ML20248B626
| ML20248B626 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/11/1998 |
| From: | Broadbent G, Stanchfield S, Withrow M ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20248B623 | List: |
| References | |
| GGNS-MS-48.0, GGNS-MS-48.0-R06, GGNS-MS-48.0-R6, NUDOCS 9806010351 | |
| Download: ML20248B626 (41) | |
Text
{{#Wiki_filter:-- Standard No.: GGNS-MS-48.0 l Revision: 6 Date: 5/N/ff Grand Gulf Nuclear Station Core Operating Limits Report Safety-Related l l i 9806010351 980521 l PDR ADOCK 05000416-P PDR , j I J
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Standard No.: GGNS-MS.48.0 Page: ii of vi
. Revision No.: 6 GRAND GULF NUCLEAR STATION NUCLEAR PLANT ENGINEERING REVIEW AND APPROVAL SHEET STANDARD NO.: GGNS.MS.48.0 REVISION: 6 STANDARD TITLE: Core Operating Limits Report This document specifies items related to nuclear safety YES [X] NO[]
This document contains Special Requirements YES [ ] NO [X] Signatures certify that the above standard was originated, verified, reviewed or waived and approved as noted below: ORIGINATED BY: .f. DATE: .6/tt, 9 VERIFIED BY: N "bigd DATE: SM//pg w v y REVIEWED BY: \%d1.h k mh Libr. L
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Group $upprvisor DATE: 6//i/93 ' J DESIGN ENGINEERING SECTION REVIEWED BY REVIEW WAIVED BY DATE 6////f8 ELECTRICAL /I&C 6. 6 MECHANICAUCIVIL M /o/ {//f7 SAFETY ANALYSIS (
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ANil: DATE: l (Insert N/A if not applicable) APPROVED BY: [dhw ' b h h.lU b r Respon\ible Manager DATE: 5//I/7e? '
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l Fonn 321.1, Revision 7 i
Standard No.: GGNS-MS-48.0 Page: iii of vi
- Revision No.: 6 SAFETY EVALUATION APPLICABILITY REVIEW FORM A) Document Evaluated: Standard GGNS-MS-48.0, Revision 6 B)- Description of the Proposed Change: Per GNRI-93-008. Amendment 106 to the Grand Gulf Operating License, Entergy committed to removing certain reactor physics parameters from the Technical Specifications and placing them in a separate report prepared for each fuel cycle. Standard GGNS-MS-48.0 is the Core Operating Limits Report (COLR) and establishes these parameters. Revision 6 to GGNS-MS-48.0 reports the Cycle 10 core operating limits.
PRE-SCREENING i Check the applicable boxes below. If any of the boxes are checked, neither a safety evaluation applicability review nor a safety evaluation is necessary and steps C, D, E, and F may be skipped. The preparer and reviewer must sign at the bottom of the form. The change is editorial as defined in Section 6.2.1 of PAP 01-S-06-24. 10CFR50.59 does not apply per Section 6.2.2 of PAP 01-S-06-24. Reference An approved safety evaluation covering all aspects of this subject already exists. Reference SE # - . - The change, in its entirety, has been approved by the NRC. Reference The change is an FSAR change that meets the exclusion criteria outlined in the 10CFR50.59 Safety Evaluation Guidelines and the change does not represent a change to the Technical Specifications or the Technical Requirements Manual. Safety Evaluation Applicability Review if any of the following questions are answered "yes", then a full 50.59 Safety Evaluation must be i completed. C) Does the proposed change or activity represent a change to the Technical Specifications? YES Explain: NO X Changes to GGNS Technical Specification are required in support of this reload. A Technical Specification change has been submitted and a NRC SER is required for the validity of Safety Evaluation 98-0035.
i Standard No.: GGNS MS-48.0 Page: iv of vi
. Revision No.: 6 D) Does the proposed change or activity represent:
(1) A change to the facility which alters, or has the potential to alter, the information, operation, function or ability to perform the function of a system, structure or component described in the SAR? YES X Explain: NO This standard reports the Cycle 10 core operating limits. Changes to Section 15 of the SAR are required to update the transients with the current results. The initial Cycle 10 changes will be processed in LDCR 1998-030 and evaluated with Safety Evaluation 98-0035. When open items involving the PRFDS event are resolved with GE. the power-dependent limits without PRFDS will be implemented under separate safety evaluation. (2) A change to a procedure which alters, or has the potential to alter, a procedure described, outlined or summarized in the SAR? , YES Explain: l NO X This standard reports the Cycle 10 core operating limits. No procedure changes are made or proposed by this report. (3) A test or experiment not described in the SAR or which requires that a system be _. operated in an abnormal manner that is not described or previously analyzed in the SAR? YES Explain: NO X This standard reports the Cycle 10 core operating limits. No tests or _ experiments are proposed by this report. PREPARER h ' h Geq 6kR Name Job TitO 'Daie REVIEWER kg mYd E,,,, y SAibs V %Id I Jo6 Title ' daie If the preparer performed an applicability review, the reviewer should check below to indicate by which means the independent review reached the same conclusions. _v' Reviewed the applicability review documentation. Completed an independent applicability review. Performed a verbal review with the preparer.
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Standard No.: GGNS-MS-48.0 Page: v of vi
. Revision No.: 6 REVISION STATUS SHEET STANDARD REVISION
SUMMARY
REVISION ISSUE DATE DESCRIPTION 0 April 1,1993 Issued for Cycle 6 1 November 12,1993 Issued for Cycle 7 2 August,26,1994 Revised for Cycle 7 to update references for QDR 0159-94 3 May 18,1995 Issued for Cycle 8 4 November 18,1996 Issued for Cycle 9 5 July 31,1997 Revised for Cycle 9 per GGCR1997-0074-00 6 5/si/d Issued for Cycle 10 PAGE REVISION STATUS PAGE NO. REVISION PAGE NO. REVISION i 6 1 6 ii 6 2 6 iii 6 3 6 iv 6 4 4 v 6 5 6 vi 6
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APPENDIX / ATTACHMENT STATUS ATTACIIMENT NO. REVISION APPENDIX NO. REVISION 1 2 2 1 3 2 _ _ _ _ . _ - - _ _ - - - - - I
Standard No.: GGNS-MS-48.0 Page: vi of vi
. Revision No.: 6 TABLE OF CONTENTS 1.0PUFOSE.......................................................................................................................I 2.0 SCONE..................................................................................................................................3 t .
3.0EFERENCES................................................................................................................... 4 .0 I) E FI N 1 TI O N S, . . . . . . . . . . . . . . . . . . . .. . .. .. . . . . . .. .. . . .. . . . . . .. .. .. . . .. . . . .. .. . . . . . . .. . . .. . . . .. . . . . . . . .. . . .. . . . . . . . . . . . . . . . . . . . . . . . 3 5.0 G EN E RA L REQ UI REM ENTS .. . ............... ......... ..... ..... . .. ..... ......... .... ............. .... ............... .. 4 5.1 Average Planar Linear Heat Generation Rates ........ ......................................................... 5 5.2 Minimum Critical Power Ratio ................. ......... .................. ................. ..... ................ ... 5 5.3 Linear H eat Generation Rate . ...... .. .. . . ... ....... ... . ..... .. ......... ... ..... ..... .. .. ...... ......... ... . ... . .. . . .. . 5 5 .4 A ppl i cabi l i ty . . .. . . . . . . .. . . . . . . . . . . . . . . . .. . .. . . . . . . . . . . . . . . . . . .. . . . .. . . . .. . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 Attachment 1 APLliGR Operating Limits Attachment 2 MCPR Operating Limits Attachment 3 LliGR Operating Limits l 1 i i I I i t I l . .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _
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Standard No.: GGNS-MS-48.0 Page: 1 of 5
. Revision No.: 6 1.0 PURPOSE-On October 4. '1988,' the NRC issued Generic Letter 88-16 [1] encouraging licensees to remove cycle-specific parameter limits from Technical Specifications and to place these limits in a formal report to be prepared by the licensee. As long as the parameter limits were developed with NRC-approved methodologies, the letter indicated that this would remove unnecessary burdens on licensee and NRC resources.
On October 29,1992, Entergy Operations submitted a Proposed Amendment to the Grand Gulf Operating License requesting changes to the GGNS Technical Specifications to remove certain - reactor physics parameter limits that change each fuel cycle [2]. This amendment committed to - placing these operating limits in a separate Core Operating Limits Report (COLR) which is defined in Technical Specifications. This PCOL was approved by the NRC by SER dated January 21,1993 [3]. The COLR is controlled via Mechanical Standard GGNS-MS-48.0. This standard is revised accordingly for each fuel cycle or remaining portion of a fuel cycle. Revision 6 of the COLR reports the Cycle 10 core operating limits. ./ I 1 i 1 I
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Standard No.: GGNS-MS-48.0 Page: 2 of 5
. Revision No.: 6 2.0 SCOPE As defined in Technical Specification 1.1, the COLR is the GGNS document that provides the core operating limits for the current fuel cycle. This document is prepared in accordance with Technical Specification 5.6.5 for each reload cycle using NRC-approved analytical methods.
The Cycle 10 core operating limits included in this report are: l
- the Average Planar Linear Heat Generation Rate (APLHGR),
e the Minimum Critical Power Ratio (MCPR), and e the Linear Heat Generation Rate (LHGR) limit. The cycle-specific MCPR safety limits are documented in Technical Specification 2.1.1.2. l l i l' _,_____1 - - - - , - - - _ - - - - - - _ _ _ - - - . - - -- - - . - - - - -
!' Standard No.: GGNS-MS-48.0 ., Page: 3 of 5 l Revision No.: 6 i
3.0 REFERENCES
I This section contains the background and cycle-specific references used in the safety analysis of Grand Gulf Cycle 10. l HACKGROUND
REFERENCES:
- 1. MAEC-88/0313, Generic Letter 88-16, " Removal of Cycle-Specific Parameter Limits from Technical Specifications", October 4,1988.
- 2. GNRO-92-00093, Proposed Amendment to Grand Gulf Operating License, PCOL-92/07, dated October 29,1992.
- 3. GNRI-93-0008, Amendment 106 to Grand Gulf Operating License, January 21,1993.
CURRENT CYCLE
REFERENCES:
- 4. General Electric 24A5414, Supplemental Reload Licensing Report for Grand Gulf Unit 1
. Reload 9 Cycle 10, Rev. O, dated March 1998.
Sa. General Electric 24A5384AA, Lattice Dependent MAPLHGR Report for Grand Gulf l Unit 1 Reload 8 Cycle 9 Rev. 2, dated March 1997. _, 5b. General Electric 24AS414AA, Lattice Dependent MAPLHGR Report for Grand Gulf Unit 1 Reload 9 Cycle 10, Rev. O, dated March 1998.
- 6. ANF-88-152 (P)(A), Generic Mechanical Design for Advanced Nuclear Fuels 9x9-5 BWR Reload Fuel, dated November 1990.
- 7. EMF-94-186, Grand Gulf Unit 1 Cycle 8 Reload Analysis, dated December 1994.
- 8. GEXI 96-00484, R.E. Kingston to J.B. Lee, " Application of Single Loop Operation )
Safety Limit MCPR to Operating Limit MCPR", dated November 15,1996.
- 9. GEXI 97-00035, R.E. Kingston to J.B. Lee, " Utilization of Power and Flow Dependent MAPLHGR and LHGR Limits", dated June 27,1997.
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Standard No.: GGNS-MS-48.0 : Page: 4 of 5
-. Revision No.: ' 4
. 4.0 DEFINITIONS
- 1. Average Planar Linear lleat Generation Rate (APLHGR) .- the APLHOR shall be applicable to_ a specific planar height and is equal to the sum of the linear heat generation rates for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.
- 2. - Average Planar Exposure - the Average Planar Exposure shall be applicable to a specific planar height and is equal to the sum of the exposure of all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle.
- 3. Critical Power Ratio (CPR) - the ratio of that power in the assembly, which is calculated by application of the fuel vendor's appropriate boiling correlation, to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
- 4. Core Operating Limits Report (COLR) - The Grand Gulf Nuclear Station specific document that provides core operating limits for the current reload cycle in accordance with Technical Specification 5.6.5.
- 5. Linear Heat Generation Rate (LHGR) - the LHGR shall be the heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
- 6. Minimum Critical Power Ratio (MCPR) - the MCPR shall be the smallest CPR which exists in the core.
- 7. MCPR Safety Limit - the minimum value of the CPR at which the fuel could be operated with the expected number of rods in boiling transition not exceeding 0.1% of the fuel rods in the core.
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l Standard No.: GGNS-MS-48.0 Pege: 5 of 5
. Revision No.: 6 5.0 GENERAL REQUIREMENTS This section reports the Grand Gulf Cycle 10 core operating limits. As discussed in Technical l Specifications 3.2.1,3.2.2, and 3.2.3, these operating limits are applicable when the core thermal power is greater than 25% of rated power. The power-dependent core operati,g limits including and excluding the pressure regulator failure downscale (PRFDS) event are provided. The current treatment of the PRFDS event in the core operating limits is repo:ted in SAR Section 15.2.1 and the associated operating limits are illustrated in TRM Sections 3.2.1,3.2.2, and 3.2.3.
5.1 Average Planar Linear Heat Generation Rates Consistent with Technical Specification 3.2.1, all APLHGRs for Siemens 9x9-5 bundles shall not exceed tue limits reported in Attachment I as a function of exposure [7]. All APLHGRs for gel 1 lattices shall not exceed the MAPLHGR limits reported in References 5a and 5b as a l function of exposure multiplied by the smaller of either the power-dependent or flow-dependent MAPLHGR factors reported in Attachment 1 [4]. For each GElI bundM type, Attachment i reports the MAPLHGR for the most limiting lattice at each exposure for re Arence purposes [4]. 5.2 Minimum Critical Power Ratio Consistent with Technical Specification 3.2.2, the MCPR shall be equal to or greater than the limits reported in Attachment 2 as functions of power, flow, and exposure [4]. 5.3 Linear IIcat Generation Rate Consistent with Technical Specification 3.2.3, the LHGR for Siemens 9x9-5 bundles shall not l exceed the limits reported in Attachment 3 as a function of exposure as multiplied by the smaller
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of either the power-dependent or flow-dependent LHGR factors reported in Attachment 3 [4,6]. All LHGRs for gel 1 lattices shall not exceed the LHGR limits reported in References 5a and 5b as a function of exposure multiplied by the smaller of either the power-dependent or flow-dependent MAPLHGR factors reported in Attachment 1 [4,9]. For each Gell bundle type, Attachment 3 reports the LHGR for the most limiting lattice at each exposure for reference ! purposes. 5.4 Applicability The attached core operating limits are applicable for operation in the Maximum Extended l Operating Domain (MEOD) and with Feedwater Heaters Out of Service. For single-loop operation, the following additional requirements must be satisfied.
- 1. The APLHGR for the GElI bundles shall not exceed the MAPLHGR limit as function of exposure reported in References 5a and 5b multiplied by 0.83 [4]. The l APLHGR for the Siemens 9x9-5 bundles shall not exceed the MAPLHGR limit reported in Attachment I multiplied by 0.86 [4].
- 2. The MCPR shall be equal to or greater than the limits determined in accordance l
with Section 5.2 above multiplied by the ratio of the single-loop MCPR safety limit to the two-loop MCPR sefety limit reported in Technical Specification 2.1.1.2 [8].
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