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the recuireevints of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.

If the allowable outage time lir;its of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or a shui.down is recuired to comply with ACTION requirements, e.g.,

Specification 3.0.3, a 24-hour allowance is providd to ,armit a delay in implementing the ACTION requirements. This provides an scequate time limit to complete Surveillance Requirements that have not been grformed. The purpose of this allowance is to permit the ccepletion of a surveillance before a shutdown is required to ecc: ply with ACTION recuirements or before other recedial measures would be required that may preclude completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availaoility of personnel, the time required to parfom the surveillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a time limit for the completion of Surveillance Raouirements that become applicable as a consequence of NODE changes imposed by ACTION requirements and for c:rpleting Surveillance Requiments that are soplicable when an exception to the requirements of Specificatica 4.0.4 is allowed. If a surveillance is not completed within the .

24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> allowance, the time limits of the ACTION rnuirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is tarminated.

Surveillance Requirements do not have to be perfonned on inoperable ecuipment because the ACTION requirements define the remedial measures that scoly.

However, the Surveillance Recuirements have to be met to demonstrate that inoperable equipment has been restcred to OPERABLE status.

---f% O - -!-:/ ' . 0 5-

.,q> .

3/4.0 APPLICABILITY Inaca( 4 (ce:Linutd) ,

BASES (Con't)

Specifictdion 4.0.4 establishes the requirement that all applicable surveillances tust be met before entry into an OPER.ATIONAL MODE or other condition of operation tpecified in the Applicability statement. The purpose of thi; specification is to ensure that system end component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL PODES or other specified conditions associated with plant shutdown as well es startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be perfanned within the specified surveillaner interval to ensure that the Limiting Conditiuns for Operation are met during initial plant startup or following a plant outage.

When a shutdown is required to comply with 7.CTION requirerents, the provisions of Specification 4.0.4 do not apply beccuse this wculd delay placing the facility in a lower MODE of operation.

Soecification 4.0.5 establishes the requirwent that inservice inspection of X3ME code class 1~~? and 3 components and inse vice testing of ASME Code Class 1, 2, and 3 pumps and valve; shall be performeo in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a. These requirements apply \

except when relief hus been provided in writing by the Comenission.

This specification includes a clarification of the frequencies for perfoming the inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification l 1s provided to ensure consistency in surveillance intervals throughout the '

Technical Specifications and to remove any ambiguities nlative to the frequencies for perfoming the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of i the Technical Specifications take precedence over the ASME Poiler and Pressure '

Yassel Code and applicable Addenda. The requirements of Specification 4.0.4 to perform surveillance activities before ritry into an OPERATIONAL MODE or other specified condition takes precedence over the ASMC Boiler and Pressure Vessel Code provision which allows pumos and valves to be tested up to one week after return to normal operation. The Technical Specification definition of OPERABLE does not allow a grace period befcre a component, that is not capable of performing its specified function, is declared inoperable and takes .

l precedence over the ASME Boiler and Pressure Vessel Code provision which I allows a valve to be incapable of performing its specified function for up to l 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.

1

- P M -SIE- -B-3/40 l l

.- . . - - . . . - . . - - - ~ ~

4 LCA 186 Rev. 1 Attachment 0 Page 1 of 5 BESE0NSLE_REQUESLEDRADillIl0NAL _ INFORMAIl0N j l

l

-'Diis attachment consists of PGE's response to the NRC letter of Au;ust 2,

['" 1990, kequest for Additional Information on the License' Amendment Application Under Generic Letter 87-09 for Trojan Nuclear Plant (TA0 No.-75774). It is included herein since it forms part of the safety

. considerations associated with the Trojan Technical Specification ]

(TTS) 3.0.4 related revisions. 4 Part 1 of this attachment deals.with affirmation that remedial measures prescribed for the affected Action Statements are consistent with the Updated Safety Analysis Report and its supporting safety analyses.

Part 2 of this attachment deals with administrative controls which limit the use of the Specification 3.0.4 exceptions grented.

ParL1 The proposed TTS changes under Generic Letter (GL) 87-09, relating to Specification 3.0.4, consist of adding Specification 3.0.4 non-applicability statements to a group of TTSs which meet the criteria of GL 87-09, 1.e., ITSs'with action requirements that permit centinued operation of the facility for an unlimited amount of time.

l-l _ These TTSs are listed in Attachment A and the proposed page revisions are

[ included in Attachment B. .Following is a swanary discussion of each such l_ proposed TTS revision including affirmation that remedial measures prescribed for the affected Action statements are consistent with the updated Safety Analysis Report and its supporting safety analyses.

I l 3.1.2.3 Charging Pump - Shutdown.

3.1.2.5 Boric Acid-Transfer Pumps - Shutdown 3.1.2.7 Borated Water Sources - Shutdown The proposed TTS changes would allow transition from Mode 6 to Mode 5 while complying with the remedial actions = contained in the ACTION

, statements. The remedial actions for each of the above shutdown L specifications include suspension of operations involvirg core l alterations or positive reactivity changes due to the affect on the

. capability to borate. The transition from Mode 6 to Mode 5 is accomplished by installing the reactor vessel head. This activity does not constitute a core alteration or a potitive reactivity change. This situation involves no impact on safety analyses nor reduction in margins of safety.

1 L TTS 3.1.3 C oR1 Lion _lndicainr_Channela 1

This TTS,' as written, allows continued indefinite operation while in

. compliance with the Action requirements. Action a. offers two ,

- niternatives with a maximum of one rod position indicator per group inoperable; either detenmining the position of the non-indicating rod by l

]

LCA 186, Rev. 1-Attachment C 1 Page 2 of 5 i

t I use of the movable incore detectors, or reducing power to <50 percent of RATED THERMAL F0WER. Action b. of fers two alternatives with a maximum of

. -one demacd position indicator per bank inoperable; either verify that all

! rod. position _ indicators for the affected bank-are operable and that all I rods in the'affected bank-are within a maximum of 12 steps of each other, ,

~

or reduce power to (50- percent of RATED THERMAL POWER. Taking exception l to the provisions of TTS 3.0.4 would allow mode changes from Mode 3 into-Mode 2, and from Mode 2 into Mode 1 while in compliance with the ACTION requirements. The remedial measures in the ACTIONS for this TIS are ,

consistent with assumptions used in the FSAR and accident enalyses.

Actions a.1 and b.1 both' provide alternate means for determining rod positions, and Actions a.2 and b.2 provide for power reduc.' ions te.

account for the possibility of a mispositioned control rod.

IIS_323 dle a c tatIrip_Systemln s trumen ta tion _( Ac tion _5)

Action 5 of this-TIS providen remedial action for having bcth channels of the source range neutron flux monitoring instrumentation inoperable.

Action 5 applies in Modes 3, 4, and 5 and-requires periodie verification of compliance with shutdown margin requirements of TTS 3.1.1.1. The two shutdown channels affected by Action 5 are not required to have reactor trip functions since the MODE applicubility dif ferentiates between the condition with the reactor trip breakers closed and the condition without the reactor trip breakers closed. The proposed IIS chanFes would allow mode changes from Mode 6 up to and including Mode 3, while complying with the Action 5 remedial requirements of substituting verification of adequnte shutdown margin for the source range mcnitors. Since this is solely a monitoring f unction when the reactor trip breakers are open, I there is no effect on the safety analysis.

.IIS. 3.3AEngincimd. Safely.lcatuc_AcluatinnJiyatemlnalrumen_tatino Action 16:

This action allows continued, indefinite operation with one inoperable channel bypassed since the minimum channels operabic requirement _is'still met with one channel eut of four inoperable.

The proposed TTS change would allow transition from Mode 5 up to and including Mode 1 while complying with Action .6_ requirements. The 1

' loss of one channel reduces the redundancy of the instrumentation but does not affect the safety analysis.

Action:17i This action allows continued, indefinite operation with less than the minimum channels of Containment radioactivity monitors operable while complying with the remedial activn requirement of maintaining the Containment ventilation valves closed. The safety function of controlling releases from Containment ic, met by isolation since the automatic isolation function is not operabic when the monitors are not operabic. The proposed TTS changes would allow transition from Mode 5 up to and including Mode 1 while complying with this action. -

This situation places the Containment ventilation in an isolated condition which is- consistent with the safety analysiF.

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~.i

't-M LCA 186, Rev. 1 Attachment C Page 3 of.5 USJhiLS.afaty_VahcL _libutdan The propv ed TTS changes wou.1d allow transition from Mode 6 up to and including Mode 4 while complying with the remedial action requirements.

The remedial action includes suspension of operations involving positive reactivity changes and placement of an operable residual heat removal (RHR) leop Arto operation in the shutdown cooling mode. This provides "

sufHelent overpressure protection while in Modes 4 or 5. No reduction /

in margin ut safety is incurred and the safety analyses are not af f ected.

IISJdd,LOpera.tlonalleelage The propased TTS cnanges would allow transition from Mode 5 up to and including Mode 1 while complying with the remedial actions of Action c.

The safety function of limiting leakage via an isolation valve is met by the remedial act?on of assuring that at least two valves in each high pressure line having a non-functional valve are in and remain in, the- .

moda corresponding to the isolatea condition. This situation is bounded by the safety anelyses and presents no reduction in the margin of safety.

HS_.3 dal._Chemialry The__ proposed TTS changes would allow transition f rom Mode 6 to Mode 5

.while complying with the requirements of the ACTION statement applicabic to Modes.5-and 6.- The action limits the maximum pressure to.500 psig and precludes entry into Mode 4 until an analysis of the out-of-limit condition and its effects nu the structural integrity of the RCS has been concluded with the result that the RCS remains acceptable for continued operations. The proposed TTS change would not reduce the margin of safety or affect safety analyses.

HE_lddl._Sitecific_Aclility i

The AC'UON applicable to Modes 1, 2, 3, 4, and 5 estaolishes a surveillance-activity until the LCO is restored. The proposed change is r administrative and clarifies that Mode changes may be made while in the sampling program.

1 US_hL h23cmponcat_Cocha gla_ts r_Syatem The proposed changes to this specification are administrative. The

. intent is - to clarify that it the ACTION is met (i.e., declare supported equipment inoperable), then the appropriate TTS for the inoperable equipment would govern. There is no need to restrict mode changes via

.TTS 3.7.3.2 in the event that the equipment declared inoperable were not L needed. The TTS for the supported equipment would dictate whether or not ACTIONS were required that may or may not restrict mode changes.

HDJ ,L&,LSatylte.3ater.lys.tcm The proposed changes to this specification are administrative. The intent is to clarify that if the ACTION is met (i.e., declare supported 4 .

LCA 136, Rev. l' Attac unent C Page 4 of 5 equipment inoperabin), th'n e the appropriate TTS for the inoperable

-equipment would govern. There is no need to restrict mode changes via TTS 3.7.4.2 in the event that the-equipa.ent declared inoperable were not needed._ The TTS for the supported equipment would dictate whether or not ,

ACTIONS were required that may or may not restrict mode changes.

j 7IS.3.1481 Eire _SupprsssipalateIJysi.cm The proposed TTS (aange would allow transition from Mode 6 up to and -

lucluding Mode 1 U lle complying with the remedial action.s contained in the Action b statement. Since the tems t'lal actions require establishment of a backup fire suppression water systs:n, vn reduction in margin of safety is involved, nor are safety analyses affected, i USJ . 641JlleciricaLEontlys t erm _ Shut dum

, The proposed TTS changes would allow transition from Mode 6 to Mode 5 while complying _with +,he remedial actions included in the ACTION statement. The remedial action requires suspension of core alterations l

and positive reactivity changes to minimize the potential for a reactivity accident while accident mitigation equipment would not be i available due te loss of. power.

- US_3d.ALA.L_DiatribnLion ._Shutsion The proposed TTS changes would allow transition from Mode 6 to Mode 5 while complying with the , remedial actions included in the ACTION statement. Since the action requires suspension of core niterations, positive reactivity changes, movement of irradiated fuel, and depressurization and venting of the Reactor Coolant System (RCS), no I reduction in margin of safety would be involved, nor any safety analysis affected.- y USldd.A_DJuDisiriblLLion - Shutdo_wn 1 l

The proposed TTS changes would allow transition from Mode 6 to Mode 5 I' while complying with the remedial actions included in the ACTION statement. Since the action requires suspension of core alterations, )

positive reactivity changes, movement of irradiated fuel, and depressurization and venting of the Reactor Coolant System (RCS), no j reduction in margin of safety would be involved, nor any saf ety analysis  !

affected. j l

US1821 L Adft_kLEmergencyl%3t.derroit>4gelrol e cRon The proposed changes would allow transition from Mode 4 up to and including Mode 1 while complying vith the Action statenient remedial actions. Remedial actions include maintaining the minimum channels operable criteria, and tripping the inoperable channel which is conservative for the one-out-of-twa taken twice channels-to-trip function; consequently, no reduction in margin of safety would be involved, and safety analyses bound the situation, l

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LCA 186, Rev. 1 Attachment 0 Page 5 of s l l

2ntt_2 l l- -The NRC to PGE letter dated August 2. 1990 requested PCE to identify and affirm those administrative controle which limit the use of the granted exceptions to Specification 3.0.1 and to affirm that Operaticas personnel are trained and instructed to utilize the controls establisned. q Administrative controls are in place in the form of t,afety-relatec equipment control and ready-for-startup procedures, 4 proceso for prioritization of maintenance activlties which gives Technical .

Specification-related equipment sufficient priority and a daily Plant  !

status report which identilles Technical Specification ACTION statement ,

which have been entered. These controla provide assurance that Technical Specification ennipment which is inoperable 1) rt 'ves routire mnagemant oversight, 2) receives managernent app'roval bef ore changing

+

modes with the equipment inoperable, and 3) receives proper pr.ioritization for return to service.

PUE currently app?ies tnese controls to Technical Specifications wnich contain Specificatloa 3.0.4 exceptions and will apply the same controls for those Specifications for which Specification 3.0.4 exceptions ara proposed in this submittal.

With regard to operator training on the administrative controls for Technical Specificaticn equipment, the operators are an integral part of the controls described atove and are trained on these controls. The i- _ operators will also be trained on the changes in this submittal when the ameadment-is issued. This training will include the Basen changes which state that an exception to the provisions of Specification 3.0.4 chould I not be interpreted as endorsing the failuro to exercise good practice in l g restoring syatems or components to OPERABLE status before Plant startup, j It should be_noted, however, that the_ administrative controls on inoperable Technica1' Specification equipment described above are the responsibility of mor9 than just the operations staff. Therefore,

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reliance'is not placed aolely on the operators to ensure the use of Specification 3.0.4 exceptions a.re not abuseo.

A SAB/bsh 5872W.0392 a

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l UNITED STATES OF AMERICA l NUCLEAR REGULATORY COMMISSION t

i In the Matter of )

)

PORTLAND GENERAL ELECTRIC COMPANY, ) Docket 50-344 THE CITY OF EUGENE, OREGON, AND ) Operating License NPF-1 PACIFIC POWER & LIGHT COMPANY ) .

)

(TROJAN NUCLEAR PLANT) )

CERTIElrAIE_0LSERVICE -

h I hereby certify that copies of this supplement to License Change Application 186, Revision 1, to the Operating License for the Trojan l' Nuclear Plant, dated 3 / p,7,1992, have been served on the following by hand delivery or by deposit in the United States mail, first class, this g7 th -day of #reec# 1992:

State of Oregon 1 Department of Energy I 625 Marion St NE Sale.m OR 97310 Mr. Michael J. Sykes Chairman of County Commissioners Columbia County Courthouse St. Helens OR 97051 jf

. L,. fl H. K. Cherno,ff Acting Manager, Licensing On this day personally appeared before me H. K. Chernoff,-to me known to be the individual who executed the foregoing instrument, and acknowledged r that he signed the same as his. free act.

l- GIVEN under my hand and seal this 17 th day of /lbreh 1992.

W^^% -

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.t J f.I )li. KnM d ct.t v -

j ftif Notary Public in and for the

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Resie1, asa siysg~~.,s ,y M,- -+- - n -1

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