ML15062A043
| ML15062A043 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  (DPR-053, DPR-069, SNM-2505) |
| Issue date: | 02/27/2015 |
| From: | George Gellrich Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| Download: ML15062A043 (5) | |
Text
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W George Gellrich AAIE'hW c1c1Wtci Site Vice President Exe Ion Generation.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5200 Office 717 497 3463 Mobile www.exeloncorp.com george.gellrich@exeloncorp.com 10 CFR 50.59 10 CFR 72.48 February 27, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation, License No. SNM-2505 NRC Docket No. 72-8
Subject:
Report of Changes, Tests, and Experiments - 10 CFR 50.59 and 10 CFR 72.48 In accordance with 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2), a report of changes, tests and experiments is provided as Attachment (1).
The attachment contains brief descriptions of changes, tests, and experiments approved under the provisions of 10 CFR 50.59 and 10 CFR 72.48 between January 1, 2014 and December 31, 2014.
There are no regulatory commitments contained in this correspondence.
Should you have questions regarding this matter, please contact Mr. Michael J. Fick at (410) 495-6714.
Respectfully, George H. Gellrich Site Vice President GHG/PSF/bjm
Attachment:
(1)
Calvert Cliffs Nuclear Power Plant Report of Changes, Tests, and Experiments [10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2)]
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Document Control Desk February 27, 2015 Page 2 cc:
NRC Project Manager, Calvert Cliffs NRC Regional Administrator, Region I NRC Resident Inspector, Calvert Cliffs S. Gray, MD-DNR C. Haney, NMSS
ATTACHMENT (1)
CALVERT CLIFFS NUCLEAR POWER PLANT REPORT OF CHANGES, TESTS, AND EXPERIMENTS
[10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2)]
Calvert Cliffs Nuclear Power Plant February 27, 2015
ATTACHMENT (1)
CALVERT CLIFFS NUCLEAR POWER PLANT REPORT OF CHANGES, TESTS, AND EXPERIMENTS
[10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2)]
Document Id Doc Type Rev Status Revision Date Issued SE00533 50.59 Approved 0002 3f712014
_Subject Unit 1 Cycle 22 Core Reload Modification Summary Proposed Activity:
The proposed activity is the Unit 1 Cycle 22 (U1C22) core reload.
Revision 0: Authorized the original Unit 1 Cycle 22 core design for operation in all plant modes.
Revision 1: Authorizes the redesigned Unit 1 Cycle 22 core for operation in Modes 5 and 6 only. Fuel assembly AA103 was determined to be a suspect leaker (CR-2014-002220) and was replaced with assembly AA434 Revision 2: Authorizes the redesigned Unit 1 Cycle 22 core for operation in all plant modes.
==
Conclusions:==
The proposed activity has been evaluated against the eight criteria of 10CFR 50.59. It is concluded that no additional License Amendment is required for Unit 1 Cycle 22.
Document Id Doc Type Rev Status Revision Date Issued SE00534 50.59 Approved 0000 12/12/2014 Subject Evaluate new UFSAR 14.4 Excess Load Return-to-Power analyses to account for a more reactive stuck rod Summary Proposed Activity:
Evaluate UFSAR 14.4, Excess Load, return to power analysis to account for a more reactive stuck rod.
==
Conclusions:==
This activity evaluates the changes needed to reconcile the Excess Load Event UFSAR 14.4 presentation with the Analysis of Record and evaluates changes that are incurred due to inclusion of a more reactive stuck rod. The proposed activity results in AFAS actuation for the Hot Zero Power case, which requires operator action to control AFW to prevent water intrusion into the steam lines. An assumed stuck open MSIV renders the action taken to terminate the event (shut the accident initiator) ineffective; therefore it is recognized that the operator must also defeat the assumed single failure (to isolate the Turbine Bypass Valve for the HFP case) or allow the affected Steam Generator to blow dry. These actions are consistent with those in EOP-04, Excessive Steam Demand. The consequences of the Excess Load Event, extended cooldown scenario are not more severe because fuel failure is not increased. The event continues to be bounded by a Steam Line Break. Application of previously approved Steam Line Break Methodology is acceptable due to the events being technically identical.
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ATTACHMENT (1)
CALVERT CLIFFS NUCLEAR POWER PLANT REPORT OF CHANGES, TESTS, AND EXPERIMENTS
[10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2)]
Document Id Doc Type Rev Status Revision Date Issued SE00536 50.59 Approved 0000 6/12/2014 Subject Unit 2 Digital Feedwater Ovation Installation Summary Proposed Activity:
The existing Digital Feedwater Control System and Steam Generator Feed Pump Turbine speed control system for Unit 2 will be replaced with a modern Distributed Control System supplied by Westinghouse. The new digital replacement system is based upon the Ovation platform manufactured by Emerson Process Management which is use at both nuclear and fossil power generation plants throughout the world.
==
Conclusions:==
The proposed activity has been evaluated against the eight criteria of 10CFR 50.59. It is concluded that a License Amendment is not required to support the upgrade of the Unit 2 DCS Digital Feedwater Control System and Steam Generator Feed Pump Turbine speed control system. This activity does not require previous NRC review or approval.
Document Id Doc Type Rev Status Revision Date Issued SE00537 50.59 Approved 0000 10/13/214 Subject 1 B, 2A, 2B Diesel Generator Rooms Mixing Damper Control Air Modifications Summary Proposed Activity:
The modifications to the 1 B, 2A, and 2B Diesel dampers and damper controls:
- Changes the air supply from non-safety related instrument air to safety related air supplied by the common header of the Saltwater Air Compressors.
- Provides a safety related accumulator, one per diesel generator, with a minimum two hour capacity to provide air to the accumulators if non-safety related air is lost and the Saltwater Air Compressors are not running.
- Modifies the operator action to start the Saltwater Air Compressors upon loss of instrument air to require starting the compressors within two hours of a loss of instrument air.
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Conclusions:==
The diesel generator rooms mixing damper control air modifications adversely affects how the UFSAR described design function is controlled because operator action is required to start a SWAC air compressor if normal instrument air is lost and a SWAC air compressor has not been automatically started on an SIAS. However, the new air accumulators will provide a minimum of two hours of DG room temperature control capability in the event that SWAC air is not immediately available, and operator action to start a SWAC air compressor if instrument air pressure is less than 90 psig and lowering is a procedurally directed operator action in AOP-07D-1/c2.
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