ML082110465

Technical Specifications, Amendment Regarding Control Room Habitability

ML082110465
Person / Time
Site:	Calvert Cliffs
Issue date:	07/29/2008
From:	Plant Licensing Branch 1
To:
Pickett D, NRR/DORL, 415-1364
References
TAC MD5928, TAC MD5929
Download: ML082110465 (12)

Text

rules, regulations, and orders of the Commission, now or hereafter applicable; and is subject to the additional conditions specified and incorporated below:

(1)

Maximum Power Level The licensee is authorized to operate the facility at steady-state reactor core power levels not in excess of 2700 megawatts-thermal in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 287, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications.

(a)

For Surveillance Requirements (SRs) that are new, in Amendment 227 to Facility Operating License No. DPR-53, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 227. For SRs that existed prior to Amendment 227, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 227.

(3)

Additional Conditions The Additional Conditions contained in Appendix C as revised through Amendment No. 267 are hereby incorporated into this license. Calvert Cliffs Nuclear Power Plant, Inc. shall operate the facility in accordance with the Additional Conditions.

(4)

Secondary Water Chemistry Monitoring Program The Calvert Cliffs Nuclear Power Plant, Inc., shall implement a secondary water chemistry monitoring program to inhibit steam generator tube degradation. This program shall include:

a.

Identification of a sampling schedule for the critical parameters and control points for these parameters;

b.

Identification of the procedures used to quantify parameters that are criticalto control points; Amendment No. 287 C.

This license is deemed to contain and is subject to the conditions set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act, and the rules, regulations, and orders of the Commission, now and hereafter applicable; and is subject to the additional conditions specified and incorporated below:

(1)

Maximum Power Level The licensee is authorized to operate the facility at reactor steady-state core power levels not in excess of 2700 megawatts-thermal in accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 264 are hereby incorporated into this license.

The licensee shall operate the facility in accordnace with the Technical Specifications.

(a)

For Surveillance Requirements (SRs) that are new, in Amendment 201 to Facility Operating License No. DPR-69, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 201. For SRs that existed prior to Amendment 201, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the Surveillance was last performed prior to implementation of Amendment 201.

(3)

Less Than Four Pump Operation The licensee shall -not operate the reactor at power levels in excess of five (5) percent of rated thermal power with less than four (4) reactor coolant pumps in operation. This condition shall remain in effect until the licensee has submitted safety analyses for less than four pump operation, and approval for such operation has been granted by the Commission by amendment of this license.

(4)

Environmental Monitoring Program If harmful effects or evidence of irreversible damage are detected by the biological monitoring program, hydrological monitoring program, and the radiological monitoring program specified in the Appendix B Technical Specifications, the licensee will provide to the staff a detailed analysis of the problem and a program of remedial action to be taken to eliminate or significantly reduce the detrimental effects or damage.

Amendment No. 264 i

CREVS 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Control Room Emergency Ventilation System (CREVS)

LCO 3.7.8 Two CREVS trains shall be OPERABLE.

---

NOTES

1. Only one CREVS redundant component is required to be OPERABLE during movement of irradiated fuel assemblies when both Units are in MODE 5 or 6, or defueled.

2.

Only one CREVS train is required to be OPERABLE for the movement of irradiated fuel assemblies.

3.

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY:

MODES 1, 2, 3, 4, During movement of irradiated fuel assemblies.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more ducts A.1 Close the OPERABLE Immediately with one outside air outside air intake intake isolation valve in each valve inoperable in affected duct.

MODE 1, 2, 3, or 4.

B.

Toilet area exhaust B.1 Restore valve to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> isolation valve OPERABLE status.

inoperable.

CALVERT CLIFFS -

UNIT 1 CALVERT CLIFFS -

UNIT 2 3.7.8-1 Amendment No. 287 Amendment No.

264

CREVS 3.7.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

One exhaust to C.1 Restore valve to 7 days atmosphere isolation OPERABLE status.

valve inoperable in MODE 1, 2, 3, or 4.

D.

One or more CREVS D.1 Initiate action to Immediately trains inoperable due implement mitigating to inoperable CRE actions.

boundary in MODE 1, 2,

3, or 4.

AND D.2 Verify mitigating 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> actions ensure CRE occupant exposures to radiological,

chemical, and smoke hazards will not exceed limits.

AND D.3 Restore CRE boundary 90 days to OPERABLE status.

E.

One CREVS train E.1 Restore CREVS train 7 days inoperable for to OPERABLE status.

reasons other than Condition A, B, C, or D in MODE 1, 2, 3, or 4.

CALVERTCLIFFS - UNIT 1 CALVERT CLIFFS -

UNIT 2 3.7.8-2 Amendment No.

287 Amendment No.

264

CREVS 3.7.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

Required Action and F.1 Be in MODE 3.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A, AND B, C, D, or E not met in MODE 1, 2, 3,

F.2 Be in MODE 5.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or 4.

G.

Required Action and G.1 Suspend movement of Immediately associated Completion irradiated fuel Time,of Condition B assemblies.

not met during movement of irradiated fuel assembl ies.

OR One or more CREVS trains inoperable due to an inoperable CRE, boundary during movement of irradiated fuel assemblies.

CALVERT CLIFFS - UNIT I CALVERT CLIFFS - UNIT 2 3.7.8-3 Amendment No.

287 Amendment No.

264

C RE VS 3.7.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H.

Two CREVS trains inoperable for reasons other than Condition A, B, C, D in MODE 1, 2, 3,

or during movement irradiated fuel assemblies.

H.1 AND Enter LCO 3.0.3.

Immediately Immediately or 4

of H.2 Suspend movement of irradiated fuel assemblies.

OR One or more ducts with two outside air intake isolation valves inoperable in MODE 1, 2, 3,

4 or during movement of irradiated fuel assemblies.

OR Two exhaust to atmosphere, isolation valves inoperable in MODE 1, 2, 3, 4 or during movement of irradiated fuel assemblies.

CALVERT CLIFFS - UNIT 1 CALVERT CLIFFS - UNIT 2 3.7.8-4 Amendment No.

287 Amendment No.

264

CREVS 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Operate each required CREVS filter train for 31 days

> 15 minutes.

SR 3.7.8.2 Perform required CREVS filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.7.8.3 Verify each CREVS train actuates on an.

24 months actual or simulated actuation signal.

SR 3.7.8.4 Perform required CRE unfiltered air In accordance inleakage testing in accordance with the with the Control Room Envelope Habitability Program.

Control Room Envelope Habitability Program CALVERT CLIFFS - UNIT 1 CALVERT CLIFFS - UNIT 2 3.7.8-5 Amendment No.

287 Amendment No.

264

Programs and Manuals 5.5 5.5 Programs and Manuals

b.

Air lock testing acceptance criteria are:

I.

Overall air lock leakage rate is

• 0.05 La when tested at Ž Pa

2.

For each door, leakage rate is

• 0.0002 L. when pressurized to Ž 15 psig.

The provisions of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program, The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.

5.5.17 Control Room Envelope Habitability Program A Control Room Envelope (CRE)

Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation System (CREVS),

CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge.

The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (OBA) conditions without personnel receiving radiation exposures in excess of 5 rem whole body or its equivalent to any part of the body for the duration of the accident.

The program shall include the following elements:

a.

The definition of CRE and the CRE boundary.

b.

Requirements for maintaining CRE boundary in its design condition including configuration, control and preventive maintenance.

c.

Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope integrity at Nuclear Power Reactors,"

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UNIT 1 5.5-18 Amendment No. 287 CALVERT CLIFFS -

UNIT 2 Amendment No. 264

Programs and Manuals 5.5 5.5 Programs and Manuals Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d.

License controlled programs will be used to verify the integrity of the CRE boundary.

Conditions that generate relevant information from those programs will be entered into the corrective action process and shall be trended and used as part of the 36 month assessments of the CRE boundary.

e.

The quantitative limits on unfiltered air inleakage into the CRE.

These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.

The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences.

Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f.

The provisions'of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and assessing the CRE boundary as required by paragraphs c and d respectively.

CALVERT CLIFFS - UNIT 1 CALVERT CLIFFS - UNIT 2 5.5-19 Amendment No.

287 Amendment No.

264 Amendment No.

Additional Conditions 246 248 267 287 This amendment requires the licensee to incorporate in the Updated Final Safety Analysis Report (UFSAR) changes associated with the aircraft hazards analysis which was evaluated by the staff in the Safety Evaluation dated August 29, 2001.

This amendment requires the licensee to incorporate in the Updated Final Safety Analysis Report (UFSAR) changes associated with the loss of feedwater flow analysis which was evaluated by the staff in the safety evaluation dated February 26, 2002.

This amendment requires the licensee develop a long-term coupon surveillance program for the Carborundum samples.

This program must verify that the Carborundum degradation rates assumed in the licensee's analyses to prove subcriticality, as required by 10 CFR 50.68, remain valid over the seventy-year life span of the Unit I spent fuel pool. The licensee must submit this modified coupon surveillance program to the NRC under the 10 CFR 50.90 requirements for its review and approval.

Upon implementation of Amendment No.

287 adopting TSTF-448, Revision 3, the determination of Control Room envelope unfiltered air inleakage as required by Surveillance Requirement (SR) 3.7.8.4 in accordance with Technical Specification 5.5.17.c.(i), and the assessment of Control Room envelope habitability as required by Technical Specification 5.5.17.c.(ii) shall be considered met. Following implementation:

(a) The first performance of SR 3.7.8.4 in accordance with Technical Specification 5.5.17.c.(i), shall be within the specified implementation Date Next update of the UFSAR Next update of the UFSAR 3 years after approval of this amendment Within 60 days following completion of the installation and testing of the plant modifications described in Amendment No. 281 issued on August 29, 2007.

Amendment No. 287 1

Amendment No.

Additional Conditions Implementation Date Frequency of 6 years (plus the 18 month allowance of SR 3.0.2) as measured from December 13, 2004, the date of the most successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b) The first performance of the periodic assessment of Control Room envelope habitability per Technical Specification 5.5.17.c.(ii) shall be within the next 9 months, because the time period since the most recent successful tracer gas test (December 13, 2004) is greater than 3 years.

Amendment No. 287 I

Amendment No.

Additional Conditions 221 224 264 This amendment requires the licensee to incorporate in the Updated Final Safety Analysis Report (UFSAR) changes associated with the aircraft hazards analysis which was evaluated by the staff in the Safety Evaluation dated August 29, 2001.

This amendment requires the licensee to incorporate in the Updated Final Safety Analysis Report (UFSAR) changes associated with the loss of feedwater flow analysis which was evaluated by the staff in the safety evaluation dated February 26, 2002.

Upon implementation of Amendment No.

264 adopting TSTF-448, Revision 3, the determination of Control Room envelope unfiltered air inleakage as required by Surveillance Requirement (SR) 3.7.8.4 in accordance with Technical Specification 5.5.17.c.(i), and the assessment of Control Room envelope habitability as required by Technical Specification 5.5.17.c.(ii) shall be considered met. Following implementation:

(a) The first performance of SR 3.7.8.4 in accordance with Technical Specification 5.5.17.c.(i), shall be within the specified Frequency of 6 years (plus the 18 month allowance of SR 3.0.2) as measured from December 13, 2004, the date of the most successful tracer gas test, or within the next 18 months if the time period since the most recent successful tracer gas test is greater than 6 years.

(b) The first performance of the periodic assessment of Control Room envelope habitability per Technical Specification 5.5.17.c.(ii) shall be within the next 9 months, because the time period since the most recent successful tracer gas test (December 13, 2004) is greater than 3 years.

Implementation Date Next update of the UFSAR Next update of the UFSAR Within 60 days following completion of the installation and testing of the plant modifications described in Amendment No. 258 issued on August 29, 2007.

Amendment No. 264 1