ML20212G241
| ML20212G241 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 09/22/1999 |
| From: | Emch R NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212G245 | List: |
| References | |
| NUDOCS 9909290171 | |
| Download: ML20212G241 (17) | |
Text
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UNITED STATES E
j NUCLEAR REGULATORY COMMISSION o
C WASHINGTON, D.C. 20555-0001 k..... p' DUKE ENERGY CORPORATION NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.
DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.180 License No. NPF-35
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
j A. The application for amendment to the Catawba Nuclear Station, Unit 1 (the facility)
Facility Operating License No. NPF-35 filed by the Duke Energy Corporation, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated July 22,1998, and supplemented by letters dated October 22,1998, January 28, May 6, June 24, August 17 and September 15,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR l
Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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9909290171 990922 PDR ADOCK 05000413 i
P PDR 1
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! 2. Accordingly, the license is hereby amended by page changes to the license and Technical Specifications as indicated in the attachment to this license amendment, and paragr e as 2.C.(2) and 2.C.(24) of Facility Operating License No. NPF-35 are hereby amended 1: 'ead as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.180, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Technical Specifications.
(24) Additional Conditions The Additional Conditions contained in Appendix D, as revised through Amendment No.180, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Additional Conditions.
3 This license amendment is effective as of its date of issuance and shall be implemented prior to beginning the installation of the Westinghouse fuel, currently projected to be Fuel Cycle 13.
FOR THE NUCLEAR REGULATORY COMMISSION
/
Richard L. Emch, Jr., Chief, Section 1 Project Dimetorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Operating License and Technical Specification Changes Date of issuance:
September 22, 1999 i
s>R cec q o
y" UNITED STATES
{
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055Mm01 6
.... 4 DUKE ENERGY CORPORATION NORTH CAROLINA MUNICIPAL POWER AGENCY NO.1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE f
Amendment No.172 License No. NPF-52
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility)
Facility Operating License No. NPF-52 fibd by the Duke Energy Corporation, acting for itself, North Carolina Municipal Power Agency No.1 and Piedmont Municipal Power Agency (licensees), dated July 22,1998, and supplemented by letters dated October 22,1998, January 28, May 6, June 24, August 17 and September 15,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.
The facility will operate n conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health ar'd safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
(
c 2. Accordingly, the license is hereby amended by page changes to the license and Technical Specifications as indicated in the attachment to this license amendment, and Paragraphs 2.C.(2) and 2.C.(13) of Facility Operating License No. NPF-52 are hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.172, which are attached hereto, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Technical Specifications.
(13) AdditionalConditions The Additional Conditions contained in Appendix D, as revised through Amendment No.172, are hereby incorporated into this license. Duke Energy Corporation shall operate the facility in accordance with the Additional Conditions.
3, This license amendment is effective as of its date of issuance and thall be implemented prior to beginning the installation of the Westinghouse fuel, currentij projected to be Fuel Cycle 11.
FOR THE NUCLEAR REGULATORY COMMISSION ML%<Af/-
Richard L. Emch, Jr., Chief, Section 1 Project Directorate ll Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Operating License and Technical Specification Changes Date of Issuance: September 22, 1999
ATTACHMENT TO LICENSE AMENDMENT NO.180 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND LICENSE AMENDMENT NO.172 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 Replace the following pages of Appendix D, Additional Conditions, of each unit's operating license with the attached revised pages. The revised pages are identified by amendment number and contain marginallines indicating the areas of change.
Remove Insert 2
2 Replace the following pages of Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginallines indicating the areas of change.
Remove Insert 2.0-2 2.0 2 2.0-3 3.2.1-4 3.2.1 -4 3.2.1-5 3.2.1-5 3.2.2-4 3.2.2-4 4.0-1 4.0-1 5.6-3 5.6-3 5.6-4 5.6-4 5.6-5 5.6-5 Replace the following pages of the Technical Specifications Bases document with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Insert B 3.2.1-11 b 3.2.1-11 B 3.2.2-9 B 3.2.2-9
o APPENDIX D 3
ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-35 (Continued)
Amendment implementation Number Additional Condition Date 173 The schedule for the performance of new and By January 31,1999 revised surveillance requirements shall be as follows:
i For surveillance requirements (SRs) that are new in Amendment No.173 the first performance is due at the end of the first surveillance interval
)
that begins at implementation of Amendment
{
No.173. For SRs that existed prior to Amendment No.173, including SRs with modified acceptance criteria and SRs whose intervals of performance are being extended, the first performance is due at
]
the end of the first surveil!ance interval that begins l
on the date the surveillance was last performed prior to implementation of Amendment No.173.
For SRs that existed prior to Amendment No.173, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after a
implementation of Amendment No.173.
180 The maximum rod average burnup for any rod shall Within 30 days of be limited to 60 GWd/mtU until the completion of an date of amendment i
NRC environmental assessment supporting an increased limit.
I l
- Amendment No.180 i
APPENDIX D ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-52 (Continued)
Amendment Implementation Number Additional Condition Date 165 The schedule for the performance of new and By January 31,1999 revised surveillance requirements shall be as follows:
For surveillance requirements (SRs) that are new in Amendment No.165 the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment No.165. For SRs that existed prior to Amendment No.165, including SRs with modified acceptance criteria and SRs whose intervals of performance are being extended, the first performance is due at the end of the first surveillance interval that begins
(
on the date the surveillance was last performed prior to implementation of Amendment No.165.
For SRs that existed prior to Amendment No.165, whose intervals of performance are being reduced, the first reduced surveillance interval begins upon completion of the first surveillance performed after implementation of Amendment No.165.
172 The maximum rod average burnup for any rod shall Within 30 days of be limited to 60 GWd/mtU until the completion of an date of amendment NRC w onmental assessment supporting an increased limit.
1 Amendment No.172
l SLs 2.0 f
670 DO NOT OPERATE IN THIS AREA 660 650 640
{
2400 psia 630 v
(U 2280 psia f--
$620 2100 psia 610 600 1945 psia 590 ACCEPTABLE OPERATION 580 0.0 0.2 0.4 0.6 0.8 1.0 1.2 Fraction of Rated Thermal Power l
Figure 2.1.1-1 Reactor Core Safety Limits Four Loops in Operation Catawba Units 1 and 2 2.0-2 Amendment No.180 (Unit 1) 172 (Unit 2)
Fe(X,Y,Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.2.1.2
NOTE----------------------------
1.
Extrapolate F%(X,Y,Z) using at least two measurements to 31 EFPD beyond the most recent measurement. If F%(X,Y,Z)is~within limits and the 31 EFPD extrapolation indicates:
F%(X,Y,Z)exrnApoutco 2 h(X,Y,Z) "EXTRAPOLATEo, F
and E"(X.Y.Z)eXTRAPOuTc0 > f%fX.Y.Z)
Fo(X,Y,Z) "exrninouiso fo(X,Y,Z)"
then:
1 Increase F"o(X,Y,Z) by the appropriate a.
factor specified in the COLR and reverify F%(X,Y,Z) s Fb(X,Y,Z) "; or b.
Repeat SR 3.2.1.2 prior to the time at which F"o(X,Y,Z) s Fo(X,Y,Z) "is extrapolated to not be met.
2.
Extrapolation of F"o(X,Y,Z) is not required for the initial flux map taken after reaching equilibrium conditions.
Verify FY(X,Y,Z) s Fb(X,Y,Z) ".
Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which F"o(X,Y,Z) was last verified AND 31 EFPD thereafter (continued)
Catawba Units 1 and 2 3.2.1 -4 Amendment Nos,180 (Unit 1) 172 (Unit 2)
Fo(X,Y,Z) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.2.1.3 N OTE S---..-----
1.
Extrapolate F"(X,Y,Z) using at least two measurements to 31 EFPD beyond the most recent measurement. If F"o(X,Y,Z) is within limits and the 31 EFPD extrapolation indicates:
F"o(X,Y,Z) EXTRAPOLATED E Fb(X,Y,Z)""8 cxtampotaico, and E"o(X.Y.Z)sxin4Potareo > E"o(X.Y.Z)
Fb(X,Y,Z)""8 Fb(X,Y,Z)""8 exia4 pot 41co -
then; a.
Increase F"(X,Y,Z) by the appropriate factor specified in the COLR and reverify.
F"o(X,Y,Z) $ Fb(X,Y,Z)""8; or b.
Repeat SR 3.2.1.3 prior to the time at which F"o(X,Y,Z) $ Fb(X,Y,Z)""8 is extrapolated to not be met.
2.
Extrapolation of F"o(X,Y,Z)is not required for the initial flux map taken after reaching equilibrium conditions.
Verify F"o(X,Y,Z)s Fb(X,Y,Z)""S.
Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions after exceeding, by 2 10% RTP, the THERMAL POWER at which F"o(X,Y,Z) was last verified 8NQ 31 EFPD thereafter Catawba Units 1 and 2 3.2.1-5 Amendment Nos.180 (Unit 1) 172 (Unit 2)
7 F s@,W 3
3.2.2
' SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.2.2.2
~ NOTES---
1.
Extrapolate F"as(X,Y) using at least two-measurements to 31 EFPD beyond the most recent measurement. If Fis(X,Y)is within limits and the 31 EFPD extrapolation indicates:-
F"3n(X,Y)EXTRAPotAfro 2 Fis(X,Y)S""%ra4potareo -
and E"inGlex1=4,otArco.> E"3sp Fis(X,Y)"exinacotareo Fis@,W" then:
a.
increase F"s(X.Y) by the appropriate factor specified in the COLR and reverify F"s(X,Y) s Fis(X,Y)5u"v or b.
Repeat SR 3.2.2.2 prior to the time at which F"s(X,Y) s Fis(X,Y)5URV is -
extrapolated to not be met.
- 2.
Extrapolation of F"s(X,Y)is not required for the initial flux map taken after reaching equilibrium conditions.
Verify F"s(X,Y) s Fis(X,Y)suav, Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions after l
exceeding, by 2 10% RTP, the THERMAL l
POWER at which F"s(X,Y) was last verified AND 31 EFPD thereafter
~ Catawba Units 1 and 2 3.2.2-4 Amendment Nos.180 (Unit 1) 172 (Unit 2) o
Fa(X,Y,Z)
B 3.2.1 BASES SURVEILLANCE REQUIREMENTS (continued) than the measured factor is of the current limit, additional actions must be taken. These actions are to meet the Fo(X,Y,Z) limit with the last F"o(X,Y,Z) increased by the appropriate factor specified in the COLR or l
to evaluate Fo(X,Y,Z) prior to the projected point in time when the extrapolated values are expected to exceed the extrapolated limits.
These alternative requirements attempt to prevent Fo(X,Y,Z) from exceeding its limit for any significant period of time without detection using the best available data. F"a(X,Y,Z)is not required to be extrapolated for the initial flux map taken after reaching equilibrium conditions since the initial flux map establishes the baseline measurement for future trending.. Also, extrapolation of F"o(X,Y,Z) limits are not valid for core locations that were previously rodded, or for core locations that were previously within 12% of the core height about the demand position of the rod tip.
Fo(X,Y,Z) is verified at power levels :t 10% RTP above the THERMAL POWER of its last verification,12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions to ensure that Fo(X,Y,Z) is within its limit at higher power levels.
The Surveillance Freauency of 31 EFPD is adequate to monitor the change of power Gtribution with core burnup. The Surveillance may be done more frequently if required by the results of Fo(X,Y,Z) evaluations.
The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.
I REFERENCES 1.
10 CFR 50.46,1974, 2.
UFSAR Section 15.4.8.
3.
10 CFR 50, Appendix A, GDC 26.
4.
10 CFR 50.36, Technical Specifications, (c)(2)(ii).
5.
DPC-NE-2011PA " Duke Power Company Nuclear Design Methodology for Core Operating Limits of Westhghouse Reactors",
March 1990.
Catawba Units 1 and 2 B 3.2.1-11 Revision No.1
F.ss@,W B 3.2.2 BASES SURVEILLANCE REQUIREMENTS (continued) channel factor to the surveillance limit is likely to decrease below the value of that ratio when the measurement was taken.
Each of these extrapolations is applied separately to the enthalpy rise hot channel factor surveillance limit. If both of the extrapolations are unfavorable, i.e., if the extrapolated factor is expected to exceed the extrapolated limit and the extrapolated factor is expected to become a larger fraction of the extrapolated limit than the measured factor is of the current limit, additional actions must be taken. These actions are to meet the F"3n(X,Y) limit with the last F"3s(X,Y) increased by the appropriate factor specified in the COLR or to evaluate F"3n(X,Y) prior to the point in time when the extrapolated values are expected to exceed the extrapolated limits. These alternative requirements attempt to prevent F"3s(X,Y) from exceeding its limit for any significant period of time without detection using the best available data. F"3s(X,Y)is not required to be extrapolated for the initial flux map taken after reaching equilibrium conditions since the initial flux map establishes the baseline measurement for future trending.
F"in(X,Y) is verified at power levels 10% RTP above the THERMAL POWER of its last verification,12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after achieving equilibrium conditions to ensure that F".sn(X,Y) is within its limit at high power levels.
The Surveillance Frequency of 3i TFPD is adequate to monitor the change of power distribution with core burnup. The Surveillance may be done more frequently if required by the results of F"3s(X,Y) evaluations.
The Frequency of 31 EFPD is adequate to monitor the change of power distribution because such a change is sufficiently slow, when the plant is operated in accordance with the TS, to preclude adverse peaking factors between 31 day surveillances.
REFERENCES 1.
UFSAR Section 15.4.8 2.
10 CFR 50, Appendix A, GDC 26.
3.
4.
10 CFR 50.36, Technical Specifications, (c)(2)(ii).
5.
DPC-NE-2005P," Duke Power Company Thermal Hydraulic Statistical Core Design Methodology", September 1992.
Catawba Units 1 and 2 B 3.2.2-9 Revision No.1
\\
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1 Design Features 4.0 l
4.0 DESIGN FEATURES 4.1 Site Location Catawba Nuclear Station is located in the north central portion of South Carolina approximately six miles north of Rock Hill and adjacent to Lake Wylie. The station center is located at latitude.35 degrees,3 minutes,5 seconds north and longitude 81 degrees,4 minutes,10 seconds west. ' The corresponding Universal Transverso Mercator Coordinates are E 493,660 and N 3,878,558, zone 17.
4.2 ' Reactor Core 4.2.1 Fuel Assemblies
.. The reactor shall contain 193 fuel assemblies. Each. assembly shall consist of a matrix of either ZlRLO or Zircalloy fuel rods with an initial composition of l
natural or slightly enriched uranium dioxide (UO ) as fuel material. Limited 2
substitutions of ZlRLO", zirconium alloy, or stainless steel filler rods for fuel l
rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by
- tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies. The control material shall be silver indium cadmium and boron carbide as approved by the NRC.
4.3-Fuel Storage
-4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
(continued)
Catawba Units 1 and 2 4.0-1 Amendment Nos. 180 (Unit 1) 172 (Unit 2)
r:
L Reporting Requirements f
5.6 i-t 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 1.
Moderator Temperature Coefficient BOL and EOL limits and 300 ppm surveillance limit for Specification 3.1.3, 2.
Shutdown Bank Insertion Limit for Specification 3.1.5, j
3.
Control Bank Insertion Limits for Specification 3.1.6, 4.
Axial Flux Difference limits for Specification 3.2.3, l
5.
Heat Flux mt Channel Factor for Specification 3.2.1, 6.
Nuclear Enthalpy Rise Hot Channel Factor for Specification 3.2.2, 7.
Overtemperature and Overpower Delta T setpoint parameter values for Specification 3.3.1, 8.
Accumulator and Refueling Water Storage Tank boron concentration limits for Specification 3.5.1 and 3.5.4, l
9.
Reactor Coolant System and refueling canal boron concentration limits for Specification 3.9.1, 10.
Spent fuel pool boron concentration limits for Specification 3.7.15, 11.
SHUTDOWN MARGIN for Specification 3.1.1.
b.
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
1.
WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY q
EVALUATION METHODOLOGY," July 1985 (W Proprietary).
2.
WCAP-10266-P 'A Rev. 2, "THE 1981 VERSION OF WESTINGHOUSE EVALUATION MODEL USING BASH CODE",
March 1987, (W Proprietary).
l l
(continued)
Catawba Units 1 and 2 5.6-3 Amendment Nos.180 (Unit 1) 172 (Unit 2)
L Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 QQREi OPERATING LIMITS REPORT (COLR) (continued) 3.
BAW-10168P-A,"B&W Loss-of-Coolant Accident Evaluation l
Model for Recirculating Steam Generator Plants," Rev.1, SER dated January 22,1991; Rev. 2, SERs Dated August 22,1996 and November 26,1996; Rev. 3, SER Dated June 15,1994 (B&W Proprietary).
4.
DPC-NE-2011P-A, " Duke Power Company Nuclear Design l
Methodology for Core Operating Limits of Westinghouse Reactors," March,1990 (DPC Proprieta>y).
5.
DPC-NE-3001P-A, " Multidimensional Reactor Transients and l
Safety Analysis Physics Parameter Methodology," November, 1991 (DPC Proprietary).
6.
DPC-NF-2010A, " Duke Power Company McGuire Nuclear Station l l
Catawba Nuclear Station Nuclear Physics Methodology for Reload Design," June,1985.
7.
DPC-NE-3002-A, Rev. 3 "FSAR Chapter 15 System Transient Analyds Methodology," SER dated February 5,1999.
8.
DPC-NE-3000PA, Rev. 2 " Thermal-Hydraulic Transient Analysis Methodology," SER Dated October 14,1998 (DPC Proprietary).
9.
DPC-NE-1004A, Rev.1," Design Methodology Using CASMO-l 3/ SIMULATE-3P," SER Dated April 26,1996.
10.
DPC-NE-2004P-A. Rev.1," Duke Power Company McGuire and l
Catawba Nuclear Stations Core Thermal-Hydraulic Methodology using VIPRE-01," SER dated February 20,1997 (DPC Proprietary).
11.
DPC-NE-2005P-A, Rev.1, " Thermal Hydraulic Statistical Core Design Methodology," SER dated November 7,1996 (DPC Proprietary).
12.
DPC-NE-2008P-A," Fuel Mechanical Reload Analysis l
Methodology Using TACO 3," SER dated April 3,1995 (DPC Proprietary).
j (continued)
Catawba Units 1 and 2 5.6-4 Amendment Nos.180 (Unit 1) 172 (Unit 2)
Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued) 13.
WCAP-10054-P-A, " Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985
~ W Proprietary).
(
14.
DPC-NE-2009P-A," Westinghouse Fuel Transition Report," SER dated September 22,1999 '(UPC Proprietary).
c.
The core operatie i limits shall be determined such that all applicable limits (e.g., fuel 'o nal mechanical limits, core thermal hydraulic limits, Emergency Coro Looling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.
d.
The COLR, including any midcycie revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.
5.6.6 Ventilation Svstems Heater Reoort When a report is required by LCO 3.6.10," Annulus Ventilation System (AVS),"
LCO 3.7,10, " Control Room Area Ventilation System (CRAVS)," LCO 3.7.12, Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)," LCO 3.7.13,
" Fuel Handling Ventilation Exhaust System (FHVES)," or LCO 3.9.3,
" Containment Penetrations," a report shall be submitted within the following 30 days. The report shall outline the reason for the inoperability and the planned actions to return the systems to OPERABLE status.
]
5.6.7 PAM Reoort When a report is required by LCO 3.3.3," Post Accident Monitoring (PAM) instrumentation," a report shall be submitted within the founwing 14 days. The i
report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.
5.6.8 Steam Generator Tube insoection Reoort T; o num' u on tubes plugged in each steam generator shall be reported a.
u to the NRC within 15 days following completion of the program; (continued) e 3
Catawba Units 1 and 2 5.6-5 Amendment Nos.180 (Unit 1) 172 (Unit 2)