Text

Proposed Technical Specification Amendment to Modify Requirements Applicable When Actions Require No Positive Reactivity Additions
	ML031630853
Person / Time
Site:	Mcguire, Catawba, McGuire
Issue date:	06/04/2003
From:	Gordon Peterson; Duke Power Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML031630853 (29)
	v • d • e

GARY R. PETERSON Vice President Catawba Nuclear Station Duke Power CNOI VP 1 4800 Concord Rd.

York, SC 29745 803 831 4251 803 831 3221 fax grpeters@duke-energy. com June 4, 2003 U.S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, D.C. 20555

Subject:

Duke Energy Corporation Catawba Nuclear Station, Units 1 and 2 Docket Numbers 50-413 and 50-414 McGuire Nuclear Station, Units 1 and 2 Docket Numbers 50-369 and 50-370 Proposed Technical Specification Amendment to Modify Requirements Applicable When Actions Require No Positive Reactivity Additions

Reference:

1) Letter from M. S. Tuckman to U.S. Nuclear Regulatory Commission dated November 20, 2002.

2) Letter from G. R. Peterson to U.S. Nuclear Regulatory Commission dated January 21, 2003.

This letter provides revised Technical Specification (TS) changes for the subject proposed TS amendment.

In References 1 and 2 Duke Energy requested an amendment to the Catawba and McGuire Nuclear Station Facility Operating Licenses and Technical Specifications (TS).

The proposed changes would revise the Required Actions requiring suspension of operations involving positive reactivity additions and various Notes that preclude reduction in boron concentration.

Recent discussions with the NRC staff have identified that certain wording in TS Task Force (TSTF) 286, revision 1 would no longer be found as acceptable.

The revised language is editorial in nature, and does not change the intent of the previous submittals.

-4 0 D www.duke-energy. com i-ftADuke tSrPowere A Duke Energy Company i

U.S. Nuclear Regulatory Commission Page 2 June 4, 2003 The items discussed in this letter and in the revised TS pages have been reviewed against the No Significant Hazards Evaluation previously submitted.

Duke has determined that the previous No Significant Hazards Evaluation still remains valid and has not been affected by any of these changes.

There are no commitments contained within this letter.

Pursuant to 10 CFR 50.91, a copy of,this letter is being sent to the appropriate state officials.

Inquiries on this matter should be directed to R. D. Hart at (803) 831-3622.

Very truly yours, G.R. Peterson RDH/s Attachments Ir

U.S. Nuclear Regulatory Commission Page 3 June 4, 2003 Gary R. Peterson affirms that he the person who subscribed his name to the foregoing statement, and that all statements and matters set forth herein are true and correct to the best of his knowledge.

Gary R. Peterson, Site Vice President Subscribed and sworn to me:

M Date Notarf Public My commission expires:

7 X

v D12-Date SEAL

U.S. Nuclear Regulatory Commission Page 4 June 4, 2003 xc (with attachments):

L.A. Reyes U.S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 E.F. Guthrie Senior Resident Inspector (CNS)

U.S. Nuclear Regulatory Commission Catawba Nuclear Station S.M. Shaeffer Senior Resident Inspector (MNS)

U.S. Nuclear Regulatory Commission McGuire Nuclear Station R.E. Martin (addressee only)

NRC Senior Project Manager (MNS/CNS)

U.S. Nuclear Regulatory Commission Mail Stop 08-G9 Washington, D.C. 20555-0001 H.J. Porter Assistant Director Department of Health and Environmental Control 2600 Bull St.

Columbia, SC 29201 Beverly 0. Hall, Section Chief Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645 I

ATTACEMENT 1 REPRINTED TECHNICAL SPECIFICATION PAGES FOR CATAWBA

RCS Loops - MODES 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops -

MODE 3 LCO 3.4.5 Three RCS loops shall be OPERABLE, and either:

a.

Three RCS loops shall be in operation when the Rod Control System is capable of rod withdrawal; or

b.

One RCS loop shall be In operation when the Rod Control System is not capable of rod withdrawal.

-~~~NOTE----

All reactor coolant pumps may be de-energized for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a.

No operations are permitted that would cause introduction of coolant into the RCS with boron concentration less than required to meet SDM of LCO 3.1.1 and maintain kff < 0.99; and

b.

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

APPLICABILITY:

MODE 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required A.1 Restore required RCS 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months RCS loop(s) inoperable.

loop(s) to OPERABLE status.

B.

Required Action and B.1 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met.

(continued)

Catawba Units I and 2 Amendment Nos.

- 3A4.5-1

RCS Loops - MODES 3 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

One or two required C.1 Restore eiequired RCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RCS loop(s) not In loop(s) to operation.

operation and Rod Control System capable OR of rod withdrawal.

C.2 De-energize all control rod 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months drive mechanisms (CRDMs).

D.

Three required RCS D.1 De-energize all CRDMs.

Immediately loops inoperable.

AND OR D.2 Suspend operations that Immediately No RCS loop in would cause introduction of operation.

coolant into the RCS with boron concentration less than required to meet SDM of LCO 3.1.1.

AND D.3 Initiate action to restore Immediately one RCS loop to OPERABLE status and operation.

Catawba Units 1 and 2 3.4.5-2 Amendment Nos.

RCS Loops - MODES 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Loops-MODE 4 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.

.a T C!rr

1.

All reactor coolant pumps (RCPs) and RHR pumps may be de-energized for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a.

No operations are permitted that would cause Introduction of coolant into the RCS wih boron concentration less than required to meet the SDM of LCO 3.1.1 and maintain ke, <

0.99; and

b.

Core outlet temperature is maintained at least 1 0°F below saturation temperature.

2.

No RCP shall be started with any RCS cold leg temperature < 285°F unless the secondary side water temperature of each steam generator (SG) is < 50°F above each of the RCS cold leg temperatures.

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.

AND Two RHR loops inoperable.

(continued)

Catawba Units 1 and 2 LCO 3.4.6

____________---------------NLJ~ I 3.4.6-1 Amendment Nos.

RCS Loops - MODES 4 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One RHR loop B.1 Be in MODE 5.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 SDM No RCS or RHR loop in of LCO 3.1.1 and maintain operation.

kff < 0.99.

AND C.2 Iniftiate 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.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.6.2 Verify SG secondary side water levels are > 12% narrow 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months range for required RCS loops.

SR 3.4.6.3 Verify correct breaker alignment and indicated power are

-7 days available to the required pump that is not in operation.

Catawba Units 1 and 2

.- C.

,1 3.4.6-2 Amendment Nos.

RCS Loops - MODES 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 efther:

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.

NOTES-

1.

The RHR pump of the loop in operation may be de-energized for

< 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 SDM 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 < 285°F unless the secondary side water temperature of each SG is < 50°F above each of the RCS cold leg temperatures.

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.

Catawba Units 1 and 2 3.4.7-1 Amendment Nos.

RCS Loops - MODES 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 SDM No RHR loop in of LCO 3.1.1.

operation.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR loop is in operation.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.7.2 Verify SG secondary side water level is > 12% narrow 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months range in required SGs.

SR 3.4.7.3 Verify correct breaker alignment and indicated power are 7 days available to the required RHR pump that is not in operation.

Catawba Units 1 and 2 3.4.7-2 Amendment Nos.

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

1. I,Irrc%

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 1 0°F below saturation temperature.

b.

No operations are permitted that would cause ntroduction of coolant into the RCS with boron concentration less than required to meet the SDM 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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)

Catawba Units 1 and 2 LCO 3.4.8

____ __---------NU~~~~~~~~

I b-_

3.4.8-1 Amendment Nos.

RCS Loops - MODES 5, Loops Not Filled 3.4.8 ACTIONS (confinued)

CONDITION REQUIRED ACTION COMPLETION TIME 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 SDM No RHR loop in of LCO 3.1.1.

operation.

AND 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.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.8.2 Verfy correct breaker alignment and indicated power are 7 days available to the required RHR pump that is not in operation.

Catawba Units I and 2

\\

3.4.8-2 Amendment Nos.

Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two Boron Dilution Mitigation System (BDMS) trains shall be OPERABLE.

=------NOTE-----

Automatic actuation of the BDMS may be blocked during core reloading until two assemblies are loaded into the core.

APPLICABILITY:

MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or both BDMS A.1.1 Suspend CORE Immediately trains inoperable.

ALTERATIONS.

AND A.1.2 Suspend operations that Immediately 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.1.3 Verify unborated water 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months source isolation valve(s) are closed and secured.

AND A.1.4 Perform SR 3.9.1.1.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR (continued)

Catawba Units 1 and 2 3.9.2-1 Amendment Nos.

RHR and Coolant Circulation - High Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Residual Heat Removal (RHR) and Coolant Circulation-High Water Level LCO 3.9.4 One RHR loop shall be OPERABLE and in operation.

The required RHR loop may be removed from operation for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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.

APPLICABILITY:

MODE 6 with the water level > 23 ft above the fop of reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

RHR loop requirements A.1 Suspend operations that Immediately not met.

would cause introducfion 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)

Catawba Units 1 and 2 3.9.4-1 Amendment Nos.

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

Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

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)

Catawba Units 1 and 2 3.9.5-1 Amendment Nos.

ATTACEMENT 2 REPRINTED TECHNICAL SPECIFICATIONS PAGES FOR MCGUIRE

RCS Loops - MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops-MODE 3 LCO 3.4.5 Three RCS loops shall be OPERABLE, and either:

a.

Three RCS loops shall be In operation when the Rod Control System is capable of rod withdrawal; or

b.

One RCS loop shall be in operation when the Rod Control System is not capable of rod withdrawal.

-NOTE-D--O-E----------

All reactor coolant pumps may be de-energized for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a.

No operations are permitted that would cause Introduction of coolant into the RCS with boron concentration less than required to meet SDM of LCO 3.1.1 and maintain Keff < 0.99; and

b.

Core outlet temperature is maintained at least 1 0°F below saturation temperature.

APPLICABILITY:

MODE 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required A.1 Restore required RCS 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months RCS loop(s) inoperable.

loop(s) to OPERABLE status.

B.

Required Action and B.1 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A not met.

(continued)

McGuire Units 1 and 2 3.4.5-1 Amendment Nos.

RCS Loops - MODE 3 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

One or two required C.1 Restore required RCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months RCS loop(s) not in loop(s) to operation.

operation and Rod Control System capable OR of rod withdrawal.

C.2 De-energize all control rod 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months drive mechanisms (CRDMs).

D.

Three required RCS D.1 De-energize all CRDMs.

Immediately loops inoperable.

AND OR D.2 Suspend operations that Immediately No RCS loop in would cause introduction of operation.

coolant into the RCS with boron concentration less than required to meet SDM of LCO 3.1.1.

AND D.3 Initiate action to restore Immediately one RCS loop to OPERABLE status and operation.

McGuire Units 1 and 2 Amendrnent Nos.

3.4.5-2

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 combinafion of RCS loops and residual heat removal (RHR) loops shall be OPERABLE, and one loop shall be in operation.

1.

All reactor coolant pumps (RCPs) and RHR pumps may be de-energized for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 SDM of LCO 3.1.1 and maintain Keff <

0.99; and

b.

Core outlet temperature is maintained at least 1 0°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).

APPLICABIUTY:

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.

AND Two RHR loops inoperable.

(continued)

McGuire Units 1 and 2 NtJ~~~~~~~~~~~~~

t:)

3.4.6-1 Amendment Nos.

RCS Loops - MODE 4 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.

One RHR loop B.1 Be in MODE 5.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 SDM 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.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.6.2 Verify SG secondary side water levels are > 12% narrow 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months range for required RCS loops.

SR 3.4.6.3 Verify correct breaker alignment and indicated power are 7 days available to the required pump that is not in operation.

McGuire Units 1 and 2 Amendment Nos.

3.4.6-2

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.

DNOTES ----

1.

The RHR pump of the loop In operation may be de-energized for

< 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 SDM of LCO 3.1.1; and

b.

Core outlet temperature is maintained at least 1 0°F below saturation temperature.

2.

One required RHR loop may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 f 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.

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 SDM 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.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR loop is in operation.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.7.2 Verify SG secondary side water level is > 12% narrow 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months range in required SGs.

McGuire Units 1 and 2 3.4.7-2 Amendment Nos.

RCS Loops - MODE 5, Loops Filled 3.4.7 SR 3.4.7.3 Verify correct breaker alignment and indicated power are 7 days available to the required RHR pump that is not in operation.

McGuire Units I and 2 3.4.7-3 Amendment Nos.

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 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be In operation.

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 SDM 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 LCO 3.4.8 3.4.8-1 Amendment Nos.

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

CONDITION REQUIRED ACTION l COMPLETION TIME 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 SDM No RHR loop in of LCO 3.1.1.

operation.

AND 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.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.8.2 Verify correct breaker alignment and indicated power are 7 days available to the required RHR pump that is not in operation.

McGuire Units 1 and 2 3.4.8-2 Amendment Nos.

,i

~

Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Nuclear Instrumentation LCO 3.9.3 Two source range nutrb fluk monitors shall be OPERABLE.

APPLICABILITY:

MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One required source A.1 Suspend CORE Immediately range neutron flux ALTERATIONS.

monitor inoperable.

AND A.2 Suspend operations that Immediately would cause introduction of coolant into the RCS with boron concentration less than required to meet the boron concentration of LCO 3.9.1.

B.

Two required source B.1 Initiate action to restore Immediately range neutron flux one source range neutron monitors inoperable.

flux monitor to OPERABLE status.

AND B.2 Perform SR 3.9.1.1.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months McGuire Units 1 and 2 3.9.3-1 Amendment Nos.

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.

~~--NOTE~-

The required RHR loop may be removed from operation for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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.

APPLICABILITY:

MODE 6 with the water level 2 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 l.

3.9.5-1 Arnendment Nos.

RHR and Coolant Circulation - Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation-LowWater Level LCO 3.9.6 APPLICABILITY:

Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.

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 2 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 I and 2 3.9.6-1 Amendment Nos.

v t e Letter Sequence Request
TAC:MB6782, (Open)
Initiation Request Acceptance... Administration Meeting Questions Answers Results Approval... Other: ML032110122, ML032130257
MONTHYEAR2003-06-04 [Table View]

ML031630853

Text

Subject:

Reference:

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