ML20211G728
| ML20211G728 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 02/06/1987 |
| From: | James O'Reilly GEORGIA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20211G734 | List: |
| References | |
| 0037M, 37M, SL-1900, TAC-64778, NUDOCS 8702250504 | |
| Download: ML20211G728 (11) | |
Text
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Georgra Power Cornpany
, 333 Piedmont Avenue s Atlanta, Georgia 30308 Telephone 404 526 7851 Maibng Address Fbst Office Box 4545 A!!anta, Georgia 30302
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r V ce Pr dont Nuclear Operatrons SL-1900 0037m February 6,1987 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS STANDBY LIQUID CONTROL SYSTEM OPERATION USING ENRICHED SODIUM PENTABORATE Gentlemen:
In accordance with the provisions of 10 CFR 50.90 as required by 10 CFR 50.59(c)(1), Georgia Power Company hereby proposes changes to the Technical Specifications, Appendix A to Operating License DPR-57.
The majority of the proposed changes address the use of sodium pentaborate enriched with the boron-10 isotope in the Standby Liquid Control System (SLCS). Georgia Power Company has proposed the use of enriched sodium pentaborate to meet the requirements of the ATWS Rule,10 CFR 50.62 paragraph (c)(4). The remainder of the changes are intended to achieve consistency between the Unit 1 and Unit 2 SLCS Technical Specifications.
Enclosure 1 provides a detailed description of the proposed changes and circumstances necessitating the change request.
Enclosure 2 details the basis for our determination that the proposed changes do not involve significant hazards considerations.
Enclosure 3 provides page change instructions for incorporating the proposed changes into the Plant Hatch Unit 1 Technical Specifications. The proposed changed Plant Hatch Unit 1 Technical Specifications pages follow Attachment 3.
Payment of filing fee is enclosed.
In order to allow time for procedure revision and orderly incorporation into copies of the Technical Specifications, we request that the proposed amendment once approved by the NRC, be issued with an effective date to be no later than 60 days from the date of issuance of the amendment.
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L U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 February 6,1987 Page 2 Pursuant to the requirements of 10 CFR 50.91, Mr. J. L. Ledbetter of the Environmental Protection Division of the Georgia Department of Natural Resources will be sent a copy of this letter and all applicable attachments.
James P. O'Reilly states that be is Senior Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.
GEORGIA P0 DER COMPANY By: k m f.W 921L Ja s P. O'Reilly g Sworn to and subscribed before me this 6th February, N WOui Notary Public
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JH/1m Enclosures xc: Georgia Power Company U. S. Nuclear Regulatory Commission Mr. J. T. Beckham, J r. Dr. J. N. Grace, Regional Administrator Mr. H. C. Nix, Jr. Mr. P. Holmes-Ray, Senior Resident GO-NORMS Inspector-Hatch Mr. G. Rivenbark, Licensing Project Manager State of Georgia Mr. J. L. Lodbetter 0037m
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U. S. Nuclear Regulatory Comission ATTN: Document Control Desk Washington, D. C. 20555 February 6,1987 Page 2 Pursuant to the requirements of 10 CFR 50.91, Mr. J. L. Ledbetter of the Environmental Protection Division of the Geor0 ai Department of Natural Resources will be sent a copy of this letter and all applicable attachments.
J;. P. O'Reilly states that he is Senior Vice President of Georgia Power Compan and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowledge and belief the facts set forth in this letter are true.
GEORGIA POWER COMPANY D
By:d JgP.O'Reilly Sworn to and subscribed before me this 6th day of February, Notary Public JH/im Enclosures xc: Georgia Power Company U. S. Nuclear Regulatory Comir.sion Mr. J. T. Beckham, Jr. Dr. J. N. Grace, Regional Administrator Mr. H. C. Nix, Jr. 11r. P. Holmes-Ray, Senior Resident GO-NORMS Inspector-Hatch Mr. G. Rivenbark, Licensing Project Manager State of Georgia Mr. J. L. Ledbetter 0037m
L k ENCLOSURE 1 TO SL-1900 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIH I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS BASIS FOR CHANGE REQUEST Of the following proposed Technical Specification changes, the first two are directly related to the use of enriched sodium pentaborate to meet the requirements of 10 CFR 50.62. The remaining two changes are proposed primarily to make the Unit I and Unit 2 Technical Specifications uniform in content.
Proposed Change 1 The current Unit 1 Technical Specifications place requirements on the volume and concentration of sodium pentaborate solution in the standby liquid control system (SLCS) tank. This change modifies these requirements to reflect the use of enriched sodium pentaborate and involves revising Figures 3.4-1 and 3.4-2. The basis for those changed requirements is reflected in revised bases for section 3/4.2.
Basis This change is proposed as a result of new requirements placed on the SLCS by the ATWS Rule,10 CFR 50.62. The ATWS Rule requires each operating BWR to have an SLCS equivalent in control capacity to a system with an 86 gpm injection rate of 13 weight percent unenriched sodium pentaborate solution, normalized to a 251 inch diameter reactor vessel. Georgia Power Company has chosen to meet this requirement for Plant Hatch by using sodium pentaborate enriched in the boron-10 isotope. This approach was one of several proposed in General Electric's licensing topical report NEDE-31096-P (Reference 1) and found acceptable by an HRC safety evaluation (Reference 2).
The increase in reactivity control capability provided by the enriched sodium pentaborate makes it possible to reduce the minimum limits on solution volume and concentration. The minimum allowable concentration of enriched sodium pentaborate is determined by the lowest concentration that will meet the requirements of the ATWS Rule. Using the calculation methods of HEDE-31096-P, a minimum concentration of 6.2 weight percent sodium pentaborate was found to adequately address the requirements of this provision of the ATWS Rule, based on sodium pentaborate enriched to 60 weight percent boron-10, an injection flow rate of 41.2 gpm, and a water mass of 434,800 pounds contained within the reactor vessel and associated piping. These values were chosen so that the results could be applied to both Hatch units.
-El 0037n
ENCLOSURE 1 TO SL-1900 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIF~.;ATIONS BASIS FOR CHANGE REQUEST 1
The effect of decreasing the solution concentration will be to reduce the precipitation temperature for the sodium pentaborate solution. This reduces the possibility of system failure due to sodium pentaborate precipitation, and increases the reliability of the system.
The minimum allowable volume of solution is a function of concentration, and is calculated to meet or exceed the existing shutdown margin of safety.
The Technical Specifications for Unit 2 require a larger margin of safety than those for Unit 1. Because it was considered desirable to have a single set of limits applicable to both units, the proposed volume limits increase the existing margin of safety for Unit 1 to that for Unit 2. The proposed minimum volume of 6.2 weight percent solution is 2883 gallons gross volume; for higher concentrations a lower volume is required. These volumes include the unusable portion of solution that would be left in the tank and suction lines following SLCS operation.
The shutdown capability of the SLCS depends on the amount of the isotope baron-10 in the SLCS tank. If enriched sodium pentaborate is to be used, it is necessary that the enrichment is verified. This will be donc prior to the acceptance of the sodium pontaborate for use on site. Currently, the sodium pentaborate solution is prepared by adding granular boric acid and borax to water. Enriched sodium pentaborate will be procured as a granular powder that can be mixed directly with water, eliminating the process of combining borax with boric acid. The contents of the SLCS tank will change only when the amount of water or enriched sodium pentaborate is changed. Once the isotopic content of the granular sodium pentaborate is verified, only the solution volume, concentration, and temperature need to be monitored. The current surveillance requirements are adequate to accomplish this.
Proposed Change 2 Replace the current bases text with text that addresses operation with enriched sodium pentaborate.
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ENCLOSURE 1 TO SL-1900 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS BASIS FOR CHANGE REQUEST Basis This change updates the bases to accurately reflect the configuration of the SLCS. Both the original SLCS design basis and the ATWS rule requirements are addressed in the proposed revision. In addition, extraneous information currently contained in the Unit 1 bases is deleted. The level of detail in the proposed revision is consistent with the Unit 2 bases and the GE Standard Technical Specifications. '
Proposed Change 3 The current Unit 1 SLCS pump minimum acceptable flow rate for surveillance testing is 43 gpm, while Unit 2 references 41.2 gpm. Change the Unit 1 value to 41.2 gpm.
Basis This change is proposed to make Unit 1 and Unit 2 surveillance requirements consistent. The proposed solution volume and concentration Ifmits were calculated based on 41.2 gpm. Neither the margin of safety nor the operation of the system is affected by this change.
Proposed Change 4 Renove the alarm setpoints from figures 3.4-1 and 3.4-2.
Basis Figures 3.4-1 and 3.4-2 currently show alarm setpoints for SLCS tank volume and temperature. These alarms are used to maintain the solution within administrative limits, and are not used to determine operability of the system. They are shown on these figures for information only. The Unit 2 Technical Specifications do not discuss these alarms. Because these alarns are shown for information only, their deletion from Figures 3.4-1 and 3.4-2 does not affect the margin of safety for the SLCS.
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ENCLOSURE 1 TO SL-1900 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS BASIS FOR CHANGE REQUEST References
- 1. " Anticipated Transients Without Scram: Response to NRC ATWS Rule,10 CFR 50.62", NEDE-31096-P, December 1985
- 2. " Safety Evaluation of Topical Report (NEDE-31096-P) ' Anticipated Transients Without Scram: Response to ATWS Rule, 10 CFR 50.62'",
October 21, 1986.
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L ENCLOSURE 2 TO SL-1900 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
10 CFR 50.92 EVALUATION Pursuant to 10 CFR 50.92, reorgia Power Company has evaluated the attached proposed amendment for Plant Hatch Unit 1 and has determined that its adoption would not involve a significant hazard. The basis for this determination is as follows.
Proposed Change 1 The current Unit 1 Technical Specifications place limits on the volume and concentration of sodium pentaborate solution in the standby liouid control system (SLCS) tank. This change decreases these limits to reflect the use of enriched sodium pentaborate. This change involves revising Figures 3.4-1 and 3.4-2, and incorporating the basis for this change into the bases section for 3/4.4 Basis This change is proposed as a result of new requirements placed on the SLCS by the ATWS Rule,10 CFR 50.62. Because it results in minor changes to plant operations, this change is consistent with Item (vii) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the Federal Register, April 6,1983.
This change does not involve a significant hazards consideration for the following reasons:
- 1. The proposed change does not increase the probability or consequences of an accident previously evaluated because the reliability and function of the SLCS are unaffected by this change. Because the injection tirne is decreased, the capability of the SLCS to respond to an ATWS is improved.
- 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated because no new plant configurations for operation result from this change.
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ENCLOSURE 2 TO SL-1900 p NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN 1. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
10 CFR 50.92 EVALUATION
- 3. The proposed change does not involve a significant reduction in the margin of safety because the minimum volume and concentration limits are calculated to increase the existing Unit 1 shutdown margin to that for Unit 2.
Proposed Change 2 Replace the current bases text with text that addresses operation with enriched sodium pentaborate.
Basis This change is consistent with Item (1) of the " Examples of Amendments that are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14,870 of the Federal _ Register, April 6, 1983. Because this change does not affect the operation of the SLCS in any way, it is administrative in nature.
This change does not involve a significant hazards consideration for the following reasons:
- 1. The proposed change does not increase the probability or consequences of an accident previously evaluated because no accident analysis is affected.
- 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated because system operation is not affected in any way.
- 3. The proposed change does not involve a significant reduction in the margin of safety because system operation is not affected in any way.
Proposed Change 3 The current Unit 1 SLCS pump minimum acceptable flow rate for surveillance testing is 43 gpm, while Unit 2 references 41.2 gpn. Change the Unit 1 value to 41.2 gpm.
Basis l This change is proposed to make Unit 1 and Unit 2 surveillance requirements consistent. Neither the margin of safety nor the operation of the system is affected by this change. Thus, this change is consistent with Item (i) of the " Examples of Amendments that are Considered Not Likely to ,
Involve Significant Mazards Considerations" listed on page 14,870 of the l Federal Register, April 6,1983.
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ENCLOSURE 2 TO SL-1900 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
10 CFR 50.92 EVALUATION, This change does not involve a significant hazards consideration for the following reasons:
- 1. The proposed change does not increase the probability or consequences of an accident previously evaluated because the capability of the SLCS to fulfill its design function is unaffected. The calculations affecting the proposed technical specification changes for SLCS are based on 41.2 gpm, not 43 gpm.
- 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated because no new modes of plant operation are introduced.
- 3. The proposed change does not involve a significant reduction in the margin of safety because 41.2 gpm was the basis for calculating the Technical Specification operating limits for SLCS.
1 Proposed Change 4 Remove the alarm setpoints from Figures 3.4-1 and 3.4-2.
Basis a Because these alarm setpoints are shown for information only, this change
! is purely administrative in nature. Thus, it is consistent with Item (i) of j the " Examples of Amendments that are Considered Not Likely to Involve l Significant Hazards Considerations" listed on page 14,870 of the Federal Register, April 6,1983 This change does not involve a significant hazards consideration for the following reasons:
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- 1. The proposed change does not increase the probability or consequences of an accident previously evaluated because no accident analyses are l affected.
- 2. The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated because no new operational configurations are presented by this i
change.
- 3. The proposed change does not involve a significant reduction in the margin of safety because the referenced alarms are used to maintain administrative limits on the solution, not to determine operability j of the systen.
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i ENCLOSURE 3 TO SL-1900 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 EDWIN I. HATCH NUCLEAR PLANT UNIT 1 i
REQUEST TO REVISE TECHNICAL SPECIFICATIONS:
INSTRUCTIONS FOR INCORPORATION 1
The proposed changes to Technical Specifications (Appendix A to Operating License DPR-57) would be incorporated as follows:
i Remove Page Insert Page j 3.4-1 3. 4 -1 3.4-4 3.4-4 3.4-5 3.4-5 3.4-6 l
- Figure 3.4-1 Figure 3.4-1 i Figure 3.4-2 Figure 3.4-2 ,
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