ML050620306

R. E. Ginna, Tech Spec Pages for Amendment 88 Regarding Increased Flexibility in Mode Restraints

ML050620306
Person / Time
Site:	Ginna
Issue date:	03/01/2005
From:	NRC/NRR/DLPM
To:
References
TAC MC2310
Download: ML050620306 (18)

Text

LCO Applicability 3.0 LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or

c. When an allowance is stated in the individual value, parameter, or other Specification.

This Specification shall not prevent changes in MODES or other specified I conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to determine OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the suppon system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event. additional evaluations and limitations may be required in accordance with Specification 5.5.14, "Safety Function Determination Program (SFDP)."

If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

R.E. Ginna Nuclear Power Plant 3.0-2 Amonrlmont RR

SR Applicability

. 3.0 SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

R.E. Ginna Nuclear Power Plant 3.0-5 Ampnrrmpnt P8R

MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)

LCO 3.1.3 The MTC shall be maintained within the limits specified in the COLR.

The maximum upper limit shall be less than or equal to 5 pcm/0 F for power levels below 70% RTP and less than or equal to 0 pcm/OF at or above 70% RTP.

APPLICABILITY: MODE 1 and MODE 2 with keff 2 1.0 for the upper MTC limit, MODES 1, 2, and 3 for the lower MTC limit.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within upper A.1 Establish administrative 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit. withdrawal limits for control banks to maintain MTC within limit.

B. Required Action and B.1 Be in MODE 2 with keff 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion < 1.0.

Time of Condition A not

- met.

C. C.1

-NOTE- -NOTE-I Required Action C.1 must LCO 3.0.4.c is applicable.

be completed whenever- _

Condition C is entered.

-Conditio Re-evaluate core design Once prior to and safety analysis, and reaching the Projected end of cycle life determine that the reactor equivalent of an (EOL) MTC not within core is acceptable for 1equilibrium RTP all lower limit. continued operation. l rods out (ARO) boron concentration of 300 ppm D. Required Action and D.1 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition C not met.

R.E. Ginna Nuclear Power Plant 3.1 .3-1 Ampnrimcnt PRf

PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

-NOTE-Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. A.1 Restore required channel to 30 days

. --- ____-- - OPERABLE status.

-NOTE-Not applicable to Functions 3 and 4.

One or more Functions with one required channel inoperable.

B. Required Action and B.1 Initiate action to prepare Immediately associated Completion and submit a special report.

Time of Condition A not met.

C. C.1 Restore required channel to 7 days

-______________. OPERABLE status.

-NOTE-Only applicable to Functions 3 and 4.

One or more Functions with required channel inoperable.

R.E. Ginna Nuclear Power Plant 3.3.3-1 Amendment 88

RCS Loops - MODES 1 < 8.5% RTP, 2, and 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops - MODES 1

• 8.5% RTP, 2, and 3 LCO 3.4.E Two RCS loops shall be OPERABLE and one loop shall be in operation.

-NOTE-Both reactor coolant pumps may be de-energized in MODE 3 for

• 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:

a. No operations are permitted that would cause reduction of the RCS boron concentration; and

b. Core outlet temperature is maintained at least 10F below saturation temperature.

APPLICABILITY: MODES 1

• 8.5% RTP, MODES 2 and 3.

ACTIONS CONDITION l REQUIRED ACTION COMPLETION TIME I A. One RCS loop A.1 Verify SDM is within limits Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> inoperable. specified in the COLR.

AND A.2 Restore inoperable RCS I,2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> loop to OPERABLE status.

B. Required Action and B.1 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A not met.

R.E. Ginna Nuclear Power Plant 3.4.5-1 Amendment 88

Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)

LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

-NOTE-

1. Separate entry into Condition A is allowed for each PORV.

1 2. Separate entry into Condition C is allowed for each block valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or both PORVs A.1 Close and maintain power 1.hour OPERABLE and not to associated block valve.

capable of being automatically controlled. OR A.2 Place associated PORV in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> manual control.

B. One PORV inoperable. B.1 Close associated block 11 hour1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> valve.

AND B.2 Remove power from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated block valve.

AND B.3 Restore PORV to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.

C. One block valve C.1 Place associated PORV in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable. manual control.

AND R.E. Ginna Nuclear Power Plant 3.4.11-1 Amendment 88

LTOP System 3.4.12 ACTIONS

-NOTE-J LCO 3.0.4.b is not applicable when entering MODE 4.

CONDITION REQUIRED ACTION COMPLETION TIME A. A.1 Initiate action to verify no Si Immediately

- pump is capable of injecting

- NOTE- into the RCS.

Only applicable to LCO 3.4.12.a.

One or-more Si pumps capable of injecting into the RCS.

B. B.1 Restore required PORV to 7 days

-- _ OPERABLE status.

- NOTE -

Only applicable to LCO 3.4.1 2.a.

One required PORV inoperable in MODE 4.

C. C.1 Restore required PORV to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />

---

. OPERABLE status.

- NOTE -

Only applicable to LCO 3.4.12.a.

One required PORV inoperable in MODE 5 or MODE 6.

D. D.1 Initiate action to verify a (Immediately

-_ maximum of one SI pump is

- NOTE- capable of injecting into the Only applicable to LCO RCS.

3.4.12.b.

Two or more Si pumps capable of injecting into the RCS.

R.E. Ginna Nuclear Power Plant 3.4.1 2-2 Amendment 88

RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:

a. One containment sump A monitor (level or pump actuation);

b. Gaseous containment atmosphere radioactivity monitor; and

c. Particulate containment atmosphere radioactivity monitor.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required containment A.1.1 Perform SR 3.4.13.1. Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> sump monitor inoperable.

OR A.1.2 Verify containment air 124 hours0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br /> cooler condensate collection system is OPERABLE.

AND A.2 Restore required .30 days containment sump monitor to OPERABLE status.

B. Gaseous containment B.1 Verify particulate 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> atmosphere radioactivity containment atmosphere monitor inoperable. radiaoctivity monitor OPERABLE.

R.E. Ginna Nuclear Power Plant 3.4.15-1 Amendmpnt 88

RCS Leakage Detection Instrumentation 3.4.15 CONDITION REQUIRED ACTION COMPLETION TIME C. Particulate containment C.1 Analyze grab samples of the Once within 12 atmosphere radioactivity containment atmosphere. hours and every 12 monitor inoperable. hours thereafter OR OR Required Action and C.2 Perform SR 3.4.13.1. Once within 12 associated Completion hours and every 12 Time of Condition B not hours thereafter met.

D. Gaseous containment D.1 Restore gaseous 30 days atmosphere radioactivity containment atmosphere monitor inoperable. radioactivity monitor to OPERABLE status.

AND OR Particulate containment atmosphere radioactivity D.2 Restore particulate 30 days monitor inoperable. containment atmosphere radioactivity monitor to OPERABLE status.

E. Required Action and E.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 Conditions A, C, AND or D not met.

E.2 Be in MODE 5. 136 hours0.00157 days <br />0.0378 hours <br />2.248677e-4 weeks <br />5.1748e-5 months <br /> F. All required monitors F.1 Enter LCO 3.0.3. Immediately inoperable. I R.E. Ginna Nuclear Power Plant 3.4.1 5-2 Amendment 88

RCS Specific Activity 3.4.16 3.4 REACXOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 The specific activity of the reactor coolant shall be within limits.

APPLICABILITY: MODES 1 and 2, MODE 3 with RCS average temperature (Tavg) 2 5000 F.

ACTIONS -

CONDITION REQUIRED ACTION COMPLETION TIME A. DOSE EQUIVALENT -- NOT---

1-131 specific activity not LCO - NOTE -

I within limit. - 3._.4.c is applicable.

A.1 Verify DOSE EQUIVALENT Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1-131 within the acceptable region of Figure 3.4.16-1.

AND A.2 Restore DOSE 7 days EQUIVALENT 1-131 to within limit.

B. Required Action and B.1 Be in MODE 3 with Tavg 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> associated Completion < 500'F.

Time of Condition A not met.

OR DOSE EQUIVALENT 1-131 specific activity in the unacceptable region of Figure 3.4.16-1.

C. Gross specific activity not C.1 Be in MODE 3 with Tavg 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> within limit. < 5001F.

R.E. Ginna Nuclear Power Plant 3.4.16-1 Amendment 88

ECCS - MODE 4 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS - MODE 4 LCO 3.5.3 One ECCS train shall be OPERABLE.

APPLICABILITY: MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS residual A.1 Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable. subsystem to OPERABLE status.

B. Required ECCS Safety B.1 Injection (SI) subsystem ----------------

inoperable. - NOTE -

LCO 3.0.4.b is not I applicable.

Restore required ECCS SI 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 5. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> associated Completion Time of Condition B not met.

R.E. Ginna Nuclear Power Plant 3.5.3-1 Amendment 88

ECCS - MODE 4 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 - NOTE -

An RHR train may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned to the ECCS mode of operation.

SR 3.5.2.4 is applicable for all equipment required to In accordance with be OPERABLE. applicable SR R.E. Ginna Nuclear Power Plant 3.5.3-2 Amendment 88

Hydrogen Recombiners 3.6.7 3.6 CONTAINMENT SYSTEMS 3.6.7 Hydrogen Recombiners LCO 3.6.7 Two hydrogen recombiners shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I A. One hydrogen A.1 Restore hydrogen 30 days recombiner inoperable. recombiner to OPERABLE status.

B. Two hydrogen B.1 Verify by administrative 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> recombiners inoperable. means that the hydrogen control function is AND maintained.

Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND B.2 Restore one hydrogen 7 days recombiner to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.7.1 Perform a system functional check for each hydrogen 24 months recombiner SR 3.6.7.2 Perform CHANNEL CALIBRATION for each hydrogen 24 months recombiner actuation and control channel.

R.E. Ginna Nuclear Power Plant 3.6.7-1 Ampnrimpnt RR

ARVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Atmospheric Relief Valves (ARVs)

LCO 3.7.4 Two ARV lines shall be OPERABLE.

APPLICABILITY: MODES 1 and 2, MODE 3 with Reactor Coolant System average temperature (Tavg)

> 5000 F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME I

A. One ARV line inoperable. A.1 Restore ARV line to 7 days OPERABLE status.

B. Required Action and B.1 Be in MODE 3 with Tavg 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> associated Completion < 500'F.

Time of Condition A not met.

C. Two ARV lines C.1 Enter LCO 3.0.3. Immediately inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Perform a complete cycle of each ARV. 24 months SR 3.7.4.2 Verify one complete cycle of each ARV block valve. t24 months R.E. Ginna Nuclear Power Plant 3.7.4-1 Amendment 88

AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Two motor driven AFW (MDAFW) trains, one turbine driven AFW (TDAFW) train, and two standby AFW (SAFW) trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One TDAFW train A.1 Restore TDAFW train 7 days flowpath inoperable. flowpath to OPERABLE status.

B. One MDAFW train B.1 Restore MDAFW train to 7 days inoperable. OPERABLE status.

C. TDAFW train inoperable. C.1 OR -NOTE-LCO 3.0.4.b is not I Two MDAFW trains applicable.

inoperable.

Restore one MDAFW train , 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OR or TDAFW train flowpath to OPERABLE status.

One TDAFW train flowpath and one MDAFW train inoperable to opposite steam generators (SGs).

R.E. Ginna Nuclear Power Plant 3.7.5-1 Ampnriminnt A.Q

ARW System 3.7.5 CONDITION REQUIRED ACTION JCOMPLETION TIME D. All AFW trains to one or D.1 more SGs inoperable. -- NO ----

- NOTE -

LCO 3.0.4.b is not I applicable.

Restore one AFW train or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> TDAFW flowpath to each affected SG to OPERABLE status.

E. One SAFW train E.1 Restore SAFW train to 14 days inoperable. OPERABLE status.

F. Both SAFW trains F.1 Restore one SAFW train to 7 days inoperable. OPERABLE status..

G. Required Action and G.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, B, AND C, D, E, or F not met.

G.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 /> H. Three AFW trains and H.1 both SAFW trains ------------------

inoperable. - NOTE -

LCO 3.0.3 and all other LCO Required Actions I requiring MODE changes are suspended until one MDAFW, TDAFW. or SAFW train is restored to OPERABLE status.

-- to--rest- ,

Initiate action to restore one Immediately MDAFW, TDAFW. or SAFW I train to OPERABLE status.

R.E. Ginna Nuclear Power Plant 3.7.5-2 Ampnrlmant RR

AFW System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each AFW and SAFW manual, power operated, 31 days and automatic valve in each water flow path, and in both steam supply flow paths to the turbine driven pump, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.5.2 - NOTE -

Required to be met prior to entering MODE , for the TDAFW pump.

Verify the developed head of each AFW pump at the In accordance with flow test point is greater than or equal to the required the Inservice developed head. Testing Program SR 3.7.5.3 Verify the developed head of each SAFW pump at the In accordance with flow test point is greater than or equal to the required the Inservice developed head. Testing Program SR 3.7.5.4 Perform a complete cycle of each AFW and SAFW In accordance with motor operated suction valve from the Service Water the Inservice System, each AFW and SAFW discharge motor Testing Program operated isolation valve, and each SAFW cross-tie motor operated valve.

SR 3.7.5.5 Verify each AFW automatic valve that is not locked. 124 months sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.5.6 -NOTE-Required to be met prior to entering MODE 1 for the TDAFW pump.

Verify each AFW pump starts automatically on an 124 months actual or simulated actuation signal.

SR 3.7.5.7 Verify each SAFW train can be actuated and 124 months controlled from the control room. I R.E. Ginna Nuclear Power Plant 3.7.5-3 Amendment 88

AC Sources - MODES 1, 2, 3, and 4 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - MODES 1, 2, 3, and 4 LCO 3.8.1 The following AC electrical sources shall be OPERABLE:

a. One qualified independent offsite power circuit connected between the offsite transmission network and each of the onsite 480 V safeguards buses required by LCO 3.8.9, "Distribution Subsystems

- MODES 1, 2, 3, and 4'; and

b. Two emergency diesel generators (DGs) capable of supplying their respective onsite 480 V safeguards buses required by LCO 3.8.9.

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

ACTIONS

-NOTE-j LCO 3.0.4.b is not applicable to DGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. Offsite power to one or A.1 Declare required feature(s) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from more 480 V safeguards inoperable when its discovery of bus(es) inoperable. redundant required Condition A feature(s) is inoperable. concurrent with inoperability of redundant required feature(s)

AND A.2 Restore offsite circuit to 172 hours0.00199 days <br />0.0478 hours <br />2.843915e-4 weeks <br />6.5446e-5 months <br /> OPERABLE status.

B. One DG inoperable. B.1 Perform SR 3.8.1.1 for the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> offsite circuit.

AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND R.E. Ginna Nuclear Power Plant 3.8.1 -1 Amendment 88