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

Date: 5l3l201Z Distribution: Duke Energy Document Transmittal # : TR-NUC-MC-QQ596Z

1. Boyer, Robert P

2. Gardner, Troy R DOCUMENTTRANSMITTALFORM Purpose : ~

Released By:

3. Howell, Pamela T Facility: MCGUIRE NUCLEAR STATION Duke Eneray

4. Mc Ginnis, Vickie L SUBJECT 13225 ttagel'.i Eeccv Rgad

5. OPS TRNG MGR.

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

6. QATS-

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 FYII E 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 FYII E 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 FYII E 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 FYII E 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 ft 3).

APPLICABILITY : MODE 4 .

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RCS loop A.1 Initiate action to restore a Immediately OPERABLE. second loop to OPERABLE status.

Two RHR loops inoperable.

(continued)

McGuire Units 1 and 2 3.4.6-1 Amendment Nos. 2161197

RCS Loops - MODE 4 3.4 .6 SURVEILLANCE REQUIREMENTS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One RHR loop B.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 /> OPERABLE.

AND ALL RCS loops inoperable.

C. Both required RCS or C. 1 Suspend operations that Immediately 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 Immediately one loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6 .1 Verify one RHR or RCS loop is in operation . In accordance with the Surveillance Frequency Control Program SR 3.4.6.2 Verify SG secondary side water levels are~ 12% narrow In accordance with range for required RCS loops. the Surveillance Frequency Control Program SR 3.4.6.3 Verify correct breaker alignment and indicated power are In accordance with available to the required pump that is not in operation . 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 FREQUENCY SR 3. 4. 6. 4 ---------------------------------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 In accordance with accumulation are sufficiently filled with water. 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 ft 3) .

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

RCS Loops - MODE 5, Loops Filled 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop A.1 Initiate action to restore a Immediately inoperable. second RHR loop to OPERABLE status.

AND OR Required SGs secondary side water A.2 Initiate action to restore Immediately levels not within limits. required SG secondary side water levels to within limits.

B. Required RHR loops B.1 Suspend operations that Immediately inoperable. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet SOM No RHR loop in of LCO 3.1.1 .

operation .

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

McGuire Units 1 and 2 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 CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop A.1 Initiate action to restore Immediately inoperable. RHR loop to OPERABLE status.

(continued)

McGuire Units 1 and 2 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 8.1 Suspend operations that Immediately inoperable. would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM No RHR loop in of LCO 3.1.1 .

operation .

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR loop is in operation . In accordance with the Surveillance Frequency Control Proqram SR 3.4.8.2 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 3.4.8.3 Verify RHR loop locations susceptible to gas In accordance with accumulation are sufficiently filled with water. the Surveillance Frequency Control Program McGuire Units 1 and 2 3.4 .8-2 Amendment Nos. 285 I 264

- - - _ _ _ _ __j

ECCS - Operating 3.5.2 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.

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

1n 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

ECCS - Operating 3.5.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify the following valves are in the listed position with In accordance with power to the valve operator removed . the Surveillance Frequency Control Number Position Function Program 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 ------------------------------NO TE-------------------------------------

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

Verify each ECCS manual, power operated , and In accordance with automatic valve in the flow path , that is not locked , the Surveillance sealed , or otherwise secured in position , is in the correct Frequency Control osition. Pro ram SR 3.5.2.3 Verify ECCS locations susceptible to gas accumulation In accordance with are sufficiently filled with water. the Surveillance Frequency Control Pro ram (continued)

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

ECCS - Operating 3.5 .2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.4 Verify each ECCS pump's developed head at the test In accordance with flow point is greater than or equal to the required the Inservice developed head . Testing Program SR 3.5.2 .5 Verify each ECCS automatic valve in the flow path that is In accordance with not locked, sealed , or otherwise secured in position, the Surveillance actuates to the correct position on an actual or simulated Frequency Control actuation signal . Program SR 3.5.2.6 Verify each ECCS pump starts automatically on an actual In accordance with or simulated actuation signal. the Surveillance Frequency Control ProQram SR 3.5.2.7 Verify, for each ECCS throttle valve listed below, each In accordance with position stop is in the correct position. the Surveillance Frequency Control Centrifugal Charging Safety Injection Program Pump Injection Throttle Pump Throttle Valve Number Valve Number Nl480 Nl488 Nl481 Nl489 Nl482 Nl490 Nl483 Nl491 SR 3.5.2.8 Verify, by visual inspection, that the ECCS containment In accordance with sump strainer assembly and the associated enclosure are the Surveillance not restricted by debris and show no evidence of structural Frequency Control distress or abnormal corrosion . 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 FREQUENCY SR 3.6.6 .1 -----------------------------------NOTE--------------------------------

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

Verify each containment spray manual and power In accordance with operated valve in the flow path that is not locked, sealed , the Surveillance or otherwise secured in position is in the correct position . 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 wh ich 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 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 requ ired boron concentration of LCO 3.9.1.

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

ACTIONS 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 FREQUENCY SR 3.9.5.1 Verify one RHR loop is in operation and circulating In accordance with reactor coolant at a flow rate of ~ 1000 gpm and RCS the Surveillance temperature is ~ 140°F. Frequency Control Program SR 3.9.5.2 Verify required RHR loop locations susceptible to gas In accordance with accumulation are sufficiently filled with water. the Surveillance Frequency Control Program McGuire Units 1 and 2 3.9.5-2 Amendment No. 285/264

RHR and Coolant Circulation - Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 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 FREQUENCY SR 3.9.6.1 Verify one RHR loop is in operation and circulating In accordance with reactor coolant at a flow rate of ~ 1000 gpm and RCS the Surveillance temperature is ~ 140°F. Frequency Control Program SR 3.9.6.2 Verify correct breaker alignment and indicated power In accordance with available to the required RHR pump that is not in the Surveillance operation . Frequency Control Program SR 3.9.6.3 Verify RHR loop locations susceptible to gas In accordance with accumulation are sufficiently filled with water. the Surveillance Frequency Control Program McGuire Units 1 and 2 3.9.6-2 Amendment No. 285/264