ML15246A118

License Amendment Request to Revise Technical Specification 5.6.3, Fuel Storage Capacity

ML15246A118
Person / Time
Site:	Millstone
Issue date:	08/31/2015
From:	Mark D. Sartain Dominion, Dominion Nuclear Connecticut
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
15-410
Download: ML15246A118 (10)

Text

Dominion Nuclear Connecticut, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 Dominion Web Address: www.dom.com August 31, 2015 U.S. Nuclear Regulatory Commission Serial No.15-410 Attention: Document Control Desk NSSL/MLC R0 Washington, DC 20555 Docket No. 50-423 License No. NPF-49 DOMINION NUCLEAR CONNECTICUT. INC.

MILLSTONE POWER STATION UNIT 3 LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATION 5.6.3, FUEL STORAGE CAPACITY Pursuant to 10 CFR 50.90, Dominion Nuclear Connecticut, Inc. (DNC) requests an amendment to Operating License NPF-49 for Millstone Power Station Unit 3 (MPS3). The proposed amendment would modify Technical Specification (TS) 5.6.3, Fuel Storage Capacity, to specify the spent fuel pool storage capacity limit in terms of the total number of fuel assemblies. provides the description and assessment of the proposed amendment. contains the corresponding marked-up TS page.

The proposed amendment does not involve a significant hazards consideration pursuant to the provisions of 10 CER 50.92(c). The Facility Safety Review Committee has reviewed and concurred with this determination.

DNC requests approval of the proposed license amendment by August 31, 2016. Once approved, the license amendment will be implemented within 60 days.

In accordance with 10 CFR 50.91(b), a copy of this license amendment request is being provided to the State of Connecticut.

If you have any questions regarding this request, please contact Wanda Craft at (804) 273-4687.

Sincerely, Mark D. Sartain Vice President - Nuclear Engineering ~Notary Public Commonwealth of Virginia COMMONWEALTH OF VIRGINIA ) ~~Reg. # 7518653 *

) Commission Expires December 31, 20L,*

_My_

COUNTY OF HENRICO The who foregoing document- was acknowledged before me, in andNuclear for the County and Commonwealth aforesaid,before today me by Mark is Vice President Nuclear Engineering of Dominion Connecticut, Inc. He has affirmed that D.

he Sartain, is duly authorized to execute and file the foregoing document in behalf of that Company, and that the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this My Commission Expires: ".a 3L

• ,/(4 day of________'* 2015.

Ac01

Serial No.15-410 Docket No. 50-423 Page 2 of 2 Commitments made in this letter: None Attachments:

1) Evaluation of Proposed License Amendment to Revise Technical Specification 5.6.3, Fuel Storage Capacity

2) Marked-Up Technical Specifications Page cc: U.S. Nuclear Regulatory Commission Region I 2100 Renaissance Blvd, Suite 100 King of Prussia, PA 19406-2713 R. V. Guzman Senior Project Manager - Millstone Power Station U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-C2 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Millstone Power Station Director, Radiation Division Department of Energy and Environmental Protection 79 Elm Street Hartford, CT 06106-5127

Serial No.15-410 Docket No. 50-423 ATTACHMENT 1 EVALUATION OF PROPOSED LICENSE AMENDMENT TO REVISE TECHNICAL SPECIFICATION 5.6.3. FUEL STORAGE CAPACITY DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Serial No.15-410 Docket No. 50-423 Attachment 1, Page 1 of 5 EVALUATION OF PROPOSED LICENSE AMENDMENT TO REVISE TECHNICAL SPECIFICATION 5.6.3, FUEL STORAGE CAPACITY

1.0 DESCRIPTION

Pursuant to 10 CFR 50.90, Dominion Nuclear Connecticut, Inc. (DNC) requests an amendment to Operating License NPF-49 for Millstone Power Station Unit 3 (MPS3).

The proposed amendment would revise Technical Specification (TS) 5.6.3, Fuel Storage Capacity, to specify the spent fuel pool (SEP) storage capacity limit in terms of the total number of fuel assemblies.

2.0 PROPOSED CHANGE

The proposed change to TS 5.6.3, Fuel Storage Capacity, is shown below (deleted text is struck through and added text is italicized and bolded).

The spent fuel storage pool contains 350 Region 1 storage locations, 673 Region 2 storage locations and 756 Region 3 storage locations, for a total of 1779toa availab~e fuel storage locations. An additional Region 2 rack with 81 storage locations may be placed in the spent fuel pool, if needed. With this additional rack installed, the Region 2 storage capacity is 754 storage locations, for a total of total availabl fuel' ztog 1860,,,-. ..... at"oz." The total storage capacity of the spent fuel pooi is limited to no more than 1860 fuel assemblies. provides the marked-up TS page to reflect the proposed change.

3.0 BACKGROUND

As described in ESAR Section 9.1, the MPS3 SFP is an L-shaped structure located in the southwestern quadrant of the fuel building. The SFP is designed to accommodate fuel racks that store new and spent fuel assemblies. The storage racks are located underwater in the SFP to provide radiation shielding. A SEP cooling and purification system removes decay heat from the spent fuel assemblies stored in the SEP and provides clarification and purification of the SEP water.

There are three different fuel storage regions in the MPS3 SEP. Region 1 contains 350 storage locations, Region 2 contains 673 storage locations, and Region 3 contains 756 storage locations, for a total of 1779 fuel storage locations. An additional Region 2 rack with 81 storage locations has been licensed by the NRC (Reference 7.2), but is not physically installed in the SFP. If this additional rack is installed, the Region 2 storage capacity is 754 storage locations, for a total storage capacity of 1860 fuel assemblies.

Serial No.15-410 Docket No. 50-423 Attachment 1, Page 2 of 5 Currently, TS 5.6.3 describes the total fuel assembly storage capacity in terms of the total "available" fuel storage locations. The number of "available" fuel storage locations is subject to change. Fuel storage availability in the three regions of the MPS3 SEP is affected when individual storage cells are unusable due to physical obstructions or removed from service because the storage cell does not meet its design basis.

Although several SEP storage locations are not physically available for use, the MPS3 design and accident analyses conservatively assume that all of the SEP storage locations contain spent fuel assemblies. DNC is requesting a change to TS 5.6.3 that more accurately reflects the design feature of fuel storage capacity. The proposed amendment would maintain the description of the storage capacity of each spent fuel pool region and modify TS 5.6.3 to specify the SEP storage capacity limit in terms of the total number of fuel assemblies.

4.0 TECHNICAL ANALYSIS

TS 5.6.3, Fuel Storage Capacity, currently specifies the total number of storage locations for each of the three SEP regions, as well as the total combined storage capacity of the entire MPS3 SEP. In contrast, Westinghouse standard TSs (STS) for fuel storage capacity (i.e., STS 4.3.3) specify a total storage limit only. DNC's proposed change to TS 5.6.3 would remove the word "available" and specify a storage capacity limit of 1860 fuel assemblies.

Fuel storage capacities in the three regions of the MPS3 SEP are affected when individual storage cells are unusable due to physical obstructions or removed from service because the storage cell does not meet its design basis. The proposed change to TS 5.6.3 is consistent with the design configuration of the MPS3 SEP. MPS3 design and accident analyses are based on a total SEP storage capacity limit (i.e., 1860 fuel assemblies).

The current TS 5.6.3 wording was approved by the Nuclear Regulatory Commission (NRC) in License Amendment 189 (Reference 7.2) in response to DNC's request to increase SEP storage capacity to support re-rack of the MP3 SEP.

The proposed change to TS 5.6.3 only revises the description of the MPS3 SEP storage capacity. The number of SEP storage locations and the maximum number of fuel assemblies allowed to be stored in the MPS3 spent fuel pool remain unchanged.

5.0 REGULATORY SAFETY ANALYSIS 5.1 Applicable Regulatory Requirements/Criteria

Serial No.15-410 Docket No. 50-423 Attachment 1, Page 3 of 5 The NRC's regulatory requirements related to the content of TSs are set forth in 10 CFR Section 50.36. The regulation requires that the TSs include items in specific categories, including: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation (LCO); (3) surveillance requirements; (4) design features; and (5) administrative controls.

10 CFR 50.36(c)(4) describes design features to be included in TSs as follows:

Design features to be included are those features of the facility such as materials of construction and geometric arrangements, which, if altered or modified, would have a significant effect on safety and are not covered in categories described in paragraphs (c) (1), (2), and (3) of this section.

As noted in the Federal Register Notice (60 FR 36953) accompanying the issuance of 10 CFR 50.36, the rule reflects that TSs were intended to be reserved for those conditions or limitations upon reactor operation necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety. That is, those conditions of controlling importance to operational safety.

The NRC issued the Westinghouse STSs as a model for improved TSs that satisfy the requirements of 10 CFR 50.36. Updating TSs consistent with the STSs has been encouraged by the NRC in a final policy statement issued in the Federal Register on July 22, 1993 (58 FR 39132).

5.2 No Significant Hazards Consideration DNC is proposing a license amendment to revise MPS3 TS 5.6.3, Fuel Storage Capacity. Currently, TS 5.6.3 describes the total fuel assembly storage capacity in terms of the total "available" fuel storage locations. Since the number of "available" fuel storage locations is subject to change, DNC is requesting a change to TS 5.6.3 that more accurately reflects this design feature. The proposed amendment would maintain the description of the storage capacity of each spent fuel pool region and modify TS 5.6.3 to specify the SFP storage capacity limit in terms of the total number of fuel assemblies.

DNC has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of Amendment," as discussed below:

1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Response: No.

Serial No.15-410 Docket No. 50-423 Attachment 1, Page 4 of 5 The proposed amendment does not represent any physical change to plant systems, structures, or components (SSC), or to procedures established for plant operation. The proposed amendment would not increase the likelihood of a malfunction of any plant SSC. Therefore, initial conditions associated with, and systems credited for mitigating the consequences of accidents previously evaluated remain unchanged.

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

2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?

Response: No.

The proposed amendment does not involve a physical alteration of the plant. No new or different types of equipment will be installed and there are no physical modifications to existing equipment associated with the proposed amendment. Similarly, the proposed amendment would not physically change any plant systems, structures, or components involved in the mitigation of any postulated accidents. Thus, no new initiators or precursors of a new of different kind of accident are created. Furthermore, the proposed amendment does not create the possibility of a new failure mode associated with any equipment or personnel failures.

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

3. Does the proposed amendment involve a significant reduction in a margin of safety?

Response: No.

The proposed amendment does not represent any physical change to plant systems, structures, or components, or to procedures established for plant operation. The proposed amendment does not affect the inputs or assumptions of any of the design basis analyses and current design limits will continue to be met. The proposed amendment does not alter or create a new mode of plant operation or configuration.

Margins of safety are not significantly reduced.

Therefore, operation of the facility in accordance with the proposed change to TS 5.6.3 does not involve a significant reduction in the margin of safety.

Based on the above, DNC concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.

Serial No.15-410 Docket No. 50-423 Attachment 1, Page 5 of 5

6.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

7.0 REFERENCES

7.1 NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 4.0, Volume 1, Specifications.

7.2 Millstone Power Station Unit 3 - Issuance of Amendment Re: Increasing Spent Fuel Storage Capacity (TAC No. MA5137), November 28, 2000 (ADAMS Accession No. ML003744387).

Serial No.15-410 Docket No. 50-423 ATTACHMENT 2 MARKED-UP TECHNICAL SPECIFICATIONS PAGE DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNIT 3

Serial No.15-410 Docket No. 50-423 Attachment 2, Page 1 of 1 DESIGN FEATURES CAPACITY 5.6.3 The spent fuel storage pool contains 350 Region~l storage locations, 673 Region 2 storage locations and 756 Region 3 storage locations, for a total of 1779 *ea-'~ufh fuel Storage locations. An additional Region 2 rack with 81 storage locations may be placed in the spent fuel pooi, if needed. With this additional rack installed, the Region 2 storage capacity is 754 storage locatio ns~vfora ttala of 1860 toa+l availabic fuci. storage loaations.

5.7 DELETED t

• limited to no more than 1860 fuel assemblies.

MILLSTONE - UNIT3 5-6a MILLTONE-UIT3-6aAmendment No. 3-9, 60, 89, -2A-3