ML032450180

Improved Technical Specification Pages

ML032450180
Person / Time
Site:	Indian Point
Issue date:	08/29/2003
From:	NRC/NRR/DLPM/LPD1
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Download: ML032450180 (20)

Text

ESFAS Instrumentation 3.3.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G.2.1 Be in MODE 3. 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> AND G.2.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> H. Main Boiler Feedwater H.1 Verify one channel Pump trip channel(s) associated with an inoperable. operating MBFP is IlAea44 p723 OPERABLE. e-K AND H.2 Restore one channel 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> associated with each I operating MBFP to OPERABLE status.

Required Action and 1.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition H not met.

J. One or more channels J.1 Verify interlock is in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. required state for existing unit condition.

OR J.2.1 Be in MODE 3. 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> AND J.2.2 Be in MODE 4. 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> INDIAN POINT 2 3.3.2 - 4 Amendment No. (R2-S5) I

ESFAS Instrumentation B 3.3.2 BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)

&vkC;. The LCO requires all instrumentation performing an ESFAS Functionto Ta S ZA-be OPERABLE. A channel Is OPERABLE with a trip setpoint value outside its calibration tolerance band provided the trip setpoint 'as-found" value does not exceed s associated Allowable Valueradr~ddoe trip setpoinvs-Iefl value is aJiustii vau It ecabrio 46- Itolerancaband of the Nominal TSetpoint. A trip spoint may be s Imorp onservative than the minal Trip Setpoias necessa in Vefonse to lant condifio alure of any instrument renders the A$' .iLD" affected channel(s) inoperable and reduces the reliability of the affected Functions.

The LCO generally requires OPERABILITY of four or three channels In each instrumentation function and two channels in each logic and manual initiation function. The two-out-of-three and the two-out-of-four configurations allow one channel to be tripped during maintenance or testing without causing an ESFAS Initiation. Two logic or manual initiation channels are required to ensure no single random failure disables the ESFAS.

The required channels of ESFAS instrumentation provide unit protection In the event of any of the analyzed accidents. ESEAS protection functions are as follows:

1. Safety Injection Safety Injection (SI) provides two primary functions:

1. Primary side water addition to ensure maintenance or recovery of reactor vessel water level (coverage of the active fuel for heat removal, clad integrity, and for limiting peak clad temperature to < 2200°F), and

2. Boration to ensure recovery and maintenance of SDM (kdf Woeeeunotieon] rc Eessary to ~mitigate the effects of highne (I. reak (HELBs) both inside and otieo otim The SI signal is also used to initiate other Functions such as:

• Phase A Isolation,

• Contanmentwlsolation, WOG STS B 3.3.2- 6 Rev. 2, 04/30/01

ESFAS Instrumentation B 3.3.2 BASES APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)

b. uxiliarv F dwater- Automati Actuation Logic Actuat Relays gance of Plant ESPIS) k} . Auto atic actuation logi nd actuation rela consist of the

-. sas features and op tein the same nner as descri d V E f ESFAS Function.b.

5ff 2. >b e Auxiliary Feedwaler - Steam Generator Water Level - Low Low

(*,. t )SG Water Level - Low Low provides D oianaalstAosso

\ e',  ; dlt 2 heat s i eMreakAside r outside f, M>_- - floss of MFW. Did ~result i a loss of-SG Kt level.~S

_ 9er eve -. ow low rovijdes iputo the -0 Levl oitrolW

,Sstrleeo .the -tation~ ogid-m-uri ale t i~~itstand: both # In~~~put failure to the conrlsystem which ma then require rotection function actu on and a single faifur in the other annets providing the p tection function actuation hus, four OPERABLE nnels are required to satisfy e requirements with t out-of-four logic. For u that ye dedicated protection nd control channels, o three

\~ ~)kXn./; reo ction channels ire-ne sary to satisfy the protive uirements. For other u s that have only three annets, a

° t~t'i$:*^p Median signal selector I rovided or ustificatio s provided in Reference 7.

With the transmitters (dip cells) located Inside containment and thus possibly experiencing adverse environmental conditions o.Qt (feed01,.~d~.L lin ak the J~ir eflects the inclusion of both steady state and adverse environmental instrument uncertainties.

c'. Auxiliary Feedwater - Safety InJeclion An Si signal starts the motor driven ndvF W pumps. The AFW initiation functions are the same as the requirements for their Si function. Therefore, the requirements T f,3< are not repeated in Table 3.3.2-1. Instead, Function 1, St, Is referenced for alt initiating functins and requirements.

q -oJ uxilie Feedwat r oss o e o d loss of offsite power to the buses)will be accompanied by a loss of reactor coolant pumping power and the subsequent WOG STS B 3.3.2 - 29 Rev. 2,04130/01

NUREG-1431 Markup Inserts ITS SECTION 3.3.2

• Engineered Safety Feature Actuation System (ESFAS) Instrumentation INSERT: B 3.3.2 -29 - 03:

The SBO Function that generates Auxiliary Feedwater system start signals uses the channels required to be OPERABLE by LCO 3.3.5, 'Loss of Power (LqP) Diesel Generator (DG) Start Instrumentation," Function c,-Including the differences in -the actuation logic generated by a unit trip and the presence of an ESFAS safety njection cID,,signal. The SBO Function generates an automatic start signal for the turbine driven AFW pump if the undervoltage condition occurs in conjunction with a unit trip I no ESFAS safety injection signal is present. The SBO Function generates an automatic start signal for the motor driven AFW pumps If the undervoltage condition occurs In conjunction with a unit trip.

As described in the Bases of LCO 3.3.5, the SBO relays (i.e., channels) consist of two sets of three relays with one set associated with 480 V safeguards bus 5A (SBO train SA) and the other set associated with safeguards bus 6A (SBO train 6A). If there is a loss of voltage on 480 V bus SA or 6A, two out of the three SBO undervoltage relays associated with either bus 5A or 6A will actuate the undervoltage portion of the SBO function.

The requirements of the SBO function for the number of OPERABLE channels, the Required Actions when one or more chan re-iu Testing of SBO channels a or 0 3.3.2, Function 6.d, Auxiliay Feedwater SBO (Emergency Bus 6A or GA e same a r ured y 3.3.5, LO DG ion.

nja r uirement in 100 3.3.5 to enter applicable Condition(s) and Required Action(s) for all DGs inoperable when there is a loss of the SBO function provides all required compensatory actions for loss of AFW automatic start on an undervoltage condition because AFW pumps can still be manually sta ed and loaded N Y Iy and automatic AFW start on SG low level and lotsof feedwater are available..S I . _a. -water~t -

X.Ai V LOU-&.Y, -1nCi` a, Auxtiary by, Feed Baar-;-Ad

`utom1-uation =

Logo _ z and Actuation Relays, and LCO 3.7.5, Auxiliary Feedwater (AFW) System, establish Az lRequired Actions and Surveillance Testing for the Auxiliary Feedwater SBO (Emergency Bus 5A or 6A) function that are n nstrumentation/-T herIe LC 3.3.2, Function 6.d, Auxiliary Feedwater SBO

- (Emergency Bus 5A or 6A) establishes requirements for the SBO function by referencing LCO 3.3.5 except for Applicability.

This function is needed because

I ESFAS Instrumentation B 3.3.2 BASES SURVEILLANCE REQUIREMENTS (continued) perforp ed every 31 days onSAGGERED TEf BASIS. Ti\

Fre ency is adequate b ed on industry operfng experienceA csidering instrument liabilityandoperati history data.

SR 3.3.2.

SR 3.3.2is the performance of a MASTER RELAY TEST. The MASTER RELAY TEST is the energizing of the master relay, verifyng contact operation and a low voltage continuity check of the slave relay coil. Upon master relay contact operation, a low voltage is a to the slave relay coil. This voltage is insufficient to pick up the slave relay, but large enough to demonstrate signal path continuity. This test is performed every 31 days on a STAGGERED TEST BASIS. The time allowed for the testing ('hours)and the surveillance interval are justified in Reference Tf w) {.,

SR 3.3.2 s the performance of a COT.

COT is performed on each required channel to ensure the entire channel ill perform the intended Function. Setpoints must be found wthi the Allowable Values specified in Table 3.3.1-1. A successful test othe required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL OPERATIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions.

The difference between the current "as found" values and the previous test "as left" values must be consistent with the drift allowance used in the setpoint methodology. The setpoint shall be left set consistent with the assumptions of the current unit specific setpoint methodology.

The "as found" and "as left" values must also be recorded and for consistency with the assumptions oflhe srieillance-Mterva requency of Qdays isjustified in Reference 5.()

WOG STS B 3.3.2 - 48 Rev. 2, 04130/01

PAM Instrumentation B 3.3.3 BASES LCO (continued)

Two channels are required to be Operable for redundancy. Aeate dication is available-usingsaturation pressure- em ta . he plant computer subcooling margin readout can be used as a s bstitute for the RCS Subcooling Margin Monitor..

22. Refueling Water Storage Tank (RWST) Level RWST Level is a Type A, Category II Function that is used to confirm RWST level prior to the manual switchover to the cold leg recirculation phase that is initiated when the RWST level has reached the low low alarm setpoint and sufficient coolant inventory to support pump operation in recirculation mode is verified in the containment.

Two channels of RWST Level indication are required consistent with LCO 3.5.4, "Refueling Water Storage Tank", requirements for OPERABILITY of two channels of the RWST level low low alarm. This is required because the P2 ESFAS design does not include automatic switchover from the safety injection mode to the recirculation mode of operation based on low low level in the RWST coincident with a safety injection signal.

The LCO requirement for two channels of RWST level indication is satisfied by the OPERABILITY of LT-920 and LT-5751.

APPLICABILITY The PAM instrumentation LCO is applicable in MODES 1, 2, and 3. These variables are related to the diagnosis and pre-planned actions required to mitigate DBAs. The applicable DBAs are assumed to occur in MODES 1, 2, and 3. In MODES 4, 5, and 6, unit conditions are such that the likelihood of an event that would require PAM instrumentation is low; therefore, the PAM instrumentation is not required to be OPERABLE in these MODES.

ACTIONS A Note has been added in the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification may be entered independently for each Function listed on Table 3.3.3-1. The Completion Time(s) of the inoperable channel(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.

INDIAN POINT 2 B 3.3.3 - 13 Revision (R2-S5) I

Remote Shutdown

.3.3.4 3.3 INSTRUMENTATION 3.3.4 Remote Shutdown

_PS hIk . *apiti LCO 3.3.4 The Remote Shutdc kIL$%+ ABLE.

APPLICABILITY: MODES 1, 2, and 3 Ts. kA?

ACTIONS

- NOTE -

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required Function 30 days Functions inoperable. to OPERABLE status.

B. Required Action and 8.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.4.2 Verify each required control circuit and transfer 24 months switch is capable of performing the intended function.

INDIAN POINT 2 3.3.4 - 1 Amendment No. (R2-S5) I

I Remote Shutdown B 3.3.4 sub. °momtro Table B 3.3.4-1 (page Remote Shutdown nstrumentz

-16 S.3 f PO gs 3IiL"?;c 1

FUNCTION/INSTRUMENT REQUIRED OR CONTROL PARAMETER NUMBER OF FUNCTIONS

1. REACTIVITY CONTROL

a. Source Range Neutron Flux (NI-5143-1). I

b. Reactor Trip and Bypass Breaker Position. 1 per breaker

c. Reactor Trip & Bypass Breaker Trip Switch; or 21 MG Set & 22 MG Set Trip Switch.

d. Seal Injection Flow 1 per RCP (FI-144, FI-143, Fl-1 16 and Fl-15)

2. REACTOR COOLANT SYSTEM PRESSURE CONTROL

a. 21 Pressurizer Backup Heater I Local/Remote transfer switch.

b. Pressurizer Pressure (P-3105-1). I

3. DECAY HEAT REMOVAL via STEAM GENERATORS

a. Hot Leg Temperature. 2 (TI-5139 for Loop 21 and TI-5141 for Loop 22)

b. Cold Leg Temperature. 2 (TI-5140 for Loop 21 and TI-5142 for Loop 22)

c. SG Pressure. 1 per SG (P1-1353, P1-1354, PI-1355 and PI-1356)

d. SG Level. 2 (LI-5001-1 for 21 SG and LI-5002-1 for 22 SG)

e. CST Level. 1

f. Atmospheric Steam Dump Valve controls. I ADV (Local nitrogen control stations in AFW Pump Building)

g. Auxiliary Feedwater Pump 21.

(Transfer switch EDC5 and breaker 1B)

INDIAN POINT 2 B 3.3.4 - 6 Revision (R2-S5) I

LOP DG Start Instrumentation 3.3.5

, 5tA#v ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.1 Restore'to OPERABLEtat 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

- NOTE - least three SBO channels Not applicable in MODE on one bus and two SBO 5 or 6. channels on the other bus.

B. Two or more SBO channels inoperable on one bus with three OPERABLE SBO channels on the other bus. I OR One SBO channel inoperable on both buses.

C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Completion Time of A or B not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />

- NOTE - D.1 Place channel in trip. 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> Not applicable in MODE 1, 2, 3 or 4.

D. One SBO channel inoperable on a required bus.

E. Two or more SBO E.1 Enter applicable Immediately channels inoperable on Condition(s) and Required both buses in MODE 1, Action(s) for all DGs 2, 3 or 4. inoperable.

OR Required Action and Completion Time of D not met.

INDIAN POINT 2 3.3.5 - 2 Amendment No. (R2-S5) I

I

((go6/ (-.- P 4

04.S LOP DG Start Instrumentation t~~~i-(\tt,)S~~~~~~s 3.3.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.1 Restore channel to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

- NOTE - OPERABLE status.

Separate Condition entry is allowed for each bus.

F. One Undervoltage Function channel inoperable.

G. G.1 Place channel in trip. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />

- NOTE -

Separate Condition entry is allowed for each bus.

One Degraded Voltage Function channel inoperable.

H. Required Action and H.1 Enter applicable Immediately associated Completion Condition(s) and Required Time of Condition F or G Action(s) for the I not met. associated DG(s) made OR inoperable by LOP DG start instrumentation.

Two Undervoltage Function channels inoperable on one or more buses.

OR Two Degraded Voltage Function channels inoperable on one or more buses.

INDIAN POINT 2 3.3.5 - 3 Amendment No. (R2-S5) I

I Containment Purge System and Pressure Relief Line Isolation Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Containment Purge System and Pressure Relief Line Isolation Instrumentation LCO 3.3.6 The Containment Purge System and Pressure Relief Line solation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3 and 4, During movement of recently irradiated fuel assemblies within containment.

ACTIONS

-NOTE -

Separate Condition entry is allowed for each Function. __

CONDITION REQUIRED ACTION COMPLETION TIME

-A. One radiation monitoring A.1 Restore the affected 7 days channel inoperable. channel to OPERABLE status.

B. One or both B.1 Enter applicable Immediately automatic actuation Conditions and Required trains inoperable. Actions of LCO 3.6.3, "Containment Isolation k OR Valves," for containment purge system and Two radiation monitoring pressure relief line channels inoperable. isolation valves made inoperable by isolation OR instrumentation.

Required Action and associated Completion Time of Condition A not met.

INDIAN POINT 2 3.3.6 - 1 Amendment No. (R3-S6) I

Containment Purge System and Pressure Relief Line Isolation Instrumentation B 3.3.6 BASES SURVEILLANCE REQUIREMENTS (continued)

Agreement criteria are determined by the unit staff, based on a combination of the channel instrument uncertainties, including ;indication and readability. If a channel is outside the criteria, it may be an indication that the sensor or the signal processing equipment has drifted outside its limit. A CHANNEL CHECK for a single channel instrument is satisfied by verification that the sensor or the signal processing equipment has not drifted outside its limit.

The Frequency is based on operating experience that demonstrates channel failure is rare. The CHANNEL CHECK supplements less formal, but more frequent, checks of channels during normal operational use of the displays associated with the LCO required channels.

SR 3.3.6.2 SR 3.3.6.2 is the performai \ < , TEST. This test is performed every 31 day -.ST BASIS. The Surveillance interval is ac 'a'lntreliability and industry operating experient 4 U SR 3.3.6.3 SR 3.3.6.3 is the performance of a MASTER RELAY TEST. The MASTER RELAY TEST is the energizing of the master relay and erifying contact t operation. Upon 6iaster relay contact operation, a low voltagbs injected to the slave relacoil. This voltage is insufficient to pick up the slabe relay, but large enoug To demonstrate signal path continuity. This testisperformed every 31 days on a STAGGERED TEST BASIS. The Surveillance interval is acceptable based on instrument reliability and industry operating experience.

SR 3.3.6.4 A COT is performed every 31 days on each radiation monitoring channel to ensure the entire channel will perform the intended Function. A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL OPERATIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specifications tests at least once per refueling interval with applicable extensions. This test verifies the capability of the instrumentation to provide INDIAN POINT 2 B 3.3.6 - 7 Revision (R2-S5) I

CRVS Actuation Instrumentation

,3.3.7 3.3 INSTRUMENTATION 3.3.7 Control Room Ventilation System (CRVS) Actuation Instrumentation LCO 3.3.7 The CRVS actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.

APPLICABILITY: MODES 1,2, 3 and 4, During movement of recently irradiated fuel assemblies. -

ftV'>

A-ACTIONS ~.%Lk

-NOTE -

Separate Condition entry is allowed for each Function. _ ____ -_--_1--

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Place one CRVS train in 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />sv inoperable. pressurization mode.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time for Condition A not AND met.

1B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C. Required Action and C.1 Suspend movement of Immediately associated Completion recently irradiated fuel Time for Condition A not assemblies.

met during movement of recently irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS

-NOTE-Refer to Table 3.3.7-1 to determine which SRs apply for each CRVS Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> INDIAN POINT 2 3.3.7 - 1 Amendment No. (R3-S6) I

&O NUREG-1431 Markup Inserts ITS SECTION 3.3.7 - Control Room Ventilation System CRVSJ Actuation Instrumentation INSERT: 3.3.7-3-01:

In MODES 1, 2, 3 and 4, automatic CRVS actuation Is needed to demonstrate compliance with 10 CFR 50.67, Accident Source Term (Ref. 1). OPERABILITY of CRVS Isolation Instrumentation ensures that exposures following each event analyzed for Modes 1, 2, 3 and 4 are significantly below the required limits (Ref. 2).

In MODES 5 and 6 without fuel handling in progress, automatic CRVS actuation need not be OPERABLE because the potential for radioactive releases is minimized and operator action is sufficient to ensure post accident offsite dos re niaintained within the limits of Reference 1.

During movem toJty irradiated fuel assemblies either In containment or te fu2handling. automatic CRVS actuation must be Qb OPERABLE to cope with the release from a fuel handling accident Involving 6gaffe recently Irradiated fuel. The CRVS Is only required to be OPERABLE during fuel handling involving iarecently irradiated fuel (i.e., fuel that has occupied part of a critical reactor core within the previous 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />), due to radioactive decay.

INSERT: B 3.3.7 02:

Condition A applies if either Air Intake Radiation Monitor (R-38-1 or R-38-2),

manual initiation or the Input from ESFAS Train A or Train B to CRVS Is inoperable. If the automatic CRVS start signal from either Function Is inopera 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Is allowed to restore the Function consistent with the limit a 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for loss of CRVS Fun ion alrowed by I CO 3.7.10.

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Actuation Instrumentation.

3.3.7

0. 3.VA>3.

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. a::7,.eI' WOG STS 3.3.7- 2 WRev. 2, 04/30/01

I CREFS Actuation Instrumentation B 3.3.7 BASES ACTIONS (continued) g.1anC'2 e Condition (applies when the Required Action and associated Completion Time for Condition AChave not been met and the unit Is in MODE 1, 2, 3, or 4. The unit must be brought to a MODE in which the LCO requirements are not applicable. To achieve this status, the unit must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.

Condition iNapplies Ye the Required ActiosnFd associated ~

Completion Timef Cnion T hatbeenmet when recegy irradiated fu semblies are biv d. Movement of~irey3t<<f irradiated Iel assemblies must suspended immediatel reduce the risk o ccidents that &ould uire CREFS>actuation.

Co ion E applies when the Required Action and a oated dmpletion Time for Condition A or B have not bin met in MODE 5 or 6.

Actions must be initiated to restore the moper e trains) to OPERABLE status immediately to ensure adequate isolion capability in the event of awaste gas decay tank rupture. ~5e SURVEILLANCE e as een ade to the a le to clarify that Table 3.3.7-1 REQUIREMENTS determ'n to which CREF SActuatio tions i;3 X g 3.3.7.1

~~SR RI

,31 -

A 5Performance of the CHANNEL CHECK once every ( hours ensures that 3.32 - a gross failure of instrumentation has not occurred, that inormaly a comparson of the parameter in ed on one chanto similar paramete other channels. It Is sed on the assum on tha instrument c nels monitoring the saparameter should ad approxim y the same value. Sign' ant deviations bet en the two instru nt channels could be an ication of excessive strument dri 2 In e oft nels or of soehin s A CHANNEL CHECK will detect gross channel failure; thus, It Is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

WOG STS 8 3.3.7- 5 Rev. 2, 04/30/01

NUREG-1431 Markup Inserts ITS SECTION 3.3.7 - Control Room Ventilation System (CRVS]

Actuation Instrumentation INSERT: B5 3..7 - 5 01M Surveillance Requirements pply to the Air Intake Radiation Monitors (R 1 and R-38-2) and manua n tjatior ? Surveillance Requirements for the ESFAS Safety Injection F ncti6(s t ate CRVS are specified In LCO 3.3.2. 1 INSERT: B 3.3.7-5 - 02:

A CHANNEL CHECK for a single channel instrument Is satisfied by verification that the sensor or the signal processing equipment has not drifted outside its limit.

Indian Point 2 Improved Technical Specification Conversion Project A.3 3.3.7: Control Room Ventilation System CRVS) Actuation Instrumentation Rev.1 Category Administrative: No Technical Changes DOC Summary:

Clarifies the requirement that the control room ventilation system operable includes the requirement for automatic actuation on each of the following: 1) Manual nit'ion, 2) Control Building air Intake Radiation Monitor; 3) Control Room air Intake Radiation r; and 4) Safety injeoton signal. These or a high radiation signal based on the CTS surveillance requirement for periodic verification that the control room ventilation system actuates on a safety injection signal or a high radiation signal.

Description of Change CTS 3.3.H.1 requires that the control room ventilation system, including an implied requirement for actuation instrumentation, be operable. CTS 4.4.E.4.b, which is a surveillance that verifies that CTS 3.3.H.1 is met, requires periodic verification that the control room ventilation system actuates on a safety injection signal or a high radiation signal. This creates an implicit requirement that Clarifies the requirement that the control room ventilation system be operable includes the requirement for automatic actuation on each of the following: 1) Manual Initiation, 2) Control Building air Intake Radiation Monitor;

3) Control Room air Intake Radiation Manager; and 4) Safety injection signal, as described in the UFSAR.

ITS LCO 3.3.7 maintains the existing requirement for Operability of the control room ventilation system actuation instrumentation including: 1) Manual Initiation, 2) Control Building air Intake Radiation Monitor;

3) Control Room air Intake Radiation Manager; and 4) Safety injection signal.

Justification for Change Adding explicit requirements for CRVS actuation instrumentation is an administrative change with no adverse impact of safety because it is an explicit statement of a reasonable interpretation of the existing requirement.

A4 3.3,7: Control Room Ventilation System CRVS) Actuation Instrumentation rev. o Category Administrative: No Technical Changes DOC Summay Clarifies that the requirement that the reactor be brought "to a hot shutdown condition utilizing normal operating procedures' if requirements for the control room ventilation system are not met is equivalent to the ITS requirement that the reactor be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Description of Chanae CTS 3.3.H.1 specifies that the reactor shall be brought to a hot shutdown condition (i.e., Mode 3) utilizing normal operating procedures if requirements for the control room ventilation system are not met within the specified completion time.

Under the same conditions, ITS LCO 3.3.7, Required Action B.1, requires that the reactor be in Mode 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

Justification for Change This change is needed and is acceptable because it is a reasonable interpretation of the existing requirement and the allowed Completion Time is reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

09-Jul-03 Revision 2 - Supplement 5

Indian Point 2 Improved Technical Specification Conversion Project M.1 3.3.7: Control Room Ventilation System (CRVS) Actuation Instrumentation Rev.I Category More Restrictive:

DOC Summary:

Reduces the allowable out of serv for loss of CRVS safety function, including actuation instrumentation, from 3.5 days toth 2hou Description of Change CTS 3.3.H.1 requires that control room air filtration (i.e., CRVS), including an implied requirement for actuation instrumentation, is operable. There is no requirement for redundancy for eitherthe CRVS or the actuation instrumentation. Likewise, CTS 3.3.H.2 establishes requirements when the CRVS is not Operable but does not distinguish between a loss of CRVS redundancy and a loss of CRVS function.

Therefore, CTS 3.3.H.2 specifies no Required Actions for a loss of CRVS redundancy and provides an allowable out of service time (AOT) of 3.5 days for a loss of CRVS function.

ITS LCO 3.7.10 requires that two CRVS trains are Operable to provide redundant CRVS capability (See ITS 3.7.10, DOC M.1); however, ITS LCO 3.3.7, maintains the requirement for a single train of CRVS actuation instrumentation consistent with the P2 design.

ITS LCO 3.3.7, Required Action A.1, establishes a new AOT of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when one or both CRVS actuation instrumentation functions are not Operable.

Justification for Chanae This change is acceptable because it does not introduce any operation which is un-analyzed while requiring a more restrictive AOT for a loss of CRVS function. Therefore, this change has no significant adverse impact on safety.

M.2 3.3.7: Control Room Ventilation System (CRVS) Actuation Instrumentation R Category More Restrictive:

DOC Summary Eliminates an allowance permitting the reactor to remain in hot shutdown condition (Mode 3) for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to initiating plant cooldown (to Mode 5) when the control room ventilation system actuation instrumentation is not restored to an operable status within the time period specified.

Description of Change CTS 3.3.H.2 specifies that if the Control Room Ventilation System, including actuation instrumentation, is not restored to an operable status within the time period specified, then the reactor shall be brought to the hot standby condition utilizing normal operating procedures. Thereafter, CTS 3.3.H.2 allows an additional 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to restore CRVS before the reactor must be placed in cold shutdown (i.e., Mode 5).

ITS LCO 3.3.7, Required Action B.1, maintains the requirement to be in hot shutdown condition utilizing normal operating procedures (See ITS 3.3.7, DOC A.3); however, Required Action B.2, requires that the plant be in Mode 5 in 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (i.e., the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> allowable out of service time in Mode 3 is deleted).

Justification for Change This change is needed and is acceptable because the plant must be placed outside the applicable Mode promptly when LCO requirements are not met. Therefore, this change has no adverse impact on safety.

09-Jul-03 Revision 2 - Supplement 5

CRVS B 3.7.10 BASES BACKGROUND (continued)

CRVS Train A is powered from safeguards power train 2A/3A (MCC-26C) and is supported by DG-22. CRVS Train A includes:

Filter booster fan (CCRBF-21) associated isolation damper (CCRF-1); HEPA/adsorber filter unit bypass damper (CCRA1);

Toilet area exhaust fan (K-8) isolation damper (CCRD4); and, air

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UnCRVS Train B is powered from safeguards power train 6A (MCC-26B) and is supported by DG-23. CRVS Train B includes:

filter booster fan (CCRF-22) and associated isolation damper

/f2JG, - . , (CCRG-1); HEPA/adsorber filter unit bypass damper (CCRA2);

44"6 v i toilet area exhaust fan (K-8) isolation damper (CCRD5); and, air XAA conditioning unit bypass fan (CCRCF-22).

The HEPA/adsorber filter unit is considered a passive component and is common to both units.

APPLICABLE At Indian Point 2, radiological consequence analyses have been revised to SAFETY demonstrate compliance with 10 CFR 50.67, Accident Source Term ANALYSES (References 2, 3 and 4). 10 CFR 50.67 requires that accident analyses show adequate radiation protection is provided to permit access to and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent for the duration of the accident.

The re-analysis of the large-break LOCA, Steam Line Break and Steam Generator Tube Rupture accidents performed to demonstrate compliance with 10 CFR 50.67 modeled the control room air filtration system in the pressurization mode of operation (mode 2). The analysis assumed 1800 cfm of outside air is drawn through HEPA and charcoal filters via booster fans and discharged into the control room envelope. The design of the control room ventilation system in the pressurization mode (mode 2) is to bring in approximately 2000 cfm of outside air and direct it through the HEPA/charcoal filters into the control room. The analysis also assumes 700 cfm of unfiltered leakage into the control room. The dose to personnel is affected more by the inleakage of unfiltered air than by the intake of filtered air, and the calculated dose to an operator in the control room is more than 20 percent below the acceptance criteria in 10 CFR 50.67.

In MODES 5 and 6 without fuel handling in progress, CRVS need not be OPERABLE because the potential for radioactive releases is minimized and operator action is sufficient to ensure post accident offsite doses are maintained within the limits of Reference 3.

INDIAN PONT2 B 3.7.10 7 -3 Revision (R2-S4)