ML033440416

Withdrawal of Request for Exemption to 10 CFR 50.44 and Appendix E,Section VI

ML033440416
Person / Time
Site:	Calvert Cliffs
Issue date:	12/05/2003
From:	Vanderheyden G Constellation Energy Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML033440416 (8)

Text

George Vanderheyden 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 Energy Group December 5, 2003 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant Unit Nos. I & 2; Docket Nos. 50-317 & 50-318 Withdrawal of Request for Exemption to 10 CFR 50.44 and 10 CFR Part 50, Appendix E, Section VI

REFERENCE:

(a) Letter from Mr. P. E. Katz (CCNPP) to Document Control Desk (NRC) dated March 28, 2003, "Request for Exemption to 10 CFR 50.44 and 10 CFR Part 50, Appendix E, Section VI and Proposed -License Amendments for Relaxation of Post-Accident Hydrogen Monitoring and Control Requirements" Reference (a) requested an exemption from the combustible gas monitoring and control of 10 CFR 50.44 and 10 CFR Part 50, Appendix E, Section VI. The definition of a design-basis loss-of-coolant accident hydrogen release and the requirements for hydrogen control systems to mitigate such a release have now been removed from the regulations by a Final Rule published in 68 Federal Register 54123, dated Tuesday, September 16, 2003. As a result, the exemption requested in Reference (a) is no longer needed.

Therefore, we wish to withdraw our request for exemption.

The second part of Reference (a) is a proposed license amendment to change the Calvert Cliffs Technical Specifications to relax the post-accident hydrogen monitoring and control requirements. This request is not withdrawn.

The background and justification presented in Attachment (1) to Reference (a) supports the Safety Evaluation put forth in the model application made available in 68 Federal Register 55416, dated Thursday, September 25, 2003. Additionally, the No Significant Hazards Discussion presented in Attachment (2) to Reference (a) is consistent with the No Significant Hazards Discussion in 68 Federal Register 55416. The marked-up Technical Specification pages were presented in Attachment (3) to Reference (a). The final Technical Specification pages are included with this letter as Attachment (1).

The retention of hydrogen monitors as non-safety-related equipment was noted in Reference (a) as a regulatory commitment. This letter does not withdraw that commitment. Additionally, Calvert Cliffs does not have an inerted Containment, therefore oxygen monitors are not required.

A-O°

Document Control Desk December 5, 2003 Page 2 We request that the license amendment proposed in Reference (a) be approved and issued by March 1, 2004. This date is a convenience to Calvert Cliffs Nuclear Power Plant and is not an operational necessity.

Should you have questions regarding this matter, we will be pleased to discuss them with you.

Very STATE OF MARYLAND  :

TO WIT:

COUNTY OF CALVERT  :

1, George Vanderheyden, 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 Ibtbe rliable.

Subscribed and sevorn before mga Notary~ublic ip and for the State of Maryland and County of

> Ž1whey ,5 , this day of &ees%4- 2003.

I . I WITNESS Amy!aiind and Notarial Seal:

My Commission Expires:

Date' GV/EMT/bjd

Attachment:

(1) Final Technical Specification Pages cc: J. Petro, Esquire H. J. Miller, NRC J. E. Silberg, Esquire Resident Inspector, NRC Director, Project Directorate 1-1, NRC R. I. McLean, DNR G. S. Vissing, NRC

ATTACHMENT (1)

FINAL TECHNICAL SPECIFICATION PAGES Calvert Cliffs Nuclear Power Plant, Inc.

December 5, 2003

TABLE OF CONTENTS 3.5.5 Trisodium Phosphate (TSP) .......................... 3.5.5-1 3.6 CONTAINMENT SYSTEMS . . . ........... 3.6.1-1 3.6.1 Containment . ....................................... 3.6.1-1 3.6.2 Containment Air Locks . . .......... 3.6.2-1 3.6.3 Containment Isolation Valves ..... 3.6.3-1 3.6.4 Containment Pressure ........................... . . .. 3.6.4-1 3.6.5 Containment Air Temperature ..... 3.6.5-1 3.6.6 Containment Spray and Cooling Systems . . ....... 3.6.6-1 3.6.7 Deleted 3.6.8 Iodine Removal System (IRS) ..... 3.6.8-1 3.7 PLANT SYSTEMS ............................. 3.7.1-1 3.7.1 Main Steam Safety Valves (MSSVs) ................... 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ................ 3.7.2-1 3.7.3 Auxiliary Feedwater (AFW) System ................... 3.7.3-1 3.7.4 Condensate Storage Tank (CST) ...................... 3.7.4-1 3.7.5 Component Cooling (CC) System ...................... 3.7.5-1 3.7.6 Service Water (SRW) System ......................... 3.7.6-1 3.7.7 Saltwater (SW) System ..................... ... ..... . 3.7.7-1 3.7.8 Control Room Emergency Ventilation System (CREVS).. 3.7.8-1 3.7.9 Control Room Emergency Temperature System (CRETS).. 3.7.9-1 3.7.10 Emergency Core Cooling System (ECCS) Pump Room Exhaust Filtration System (PREFS) .3.7.10-1 3.7.11 Spent Fuel Pool Exhaust Ventilation System (SFPEVS) .3.7.11-1 3.7.12 Penetration Room Exhaust Ventilation System (PREVS) . ........................................ 3.7.12-1 3.7.13 Spent Fuel Pool (SFP) Water Level ...... ............ 3.7.13-1 3.7.14 Secondary Specific Activity ........................ 3.7.14-1 3.7.15 Main Feedwater Isolation Valves (MFIVs) ............ 3.7.15-1 3.7.16 Spent Fuel Pool (SFP) Boron Concentration .......... 3.7.16-1 3.7.17 Spent Fuel Pool (SFP) Storage ...................... 3.7.17-1 3.8 ELECTRICAL POWER SYSTEMS . . . .......... 3.8.1-1 3.8.1 AC Sources-Operating .............................. 3.8.1-1 3.8.2 AC Sources-Shutdown ............................... 3.8.2-1 3.8.3 Diesel Fuel Oil .................................... 3.8.3-1 3.8.4 DC Sources-Operating .............................. 3.8.4-1 3.8.5 DC Sources-Shutdown ............................... 3.8.5-1 3.8.6 Battery Cell Parameters . . . ......... 3.8.6-1 3.8.7 Inverters-Operating .................................. 3.8.7-1 CALVERT CLIFFS - UNIT 1 iii Amendment No.

CALVERT CLIFFS - UNIT 2 Amendment No.

PAM Instrumentation 3.3.10 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions C.1 Restore one 7 days I with two required indication channel to indication channels OPERABLE status.

inoperable.

D. Required Action and D.1 Enter the Condition Immediately I associated Completion referenced in Time of Condition C Table 3.3.10-1 for not met. the channel.

E. As required by E.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 /> Required Action D.1 and referenced in AND Table 3.3.10-1.

E.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 /> I F. As required by F.1 Initiate action in Immediately Required Action D.1 accordance with and referenced in Specification 5.6.7.

Table 3.3.10-1.

CALVERT CLIFFS - UNIT 1 3.3.10-2 Amendment No.

CALVERT CLIFFS - UNIT 2 Amendment No.

PAM Instrumentation 3.3.10 SURVEILLANCE REQUIREMENTS

---

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

These Surveillance Requirements apply to each PAM instrumentation Function in Table 3.3.10-1.

SURVEILLANCE FREQUENCY SR 3.3.10.1 Perform CHANNEL CHECK for each required 31 days indication channel that is normally energized.

SR 3.3.10.2 Deleted SR 3.3.10.3 ---------------- NOTE-------------------

Neutron detectors, Core Exit Thermocouples, and Reactor Vessel Level Monitoring System are excluded from CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION on each 24 months indication channel.

CALVERT CLIFFS - UNIT 1 3.3.10-3 Amendment No.

CALVERT CLIFFS - UNIT 2 Amendment No.

I PAM Instrumentation 3.3.10 Table 3.3.10-1 (page 1 of 2)

Post-Accident Monitoring Instrumentation CONDITIONS REQUIRED REFERENCED FROM INDICATION REQUIRED ACTION FUNCTION CHANNELS E.1

1. Wide Range Logarithmic Neutron Flux 2 F

2. Reactor Coolant Outlet Temperature 2 F

3. Reactor Coolant Inlet Temperature 2 F

4. RCS Subcooled Margin Monitor 1 N/A

5. Reactor Vessel Water Level 2 G

6. Containment Water Level (wide 2 F range)

7. Containment Pressure 2 F

8. Containment Isolation Valve 2 per F Position penetration flow path(a)(b)

9. Containment Area Radiation (high 2 G range)

10. Pressurizer Pressure (wide range) 2 F I

11. Steam Generator Pressure 2 per steam F I generator

12. Pressurizer Level 2 F I

13. Steam Generator Water Level (wide 2 per steam F I range) generator CALVERT CLIFFS - UNIT 1 3.3.10-4 Amendment No.

CALVERT CLIFFS - UNIT 2 Amendment No.

e &

PAM Instrumentation 3.3.10 Table 3.3.10-1 (page 2 of 2)

Post-Accident Monitoring Instrumentation CONDITIONS REQUIRED REFERENCED FROM INDICATION REQUIRED ACTION FUNCTION CHANNELS E.1

14. Condensate Storage Tank Level 2 F

15. Core Exit Temperature-Quadrant 1 2() F

16. Core Exit Temperature-Quadrant 2 2W F

17. Core Exit Temperature-Quadrant 3 2() F

18. Core Exit Temperature-Quadrant 4 2(c F

19. Pressurizer Pressure (low range) 2 F (a) Not required for isolation valves whose associated penetration is isolated by at least one closed and de-activated automatic valve, closed manual valve, check valve with flow through the valve secured, blind flange, or equivalent.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

Cc) A channel consists of two or more core exit thermocouples.

CALVERT CLIFFS - UNIT 1 3.3.10-5 Amendment No.

CALVERT CLIFFS - UNIT 2 Amendment No.