ML17136A360

Technical Specification Amendment Nos. 285/264

ML17136A360
Person / Time
Site:	Mcguire, McGuire
Issue date:	05/03/2017
From:	Duke Energy Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML17136A360 (18)

Text

Duke Energy Date: 5l3l201Z Distribution:

Document Transmittal # : TR-NUC-MC-QQ596Z

1. Boyer, Robert P DOCUMENTTRANSMITTALFORM Purpose : ~

2. Gardner, Troy R

3. Howell, Pamela T Released By:

4.

Mc Ginnis, Vickie L Facility: MCGUIRE NUCLEAR STATION Duke Eneray

5. OPS TRNG MGR.

SUBJECT 13225 ttagel'.i Eeccv Rgad

6. QATS-Te!:;h SRe!:; - Amendment NQ~. 28Sl264 DQgimeot Mi!Di!gemeot

7.

RESIDENT NRC INSPECT MG02DM

8.

SERV BLDG FILE ROOM -

l::luoteriville, Ht zsozs

9. U S NUC REG WASHINGTON, DC,/

HHSDCRM@duke-eoergy,!:;Qffi

10. USNRC

11. WESTlNGHOUSE ELECTRIC CO LLC Page 1of1 Document ID 1

2 3

4 5

6 7

8 9

10 11 LICN - MC - MNS-TS-3.4.6 - 001 - ISSUED FYIIE FYIIE FYIIE FYIIE R&AIE FYIIE PRINT I LP FYIIE R&AIE R&AIE R&AIE LICN - MC - MNS-TS-3.4.7 - 001 - ISSUED FYIIE FYIIE FYIIE FYIIE R&AIE FYIIE PRINTILP FYIIE R&AIE R&AIE R&AIE LICN - MC - MNS-TS-3.4.8 - 001 - ISSUED FYIIE FYIIE FYIIE FYIIE R&AIE FYIIE PRINTILP FYIIE R&AIE R&AIE R&AIE LICN - MC - MNS-TS-3.S.2 - 001 - ISSUED FYIIE FYIIE FYIIE FYIIE R&AIE FYIIE PRINT I LP FYIIE R&AIE R&AIE R&AIE LICN - MC - MNS-TS-3.6.6 - 002 - ISSUED FYIIE FYIIE FYIIE FYIIE R&AIE FYIIE PRINTILP FYIIE R&AIE R&AIE R&AIE LICN - MC - MNS-TS-3.9.S - 001 - ISSUED FYIIE FYIIE FYIIE FYIIE R&AIE FYIIE PRINTILP FYIIE R&AIE R&AIE R&AIE LICN - MC - MNS-TS-3.9.6 - 001 - ISSUED FYIIE FYIIE FYIIE FYIIE R&AIE FYIIE PRINTILP FYIIE R&AIE R&AIE R&AIE Remarks:

RCS Loops - MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops-MODE 4 LCO 3.4.6 Two loops consisting of any combination of RCS loops and residual heat removal (RHR) loops shall be OPERABLE, and one loop shall be in operation.

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NOTES----------------------------------------

1.

All reactor coolant pumps (RCPs) and RHR pumps may be de-energized 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 introduction of coolant into the RCS with boron concentration less than required to meet the SOM of LCO 3.1.1 and maintain Keff <

0.99; and

b.

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

2.

No RCP shall be started with any RCS cold leg temperature~ 300°F unless:

a.

Secondary side water temperature of each steam generator (SG) is~ 50°F above each of the RCS cold leg temperatures, or

b.

Pressurizer water level is < 92% (1600 ft3).

APPLICABILITY:

MODE 4.

ACTIONS A.

CONDITION One RCS loop OPERABLE.

Two RHR loops inoperable.

McGuire Units 1 and 2 A.1 REQUIRED ACTION Initiate action to restore a second loop to OPERABLE status.

COMPLETION TIME Immediately (continued) 3.4.6-1 Amendment Nos. 2161197

RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS (continued)

CONDITION REQUIRED ACTION B.

One RHR loop B.1 Be in MODE 5.

OPERABLE.

AND ALL RCS loops inoperable.

C.

Both required RCS or C. 1 Suspend operations that RHR loops inoperable.

would cause introduction of coolant into the RCS with OR boron concentration less than required to meet the No RCS or RHR loop in SOM of LCO 3.1.1 and operation.

maintain Keff < 0.99.

AND C.2 Initiate action to restore one loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.6.1 Verify one RHR or RCS loop is in operation.

SR 3.4.6.2 Verify SG secondary side water levels are~ 12% narrow range for required RCS loops.

SR 3.4.6.3 Verify correct breaker alignment and indicated power are available to the required pump that is not in operation.

COMPLETION TIME 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program McGuire Units 1 and 2 3.4.6-2 Amendment Nos. 261/241

RCS Loops - MODE 4 3.4.6 SURVEILLANCE REQUIREMENTS continued SURVEILLANCE SR 3. 4. 6. 4

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

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE4.

Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water.

FREQUENCY In accordance with the Surveillance Frequency Control Pro ram McGuire Units 1 and 2 3.4.6-3 Amendment Nos. 285/264

RCS Loops - MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops-MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) loop shall be OPERABLE and in operation, and either:

a.

One additional RHR loop shall be OPERABLE; or

b.

The secondary side water level of at least two steam generators (SGs) shall be~ 12% narrow range.

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NOTES----------------------------------

1.

The RHR pump of the loop in operation may be de-energized 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 introduction of coolant into the RCS with boron concentration less than required to meet the SOM of LCO 3.1.1; and

b.

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

2.

One required RHR loop may be inoperable 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 provided that the other RHR loop is OPERABLE and in operation.

3.

No reactor coolant pump shall be started with one or more RCS cold leg temperatures~ 300°F unless:

a.

Secondary side water temperature of each SG is~ 50°F above each of the RCS cold leg temperatures, or

b.

Pressurizer water level is< 92% (1600 ft3).

4.

All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

APPLICABILITY:

MODE 5 with RCS loops filled.

McGuire Units 1 and 2 3.4.7-1 Amendment Nos. 216 I 197

ACTIONS CONDITION A.

One RHR loop A.1 inoperable.

AND OR Required SGs secondary side water A.2 levels not within limits.

B.

Required RHR loops B.1 inoperable.

OR No RHR loop in operation.

AND B.2 McGuire Units 1 and 2 RCS Loops - MODE 5, Loops Filled 3.4.7 REQUIRED ACTION COMPLETION TIME Initiate action to restore a Immediately second RHR loop to OPERABLE status.

Initiate action to restore Immediately required SG secondary side water levels to within limits.

Suspend operations that Immediately would cause introduction of coolant into the RCS with boron concentration less than required to meet SOM of LCO 3.1.1.

Immediately Initiate action to restore one RHR loop to OPERABLE status and operation.

3.4.7-2 Amendment Nos. 216 I 197

RCS Loops - MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR loop is in operation.

In accordance with the Surveillance Frequency Control ProQram SR 3.4.7.2 Verify SG secondary side water level is ~ 12% narrow In accordance with range in required SGs.

the Surveillance Frequency Control Program SR 3.4.7.3 Verify correct breaker alignment and indicated power are In accordance with available to the required RHR pump that is not in the Surveillance operation.

Frequency Control Program SR 3.4.7.4 Verify required RHR loop locations susceptible to gas In accordance with accumulation are sufficiently filled with water.

the Surveillance Frequency Control ProQram McGuire Units 1 and 2 3.4.7-3 Amendment Nos. 285 I 264

RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops-MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.

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NOTES------------------------------------------

1.

All RHR pumps may be de-energized for~ 15 minutes when switching from one loop to another provided:

a.

The core outlet temperature is maintained at least 10°F below saturation temperature.

b.

No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet the SOM of LCO 3.1.1; and

c.

No draining operations to further reduce the RCS water volume are permitted.

2.

One RHR loop may be inoperable for~ 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

APPLICABILITY:

MODE 5 with RCS loops not filled.

ACTIONS A.

CONDITION One RHR loop inoperable.

McGuire Units 1 and 2 REQUIRED ACTION A.1 Initiate action to restore RHR loop to OPERABLE status.

COMPLETION TIME Immediately (continued) 3.4.8-1 Amendment Nos. 216 I 197

RCS Loops - MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

Required RHR loops inoperable.

8.1 Suspend operations that Immediately No RHR loop in operation.

SURVEILLANCE REQUIREMENTS would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of LCO 3.1.1.

B.2 Initiate action to restore one RHR loop to OPERABLE status and operation.

SURVEILLANCE SR 3.4.8.1 Verify one RHR loop is in operation.

SR 3.4.8.2 Verify correct breaker alignment and indicated power are available to the required RHR pump that is not in operation.

SR 3.4.8.3 Verify RHR loop locations susceptible to gas accumulation are sufficiently filled with water.

Immediately FREQUENCY In accordance with the Surveillance Frequency Control Proqram In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program McGuire Units 1 and 2 3.4.8-2 Amendment Nos. 285 I 264 j

3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS-Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ECCS -

Operating 3.5.2

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

1 n MODE 3, both safety injection (SI) pump or RHR pump flow paths may be isolated by closing the isolation valves for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform pressure isolation valve testing per SR 3.4.14.1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more trains A.1 Restore train(s) to 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s*t inoperable.

OPERABLE status.

AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available.

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 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 />

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

• ' A' Train ECCS is allowed to be inoperable for a total of 14 days for the correction of a degraded condition on the 'A' Train NSWS supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 1, 2017, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the 'A' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is perfomied on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures and Commitments as described in MNS LAR submittal correspondence letter MNS-16-005.

t For Unit 1 only, the Completion Time for Required Action A.1 may be extended one-time to 10 days during the 1A RHR AHU repair evolution and is contingent on meeting the compensatory measures described in MNS correspondence letter MNS-15-093. Upon completion of the repair evolution, this footnote is no longer applicable and will expire on March 31, 2016.

McGuire Units 1 and 2 3.5.2-1 Amendment Nos. 282/261

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.5.2.1 Verify the following valves are in the listed position with power to the valve operator removed.

Number Position Function Nl162A Open SI Cold Leg Injection Nl121A Closed SI Hot Leg Injection Nl1528 Closed SI Hot Leg Injection Nl1838 Closed RHR Hot Leg Injection N1173A Open RHR Cold Leg Injection Nl178B Open RHR Cold Leg Injection Nl1008 Open SI Pump RWST Suction FW27A Open RHR/RWST Suction Nl147A Open SI Pump Mini-Flow SR 3. 5. 2. 2

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NO TE-------------------------------------

N ot required to be met for system vent flow paths opened under administrative control.

Verify each ECCS manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct osition.

SR 3.5.2.3 Verify ECCS locations susceptible to gas accumulation are sufficiently filled with water.

ECCS -

Operating 3.5.2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Pro ram In accordance with the Surveillance Frequency Control Pro ram (continued)

McGuire Units 1 and 2 3.5.2-2 Amendment Nos. 285/264

SURVEILLANCE REQUIREMENTS (continued)

SR 3.5.2.4 SR 3.5.2.5 SR 3.5.2.6 SR 3.5.2.7 SURVEILLANCE Verify each ECCS pump's developed head at the test flow point is greater than or equal to the required developed head.

Verify each ECCS automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

Verify each ECCS pump starts automatically on an actual or simulated actuation signal.

Verify, for each ECCS throttle valve listed below, each position stop is in the correct position.

Centrifugal Charging Pump Injection Throttle Valve Number Nl480 Nl481 Nl482 Nl483 Safety Injection Pump Throttle Valve Number Nl488 Nl489 Nl490 Nl491 SR 3.5.2.8 Verify, by visual inspection, that the ECCS containment sump strainer assembly and the associated enclosure are not restricted by debris and show no evidence of structural distress or abnormal corrosion.

ECCS -

Operating 3.5.2 FREQUENCY In accordance with the I nservice Testing Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control ProQram In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program McGuire Units 1 and 2 3.5.2-3 Amendment Nos. 261/241

Containment Spray System 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment Spray System LCO 3.6.6 Two containment spray trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One containment spray A.1 Restore containment spray 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s*

train inoperable.

train to OPERABLE status.

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 not met.

AND B.2 Be in MODE 5.

84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />

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

• 'A' Train Containment Spray is allowed to be inoperable for a total of 14 days for the correction of a degraded condition on the 'A' Train supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 1, 2017, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the 'A' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures and Commitments described in MNS LAR submittal correspondence letter MNS-16-005.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3. 6. 6.1

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

Not required to be met for system vent flow paths opened under administrative control.

Verify each containment spray manual and power operated valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.

FREQUENCY In accordance with the Surveillance Frequency Control Pro ram (continued)

McGuire Units 1 and 2 3.6.6-1 Amendment Nos. 285/264

Containment Spray System 3.6.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.6.2 Verify each containment spray pump's developed head at In accordance with the flow test point is greater than or equal to the required the lnservice developed head.

Testing Program SR 3.6.6.3 Not Used Not Used SR 3.6.6.4 Not Used Not Used SR 3.6.6.5 Verify that each spray pump is de-energized and In accordance with prevented from starting upon receipt of a terminate signal the Surveillance and is allowed to manually start upon receipt of a start Frequency Control permissive from the Containment Pressure Control Program System (CPCS).

SR 3.6.6.6 Verify that each spray pump discharge valve closes or is In accordance with prevented from opening upon receipt of a terminate the Surveillance signal and is allowed to manually open upon receipt of a Frequency Control start permissive from the Containment Pressure Control Program System (CPCS).

SR 3.6.6.7 Verify each spray nozzle is unobstructed.

Following activities which could result in nozzle blockage SR 3.6.6.8 Verify containment spray locations susceptible to gas In accordance with accumulation are sufficiently filled with water.

the Surveillance Frequency control ProQram McGuire Units 1 and 2 3.6.6-2 Amendment Nos. 285/264

RHR and Coolant Circulation - High Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation-High Water Level LCO 3.9.5 APPLICABILITY:

ACTIONS One RHR loop shall be OPERABLE and in operation.

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

The required RHR loop may be removed from operation 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 no operations are permitted that would cause introduction of coolant into the Reactor Coolant System with boron concentration less than required to meet the minimum required boron concentration of LCO 3.9.1.

MODE 6 with the water level ~ 23 ft above the top of reactor vessel flange.

CONDITION REQUIRED ACTION COMPLETION TIME A

RHR loop requirements A.1 Suspend operations that.

• Immediately not met.

would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1 AND A.2 Suspend loading irradiated Immediately fuel assemblies in the core.

AND A.3 Initiate action to satisfy Immediately RHR loop requirements.

AND (continued)

McGuire Units 1 and 2 3.9.5-1 Amendment No. 216/197

RHR and Coolant Circulation - High Water Level 3.9.5 CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.4 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.9.5.1 Verify one RHR loop is in operation and circulating reactor coolant at a flow rate of ~ 1000 gpm and RCS temperature is ~ 140°F.

SR 3.9.5.2 Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water.

FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program McGuire Units 1 and 2 3.9.5-2 Amendment No. 285/264

3.9 REFUELING OPERATIONS RHR and Coolant Circulation - Low Water Level 3.9.6 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

APPLICABILITY:

MODE 6 with the water level< 23 ft above the top of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE.

OPERABLE status.

OR A.2 Initiate action to establish Immediately

~ 23 ft of water above the top of reactor vessel flange.

B.

No RHR loop in B.1 Suspend operations that Immediately operation.

would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

AND (continued)

McGuire Units 1 and 2 3.9.6-1 Amendment No. 216/197

RHR and Coolant Circulation - Low Water Level 3.9.6 CONDITION REQUIRED ACTION COMPLETION TIME

8.

(continued) 8.2 Initiate action to restore Immediately one RHR loop to operation.

8.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.9.6.1 Verify one RHR loop is in operation and circulating reactor coolant at a flow rate of ~ 1000 gpm and RCS temperature is ~ 140°F.

SR 3.9.6.2 Verify correct breaker alignment and indicated power available to the required RHR pump that is not in operation.

SR 3.9.6.3 Verify RHR loop locations susceptible to gas accumulation are sufficiently filled with water.

McGuire Units 1 and 2 3.9.6-2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 285/264