ML20235Q835
| ML20235Q835 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/20/1989 |
| From: | Mcduffie M CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20235Q839 | List: |
| References | |
| GL-88-16, NLS-89-038, NLS-89-38, NUDOCS 8903030049 | |
| Download: ML20235Q835 (19) | |
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cwuu P. O. Box 1551
- Rale 6gh. N. CI 27602 FB 201989 SERIAL: NLS-89-038
. M A. McDUFFIE senior v6ce President 10CFR50.90, Nuclear Generation TSC 87TSB03 l
Unite'd States Nuclear. Regulatory Commission
-' ATTENTION: Document Control Desk
' Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT,. UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62
. SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT.
ELIMINATION OF CYCLE-SPECIFIC PARAMETER-LIMITS (NRC GENERIC LETTER 88-16):
- Gentlemen:
In accordance with the Code ^of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power & Light Company (CP&L) hereby requests a revision to the Technical Specifications for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2..This request is provided as a supplement to the original Elimination of Cycle Specific Variables Amendment Package that was submitted on September 4, 1987, and supplemented on April 5, 1988.
This submittal incorporates the guidance provided by'the NRC in Generic Letter 88-16 dated October 4 1988 and the NRC Safety Evaluation Report'for
' Amendment 19 to General Electric Licensing Topical Report NEDE-240ll-P-A
. (GESTAR-II) '. To avoid confusion and eliminate. potential problems, previously submitted Instructions for Incorporation, Summary Lists of Revisions, and revised Technical Specification pages are totally superceded by Enclosures 3 through 6 of this submittal. provides a detailed description of the proposed changes and the basis for the changes. details the basis for the company's determination that the proposed changes do not involve a significant hazards consideration. provides instructions for incorporation of the proposed changes into the Technical Specifications for each unit. provides a summary of the proposed Technical Specification changes for each unit on a page by pa6e basis. provides the proposed Technical Specification pages for Unit 1. provides the proposed Technical Specification pages for Unit 2.
i 8903030049 890:220 ig PDR ADOCK 05000324 P
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Document Control Desk NLS-89-038 / Page 2
, provides the Core Operating Limits Report for the Brunswick Plant, Unit 1, Cycle 7. provides the Core Operating Limits Report for the Brunswick Plant, Unit 2, Cycle 8.
In order to allow time for procedure revision and orderly incorporation into copies of the Technical Specifications, CP&L requests that the proposed amendments, once approved by the NRC, be issued with an effective date to be no later than 60 days from the issuance of the amendment.
l Please refer any questions regarding this submittal to Mr. Stephen D. Floyd at (919) 836-6901.
Yours very truly, f
l' O
M. A. McDuffie WRM/ PDM (\\cor\\87TSB03)
Enclosures:
1.
Basis for Change Request 2.
10CFR50.92 Evaluation 3.
Instructions for Incorporation 4.
Summary List of Revisions 5.
Technical Specification Pages - Unit 1 6.
Technical Specification Pages - Unit 2 7.
Core Operating Limits Report - Unit 1, Cycle 7 8.
Core Operating Limits Report - Unit 2, Cycle 8 cc:
Mr. Dayne H. Brown Mr. M. L. Ernst Mr. W. H. Ruland Mr. E. G. Tourigny M. A. McDuffie, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power & Light Company.
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ENCLOSURE 1 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50 325 & 50-324-OPERATING LICENSES DPR-71 & DPR-62 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT ELIMINATION OF CYCLE-SPECIFIC PARAMETER LIMITS i
i BASIS FOR CHANGE REQUEST Proposed Chance 1 Based on the guidance provided in NRC Generic Letter 88-16, the proposed change removes the values of cycle-specific parameter limits from the BSEP Technical Specifications.and makes related administrative and format changes.
Basis As stated in the CP&L's original request for elimination of cycle-specific
-variables (Reference 1:
September 4, 1987), the current BSEP Technical Specifications include the following cycle-specific power distribution limits: Minimum Critical Power Ratio (MCPR); Average Planar Linear Heat Generation Rate (APLHCR); Linear Heat Generation Rate (LHGR); and Average Pouer Range Monitor (APRM) setpoints. Typically, changes to the power.
distribution limits, such as MCPR, APLHGR, and LEGR, are required at each refueling to reflect upcoming cycle-specific characteristics.
Since the values represented in such changes are developed using an NRC-approved methodology, CP&L believed that the processing of such changes was an unnecessary burden on the Company's as well as the NRC's resources.
Subsequently, the NRC issued Generic Letter 88-16 entitled " Removal of Cycle-Specific Parameter Limits From Technical Specifications" (Reference 3:
October 4, 1988).
This Generic Letter guidance was based on the NRC's review and approval of a lead-plant proposal for an alternative that eliminates the need for a license amendment to update the cycle-specific parameter limits at each fuel cycle.
This request was submitted for the Oconee plant with the endorsement of the Babcock and Wilcox Owners' Group. Use of the Generic Letter 88-16 alternative i
consists of three separate actions to modify BSEP Technical
)
Specifications:
(1) the addition of the definition of a named formal report (CORE OPERATING LIMITS REPORT) that includes the values of the cycle-specific parameter limits that have been established using an NRC-approved methodology and are consistent with the applicable limits of the safety analysis as addressed in the BSEP Updated Final Safety Analysis i
Report (FSAR), (2) the addition of an administrative reporting requirement l
to submit the CORE OPERATING LIMITS REPORT to the Commission for information, and (3) the modification of individual Technical Specifications to eliminate cycle-specific parameter limits and to note that the cycle-specific parameters shall be maintained within the limits provided in the CORE OPERATING LIMITS REPORT, The NRC Staff began their review of CP&L's original elimination of cycle-specific variables submittals (References 1 and 2:
September 4, 1987 and El-1
e
<a April 5, 1988) after-the issuance of Generic Letter 88-16 (Reference 3:
October 4, 1988). As a result, a telephone conference (Reference 4:
January 19, 1989) was held between the NRC Staff and CP&L representatives to discuss Staff comments relative to the differences between CP&L's original submittals and Generic Letter 88-16 guidance.
Consequently, the purpose of this submittal is to incorporate resolution of Staff comments and assure consistency with the guidance provided in Generic Letter 88-16.
To avoid the potential confusion of handling revised Technical Specification pages from three submittals, Enclosures 3 through 6 of this submittal constitute a complete set of Instructions for Incorporat' 3n, Summary Lists of Revisions, and revised Technical Specification pases.
Therefore, similar enclosures from the previous submittals are superceded.
Proposed Chance 2 Based on the guidance in the NRC Safety Evaluation Report (SER) for Amendment 19 to General Electric Licensing Topical Report NEDE-24011-P-A t
(Reference 5: November 17, 1987), the proposed change eliminates BSEP Technical Specification 3/4.2.4, Linear Heat Generation Rate, and the associated Total Peaking Factor (TPF). The use of TPF in the formulation of the APRM flow-blased scram and rod block setpoint setdown requirements of Specification 3/4.2.2 is being revised, along with associated definitions that are added, deleted, or revised.
The associated revision of Technical Specification 3/4.2.1 specifies that only the most limiting lattice APLHGR limit for multiple lattice fuel types'will be specified.
Easis Two of the core thermal performance parameters for a BWR are the APLHGR and the LHGR. The APLHGR limit is determined by the more limiting of the emergency core cooling system (ECCS) analyses and the mechanical design analysis limits.
The LHGR limit is determined by the mechanical design analysis limit. As such, the LHGR limit is essentially redundant to the APLHGR limit.
This redundancy was documented in the request for Amendment 19 to GESTAR-II and accepted by the NRC Staff in the SER prepared for that amendment (Reference 5: November 17, 1987).
The NRC Staff's SER was intended to be referenced by licensees with "E fuel to support submittals for changes similar to those described in the SER.
The proposed changes to the BSEP Technical Specifications include revision j
of the definitions for APLHGR and Limiting Control Rod Pattern; deletion i
of the definitions for LHGR, TPF, Fraction of Limiting Power Density, and Maximum Total Peaking Factor; and the addition of definitions for Maximum Average Planar Linear Heat Generation Rate Ratio, Fraction of Rated Power, l
and Core Maximum Average Planar Linear Heat Generation Rate Ratio.
The use of the LHGR associated parameter TPF in the formulation of the APRM flow-biased setpoint setdown requirements of Specification 3/4.2.2 is revised. The new formulation and terms associated with APLHGR provide for equivalent adjustments to that of the TPF based formulation.
Specification 3/4.2.4 is eliminated in its entirety due to the essential redundancy of LHGR to APLHGR as described in the SER to Amendment 19 for GESTAR-II (Reference 5: November 17, 1987).
El-2
In addition to finding the above types of changes acceptable, the NRC Staff, in the SER for Amendment 19 for GESTAR-II (Reference 5: November
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17, 1987), concluded that, in practice, the changes would result in the same operating power distribution limits and safety margins as required by current Technical Specifications.
Furthermota, the complexity of Technical Specifications would be reduced by removing Specifications which are, in effect, redundant. Additionally, removal of these Specifications would preclude the need to specify numerous lattico specific APLEGR limits for fuel types with multiple lattice types.
To support the proposed changes, the NRC Staff requires licensees to maintain procedural controls on LHGR limits using process computer monitoring and to provide documentation on APLHGRs and Local Peaking Factors (LPFs).
Current BSEP procedures will continue to monitor LHGR limits using process ceaputer monitoring.
The documentation of APLHGR limits and LPF values for fuel types with multiple lattice types will be identified in the proprietary Loss of Coolant Accident (LOCA) Report applicable to each BSEP Unit.
The LOCA Report also contains a bundle description providing the same type of proprietary information as found in GESTAR-II. Along with identification of the axial location, a table of composite APLHGR limits of each lattice in multiple lattice fuel types will be provided. Consistent with the inclusion of APLHGR limits in the CORE OPERATING LIMITS REPORT, a plot of the most limiting value of APLMGR for the most limiting lattice (excluding natural uranium) for each fuel type as a function of planar exposure will be provided in the CORE OPERATING LIMITS REPORT for each nultiple lattice fuel type.
References 1.
September 4, 1987, CP&L Letter Serial No. NLS-87-185.
Original CP&L request to eliminate cycle-specific variables from BSEP Technical Specifications.
2.
April 5, 1988, CP&L Letter Serial No. NLS-88-062.
Supplement to the September 4, 1988 submittal.
3.
October 4, 1988, NRC Letter.
NRC issuance of Generic Letter 88-16 titled " Removal of Cycle-Specific Parameter Limits From Technical Specification Changes."
4.
January 19, 1989 Telephone Conference.
NRC Staff and CP&L representatives discussed Staff comments relative to differences between Reference 1 and 2 submittals and Generic Letter 88-16 guidance.
5.
November 17, 1987, NRC Letter to General Electric.
Transmitted acceptance for referencing and an SER for Amendment 19 to General Electric Licensing Topical Report NEDE-240ll-P-A (CESTAR-II),
" General Electric Standard Application for Reactor Fuel", dated April 7, 1987.
El-3
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I ENCLOSURE 2
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BRUNSWICK STFAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324 OPERATING LICENSES DPR-71 & DPR-62 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT h
ELIMINATION OF CYCLE-SPECIFIC PARAMETER LIMITS 10CFR50.92 EVALUATION The Commission has provided standards in 10CFR50.92(c)'for determining whether a significant hazards consideration exists. A proposed amendment to an operating license for a facility involves no significant hazards'4 consideration if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin I
of safety. Carolina Power & Light Company has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards. consideration. The bases for this determination are as follows:
Proposed Change 1 Based on the guidance provided in NRC Generic Letter 88-16, the proposed change removes the values of cycle-specific parameter limits from the BSEP Technical Specifications and makes related administrative and format changes.
Basis The change does not involve a significant hazards consideration for the following reasons:
1.
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The abnormal operational transienta analyzed in the BSEP Updated Final Safety Analysis Report will remain bounded.
There will be no change in the operation of the facility as a result of the amendment. No safety-related equipment or function will be altered.
The proposed amendment merely removes cycle-specific parameter limits from the Technical Specifications and references their inclusicn in the CORE OPERATING LIMITS REPORT. NRC approved analytical methodology will continue to be used as the basis for the results that will now be reported in the CORE OPERATING LIMITS REPORT.
2.
The proposed smendment does not create the possibility of a new or different kind of accident from any eccident previously evaluated.
As stated above, no safety-related equipment, safety function, or plant operations will be altered as a result of this amendment.
The requested change does not create any new accident mode.
The proposed amendment is in accordance with the guidance provided in E2-1
1 Generic Letter 88-16 for licensees requesting removal of the values of cycle-specific parameters from Technical Specifications. The establishment of these limits in accordance with an NRC-approved methodology and the incorporation of these limits into the CORE OPERATING LIMITS REPORT will ensure that proper steps have been taken to establish the values:of these limits. Furthermore, the submittal of the CORE OPERATING LIMITS REPORT to the Commission will allow the Staff to continue to trend the values'of these limits without the need for prior Staff approval of these limits and without introduction of an unreviewed safety question.
3..
The proposed amendment does not alter the requirement that the plant
.be operated within the limits for cycle-specific parameters nor the required remedial actions that must be taken if these limits are not met. yhile it is recognized that such limits are essential to plant safety, the values of such limits can be determined in accordance.
with NRC-approved methods without affecting nuclear safety.. The removal of the values of these limits from the BSEP Technical Specifications is coincident with their incorporation into the. CORE OPERATING. LIMITS REPORT that'is submitted to the Commission.
Hence,.
appropriate measures exist;to control the values of these' limits.
.Therefore, the proposed changes are administrative in. nature and do' not impact the operation of the facility in a manner that involves a reduction in the margin of safety.
Indeed, as stated in Generic Letter 88-16, the proposed amendment is responsive to industry and NRC efforts on improvements in Technical Specifications, and will result in a resource savings for the' licensee and the'NRC by eliminating the majority of license amendment requests for changes in values of cycle-specific parameters in Technical Specifications, Indirectly, this is a safety improvement because the released resources may now be utilized on more consequential tasks.
o E2-2 v%
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Proposed Chance 2 Based on the guidance in the NRC Safety Evaluation Report for General Electric Licensing Topical Report NEDE-240ll-P-A (GESTAR-II), the proposed change eliminates BSEP Technical Specification 3/4.2.4, Linear Heat Generation Rate,'and the associated Total Peaking Factor. The use of Total Peaking Factor in the formulation of the Average Power Range Monitor (APRM) flow-biased scram and rod block setpoint setdown requirements of.
Specification 3/4.2.2 is being revised, along with associated definitions that are added, deleted, or revised. The associated revision of Technical Specification 3/4.2.1 specifies that only the most limiting lattice Average Planar Linear Heat Generation Rate (APLHGR) limit for multiple lattice fuel types will be specified.
Basis The c,hange does not involve a significant hazards consideration for the l
following reasons:
j 1.
The proposed amendment does not involve a significant increase in the consequences of any accident previously evaluated. The NRC Safety Evaluation Report for Amendment 19 to GESTAR-II concluded that a change similar to the proposed change "...will, in practice, result in the same operating power distribution limits and safety margins as the current Technical Specifications." The essential redundancy of the Linear Heat Generation Rate and the Average Planar Linear Heat Generation Rate,,and the equivalence of the formulation of the APRM flow-biased setpoint setdown requirement, has been established and is documented in the NRC Safety Evaluation Report for Amendment 19 of GESTAR-II.
Since the same operating power distribution limits as current Technical Specifications will, in practice, be required, the proposed change does not involve a significant increase in the consequences of any accident previously evaluated.
The proposed change eliminates a thermal performance limit, modifies several definitions and provides an equivalent basis for adjusting APRM flow-biased setpoint setdown based on power distribution parameters. As such the change only affects power distribution parameters which do not influence the probability of any accident.
Therefore, the proposed change does not result in a significant increase in the probability of any accident previously evaluated.
2.
The proposed change does not alter the function of any component or j
system and, therefore, does not create the possibility of a new or j
different kind of accident from any accident previously evaluated.
3.
The margin of safety, as established by current Technical Specification power distribution limits, are based on the assumptions and analyses documented in the BSEP Updated Final Safety Analysis Report. The proposed amendment will, in practice, result in the same power distribution limits as contained in current Technical Specifications; therefore, the proposed change does not involve a significant reduction in the margin of safety.
E2-3
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. ENCLOSURE'3
-BR'UNSWICK STEAM ELECTRIC' PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 & 50-324
-OPERATING LICENSES DPR-71 & DPR-62
' SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT:
U ELIMINATION'0F CYCLE-SPECIFIC PARAMETER LIMITS INSTRUCTIONSFORINCORh0 RATION'
.The proposed changes to the Technical Specifications (Appendix'A to-Operating Licenses DPR-71 and DPR-62) would be incorporated as follows:
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-' ENCLOSURE 4 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 NRC DOCKETS 50-325 6'50-324
^
OPERATING LICENSES DPR-71 & DPR 62 l
SUPPLEMENT TO REQUEST FOR LICENSE' AMENDMENT b
' ELIMINATION OF CYCLE-SPECIFIC PARAMETER' LIMITS L
SUMMARY
LIST OF REVISIONS
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UNIT 1 i
Pages Description of Chane.gs-
-I Add newtindex entries,for CORE MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION' RATE RATIO,.. CORE. 1 7
OPERATING LIMITS REPORT, FRACTION OF
.j l
RATED THERMAL POWER, and MAXIMUM 1
AVERAGE PLANAR HEAT GENERATION RATE RATIO.
Delete index. entries for LINEAR HEAT GENERATION RATE,.and MAXIMUM TOTAL PEAKING FACTOR.
.j II Delete index entry for TOTAL PEAKING FACTOR. -Repaginate index entries,
'I III Repaginate index entries.in Sections 2.11and 2.2.
IV Repaginate index entries for Specifications 3/4.2.2 and 3/4.2.3.
Delete index entry for Specification.
3/4.2.4, Linear Heat Generation Rate. Add index entry for Control Rod Drive Housing Support.
X Repaginate index entries for Bases l
Sections 3/4.2.2 and 3/4.2.3.
4 Delete index entry for Bases Section 3/4.2.4, Linear Heat Generation Rate.
XV Add new index entry for CORE OPERATING LIMITS EEPORT.
I XVI Repaginate index entries for Administrative Controls Sections 6.1 1
through 6.15.
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Pages Description of Chances j
ii 1-1=
Revise the definition'of-AVERAGE PLANAR EXPOSURE and AVERAGE PLANAR LINEAR HEAT GENERATION RATE.
1-2' AdddefinitiodsforCOREMAXIMUM
.+
AVERAGE PLANAR LINEAR HEAT n
GENERATION RATE RATIO and CORE OPERATING LIMITS REPORT.
L h' s
Repaginate.
1-3
' Add the definition of FRACTION OF, RATED THERMAL POWER. Revise definition of LIMITING CONTROL R0D PATTERN. Repaginate.
1-4 Delete definitions of LINEAR HEAT GENERATION RATE, and MAXIMUM TOTAL--
PEAKING FACTOR. Add definition for.
MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE RATIO.
Repaginate
(
1 Revise definition of PHYSICS TESTS.
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Repaginate.
1-6 Repaginate.
l-1-7
. Repaginate.
1-8 Delete the definition of TOTAL PEAKING FACTOR. Repaginate.
1-9 Repaginate.
1-10 Repaginate.
1-11 Repaginate.
B 2-1 Remove the specific MCPR value and add reference to the Safety Limit CPR of Specification 2.1.2.
-B 2-2 Revise the discussion of Safety Limits Bases 2.1.2 including the i
Reference and Tables, i
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j Pages Description cf Changes g:
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B 2 Repaginate.
B 2-4'.
Remove the' specific MCPR value and add reference'to the Safety Limit pf
. MCPR of Specification 2.1.2.
g Repaginate.
b B 2-5 Add location of specified formula' =
4 Specification 3.2.2.. Repaginate' g
~L Bi2-6 Repaginate.
B.2-7 Repaginate.
3/4 1-17 Removefthe spe'cific Safety-Limiti MCPR value and add reference to'the Safety Limit MCPR of Specification 2.1.2.
3/4 2-1 Remove. references to specific.4ralues shown on Figures. Incorporate references to the. CORE OPERATION..
LIMITS REPORT and Specification 3.2.1.
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3/A 2-2 Remove references to TPF, MTPF, and R
LIMITING CONTROL ROD PATTERN, and related values. Add reference to the FRTP (FRACTION OF RATED THERMAL POWER) and CMAPRAT.(CORE MAXIMUM AVERAGE Pil.NAR LINEAR. HEAT' GENERATION RATE RATIO).
Clarify wording.ofl Specification 4.2.2.
Repaginate.
3/4 2-3 Revise the discussion of MCPR limits, specifically deleting. values and adding references to the CORE OPERATING LIMITS REPORT.
Repaginate.
3/4 2-4 Add reference to the CORE OPERATING LIMITS REPORT. Repaginate.
3/4'2-5 Add reference to the CORE OPERATING LIMITS REPORT. Repaginate.
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UNIT 1 1
Pages Description of Channes 3/4 3-39 Remove the specific MCPR'value.and add reference to Specification.
'2.1.2.
B 3/4 1-2' Revise.the discussion of CONTROL
-RODS to delete MCPR values; (B 3/4 2-1 Revise the discussion of APlRGR, specifically deleting values and-
' Figure references, adding reference to the CORE OPERATING LIMITS' REPORT, and. clarifying content.
B'3/4 2-2 Revise the discussion of APRM setpoints, specifically. deleting.
reference to MCPR,:TPF and.MTPF and associated values; and adding reference to Specification 3.2.2.
' Revise the discussion of MCPR'to' add reference'to the CORE OPERATING LIMITS REPORT and Reference 1.
Delete LHCR discussion. Repaginate.
B 3/4 2-3 Revise Reference list. Repaginate.
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6-25 Add information on CORE OPERATING i
LIMITS REPORT. Repaginate.
6-26 Add information on CORE OPERATING LIliITS REPORT. Repaginate.
6-27 Repaginate.
6-28 Repaginate.
6-29 Repaginate.
6-30 Repaginate.
6-31 Repaginate.
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Description:==
of' Chances Pages i
b il Add.new index' entries for CORE
' MAXIMUM AVERAGE PIANAR ^ LINEAR HEAT -
GENERATION RATE RATIO, CORE-
- OPERATING-LIMITS REPORT,. FRACTION.OF-
" RATED THERMAL POWER, and MAXIMUM AVERAGE. PLANAR HEAT GENERATION RATE
- RATIO.. Delete index entries for iLINEAR HEAT GENERATION RATE, MAXIMUM FRACTION OF LIMITING POWER DENSITY,.
and MAXIMUM TOTAL' PEAKING FACTOR.
II-Delete index entry for TOTAL PEAKING FACTOR.
L:
III Repaginate index entries for V
Sections 2.1 and 2.2.
IV -
-Repaginate-.index entries.for-Specifications.3/4.2.2 and 3/4.2.3 Delete index entry for Specification-3/4.2.4, Linear-Heat. Generation Rate.
X Repaginate index entries for Bases Sections 3/4.2.2 and 3/4-2.3.
Delete index entry for Bases Section
-3/4.2.4, Linear Heat Generation Rate.
XV, Add new index entry.for CORE OPERATING LIMITS REPORT.
XVI Repaginate index entries for Administrative Controls Sections 6.1 through 6.15.
1-1 Revise the definition of AVERAGE PLANAR EXPOSURE and MERAGE PLANAR LINEAR HEAT GENERAT' 4 RATE.
1-2 Add definitions fo,,0RE MAXIMUM AVERAGE PLA14AR LINr, A HEAT GENERATION RATE RATIO and CORE OPERATING LIMITS REPORT. Revise definition of CRITICAL POWER RATIO.
Repaginate.
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I UNIT 2.
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-Description of Chances 1-3 Add.the definition of FRACTION'0F RATED. THERMAL POWER. Repaginate.
1-4 Delete definitions of LINEAR HEAT' GENERATION RATE, MAXIMUM FRACTION OF--
' LIMITING POWER DENSITY,-and MAXIMUM TOTAL PEAKING FACTOR. Add' definition for MAXIMUM AVERAGE PLANAR LINEAR HEAT. GENERATION RATE RATIO. Revise' definition of LIMITING CONTROL ROD' PATTERN.
Repaginate.
1-8 Delete the definition of TOTAL ~
PEAKING FACTOR.- Repaginate.-
u' 1-9 Repaginate.
B 2-1 Remove the specific MCPR value'and add reference to the Safety Limit CPR of Specification 2.1.2.
B 2-2 Remove references to Reference 2'.
Revise Reference'1.and indicate
" latest approved version".
B 2 Remove the' specific MCPR value and add reference.to the Safety Limit MCPR of Specification 2.1.2.
B 2-5 Add location of specified formula -
Specification 3.2.2.
l 3/4'l-17 Remove the specific Safety Limit-MCPR value and add reference to the Safety Limit MCPR of Specification 2.1.2.
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'3/4 2-1 Remove references to specific values shown on Figures. Incorporate references to the CORE OPERATION LIMITS REPORT and Specification 3.2.1.
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UNIT 2 Pages Description of Chances
'3/4 2-2 Remove references-to TPF, MTPF, and LIMITING CONTROL ROD PATTERN, and related values. Add reference to the FRTP'(FRACTION OF RATED THERMAL
?
POWER) and CMAPRAT (CORE MAXIMUM AVERAGE PIANAR LINEAR HEAT GENERATION RATE RATIO). Clarify wording of Specification 4.2.2.
Repaginate.
3/4 2-3 Revise the. discussion of MCPR-limits, specifically deleting values and adding reference to the CORE OPERATING LIMITS REPORT.
Repaginate.
3/4 2-4 Add reference to the CORE OPERATING
. LIMITS _ REPORT. Repaginate.
3/4 2-5~
Add reference to the CORE OPERATING LIMITS REPORT. Repaginate.
3/4-3-39 Remove the specific.MCPR value.and' add reference to Specification 2.1.2.
B 3/4 1-2 Revise the discussion of CONTROL RODS to delete MCPR values.
B 3/4 2-1 Revise the discussion of APLHGR, specifically deleting values and.
Figure references, adding. reference to the CORE OPERATING LIMITS REPORT, and clarifying content.
B 3/4 2-2 Revise the discussion of APRM setpoints, specifically deleting
-reference to MCPR, TPF and MTPF and associated values; and adding reference to Specification 3.2.2.
Revise the discussion of MCPR to add reference to the CORE OPERATING LIMITS REPORT and Reference 1.
Delete LHGR discussion. Repaginate.
B 3/4 2-3 Revise Reference list. Repaginate.
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. UNIT 2-Pages Description of Channes.
' Add information on CORE OPERATING-6-25 LIMITS REPORT... Repaginate.
6'- 2 6 '
Add'information.on CORE OPERATING' LIMITS REPORT., Repaginate.
6-27 Repaginate.
6-28
. Repaginate.
p 6-29
. Repaginate.
6-30' Repaginate.
6-31' Repaginate.
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