LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location

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License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location
ML23111A103
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 04/21/2023
From: Mannai D
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
LR-N23-0010, LAR S23-01, LAR H23-01
Download: ML23111A103 (1)
v • d • e


Text

PSEG Nuclear LLC P.O . Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG NuclearLLC 10 CFR 50.90 LR-N23-0010 LAR S23-01 LAR H23-01 April 21, 2023 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station Units 1 and 2 Renewed Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete TS Section 5.5 -

Meteorological Tower Location

References:

1. PSEG Letter to NRC, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS, dated September 29, 2021 (ADAMS Accession No. ML21272A184)
2. Letter from NRC to Eric Carr, Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 230, 342, and 323 RE: Deletion of Specified Definitions and Figures (EPID L-2021-LLA-0171), dated February 14, 2022 (ADAMS Accession No. ML22012A435)

In accordance with 10 CFR 50.90, PSEG Nuclear LLC (PSEG) hereby requests amendments to Renewed Facility Operating License (FOL) Nos. DPR-70 and DPR-75 for Salem Generating Station Units 1 & 2 (Salem) respectively and FOL No. NPF-57 for Hope Creek Generating Station (Hope Creek). In accordance with 10 CFR 50.91(b)(1), a copy of this request for amendment has been sent to the State of New Jersey.

LR-N23-0010 10 CFR 50.90 Page 2 The proposed amendment revises the TS for the above plants to remove TS Section 5.5, Meteorological Tower Location, in its entirety. Impact to this TS section was not identified in the changes requested in the Reference 1 License Amendment Request (LAR) which removed selected TS Definitions and Figures. One of the figures removed in the Reference 1 LAR is referenced in TS 5.5.1. The proposed amendment removes the reference to the figures removed from TS by the Reference 2 amendments.

The enclosure to this letter provides a detailed description and evaluation of the proposed changes.

Attachments 1 and 2 provide markups of the proposed changes to the affected pages of the TS for Salem Unit 1 and Salem Unit 2 respectively. provides a markup of the proposed changes to the affected pages of the TS for Hope Creek.

PSEG considers the proposed changes to be administrative in nature and therefore requests approval of this LAR within six months of NRC acceptance. Once approved, the amendment will be implemented within 60 days from the date of issuance.

There are no regulatory commitments contained in this letter.

If there are any questions or if additional information is needed, please contact Mr. Michael Wiwel at 856-339-7907.

I declare under penalty of perjury that the foregoing is true and correct.

04/21/2023 Executed on _______________________

(Date)

Respectfully, Digitally signed by Mannai, Mannai, David David Date: 2023.04.21 10:12:56

-04'00' David Mannai Executive Director - Regulatory Affairs and Nuclear Oversight PSEG Nuclear

Enclosure:

Description and Evaluation of the Proposed Change : Mark-up of the Current Salem Generating Station Unit 1 Technical Specification Pages : Mark-up of the Current Salem Generating Station Unit 2 Technical Specification Pages : Mark-up of the Current Hope Creek Generating Station Technical Specification Pages cc: Administrator, Region I, NRC Mr. J. Kim, NRC Project Manager, Salem & Hope Creek NRC Senior Resident Inspector, Salem NRC Senior Resident Inspector, Hope Creek Ms. Ann Pfaff, Manager NJBNE

LR-N23-0010 LAR S23-01 LAR H23-01 Enclosure Description and Evaluation of the Proposed Change License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location Table of Contents 1.0

SUMMARY

DESCRIPTION.2 2.0 DETAILED DESCRIPTION ............................................................................................... 2 2.1 Salem Unit 1 and Unit 2 TS Section to be Deleted .................................................... 2 2.2 Hope Creek TS Section to be Deleted ....................................................................... 2 2.3 Reason for the Proposed Change...2 2.4 Description of the Proposed Change..3

3.0 TECHNICAL EVALUATION

............................................................................................. 3

4.0 REGULATORY EVALUATION

......................................................................................... 3 4.1 Applicable Regulatory Requirements/Criteria ............................................................ 3 4.2 Precedents ................................................................................................................. 3 4.3 No Significant Hazards Consideration Analysis ......................................................... 4 4.4 Conclusion ................................................................................................................. 5

5.0 ENVIRONMENTAL CONSIDERATION

............................................................................ 5

6.0 REFERENCES

.................................................................................................................. 6 ATTACHMENTS:

1. Mark-up of the Current Salem Generating Station Unit 1 Technical Specification Pages
2. Mark-up of the Current Salem Generating Station Unit 2 Technical Specification Pages
3. Mark-up of the Current Hope Creek Generating Station Technical Specification Pages 1 of 6

LR-N23-0010 LAR S23-01 LAR H23-01 1.0

SUMMARY

DESCRIPTION This license amendment request proposes to remove Section 5.5, Meteorological Tower Location, in its entirety from both the Salem Generating Station (Salem) and Hope Creek Generating Station (Hope Creek) Technical Specifications (TS). This TS section was impacted by the Reference 2 License Amendment which removed Site Figures from both stations TS.

One of the Site figures removed was referenced by TS 5.5.1. The information contained in TS Section 5.5, Location of the Meteorological Tower, does not meet the requirements in 10 CFR 50.36, Technical Specifications (Reference 5) and is already contained in plant documentation such as the Updated Final Safety Analysis Report (UFSAR) and Offsite Dose Calculation Manuals (ODCMs). The proposed changes to both the Salem and Hope Creek TS are administrative in nature and are in alignment with NUREG-1431 (Reference 3) and NUREG-1433 (Reference 4) respectively.

2.0 DETAILED DESCRIPTION The Salem and Hope Creek TS proposed to be deleted are identified below.

2.1 Salem Unit 1 and Unit 2 TS Section to be Deleted 5.5 Meteorological Tower Location 5.5.1 The meteorological tower shall be located as shown in Figure 5.1-1 2.2 Hope Creek TS Section to be Deleted 5.5 Meteorological Tower Location 5.5.1 The meteorological tower shall be located as shown in Figure 5.1.1-1 The Index pages for both Salem and Hope Creek TS will be revised to reflect the deletion of Section 5.5 as depicted in the attached markups.

2.3 Reason for the Proposed Change The proposed deletion of TS Section 5.5 from both the Salem and HC TS addresses a condition of a disconnected TS that resulted from the Reference 2 LAR that, among other changes, removed TS Figure 5.1-1 from the Salem TS and TS Figure 5.1.1-1 from the Hope Creek TS. These figures depicted the overall site layout for each plant, including a depiction of the location of the meteorological tower. These TS Figures are respectively referenced by the Salem and Hope Creek TS 5.5.1. The impact to TS 5.5.1 was not identified in the changes requested in the Reference 1 LAR. The Reference 1 LAR was subsequently approved in the Reference 2 TS Amendment for both plants.

The proposed changes to both the Salem and Hope Creek TS are administrative in nature and are in alignment with NUREG-1431 (Reference 3) and NUREG-1433 (Reference 4) respectively.

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LR-N23-0010 LAR S23-01 LAR H23-01 2.4 Description of the Proposed Change TS Section 5.5 described above in Sections 2.1 and 2.2 for Salem and Hope Creek respectively will be deleted in its entirety as shown in Attachments 1 through 3.

3.0 TECHNICAL EVALUATION

The proposed change deletes Section 5.5 in its entirety from the Salem and Hope Creek TS.

The location of the meteorological tower is already defined in station controlled documents such as plant drawings, the UFSAR and the ODCMs for both stations. Having these terms defined in the TS in addition to licensee-controlled station documents is duplicative. Deletion of Section 5.5 from the TS does not affect the substance of any other TS requirement. Deleting this TS for both stations is considered to be administrative in nature, does not affect the design or operation of any plant Structures, Systems or Components (SSCs) and will align the Salem and Hope Creek TS with NUREG-1431 and NUREG-1433 respectively relative to unnecessary information within the TS.

10 CFR 50.36 contains a set of objective criteria for determining which regulatory requirements and operating restrictions should be included in TS. The description of the location of the Site meteorological tower in TS Section 5.5 does not meet the requirements of 10 CFR 50.36 (c)(4),

Design Features of Technical Specifications. The proposed deletions of TS Section 5.5 will not impact any safety limits, limiting safety system settings, limiting conditions of operation or surveillance requirements as described in paragraphs (c)(1),(2), and (3) of 10 CFR 50.36.

Therefore the deletion of this section from station TS conforms to the requirements of 10 CFR 50.36.

4.0 REGULATORY EVALUATION

4.1 Applicable Regulatory Requirements/Criteria 10 CFR 50.36(c) contains a set of objective criteria for determining which regulatory requirements and operating restrictions should be included in TS. These criteria include Limiting Conditions for Operation (LCOs), Safety Limits (SLs), Limiting Safety System Settings (LSSSs) and Surveillance Requirements (SRs) associated with plant structures, systems and components (SSCs) that support the safety analyses of plant. The proposed change involves removing information from the TS that does not fit the requirements of 10 CFR 50.36 for inclusion in TS. The proposed removal of TS Section 5.5, Meteorological Tower Location, is in alignment with the level of information necessary for station TS and is considered administrative in nature. All LCOs, SLs and LSSSs associated with plant SSCs remain unchanged from this proposed amendment.

All TS requirements for plant SSCs remain in accordance with 10 CFR 50.36(c).

Therefore, the proposed changes are consistent with current regulations.

4.2 Precedents Removal of Section 5.5, Meteorological Tower Location, is aligned with the Improved Standard Technical Specifications detailed in NUREG-1431 and NUREG-1433 and reflected in the TS for multiple plants.

3 of 6

LR-N23-0010 LAR S23-01 LAR H23-01 Amendments approving adoption of Improved Standard Technical Specifications have characterized the removal of the meteorological tower location as administrative changes. The proposed changes to remove TS Section 5.5 from TS are consistent with the following precedents:

1. Letter from NRC to M. Nazar, St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map (EPID L-2018-LLA-0198), dated November 2, 2018 (ADAMS Accession No. ML18274A224)
2. Letter from NRC to J. A. Price, Millstone Power Station, Unit Nos. 1, 2, and 3 -

Issuance of Amendments RE: Administrative and Editorial Changes (TAC Nos.

MB3394, MB3395, and MB3396), Dated September 17, 2002 (ADAMS Accession No. ML022000322)

3. Letter from NRC to C. R. Hutchinson, Arkansas Nuclear One, Unit No. 2 - Issuance of Amendment RE: Design Features and Administrative Controls (TAC No.

MA2403), Dated May 19, 1999 (ADAMS Accession No. ML021560327)

4. Letter from NRC to R.E. Denton, Issuance of Amendments for Calvert Cliffs Nuclear Power Plant, Unit No. 1 (TAC No. M88429) and Unit No. 2 (TAC No. M88430),

Dated March 14, 1995, (ADAMS Accession No. ML010580033) 4.3 No Significant Hazards Consideration Analysis The proposed changes delete Section 5.5, Meteorological Tower Location, within the Salem Generating Station (Salem) and Hope Creek Generating Station (Hope Creek)

Technical Specifications (TS). The location of the site meteorological tower is already contained in the Offsite Dose Calculation Manual (ODCM) for both the Salem and Hope Creek sites as well as in plant drawings and the Updated Final Safety Analysis Report (UFSAR) for both plants. The changes do not affect any system, structure or component nor does it alter any requirement relative to plant operations, hence the changes do not involve any significant hazard.

The discussion below addresses each criterion and demonstrates that the proposed amendment does not constitute a significant hazard.

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

Response: No.

The requested changes to delete Section 5.5, Meteorological Tower Location, from the Salem Generating Station and Hope Creek Generating Station TS are administrative in nature. No actual plant equipment, accident analyses or dose consequences are affected by the proposed changes.

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

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LR-N23-0010 LAR S23-01 LAR H23-01

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

Response: No.

This request involves administrative changes to the Salem and Hope Creek TS to remove Section 5.5, Meteorological Tower Location.

The changes are administrative in nature and no actual plant equipment or accident analyses will be affected by the proposed changes and no new failure modes or accident initiators will be created.

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

3. Do the proposed amendments involve a significant reduction in a margin of safety?

Response: No.

The changes being proposed are administrative in nature. Margins of safety are associated with confidence in the ability of the fission product barriers to limit the level of potential dose to the public. No actual plant equipment or accident analyses will be affected by the proposed change. Additionally, the proposed changes will not relax any criteria used to establish safety limits, will not relax any safety systems settings, nor will they relax the bases for any limiting conditions of operation.

Therefore, the proposed amendments do not involve a significant reduction in the margin of safety.

Based on the above, PSEG concludes that the proposed amendments present no 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.

4.4 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 Commission's 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

A review has determined that the proposed administrative amendment does not change any requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, nor does it change an inspection or surveillance requirement. 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 5 of 6

LR-N23-0010 LAR S23-01 LAR H23-01 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.

6.0 REFERENCES

1. PSEG Letter to NRC, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS, dated September 29, 2021 (ADAMS Accession No. ML21272A184)
2. Letter from NRC to Eric Carr, Hope Creek Generating Station and Salem Nuclear Generating Station , Unit Nos. 1 and 2 - Issuance of Amendment Nos. 230, 342, and 323 RE: Deletion of Specified Definitions and Figures (EPID L-2021-LLA-0171), dated February 14, 2022 (ADAMS Accession No. ML22012A435)
3. NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 5.
4. NUREG-1433, Standard Technical Specifications - General Electric Plants (BWR/4), Revision5.
5. 10 CFR 50.36 - Technical Specifications 6 of 6 LAR S23-01 LR-N23-0010 LAR H23-01 Mark-up of the Current Salem Generating Station Unit 1 Technical Specification Pages The following Technical Specifications pages for Renewed Facility Operating License DPR-70 are affected by this change request:

Technical Specification Page INDEX XVII 5.5 5-5 1

INDEX DESIGN FEATURES

============================================================

SECTION PAGE 5.1 SITE LOCATION. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . .. . . . .. . . . .. . . . .5-1 5.2 CONTAINMENT Configuration . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. . . . .. . . . . . . . . . . .. . . . . . . . 5-1 Design Pressure and Temperature . . . . . . . . . . . . . . . . . .. . . . .. . . . .. . . .. . . . . . 5-4 5.3 REACTOR CORE Fuel Assemblies . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. . . . .. . . . .. . . .. . . 5-4 Control Rod Assemblies . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. . . . .. . . . . . . . 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature . . . . . . . . . . . . . . . . . .. . . . .. . . . .. . . . . . . . . 5-4 5.5 METEOROLOGICAL TOWER LOCATION . DELETED . . . . . . . . .. . . . .. . . . .. . . . . . . . . .. 5-5 5.6 FUEL STORAGE Criticality . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. . . . .. . . . . .. . . . . . . 5-5 Drainage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .. . . . .. . . . . . . . . 5-6a Capacity . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . .. . . . .. . . . .. . . . . . . 5-6a 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT . . . .. . . . .. . . . .. . . . . . . . . . . . 5-6a XXX SALEM - UNIT 1 XVII Amendment No. 342

DESIGN FEATURES

a. In accordance with the code requirements specified in Section 4.1 of the FSAR, with allowance for nonnal degradation pursuant to the applicable Surveillance Requirements,
b. For a pressure of 2485 psig, and
c. For a temperature of 650°F, except for the pressurizer which is 680"F.

5.5 METEOROLOGICAL TOWER LOCATION DELETED s.s.1 The meteorological tower shall be located as shown on Figure 5.1-1 ..

5.6 FUEL STORAGE CRITICALITY 5.6.1.l The new fuel storage _racks are *designed and shall be maintained with:

a. A maximU11\ K.u equivalent of o*.95 with the storage racks flooded with unborated water.
b. A nominal 21.0 inch center-to-center distance between fuel assemblies.
c. Unirradiated fuel assemblies with enrichments less than or equal to 4.25 weight percent (w/o) U-235 with po requirements for Integral Fuel Burnable Absorber (IFBA) pins.
d. Unirradiated fuel assemblies with enrichments (E) greater than 4.25 w/o U-235 and less than or equal to 5.0 w/o U-235 which contain a minimum number of Integral FU.el Burnable Absorber (IFBA) pins. This minimum number of IFBA pins shall have an equivalent reactivity hold-down which is greater than or equal to the reactivity ho1d down associated with N IFllA pins, at a
  • nominal 2.35 mg B-10/linear inch loading (1.SX), determined by the.equation below:

N = 42,67 { E - 4.25)

XXX SALEM - UNIT 1 5-5 runendment No. 'Jf:IJ LAR S23-01 LR-N23-0010 LAR H23-01 Mark-up of the Current Salem Generating Station Unit-2 Technical Specification Pages The following Technical Specifications pages for Renewed Facility Operating License DPR-75 are affected by this change request:

Technical Specification Page INDEX XVII 5.5 5-5 1

INDEX DESIGN FEATURES

============================================================

SECTION PAGE 5.1 SITE LOCATION ............................................. ......... .......... .......................... ......5-1 5.2 CONTAINMENT Configuration ............................................. ... ...................................... ...................5-1 Design Pressure and Temperature ...... ............................................. .....................5-4 5.3 REACTOR CORE Fuel Assemblies ............. ............ ............................................................ ...............5-4 Control Rod Assemblies .............. ........................... ............................ ...................5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature ........... ................................ ........ ....................5-4 5.5 METEOROLOGICAL TOWER LOCATION ............ DELETED .................... ..........................5-5 5.6 FUEL STORAGE Criticality ............................... ............... .................................... ..............................5-5 Drainage ............... ........................................... ......................... .............................5-5b Capacity ................. ........................................... ............................. ........................5-5b 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT...... .................. ...........................5-5b XXX SALEM - UNIT 2 XVII Amendment No 323

DESIGN FEATURES 5.5 METEOROLOGICAL TOWER LOCATION DELETED 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The new fuel storage racks are designed and shall be maintained with:

a. A maximum Keff equivalent of equal to 0.95 with the storage racks flooded with unborated water.
b. A nominal 21.0 inch center-to-center distance between fuel assemblies.
c. Unirradiated fuel assemblies with enrichments less than or equal to 4.25 weight percent (w/o) U-235 with no requirements for Integral Fuel Burnable Absorber (IFBA) pins.
d. Unirradiated fuel assemblies with enrichments (E) greater than 4.25 w/o U-235 and less than or equal to 5.0 w/o U-235 which contain a minimum number of Integral Fuel Burnable Absorber (IFBA) pins. This minimum number of IFBA pins shall have an equivalent reactivity hold-down which is greater than or equal to the reactivity hold down associated with N IFBA pins, at a nominal 2.35 mg B-10/linear inch loading (1.SX), determined by the equation below:

N = 42.67 ( E - 4.25 5.6.1.2 The spent fuel storage racks are designed and shall be maintained with:

a. A maximum Keff equivalent of 0.95 with the storage racks filled with unborated water.
b. A nominal 10.5 inch center-to-center distance between fuel assemblies stored in Region 1 (flux trap type) racks.
c. A nominal 9.05 inch center-to-center distance between fuel assemblies stored in Region 2 (non-flux trap) racks.

XXX SALEM - UNIT 2 5-5 Amendment No, 244 LAR S23-01 LR-N23-0010 LAR H23-01 Attachment 3 Mark-up of the Current Hope Creek Generating Station Technical Specification Pages The following Technical Specifications pages for Renewed Facility Operating License NPF-57 are affected by this change request:

Technical Specification Page INDEX xxiii 5.5 5-5 1

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE LOCATION ......................... ....................................................................... 5-1 5.2 CONTAINMENT Configuration .............................................................................................. 5-1 Design Temperature and Pressure ............................................................. 5-1 Secondary Containment ............................................................................. 5-1 5.3 REACTOR CORE Fuel Assemblies......................... ................................................................ . 5-4 Control Rod Assemblies ............................................................................. 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature ............................................................. 5-4 Volume ....................................................................................................... 5-5 5.5 METEOROLOGICAL TOWER LOCATION ...........................................................

DELETED 5-5 5.6 FUEL STORAGE Criticality ..................................................................................................... 5-5 Drainage ..................................................................................................... 5-5 Capacity ..................................................................................................... 5-5 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT.................................................... 5-5 Table 5.7.1 1 Component Cyclic or Transient Limits ....................... 5-6 XXX HOPE CREEK xxiii Amendment No. 230

PE§IQN fEAIYBE§ 5.4 REACTOR COOLANT SYSTEM (continued)

VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 21,970 cubic feet at a nominal steam dome saturation temperature of 547°F.

5.5 METEOROLOGICAL TOWER LOCATION DELETED 5.5.1 The meteorological tower shall be located as shown on Figure 5.1.1-1.

5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:

a. A ket, equivalent to less than or equal to 0.95 when flooded with unborated water, including all calculational uncertainties and biases as described in Section 9.1.2 of the FSAR.
b. A nominal 6.308 inch center-to-center distance between fuel assemblies placed in the storage racks.

5.6.1.2 The ket, for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation Is assumed.

DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent Inadvertent draining of the pool below elevation 199' 4".

CAPACITY 5.6.3 The spent fuel storage pool shall be limited to a storage capacity of no more than 4006 fuel assemblies.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components Identified in Table 5.7.1-1 are designed and shall be maintained within the cyclic or transient limits of Table 5. 7.1-1.

XXX HOPE CREEK 5-5 Amendment No. 184

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