L-2018-120, License Amendment Request to Remove the Site Area Map from the Technical Specifications
| ML18206A275 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 06/25/2018 |
| From: | Deboer D Florida Power & Light Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| L-2018-120 | |
| Download: ML18206A275 (17) | |
Text
U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington D C 20555-0001 RE:
St. Lucie Units 1 and 2 Docket Nos. 50-335 and 50-389 JUL 2 5 2018 L-2018-120 10 CFR 50.90 Renewed Facility Operating Licenses DPR-67 and NPF-16 License Amendment Request to Remove the Site Area Niap from the Technical Specifications Pursuant to 10 CFR Part 50.90, Florida Power & Light Company (FPL) hereby requests amendments to Renewed Facility Operating Licenses DPR-67 for St. Lucie Nuclear Plant Unit 1 and NPF-16 for St. Lucie Nuclear Plant Unit 2. The proposed license a1nendments modify the St. Lucie Unit 1 and St. Lucie Unit 2 (St. Lucie) Technical Specifications (TS) by removing Figure 5.1-1, Site Area Map.
The enclosure to this letter provides FPL's evaluation of the proposed changes. Attachment 1 to the enclosure provides the existing St. Lucie Unit 1 and St. Lucie Unit 2 TS pages marked up to show the proposed changes. Attachment 2 provides the St. Lucie Unit 1 and St. Lucie Unit 2 TS retyped (clean copy) TS pages with revision bars to identify the proposed changes. There are no changes proposed to the St. Lucie Unit 1 and St. Lucie Unit 2 TS Bases.
FPL has detennined that the proposed changes do not involve a significant hazards consideration pursuant to 10 CFR 50.92(c), and there are no significant environmental impacts associated with the change. The St. Lucie Plant Onsite Review Group (ORG) has reviewed the proposed license amendments. In accordance with 10 CFR 50.91(b)(1), copies of the proposed license amendments are being forwarded to the state designee for the State of Florida.
FPL requests that the proposed license a1nendn1ents are processed as a nonnal an1endn1ent request with approval within one year of the subn1ittal date. Once approved, the amendments shall be implemented within 90 days.
Tl1is letter contains no new regulatory commitments.
If you have any questions or require additional information, please contact Nir. Michael Snyder, St.
Lucie Licensing Nianager, at (772) 467-7036.
Florida Power & Light Company 6501 S. Ocean Drive, Jensen Beach, FL 34957
St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 I declare under penalty of perjury that the foregoing is true and correct.
Executed on JUL 2 5 2018 Sincerely, Daniel DeBoer Site Director-St. Lucie Nuclear Plant, Units 1 and 2 Florida Power & Light Company Enclosure cc: USNRC Regional Administrator, Region II USNRC Project Manager, St. Lucie Nuclear Plant, Units 1 and 2 USNRC Senior Resident Inspector, St. Lucie Nuclear Plant, Units 1 and 2 Ms. Cindy Becker, Florida Department of Health L-2018-120 Page 2 of2
St. Lucie Nuclear Plant L-2018-120 Docket Nos. 50-335 and 50-389 Enclosure Page 1 of 15 ENCLOSURE Evaluation of the Proposed Changes St. Lucie Nuclear Plant, Units 1 and 2 License Amendment Request to Remove Site Area Map from the Technical Specifications 1.0
SUMMARY
DESCRIPTION........................................................................................................ 2 2.0 DETAILED DESCRIPTION....................................................................................................... 2 2.1 System Design and Operation............................................................................................... 2 2.2 Current Requirements / Description of the Proposed Changes.................................... 2 2.3 Reason for the Proposed Change......................................................................................... 2
3.0 TECHNICAL EVALUATION
..................................................................................................... 3
4.0 REGULATORY EVALUATION
................................................................................................. 3 4.1 Applicable Regulatory Requirements/ Criteria................................................................... 3 4.2 No Significant Hazards Consideration................................................................................. 3 4.3 Conclusion................................................................................................................................ 5
5.0 ENVIRONMENTAL CONSIDERATION
............................................................................. 5
6.0 REFERENCES
................................................................................................................................. 5
- Proposed Unit 1 and Unit 2 Technical Specification Pages (markup)......6
- Proposed Unit 1 and Unit 2 Technical Specification Pages (clean copy).11
St. Lucie Nuclear Plant L-2018-120 Docket Nos. 50-335 and 50-389 Enclosure Page 2 of 15 1.0
SUMMARY
DESCRIPTION Florida Power & Light Company (FPL) requests amendments to Renewed Facility Operating Licenses DPR-67 for St. Lucie Nuclear Plant Unit 1 and NPF-16 for St. Lucie Nuclear Plant Unit 2. The proposed license amendments modify the St. Lucie Unit 1 and St.
Lucie Unit 2 (St. Lucie) Technical Specifications (TS) by removing Figure 5.1-1, Site Area Map.
2.0 DETAILED DESCRIPTION 2.1 System Design and Operation The St. Lucie nuclear units are located on Hutchinson Island in St. Lucie County, about halfway between the cities of Fort Pierce and Stuart on the east coast of Florida. The site for St. Lucie Units 1 and 2 consists of approximately 1,132 acres owned by FPL. The minimum site exclusion radius is 5,100 feet. The area preempted by the St. Lucie plants is about 300 acres, or approximately 27 percent of the total land owned by FPL. There are no industrial, commercial, institutional, or residential structures within the plant area.
The radius of the exclusion area is 0.97 miles from the center of the St. Lucie Plant.
The low population zone (LPZ) includes that area within one mile of the center of the St. Lucie Plant. No residents reside within the LPZ. However, access to the Walton Rocks public beach lies within the LPZ. Recreational facilities for limited use by FPL employees and their families are also located within the LPZ.
Maps of FPL's St. Lucie site are provided in the St. Lucie Unit 1 and St. Lucie Unit 2 Updated Final Safety Analysis Report (UFSAR). The maps detail site property lines, perimeter, principal plant structures, and boundary lines of the exclusion area and LPZ.
2.2 Current Requirements / Description of the Proposed Changes Figure 5.1-1, Site Area Map, is provided in Section 5.0, Design Features, of the St.
Lucie Unit 1 and the St. Lucie Unit 2 TS.
The proposed change removes Figure 5.1-1, Site Area Map, from the St. Lucie Unit 1 and St. Lucie Unit 2 TS.
2.3 Reason for the Proposed Change Inclusion of the maps in the TS adds excessive detail and precludes any changes to the property outside regulatory requirements. Additionally, the NRC Standard TS, NUREG 1432, does not contain this level of detail. The proposed change would more appropriately place the disposition of the site under licensee control.
St. Lucie Nuclear Plant L-2018-120 Docket Nos. 50-335 and 50-389 Enclosure Page 3 of 15
3.0 TECHNICAL EVALUATION
The proposed license amendments modify the St. Lucie Unit 1 and St. Lucie Unit 2 TS by removing Figure 5.1-1, Site Area Map, to facilitate changes to the FPL owner controlled area.
The proposed license amendments remove the site maps from the TS but otherwise propose no changes to the site boundary or the activities within, as currently licensed and described in the St. Lucie Unit 1 and St. Lucie Unit 2 UFSARs. The proposed changes are administrative in nature and have no impact on existing plant operations, plant safety analyses or applicable regulations, codes and standards. Deletion of Figure 5.1-1 is acceptable since the site maps cannot affect plant safety, do not meet any other 10 CFR 50.36 criteria, and as such, do not satisfy the 10 CFR 50.36(c)(4) conditions for TS inclusion as a design feature. Moreover, the Figure 5.1-1 maps are redundant to the site maps maintained in the St. Lucie Unit 1 and St. Lucie Unit 2 UFSARs, hence rendering Figure 5.1-1 unnecessary. The proposed change is consistent with the regulatory guidance provided in the Improved Standard Technical specifications of NUREG-1432 (Reference 6.1), which does not specify a site map in Section 4.1, Site Location, and is thereby reasonable.
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/ Criteria 10 CFR 50.36(c)(4) states that 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 [10 CFR 50.36(c)(2)(i)]
section.
The proposed license amendments do not alter the manner in which St. Lucie Unit and St. Lucie Unit 2 will be operated or maintained, consistent with 10 CFR 50.36(c)(4) and all other applicable regulatory requirements.
4.2 No Significant Hazards Consideration The proposed license amendments modify the St. Lucie Unit 1 and St. Lucie Unit 2 (St. Lucie) Technical Specifications (TS) by removing Figure 5.1-1, Site Area Map, to facilitate changes to the FPL owner controlled area.
As required by 10 CFR 50.91(a), FPL has evaluated the proposed changes using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazards consideration. An analysis of the issue of no significant hazards consideration is presented below:
St. Lucie Nuclear Plant L-2018-120 Docket Nos. 50-335 and 50-389 Enclosure Page 4 of 15 (1)
Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change does not modify any plant equipment or affect plant operation. The proposed change neither impacts any structures, systems, or components (SSCs), nor alters any plant processes or procedures. The proposed change is administrative in nature and cannot adversely impact safety.
Therefore, the proposed changes do 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 change has no impact on the design, function or operation of the plants. The proposed change is administrative in nature, and thereby cannot introduce new failure modes or unanticipated outcomes.
Therefore, the proposed changes do 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 change does not affect plant safety margins or the reliability of the equipment assumed to operate in the safety analyses. The proposed change is administrative in nature, and thereby cannot affect any safety analysis assumptions, safety limits or limiting safety system settings.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based upon the above analysis, FPL concludes that the proposed license amendment does not involve a significant hazards consideration, under the standards set forth in 10 CFR 50.92, Issuance of Amendment, and accordingly, a finding of no significant hazards consideration is justified.
St. Lucie Nuclear Plant L-2018-120 Docket Nos. 50-335 and 50-389 Enclosure Page 5 of 15 4.3 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20, and would change an inspection or surveillance requirement. However, the proposed change 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 change 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 change.
6.0 REFERENCES
6.1 NUREG-1432, Standard Technical Specifications - Combustion Engineering Plants, Revision 4.0, Volume 1, Specifications (Accession No. ML12102A165)
St. Lucie Nuclear Plant L-2018-120 Docket Nos. 50-335 and 50-389 Enclosure Page 6 of 15 ST. LUCIE UNIT 1 AND ST. LUCIE UNIT 2 PROPOSED TECHNICAL SPECIFICATIONS PAGE (MARKUP)
(4 pages follow)
St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ST. LUCIE UNIT lAND ST. LUCIE UNIT 2 PROPOSED TECHNICAL SPECIFICATIONS PAGE (MARKUP) 5.0 DESIGN FEATURES 5.1
--st'fE-~
EXCLUSION AREA
&:4.4 The e)Eelusien area is shO'.vn en Fi§ure &.1 1.
LOV".' POPULATION ZONE
~ The low population :cone is shovm eA Figure §.1 1.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The containment structure is comprised of a steel containment vessel, having the shape of a right circular cylinder with a hemispherical dome and ellipsoidal bottom, surrounded by a reinforced concrete shield building. The radius of the shield building is at least 4 feet greater than the radius of circular cylinder portion of the containment vessel at any point.
5.2.1.1 CONTAINMENTVESSEL
- a.
Nominal inside diameter= 140 feet.
- b.
Nominal inside height = 232 feet.
- c.
Net free volume= 2.5 x 106 cubic feet.
- d.
Nominal thickness of vessel walls = 2 inches.
- e.
Nominal thickness of vessel dome = 1 inch.
- f.
Nominal thickness of vessel bottom = 2 inches.
ST. LUCIE -UNIT 1 5-1 Amendment No..W, 142 L-2018-120 Enclosure Page 7 of 15
St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ST. LUCIE UNIT lAND ST. LUCIE UNIT 2 PROPOSED TECHNICAL SPECIFICATIONS PAGE (MARKUP)
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St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ST. LUCIE UNIT lAND ST. LUCIE UNIT 2 PROPOSED TECHNICAL SPECIFICA'tiONS PAGE (MARKUP)
- ~ =~
EXCLUSION AREA
§.:4:.4
~~n area st:Jall ee as sh&Nn in Figure 6,1 1.
LQtN POPULATION ZONE
§.:4:2 The low population zone shall be as sho'lm on Figure 5.1 1.
5.2 CONTAINMENT CONHGURATION 5.2.1 The reactor containment building is a steel building of cylindrical shape, with a dome roof and having the following design features:
- a.
Nominal inside diameter= 140 feet.
- b.
Nominal inside height = 232 feet.
- c.
Net free volume = 2.506 x 1 06 cubic feet.
- d.
Nominal thickness of vessel walls = 2 inches.
- e.
Nominal thickness of vessel dome = 1 inch.
- f.
Nominal thickness of vessel bottom = 2 inches.
5:2.1.2 SHIELD BUILDING
- a.
Minimum annular space = 4 feet.
- b.
Annulus nominal volume= 543,000 cubic feet.
- c.
Nominal outside height (measured from top of foundation mat to the top of the dome) = 228.5 feet.
- d.
Nominal inside diameter= 148 feet.
- e.
Cylinder wall minimum thickness = 3 feet.
- f.
Dome minimum thickness= 2.5 feet.
- g.
Dome inside radius = 112 feet.
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The steel reactor containment building is designed ;:~nd shall be maintained for a maximum internal pressure of 44 psig and a temperature of 264°F.
ST. LUCIE-UNIT 2 5-1 Amendment No. 8 L-2018-120 Enclosure Page 9 of 15
St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 L-2018-120 Enclosure Page 10 of 15 ST. LUCIE UNIT lAND ST. LUCIE UNIT 2 PROPOSED TECHNICAL SPECIFICATIONS PAGE (MARKUP)
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St. Lucie Nuclear Plant L-2018-120 Docket Nos. 50-335 and 50-389 Enclosure Page 11 of 15 ST. LUCIE UNIT 1 AND ST. LUCIE UNIT 2 PROPOSED TECHNICAL SPECIFICATIONS PAGE (CLEAN COPIES)
(4 pages follow)
St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ST. LUCIE UNIT lAND ST. LUCIE UNIT 2 L-2018-120 Enclosure Page 12 o£15 PROPOSED TECHNICAL SPECIFICATIONS PAGE (CLEAN COPIES) 5 0 DESIGN FEATURES 5.1 DELETED 5.2 CONTAINMENT CONFIGURATION 5.2.1 The containment structure is comprised of a steel containment vessel, having the shape of a right circular cylinder with a hemispherical dome and ellipsoidal bottom, surrounded by a reinforced concrete shield building. The radius of the shield building is at least 4 feet greater than the radius of circular cylinder portion of the containment vessel at any point.
5.2.1.1 CONTAINMENTVESSEL
- a.
Nominal inside diameter= 140 feet.
- b.
Nominal inside height = 232 feet.
C.
Net free volume= 2.5 x 106 cubic feet.
- d.
Nominal thickness of vessel walls = 2 inches.
- e.
Nominal thickness of vessel dome = 1 inch.
- f.
Nominal thickness of vessel bottom = 2 inches.
ST. LUCIE-UNIT 1 5-1 Amendment No. W, ~
St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ST. LUCIE UNIT lAND ST. LUCIE UNIT 2 L-2018-120 Enclosure Page 13 o£15 PROPOSED TECHNICAL SPECIFICATIONS PAGE (CLEAN COPIES)
Figure 5.1-1 Deleted ST. LUCIE-UNIT 1 5-2 Amendment No. W, ~
St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ST. LUCIE UNIT lAND ST. LUCIE UNIT 2 L-2018-120 Enclosure Page 14 o£15 PROPOSED TECHNICAL SPECIFICATIONS PAGE (CLEAN COPIES) 5 0 DESIGN FEATURES 5.1 DELETED 5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel building of cylindrical shape, with a dome roof and having the following design features:
- a.
Nominal inside diameter= 140 feet.
- b.
Nominal inside height = 232 feet.
- c.
Net free volume= 2.506 x 106 cubic feet.
- d.
Nominal thickness of vessel walls = 2 inches.
- e.
Nominal thickness of vessel dome = 1 inch.
- f.
Nominal thickness of vessel bottom = 2 inches.
5.2.1.2 SHIELD BUILDING
- a.
Minimum annular space = 4 feet.
- b.
Annulus nominal volume = 543,000 cubic feet.
- c.
Nominal outside height (measured from top of foundation mat to the top of the dome) = 228.5 feet.
- d.
Nominal inside diameter= 148 feet.
- e.
Cylinder wall minimum thickness= 3 feet.
- f.
Dome minimum thickness = 2.5 feet.
- g.
Dome inside radius = 112 feet.
DESIGN PRESSURE AND TEMPERATURE 5.2.2 The steel reactor containment building is designed and shall be maintained for a maximum internal pressure of 44 psig and a temperature of 264°F.
ST. LUCIE - UNIT 2 5-1 Amendment No.-3
St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ST. LUCIE UNIT lAND ST. LUCIE UNIT 2 L-2018-120 Enclosure Page 15 of 15 PROPOSED TECHNICAL SPECIFICATIONS PAGE (CLEAN COPIES)
Figure 5.1-1 Deleted ST. LUCIE - UNIT 2 5-2 Amendment No.~