Text

License Amendment Request: Improvement to Definition of Operations Involving Positive Reactivity Changes
	ML031130176
Person / Time
Site:	Calvert Cliffs
Issue date:	04/17/2003
From:	Katz P; Constellation Energy Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML031130176 (26)
	v • d • e

i Peter E. Katz 1650 Calvert Cliffs Parkway Vice President Lusby, Maryland 20657 Calvert Cliffs Nuclear Power Plant 410 495-4455 Constellation Generation Group, LLC 410 495-3500 Fax Constellation v wEnergy Group April 17, 2003 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 License Amendment Request: Improvement to the Definition of Operations Involving Positive Reactivity Changes

REFERENCE:

(a) Industry/TSTF Standard Technical Specification Change Traveler TSTF-286, Revision 2, Define "Operations Involving Positive Reactivity Changes" Pursuant to 10 CFR 50.90, Calvert Cliffs Nuclear Power Plant (Calvert Cliffs) hereby requests an amendment to Renewed Operating License Nos. DPR-53 and DPR-69 to incorporate the change described below into the Technical Specifications for Calvert Cliffs Unit Nos. 1 and 2.

DESCRIPTION The proposed amendment will revise Technical Specification actions requiring suspension of operations involving positive reactivity addition and revise various notes precluding reduction in boron concentration. The proposed revisions will allow only those positive reactivity additions that do not adversely affect shutdown margin (SDM) or refueling boron concentration. This requested change is consistent with Technical Specification Change Traveler (TSTF)-286, Revision 2. Changes to the Technical Specification Bases consistent with this TSTF will be made once this request is approved.

JUSTIFICATION As currently written, certain Technical Specifications applicable in shutdown Modes categorically prohibit the addition of positive reactivity to the shutdown reactor. This prohibition poses operational difficulties. For example, additions of water to the Reactor Coolant System (RCS) are routinely required.

If the makeup source is at a boron concentration lower than the boron concentration of the RCS, the makeup operation will introduce positive reactivity. In addition, water in the Refueling Water Tank at the same boron concentration as the RCS or refueling pool may appear to be at a slightly lower boron concentration due to chemistry sampling uncertainties. Nevertheless, makeup to the RCS under these circumstances is an entirely safe operation provided the makeup boron concentration is greater than the concentration required to preserve the required shutdown margin. The requested change clarifies that God

i Document Control Desk April 17, 2003 Page 2 such operations are permissible. Calvert Cliffs normally maintains boron concentration in the RCS that is well above the shutdown margin required by Technical Specifications. Plant procedures and systems, which are already in place, properly monitor the overall effect on core reactivity and the required SDM, and maintain the required refueling boron concentration.

Reduction of boron in the RCS can lead to a boron dilution event, which is a Updated Final Safety Analysis Report, Chapter 14 design basis event. However, the analysis of the event assumes boron concentration at the beginning of the event is exactly the amount needed to maintain shutdown margin.

Since the proposed changes to these Technical Specifications restrict boron additions to those that do not adversely impact shutdown margin, the Boron Dilution Event analysis is not affected by this change.

Therefore, the actions allowed by TSTF-286, Revision 2 remain bounded by the Updated Final Safety Analysis Report accident analyses.

In addition to boron concentration, temperature changes in the RCS impose reactivity changes by means of the moderator temperature coefficient of reactivity. Small, controlled changes in RCS temperature being unavoidable, the requested change clarifies that such changes are permissible so long as the required shutdown margin is maintained.

TECHNICAL SPECIFICATION CHANGES The proposed change would make 19 specific changes to the Calvert Cliffs Technical Specifications as shown in the markup (Attachment 1) and as also described in the following table. These changes were developed in accordance with TSTF-286, Revision 2 with one deviation. The Note for Change No. 1 has been modified because the TSTF note does not allow for plant temperature increases when moderator temperature coefficient is positive. The revised wording is taken from the Bases for Limiting Condition for Operation 3.3.13 mark-up for TSTF-286, Revision 2.

TITLE EXISTING WORDING PROPOSED WORDING 1 3.3.12 Wide Range None NOTE A.1 Logarithmic Limited plant control operations Neutron Flux are allowed provided the change is Monitor accounted for in the calculated Channels SDM 2 3.4.5 RCS Loops - No operations are permitted that No operations are permitted that NOTE MODE 3 would cause reduction of RCS would cause introduction into the L.a boron concentration; and RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1. 1; and 3 3.4.5 RCS Loops - Suspend all operations involving Suspend operations that would C. 1 MODE 3 a reduction of RCS boron cause introduction into the RCS, concentration. coolant with boron concentration less than required to meet the SDM of LCO 3.1.1 4 3.4.6 RCS Loops - No operations are permitted that No operations are permitted that NOTE MODE 4 would cause reduction of RCS would cause introduction into the l.a boron concentration; and RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1. 1; and

Document Control Desk April 17, 2003 Page 3 TITLE EXISTING WORDING PROPOSED WORDING 5 3.4.6 RCS Loops - Suspend all operations involving Suspend operations that would C.I MODE 4 a reduction of RCS boron cause introduction into the RCS, concentration. coolant with boron concentration less than required to meet the SDM of LCO 3. 1.1 6 3.4.7 RCS Loops - No operations are permitted that No operations are permitted that NOTE MODE 5, Loops would cause reduction of RCS would cause introduction into the L.a Filled boron concentration; and RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and 7 3.4.7 RCS Loops - Suspend all operations involving Suspend operations that would B.1 MODE 5, Loops a reduction of RCS boron cause introduction into the RCS, Filled concentration. coolant with boron concentration less than required to meet the SDM of LCO 3.1.1 8 3.4.8 RCS Loops - No operations are permitted that No operations are permitted that NOTE MODE 5, Loops would cause reduction of RCS would cause introduction into the L.b Not Filled boron concentration; and RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and 9 3.4.8 RCS Loops - Suspend all operations involving Suspend operations that would B.1 MODE 5, Loops a reduction of RCS boron cause introduction into the RCS, Not Filled concentration. coolant with boron concentration less than required to meet the SDM of LCO 3.1.1 10 3.8.2 AC Sources - Initiate action to suspend Suspend operations involving A.2.3 Shutdown operations involving positive positive reactivity additions that reactivity additions could result in loss of required SDM or boron concentration 11 3.8.2 AC Sources - Initiate action to suspend Suspend operations involving B.3 Shutdown operations involving positive positive reactivity additions that reactivity additions could result in loss of required SDM or boron concentration 12 3.8.5 DC Sources - Initiate action to suspend Suspend operations involving A.2.3 Shutdown operations involving positive positive reactivity additions that reactivity additions could result in loss of required SDM or boron concentration 13 3.8.8 Inverters - Initiate action to suspend Suspend operations involving A.2.3 Shutdown operations involving positive positive reactivity additions that reactivity additions could result in loss of required SDM or boron concentration 14 3.8.10 Distribution Initiate action to suspend Suspend operations involving A.2.3 Systems- operations involving positive positive reactivity additions that Shutdown reactivity additions could result in loss of required SDM or boron concentration

Document Control Desk April 17, 2003 Page 4 TITLE EXISTING WORDING PROPOSED WORDING 15 3.9.2 Nuclear Suspend positive reactivity Suspend operations that would A.2 Instrumentation additions cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1 16 3.9.4 SDC and Coolant The required SDC Loop may be The required SDC Loop may be NOTE Circulation-High not in operation for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per not in operation for < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per 1 Water Level 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period, provided no operations are permitted that operations are permitted that would would cause reduction of the cause introduction into the RCS, Reactor Coolant System boron coolant with boron concentration concentration. less than that required to meet the minimum boron concentration of LCO 3.9.1 17 3.9.4 SDC and Coolant No operations are permitted that No operations are permitted that NOTE Circulation-High would cause reduction to reactor would cause introduction into the 2.a Water Level coolant boron concentration; RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1; 18 3.9.4 SDC and Coolant Suspend operations involving a Suspend operations that would A.2 Circulation-High reduction of reactor coolant cause introduction into the RCS, Water Level boron concentration. coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1 19 3.9.5 SDC and Coolant Suspend operations involving a Suspend operations that would B. I Circulation-Low reduction of reactor coolant cause introduction into the RCS, Water Level boron concentration. coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1 DETERMINATION OF SIGNIFICANT HAZARDS The proposed amendment makes 19 changes to the Calvert Cliffs Nuclear Power Plant (Calvert Cliffs)

Technical Specifications. These changes reflect the content of Technical Specification Change Traveler (TSTF)-286, Revision 2. Specifically, the requested change would allow additions of water and changes in the boron content of the Reactor Coolant system as long as the shutdown margin is maintained.

The proposed changes have been evaluated against the standards in 10 CFR 50.92 and have been determined not to involve a significant hazards consideration in that operation of the facility in accordance with the proposed amendment:

1. Would not involve a significantincrease in the probabilityor consequences of an accidentpreviously evaluated.

The intent of this change is to clarify those Technical Specifications involving positive reactivity additions to the shutdown reactor so that small, controlled, safe insertions of positive reactivity will be allowed where they are now categorically prohibited, posing operational difficulties. These

Document Control Desk April 17, 2003 Page 5 controlled activities could result in a slight change in the probability of an event occurring as Reactor Coolant System (RCS) manipulations that are currently prohibited would now be allowed. However, RCS manipulations are rigidly controlled to minimize the possibility of a significant reactivity increase. In addition, there is sufficient shutdown margin available in these conditions to allow for these slight reactivity changes without significantly increasing the probability of an accident previously evaluated.

The proposed change does not permit the shutdown margin required by the Technical Specifications to be reduced. While the proposed change will permit changes in the discretionary boron concentration above the technical specification requirements, this excess concentration is not credited in the Updated Final Safety Analysis Report safety analysis. Because the initial conditions assumed in the safety analysis are preserved, no increase in the consequence of an accident previously evaluated would occur. In addition, small temperature changes in the RCS impose reactivity changes by means of the moderator temperature coefficient of reactivity. These small changes are within the required shutdown margin, therefore, there is no increase in the consequence of an accident previously evaluated.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Would not create the possibility of a new or different kind of accidentfrom any accidentpreviously evaluated This proposed amendment allows for minor plant operational adjustments without adversely impacting the safety analysis required shutdown margin. It does not involve any change to plant equipment or the shutdown margin requirements in the Technical Specifications.

Therefore, the proposed change will not create the possibility of a new or different kind of accident from any accident previously evaluated.

3. Would not involve a signifcant reduction in the margin of safety.

The margin of safety in Modes 3, 4, 5, and 6 is preserved by the calculated shutdown margin which prevents a return to criticality. The proposed change will permit reductions in the discretionary shutdown margin beyond the Technical Specification requirements. However, the shutdown margin required by the Technical Specifications is not changed. The proposed change only affects Reactor Coolant System temperature and boron concentration above the calculated shutdown margin. By not impacting the shutdown margin, the margin of safety is not affected.

Therefore, the proposed change will not involve a significant reduction in the margin of safety.

ASSESSMENT AND REVIEW We have determined that operation with the proposed amendment would not result in any significant change in the types, or significant increases in the amounts, of any effluents that may be released offsite, nor would it result in any significant increase in individual cumulative occupational exposure. Therefore, the proposed amendment is eligible for categorical exclusion as set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment is needed in connection with the approval of the proposed amendment.

Document Control Desk April 17, 2003 Page 6 SAFETY COMMITTEE REVIEW The Plant Operations and Safety Review Committee and Offsite Safety Review Committee have reviewed this proposed change and concur that operation with the proposed changes will not result in an undue risk to the health and safety of the public.

SCHEDULE This change is requested to be approved and issued by March 1, 2004.

PRECEDENTS The following plants have received approval for adopting TSTF-286:

St. Lucie - November 19, 2001

South Texas - August 13, 2001

Robinson - March 14,2001

SONGS - December 20, 2000

Callaway - May 1, 2002

Document Control Desk April 17, 2003 Page 7 Should you have questions regarding this matter, we will be pleased to discuss them with you.

Very truly yours, STATE OF MARYLAND COUNTY OF CALVERT

TO WIT:

I I, Peter E. Katz, being duly sworn, state that I am Vice President - Calvert Cliffs Nuclear Power Plant, Inc. (CCNPP), and that I am duly authorized to execute and file this License Amendment Request on behalf of CCNPP. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other CCNPP employees and/or onsultants. Such information has been reviewed in accordance with company practice and I believe it t e reliable.

Subscribed and sworn before me a Notary Public in and for the State of Maryland and County of C o , this /7 day of ZAul 2003.

WITNESS my Hand and Notarial Seal:

Notary Publi My Commission Expires:

Date PEKiEbT/tjd 2w

,1 _. I Attac'hnent^--Ji) Technical Specification Markup cc: J. Petro, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate I-1, NRC R. I. McLean, DNR G. S. Vissing, NRC

ATTACHMENT (1)

TECHNICAL SPECIFICATION MARKUP Calvert Cliffs Nuclear Power Plant, Inc.

April 17,2003

Wide Range Logarithmic Neutron Flux Monitor Channels 3.3.12 3.3 INSTRUMENTATION 3.3.12 Wide Range Logarithmic Neutron Flux Monitor Channels LCO 3.3.12 Two channels of wide range logarithmic neutron flux monitoring instrumentation shall be OPERABLE.

APPLICABILITY: MODES 3, 4, and 5, with the reactor trip circuit breakers open or Control Element Assembly Drive System not capable of Control Element Assembly withdrawal.

ACTIONS CONDITION IREQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend all Immediately channels inoperable. operations involving positive reactivity additions.

AND Irscf-A.2 Perform SDM 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months verification in accordance with AND SR 3.1.1.1.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.12.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months CALVERT CLIFFS - UNIT 1 3.3.12-1 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

RCS Loops - MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Loops - MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE and one RCS loop shall be in operation.

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

1. All reactor coolant pumps may be not in 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 and < 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period for low flow testing, provided:

a a__fllo e oparationa-a--eer-

~~Qf ~-red~etlen-o-t-e-RC-S-bor-on--oncenl-rt n-ad

b. Core outlet temperature is maintained at least 100F below saturation temperature.

2. No reactor coolant pump shall be started with any RCS cold leg temperature

3650F (Unit 1), < 3010F (Unit 2) unless:

a. The pressurizer water level is < 170 inches;

b. The pressurizer pressure is < 300 psia (Unit 1),

< 320 psia (Unit 2); and

c. The secondary water temperature of each steam generator is < 300F above the RCS temperature.

APPLICABILITY: MODE 3.

CALVERT CLIFFS - UNIT 1 3.4.5-1 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

RCS Loops - MODE 3 3.4.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop A.1 Restore required RCS 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. loop 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.

C. No RCS loop OPERABLE. C.1 -a- Immediately OR a-rec -t f-RG-S-

" bo-rn-cenc-e-nt-rati-t No RCS loop in operation. AND C.2 Initiate action to Immediately restore one RCS loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loop is in operation. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.2 Verify secondary side water level in each 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months steam generator > -50 inches.

CALVERT CLIFFS - UNIT I 3.4.5-2 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

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 shutdown cooling (SDC) loops shall be OPERABLE loops and and at least one loop shall be in operation.

NOTES

1. All reactor coolant pumps and----------------------------

SDC pumps may be not in 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:

b. Core outlet temperature is maintained at least 100F below saturation temperature.

2. No reactor coolant pump shall be started with any RCS cold leg temperature c 365 0F (Unit 1), 5 301OF (Unit 2) unless:

a. Pressurizer water level is 5 170 inches;

b. Pressurizer pressure is

300 psia (Unit 1),

< 320 psia (Unit 2); and

c. Secondary side water temperature in each steam generator is

300F above the RCS temperature.

I APPLICABILITY: MODE 4.

CALVERT CLIFFS - UNIT 1 3.4.6-1 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

RCS Loops - MODE 4 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop A.1 Initiate action to Immediately inoperable. restore a second loop to OPERABLE status.

AND Two SDC loops inoperable.

B. One required SDC loop B.1 Be in MODE 5. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable.

AND Two required RCS loops inoperable.

C. Required RCS or SDC C.1 Immediately loops inoperable. operati ons involving OR No RCS or SDC loops AND in operation.

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

CALVERT CLIFFS - UNIT 1 3.4.6-2 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

nrr s ____ Ad KUt LOOPS - MUDE 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 shutdown cooling (SDC) loop shall be OPERABLE and in operation, and either:

a. One additional SDC loop shall be OPERABLE; or

b. The secondary side water level of each steam generator (SG) shall be 2 -50 inches.

NOTES-------------- _ - _

1. The SDC pump of the loop in operation may be not in 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:

a.1 ooeain~r-e-penmi-tted-t-hat-wou44-cau-se r~::"~~~~\ ,/~\redue-t~on-off-the RGS-boro-eeac~neatraltio;a, d

b. Core outlet temperature is maintained at least 100F below saturation temperature.

2. One required SDC 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 SDC loop is OPERABLE and in operation.

3. No reactor coolant pump shall be started with any RCS cold leg temperature

365OF (Unit 1), < 301OF (Unit 2) unless:

a. The pressurizer water level is

170 inches;

b. Pressurizer pressure is

300 psia (Unit 1),

320 psia (Unit 2); and

c. The secondary side water temperature in each SG is

300F above the RCS temperature.

4. All SDC loops may be not in operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

CALVERT CLIFFS - UNIT 1 3.4.7-1 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

RCS Loops - MODE 5, Loops Filled

3.4.7 APPLICABILITY

MODE 5 with RCS loops filled.

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

Any SG with secondary OR side water level not within limit. A.2 Initiate action to Immediately restore SG *secondary side water levels to within limits.

B. Required SDC loops 8 .1 spend-all Immediately inoperable.

OR No SDC loop in AND operation.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

-SR-3.4-.7-.1 Verify-one--SDC---loop-=s :jirfd-e-~tion:.--- -- 12 Thours I

CALVERT CLIFFS - UNIT 1 3.4.7-2 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

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 shutdown cooling (SDC) loops shall be OPERABLE and one SDC loop shall be in operation.

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

1. All SDC pumps may be not in operation for S 15 minutes when switching from one loop to another provided:

a. The core outlet temperature is maintained at least 100F below saturation temperature;

b. -s-ae-pemi-tted-that-wo

)reduction of the RCS--boron-rzncent-r-at-i4---and

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

2. One SDC 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 the other SDC loop is OPERABLE and in operation.

APPLICABILITY: MODE 5 with RCS loops not filled.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SDC loop A.1 Initiate action to Immediately inoperable. restore SDC loop to OPERABLE status.

CALVERT CLIFFS - UNIT 1 3.4.8-1 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

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

CONDITION REQUIRED ACTION COMPLETION TIME B. Required SDC loops B.1 Immediately inoperable.

Xr-ehrit-o-RGi-OR nc-e No SDC loop in AND operation.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one SDC 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 7 days indicated power available to the required SDC loop components that are not in operation.

CALVERT CLIFFS - UNIT 1 3.4.8-2 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

AC Sources-Shutdown 3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (Continued) A.2.3 Immediately invoving FF}postiv reac-3^t- eadtir_

A.2.4 Initiate action to Immediately restore required offsite power circuit to OPERABLE status.

B. One required DG B.1 Suspend CORE Immediately inoperable. ALTERATIONS.

AND B.2 Suspend movement of Immediately irradiated fuel assemblies.

AND B.3 Immediately susped--operaios Vinvolving-positv AND B.4 Initiate act Immediately restore required DG to OPERABLE status.

CALVERT CLIFFS - UNIT 1 3.8.2-3 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

DC Sources-Shutdown 3.8.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Immediately A.2.4 Initiate action to Immediately restore required DC electrical power subsystems to OPERABLE status.

CALVERT CLIFFS - UNIT 1 3.8.5-2 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

Inverters-Shutdown 3.8.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 on-to- Immediately suspend-oper-at4ons i-nc~ing os4itive reacti-v4ty--ad d4t4nso AND c i A.2.4 Initiate action to Immediately restore required inverters to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage and 7 days alignment to required AC vital buses.

CALVERT CLIFFS - UNIT 1 3.8.8-2 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

i Distribution Systems-Shutdown 3.8.10 ACTIONS (continued)

CONDITION I REQUIRED ACTION I COMPLETION TIME A. (continued) A.2.2 Suspend movement of Immediately irradiated fuel assemblies.

AND A.2.3 Immediately AND A.2.4 Initiate actions to Immediately restore required AC, DC, and AC vital bus electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required shutdown cooling subsystem(s) inoperable and not in operation.

CALVERT CLIFFS - UNIT 1 3.8.10-2 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

i Nuclear Instrumentation 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Nuclear Instrumentation LCO 3.9.2 Two source range monitors (SRMs) shall be OPERABLE.

APPLICABILITY: MODE 6.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required SRM A.1 Suspend CORE Immediately inoperable. ALTERATIONS.

AND A.2 < Immediately trwNF~hety-dd44SwN B. Two required SRMs B.1 Initiate action to Immediately inoperable. restore one SRM 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 CALVERT CLIFFS - UNIT 1 3.9.2-1 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

SDC and Coolant Circulation-High Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level LCO 3.9.4 One SDC loop shall be OPERABLE and in operation.

NOTES--------------------- _-_

1. The required SDC loop may be not in 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 the Reactor Coolant SvstemAboron conce

2. The shutdown cooling pumps removed from operation during the time required for local leak rate testing of containment penetration number 41 pursuant to the requirements of SR 3.6.1.1 or to permit maintenance on valves located in the common SDC suction line, provided:

a. no operations are permitted that would cause X Reactor Coolant System boron conct~

b. CORE ALTERATIONS are suspended, and

c. all containment penetrations are in the status described in LCO 3.9.3.

APPLICABILITY: MODE 6 with the water level 2 23 ft above the top of the irradiated fuel assemblies seated in the reactor vessel.

CALVERT CLIFFS - UNIT 1 3.9.4-1 Amendment No. 242 CALVERT CLIFFS - UNIT 2 Amendment No. 216

SDC and Coolant Circulation-High Water Level 3.9.4 ACTIONS CONDITION I REQUIRED ACTION COMPLETION TIME A. One required SDC loop A. 1 Initiate action to Immediately inoperable or not in restore SDC loop to operation. OPERABLE status and operation.

AND A.2 A.A spend op RStan Immediately in reaetor-eoolai:G AND A.3 Suspend loading of Immediately irradiated fuel assemblies in the core.

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

CALVERT CLIFFS - UNIT 1 3.9.4-2 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

SDC and Coolant Circulation-Low Water Level 3.9.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No SDC loop OPERABLE B.1 spend operatin Immediately or in operation. involving a U

edbtlen 4--n-~c0 Gncolnt bron AND B.2 Initiate action to Immediately restore one SDC loop to OPERABLE status and to operation.

AND B.3 Close all 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months containment penetrations providing direct access from containment atmosphere to outside atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify required SDC loops are OPERABLE and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months one SDC loop is in operation.

SR 3.9.5.2 Verify SDC loop in operation is circulating 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months reactor coolant at a flow rate of

> 1500 gpm.

CALVERT CLIFFS - UNIT 1 3.9.5-2 Amendment No. 227 CALVERT CLIFFS - UNIT 2 Amendment No. 201

Insert 1 NOTE Limited plant control operations are allowed provided the change is accounted for in the calculated SDM Insert 3 Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1 Insert 4 Suspend operations that would cause introduction into the RCS, coolant with boron concentration less than required to meet the boron concentration of LCO 3.9.1 Insert 5 No operations are permitted that would cause introduction into the RCS, coolant with boron concentration less than required to meet the SDM of LCO 3.1.1; and Insert 7 less than that required to meet the minimum boron concentration of LCO 3.9.1.

Insert 8 Suspend operations involving positive reactivity additions that could result inloss of required SDM or boron concentration.

ML031130176

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3.4.7 APPLICABILITY

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ML031130176

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3.4.7 APPLICABILITY

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