|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20196J8351998-12-0808 December 1998 Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys ML20196C0251998-11-27027 November 1998 SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station ML20196A6881998-11-25025 November 1998 Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds ML20249B6281998-06-12012 June 1998 Safety Evaluation Accepting 980303 Request to Review & Approve Proposed Change to Plant,Units 1 & 2 TS Re Relocation of Meteorological Tower ML20248B0441998-05-27027 May 1998 Safety Evaluation Authorizing Proposed Alternative Use of Current TS Section 3/4.7.8 Requirements for Snubber Visual Exam & Functional Testing,Based on Finding That Proposed Alternative Proposes Acceptable Level of Quality & Safety ML20247M0861998-05-21021 May 1998 SER Accepting 1997 Rev to Catawba UFSAR Submitted on 970925. Rev Added Analysis for Postulated Accident Involving Dropping of Sf Pool Weir Gate Onto Sf Assemblies ML20216E1771998-04-13013 April 1998 Safety Evaluation Accepting Relief Request 98-01 for Catawba Nuclear Station Units 1 & 2 from Requirements of ASME Boiler & PV Code for Second 10-year Interval Program for Inservice Testing of Pumps & Valves ML20217M4211998-04-0303 April 1998 Safety Evaluation Approving Request for Relief 97-04, non-code Repair Valves.Relief Granted Retroactively to Unit 1 & Expired Dec 1997.Relief for Unit 2 Will Expire at End of Cycle 9 Outage or Next Scheduled Outage Exceeding 30 Days ML20197A6551998-03-0202 March 1998 Safety Evaluation Supporting Licensee Proposed Action to Set Gwl Alarm at Higher Elevation than Current Level of El 731 Feet ML20203B1071998-02-0404 February 1998 Safety Evaluation Approving Proposed Alternative to Reactor Vessel Augmented Exam Requirement of Reactor Vessel Shell Welds,Per 10CFR50.55a(g)(6)(ii)(A)(5) ML20199F3361998-01-28028 January 1998 Safety Evaluation Supporting 951227 Request for NRC Approval of Proposed EALs to McGuire Nuclear Station,Units 1 & 2 ML20199A5521998-01-22022 January 1998 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, for Cns,Units 1 & 2 ML20199A6421998-01-22022 January 1998 Safety Evaluation Accepting Proposed EALs Changes for Plant, Units 1 & 2.Concludes That Changes Consistent W/Guidance in NUMARC/NESP-007,w/variations as Identified & Accepted in Review & Meets Requirements of 10CFR50.47(b)(4) ML20198P9641998-01-15015 January 1998 SE Granting Relief Request 97-03 for Second 10-yr Interval Inservice Insp Program ML20198R9951997-10-30030 October 1997 Safety Evaluation Authorizing Request for Approval of Alternative to Exam Requirement of Reactor Vessel Shell Weld,Per 10CFR50.55a(g)(6)(ii)(A)(5) ML20198J7651997-10-15015 October 1997 Safety Evaluation Accepting 10-yr Interval Insp Program Plan Alternatives for Listed Plants Units ML20211F8801997-09-22022 September 1997 Safety Evaluation Supporting Second ten-year Interval Inservice Inspection Program Plan & Associated Requests for Relief for Catawba Nuclear Station Unit 1 ML20211E6871997-09-22022 September 1997 SER Accepting DPC Responses to GL-95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20149K8281997-07-29029 July 1997 SER Granting Request for Exemption from Requirements of 10CFR70.24 for Units 1 & 2 ML20148S2231997-07-0202 July 1997 Safety Evaluation Accepting Supplemental Test Program for Relief Request 1.4.2 for Units 1 & 2 ML20141E1121997-06-16016 June 1997 Safety Evaluation Approving Licensee Position That UFSAR Table 6-77 Be Revised to Identify SA-1 & SA-4 Instead of SA-3 & SA-6 as Containment Isolation Valves ML20148H2501997-06-0505 June 1997 Safety Evaluation Accepting Proposed Restructuring of Util Through Acquisition Of,& Merger W/Panenergy Corp ML20141G6701997-05-20020 May 1997 Safety Evaluation Accepting Proposed Alternative Use of TS Requirement for Code Class Snubbers ML20135B3051997-02-27027 February 1997 Safety Evaluation Granting Second 10 Yr ISI Program Plan & Associated Requests for Relief ML20134P2421997-02-20020 February 1997 Safety Evaluation Accepting TR BAW-10199P for Ref in Plants Licensing Documentation & Use in Licensing Applications ML20134L4081996-11-19019 November 1996 SER Accepting Performance of Plant Standby Nuclear Svc Water Pond ML20134G5551996-11-0707 November 1996 Safety Evaluation Accepting Proposed Application of BWU-Z CHF Correlation for Plants Mark-BW 17x17 Type Fuel ML20129E4851996-10-0101 October 1996 Safety Evaluation Recommending That Relief Request 96-02 Be Granted,Per 10CFR50.55a(g)(6)(i),per Request ML20059G8601993-10-29029 October 1993 SE Granting 921130 Request for Relief from Requirements of 1986 Edition of ASME Boiler & Pressure Vessel Code,Section XI Re Inservice Insp of safety-related Snubbers During Second 10-yr Interval ML20057F4121993-10-12012 October 1993 Safety Evaluation Re Inservice Testing Program Requests for Relief.Alternatives Authorized Per 10CFR50.55a(a)(3) or Relief Granted Per 10CFR50.55a(f)(6)(i) ML20057A0361993-08-26026 August 1993 Safety Evaluation Supporting Amends 138 & 120 to Licenses NPF-9 & NPF-17,respectively ML20056H3191993-08-24024 August 1993 SER Accepting Proposed TS Changes Re RWST & Cla Boron Concentrations ML20056D9611993-07-30030 July 1993 SER Accepting Licensee 930325-0429 Submittals of Technical Info to Support Continued Operation of Facility for Remainder of Fuel Cycle 7 ML20126H3171992-12-28028 December 1992 Safety Evaluation Granting Extension of First 10-yr ISI Interval to Coincide W/Start of end-of-cycle 8 Refueling Outage ML20058N7961990-08-0909 August 1990 Safety Evaluation Approving Relief Request 89-01 Re ASME Code Test Requirements for Nuclear Svc Water Sys ML20055H9151990-07-27027 July 1990 Safety Evaluation Accepting Actions Taken to Resolve NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generators Tubes ML20247K2531989-09-11011 September 1989 Safety Evaluation Supporting Amends 123 & 41 to Licenses DPR-61 & NPF-49,respectively ML20247E3761989-09-0707 September 1989 Safety Evaluation Supporting Amends 122,34,143 & 40 to Licenses DPR-61,DPR-21,DPR-65 & NPF-49,respectively ML20248C0731989-08-0303 August 1989 Sser Accepting 880601,0909 & 890602 Changes to ATWS Mitigation Sys Actuation Circuitry for Plants ML20247H7611989-07-18018 July 1989 Safety Evaluation Supporting Amends 100 & 82 to Licenses NPF-9 & NPF-17,respectively 1999-09-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20210S2891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20210S2951999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20206N8391999-05-0404 May 1999 Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20196A0041999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206R1811999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206N8261999-04-22022 April 1999 Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206R1931999-03-31031 March 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C9111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 1999-09-07
[Table view] |
Text
$
2E80pg '
- Io., UNITED STATES 8 [$ a NUCLEAR REGULATORY COMMISSION i I wasmNoToN, o. c, rosss s I
%, ...../
- ENCLOSURE SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO RELOAD STARTUP PHYSICS TEST PROGRAM DUKE POWER COMPANY HCGUIRE NUCLEAR STATION, UNITS 1 AND 2 CATAWBA NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370 DOCKET N05. 50-413 AND 50-414
1.0 INTRODUCTION
By letter dated February 2,1988, Duke Power Company (DPC), the licensee for the ficGuire and Catawba Nuclear Stations, Units 1 and 2, submitted a startup physics test program which would be used for plant cycle startup following a refueling cutage. The purpose of the submittal was to formally document the minimum reload physics tests necessary to ensure that the reactor core can be operated as designed. DPC states that there were no significant changes in the proposed physics test program to that currently being performed following refueling at the four units. NRC approval was requested because the proposed reload startup physics program was intended to replace the initial cycle physics test program described in the FSARs.
The DPC startup physics test program is modeled primarily after the ANSI /ANS 19.6.1-1985 standard on reload start-up tests for PWRs. This standard has been extensively reviewed by the staff, as well as others, and incorporates the changes and views suggested by the staff. By letter dated April 18, 1985, this standard was approved with comments by the NRC staff member on the American flational Standards Comittee N17 on Research Reactors, Reactor Physics, and Radiation Shielding. The standard ANSI /ANS-19.6.1 1985 currently serves as the staff guidance on the minimum startup physics test program for a PWR following a refueling outage, kk P
D
3
. ?
2 I
~ !
The staff performed an initial review of DPC's February 2,1988 subnittal l and by letter dated March 11, 1988, informed DPC that the proposed startup i physics test program was unacceptable. A telephone conference call was held on March 24, 1988 to discuss the dental and to identify the means for resolving the staff's concerns. Subsequently, DPC resubmitted its proposed startup i physics test program by letter dated April 14, 1988. j i
The staff's evaluatien of the proposed DPC startup physics test program, as resubmitted, follows. ,
2.0 EVALUATION -
Because DPC's proposed startup physics test program is modeled after the j ANSI /ANS-19.6.1-1985 standard on reload startup physics tests for PWRs and {
because this standard provides acceptable guidance on such tests for the staff. I our review and evaluation of DPC's test program was performed on the basis of )
confornance to the standard. The staff's evaluation of each proposed test f' follows+
A. Critical Boron Concentration Measurement - All Rods Out DPC has changed the description of the tests initial condition which states that the lead test bank should be inserted to less than 20 inches in the core to state that the lead test bank should be near fully withdrawn. DPC states that this limits the inserted reactivity to the verified measurement range of the reactivity cor.puter (typically + 0.00055 j delta rho for positive reactivity insertions) ratNr than to an arbitrary bank position. This change is acceptable since it meets the intent of standard ANSI-19.6.1-1985.
The staff concludes that the initial conditions, the test method, and acceptance criterion are consistent with the standard and, therefore, this test is acceptable.
1
I :
i 3 i l
I' B. Isothermal Temperature Coefficient j 1
l The staff concludes that the initial conditions, the test method, and i I
] acceptance criterion are consistent with the standard and, therefore, J
this test is acceptable. ,
! i r
C. Control Rod Bank Worth j By letter dated May 22, 1987, the NRC had previously approved OPC's rod i swap nethodology based upon a two-level set of criteria: (1) review criteriaessociatedwithmeetingdesigncriteriaand(2) acceptance
]
criteria associated with meeting safety analyses assumptions. The review l criteria correspond to the recomended test criteria of the ANSI /
j ANS-19.6.1-1985 standard. OPC states that if a review criteria is missed, ,
j remedial action will be taken based on the NRC's May 22, 1987 Safety l j Evaluation Report on DPC's rod swap methodology. These review and !
i acceptance criteria are acceptable since they meet the intent of the )
ANSI /ANS-19.6.1-1985 standard. l f
The staff concludes that the initial conditions, the test method, the
- review and acceptance criteria, and the fact that all control and shutdown i batiks will be measured, constitute an acceptable control rod bank worth f test program in accordance with the standard and this test is, therefore, av eptable, i
O. Flux Symetry Check Low Power DPC has changed the upper power level limit of this test from the 30%
recomnended by the ANS!/ANS-19.6.1-1985 standard to 40% of full rated l
j thermal power. We find that this is acceptable because moderator J
feedback effects in going from 30% to 40% power are not expected to affect
, significantly any power distribution asymmetries. This change is desired by DPC to improve scheduling flexibility of testing during the refueling j outage.
i 1
1 l
_=
3 i
4 !
~ ,
i Rather than using synnetric core locations for performing the test, OPC ,
uses all operable instrumented locations and compares measured to i
predicted values of F N H or normalized reaction rates. This change to ;
1 the test method is required due to the limited nuriter of quarter core l 1
symmetric instrumented locations and the use of a novable fission l
detector. :
I j The staff concludes that both of the changes described above are j f acceptable since they meet the intent of the ANSI /ANS-19.6.1-1985 i i standard with regard to the flux synnetry test at low power. The initial corditions, the test method, and acceptance criteria are consistent with ,
I the standard and, therefore, this test is acceptable. !
- E. Core Power Distributien - Intermediate Power ;
j DPC has changed the lower limit of the power range reconnended in the ANSI /ANS-19.6.1-1985 standard fren 40% to 50% power. Similarly, DPC has
! changed the upper limit from 75% to 80% power. These changes in the !
upper and lower limits have been proposed by DPC to improve scheduling i flexibility of testing during tha **':'eling outage. Neither of these 1
changes is of any significance since the intent of the test is to measure i the core power distribution at some internediate power level with broadly j defined but arbitrary limits on the power range. Thus the DPC changes j meet the intent of the ANSI /ANS-19.6.1-1985 standard for perforaing a core i power distribution measurement at some intermediate power level.
4 j The staff concludes that the initial conditions, the test method and
{ acceptance criteria are consistent with the standard and, therefore, this l j test is ecceptable.
l i
i 4
s
I !
a 5 !
F. Core Power Distribution - High Power j i
The staff concludes that the initial conditions, test method, and acceptance criteria are ici accordance with the standard and, therefore.
this test is acceptable.
G. All Rods Out Critical Boron Concentration - High Power The staff concludes that the initial conditions, test method, and )
acceptance criterion are in accordance with the standard and, therefore, this test is acceptable.
The ANSI /ANS-19.6.1-1985 standard also requires the measurement of the critical boron concentration at hot, zero power with all control rods inserted. OPC l does not explicitly include this test as part of its reload startup physics test program. However, DPC notes that this test would be performed as part i of the control rod bank worth test using the rod swap method. The staff concurs with DPC's assessment concerning this test and the changes noted when the reference bank of the rod swap method is used for the test. The staff concludes that DPC's inclusion of this test in the control rod bank worth test is acceptable because the intent of ANS!/ANS-19.6.1-1985 standard with regard to the comparison of measured and predicted differential boron worth is met.
DPC states that the reload startup physics test program is a minimum program.
Additional tests will be performed when circumstances or unusual conditions require them. This position is acceptable to the staff and conforms to current
]
Industry practicts. l
3.0 CONCLUSION
S For the reasons discussed above, the staff concludes that OPC's proposed reload startup physics test program for NcGuire and Catawba Nuclear Stations, '
l
i 6
linits 1 and 2 is acceptable because it meets, with the changes noted, the intent of the test program discussed in the AflS!/ANS-19.6.1 1985 standard used for staff guidance.
1
.