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{{#Wiki_filter:Attachment o SERIAL: HNP-94-013 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TIMNSITION- SUPPLEMENTAL INFORMATION TECHNICAL SPECIFICATION PAGES q0050400 Bg qp0217 05000000 pgR   ADQC       pDR P
{{#Wiki_filter:Attachment o SERIAL: HNP-94-013 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TIMNSITION-SUPPLEMENTAL INFORMATION TECHNICALSPECIFICATION PAGES q0050400 05000000 Bg qp0217 pgR ADQC pDR P


ADMINISTRATIVE CONTROLS 6 9 1 6     CORE OPERATING   LIMITS REPORT 6.9.1.6.1       Core operating limits shall be established and documented in the CORE OPERATING     LIMITS REPORT (COLR), plant procedure PLP-106, prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:
ADMINISTRATIVE CONTROLS 6
: a.     Moderator Temperature Coefficient Positive and Negative Limits and 300 ppm   surveillance   limit for Specification 3/4.1.1.3,
9 1
: b.     Shutdown Bank   Insertion Limits for Specification 3/4.1.3.5,
6 CORE OPERATING LIMITS REPORT 6.9.1.6.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106, prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:
: c.     Control Bank Insertion Limits for Specification 3/4.1.3.6,
a.
: d.     Axial Flux Difference Limits       t                   and APL D
Moderator Temperature Coefficient Positive and Negative Limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, b.
for Specification 3/4.2.1, V
Shutdown Bank Insertion Limits for Specification 3/4.1.3.5, c.
: e.     Heat Flux Hot Channel Factor, F<"         , K(Z),                     and Pf(Z) for Specification 3/4.2.2,
Control Bank Insertion Limits for Specification 3/4.1.3.6, d.
: f.     Enthalpy Rise Hot Channel Factor,         FaH   ,  and Power Factor Multiplier,   PFoH for Specification 3/4.2.3.
Axial Flux Difference Limits t and APL for D
: g.     Boron   Concentration for Specification 3/4.9.1.
Specification 3/4.2.1, V
  '.9.1.6.2         The analytical   methods used to determine the core operating                   limits shall     be those previously reviewed and     a     roved b the NRC
and Pf(Z) e.
                                                ~     a< c me,             c reload anaiySn   are. per orgcd and one approve       rats(on pucnbcr Sha(l bc identified s
Heat Flux Hot Channel Factor, F<"
(~S<~STATEMC~            2 HERE)
, K(Z),
I g      WCAP-9272-P-A, "WESTINGHOUSE RELO July 1985 (W Proprietary)     ~
for Specification 3/4.2.2, f.
SAFETY EVALUATION METHODO (Methodolo      for S ecification              3 - Moderator Temperat Coefficient, 3.1.3.5 -            own Bank Insertion Lim'                    .3.6 Control Bank          tion Limit 3.2.1-                                      c      3.2.2 Heat Flux Hot Channel Factor,        .2.3    - Nuclear Enthalpy Rise Hot and    Channel Factor an                                        3.0    ~
Enthalpy Rise Hot Channel Factor, FaH and Power Factor Multiplier, PFoH for Specification 3/4.2.3.
: b.     WCAP-11914,   "SAFETY EV   UATION SUPPORTING A MORE N                 IVE EOL MODERATOR TEMPERA           OEFFICIENT TECHNICAL SP                 ICATION FOR THE SHEARON .HARRIS     LEAR POWER PIANT", Augus               88 (W Proprietary).
g.
Approved         C Safety Evaluation date             ay 22, 1989.
Boron Concentration for Specification 3/4.9.1.
ethodology for Specification         .   .1.3 - Moderator Temperature Coefficient).
(Methodolo for S ecification 3 - Moderator Temperat Coefficient, 3.1.3.5 own Bank Insertion Lim'
c ~   WCAP-10216-P-A, "          TION OF CONSTANT AXIAL OFFSE                ONTROL Fq SURVEILLANCE T       ICAL SPECIFICATION", JUNE 1983                   Proprietary).
.3.6 Control Bank tion Limit 3.2.1-c 3.2.2 Heat Flux Hot Channel Factor,
(Metho   ogy for Specifications 3.2.1           -    'al   Flux Difference (Re ~ed Axial Offset Control) and           3.       - Heat   Flux Hot Channel actor (Fo Methodology for W(Z) su             illance requirements) ) .
.2.3
SHEARON HARRIS -       UNIT 1                 6-24                                     Amendment No.       ~
- Nuclear Enthalpy Rise Hot and Channel Factor an 3.0
~
'.9.1.6.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and a roved b the NRC
~
a<
c me, c reload anaiySn are. per orgcd s
(~S<~STATEMC~ 2 HERE) and one approve rats(on pucnbcr Sha(l bc identified Ig WCAP-9272-P-A, "WESTINGHOUSE RELO SAFETY EVALUATION METHODO July 1985 (W Proprietary)
~
b.
WCAP-11914, "SAFETY EV UATION SUPPORTING A MORE N IVE EOL MODERATOR TEMPERA OEFFICIENT TECHNICAL SP ICATION FOR THE SHEARON
.HARRIS LEAR POWER PIANT", Augus 88 (W Proprietary).
Approved C Safety Evaluation date ay 22, 1989.
ethodology for Specification
..1.3
- Moderator Temperature Coefficient).
c ~
WCAP-10216-P-A, TION OF CONSTANT AXIALOFFSE ONTROL Fq SURVEILLANCE T ICAL SPECIFICATION", JUNE 1983 Proprietary).
(Metho ogy for Specifications 3.2.1
'al Flux Difference (Re ~ed Axial Offset Control) and 3.
- Heat Flux Hot Channel actor (Fo Methodology for W(Z) su illance requirements) ).
SHEARON HARRIS
- UNIT 1 6-24 Amendment No. ~


ADMINISTRATIVE CONTROLS j         WCAP-10266-P-A, Rev. 2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).
ADMINISTRATIVE CONTROLS j
(Methodology Eor Specification 3.2.2       - Heat Flux Hot Channel.
WCAP-10266-P-A, Rev. 2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).
(Methodology Eor Specification 3.2.2 - Heat Flux Hot Channel.
Factor).
Factor).
WCAP"8385, "POWE       STRIBUTION CONTROL AND         FOLLOWING PROCEDUR
WCAP"8385, "POWE STRIBUTION CONTROL AND FOLLOWING PROCEDUR
                      - TOPICAL R       T", September 1974 (W P rietary).
- TOPICAL R
odology Eor   Specificat'.2.1       - Axial Flux DifE   ence Consr ant Axial Offset       troL ) ) .
T", September 1974 (W
e       WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", Jynuary 1990 (W Proprietary).
P rietary).
odology Eor Specificat'.2.1
- Axial Flux DifE ence Consr ant Axial Offset troL ) ).
e WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", Jynuary 1990 (W Proprietary).
(Methoclolog'/ +or Speci<<ca+'nn 3.2,3-uuclsaiE~l py Siss, Hc+ Qhanncl Fackr).
(Methoclolog'/ +or Speci<<ca+'nn 3.2,3-uuclsaiE~l py Siss, Hc+ Qhanncl Fackr).
6.9.1.6.3       The core operating limits shall be determined so that all Thing~ ~applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic l,imits, nuclear L.imits such as shutdown margin, and transient and accident, analysis limits) oE the safety analysis are met.
6.9.1.6.3 The core operating limits shall be determined so that all Thing~ ~applicable limits (e.g.,
6~9 ~ 1.6.4     The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, shall be provided, upon issuance Eor each reload cycle, to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspecror.
fuel thermal-mechanical limits, core thermal-hydraulic l,imits, nuclear L.imits such as shutdown margin, and transient and accident, analysis limits) oE the safety analysis are met.
SPECIAL REPORTS 6.9.2     Special reports shall be submitted to the NRC in accordance with 10CFR50.4     within the time period specifi'ed for each report.
6 ~ 9 ~ 1.6.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, shall be provided, upon issuance Eor each reload cycle, to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspecror.
6.10     RECORD RETENTION 6.10.1     In addition to the applicable record retention requirements of Title   10, Code   of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the NRC in accordance with 10CFR50.4 within the time period specifi'ed for each report.
6.10.2     The   following records shall     be retained Eor at least 5 years:
6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
a ~   Records and Logs of     unit operation covering time intervaL at       each power level;
6.10.2 The following records shall be retained Eor at least 5 years:
: b. Records and Logs     of principal maintenance activities, inspections, repair,   and replacement   of principal items oE equipment reLated to nuclear safety; C ~   All REPORTABLE     EVENTS; d ~   Records of surveillance activities, inspections,         and'alibrations required by these Technical Specifications; SHEARON HARRIS       - UNIT 1               6"24a                       Amendment No.
a ~
Records and Logs of unit operation covering time intervaL at each power level; b.
Records and Logs of principal maintenance activities, inspections,
: repair, and replacement of principal items oE equipment reLated to nuclear safety; C ~
All REPORTABLE EVENTS; d ~
Records of surveillance activities, inspections, and'alibrations required by these Technical Specifications; SHEARON HARRIS - UNIT 1
6"24a Amendment No.


(zNacT   7o Fige'           Statement  g
(zNacT 7o Fige'
                  -2V~
-2V~
            ~A)         lakes% f4''is,ion a,nd Juppk,we.efg>
Statement g
E<F-gg-gal&         "Statistical       Setppint/Transient     Mettpdpipgy     fpr Westinghouse Type Reactors.," Siemens Power Corporation, Richland       MA 99352.
~A) lakes%
(Methodology     for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3e6 - Control Bank Insertion Limits, 3.2. 1 - Axial Flux Oifference, 3.2.2 - Meat Flux Mot Channel Factor,   and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
f4''is,ion a,nd Juppk,we.efg>
Jafesi. PeVisioA and $ gpp'rernehks>
E<F-gg-gal&
EMF-92-153+/, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel," Siemens Nuclear Power Corporation, Richland MA 99352.
"Statistical Setppint/Transient Mettpdpipgy fpr Westinghouse Type Reactors.,"
(Methodology   for Specification 3.2.3       - Nuclear Enthalpy Rise Hot Channel Factor}.
Siemens Power Corporation, Richland MA 99352.
                    /a~esy Revision   and SUpptemt'.nts, XN-NF-82-49(A)                                                 A~uniate~
(Methodology for Specification
Small Break Model," Exxon "Exxon Nuclear Company Evaluation Model         EXEM PMR Nuclear Company, Richland MA 99352.
: 3. 1. 1.3 Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3e6
                                                                            - Heat (Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2   Hot  Channel Flux Hot Channel Factor, and 3.2.3         - Nuclear Enthalpy Rise Factor).
- Control Bank Insertion Limits, 3.2. 1 - Axial Flux Oifference, 3.2.2
- Meat Flux Mot Channel
: Factor, and 3.2.3
- Nuclear Enthalpy Rise Hot Channel Factor).
Jafesi.
PeVisioA and $ gpp'rernehks>
EMF-92-153+/,
"HTP: Departure from Nucleate Boiling Correlation for High 99352.
Thermal Performance Fuel," Siemens Nuclear Power Corporation, Richland MA (Methodology for Specification 3.2.3
- Nuclear Enthalpy Rise Hot Channel Factor}.
/a~esy Revision and SUpptemt'.nts, XN-NF-82-49(A)
A~uniate~
"Exxon Nuclear Company Evaluation Model EXEM PMR Small Break Model," Exxon Nuclear
: Company, Richland MA 99352.
(Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel
: Factor, and 3.2.3
- Nuclear Enthalpy Rise Hot Channel Factor).


ADMINISTRATIVE CONTROLS 6.9. 1. 6   CORE OPERATING   LIMITS   REPORT 6.9. 1.6. 1   Core operating limits shall be established and documented in the CORE OPERATING     LIMITS REPORT (COLR), plant procedure PLP-106, prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:
ADMINISTRATIVE CONTROLS 6.9. 1. 6 CORE OPERATING LIMITS REPORT 6.9. 1.6. 1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106, prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:
: a. Moderator Temperature Coefficient Positive and Negative Limits and 300 ppm   surveillance   limit for Specification 3/4. 1. 1.3,
a.
: b. Shutdown Bank   Insertion Limits for Specification 3/4. 1.3.5,
Moderator Temperature Coefficient Positive and Negative Limits and 300 ppm surveillance limit for Specification 3/4. 1. 1.3, b.
: c. Control Bank Insertion Limits for Specification 3/4. 1.3.6,
Shutdown Bank Insertion Limits for Specification 3/4. 1.3.5, c.
: d. Axial Flux Difference Limits for Specification 3/4.2. 1,
Control Bank Insertion Limits for Specification 3/4. 1.3.6, d.
: e. Heat Flux Hot Channel     Factor, F,"~, K(Z),     and V(Z) for Specification 3/4.2.2,
Axial Flux Difference Limits for Specification 3/4.2. 1, e.
: f. Enthalpy Rise Hot Channel Factor,         F~R~, and Power Factor Multiplier, PF~ for Specification 3/4.2.3.
Heat Flux Hot Channel
: g. Boron Concentration     for Specification 3/4.9.     1.
: Factor, F,"~, K(Z), and V(Z) for Specification 3/4.2.2, f.
Enthalpy Rise Hot Channel
: Factor, F~R~,
and Power Factor Multiplier, PF~ for Specification 3/4.2.3.
g.
Boron Concentration for Specification 3/4.9. 1.
6.9. 1.6.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC at the time the reload analyses are performed, and the approved, revision number shall be identified in the COLR.
6.9. 1.6.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC at the time the reload analyses are performed, and the approved, revision number shall be identified in the COLR.
a ~   XN-75-27(A), latest Revision and Supplements, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors," Exxon Nuclear Company, Richland WA 99352.
a ~
(Methodology   for Specification 3. 1. 1.3     - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor, and 3.9. 1 - Boron Concentration).
XN-75-27(A), latest Revision and Supplements, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors,"
: b. ANF-89-151(A),   latest Revision, "ANF-RELAP Methodology for Pressurized Water Reactors: Analysis of Non-LOCA Chapter 15 Events,"
Exxon Nuclear
: Company, Richland WA 99352.
(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5
- Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, 3.2.3
- Nuclear Enthalpy Rise Hot Channel
: Factor, and 3.9. 1 - Boron Concentration).
b.
ANF-89-151(A), latest Revision, "ANF-RELAP Methodology for Pressurized Water Reactors:
Analysis of Non-LOCA Chapter 15 Events,"
Advanced Nuclear Fuels Corporation, Richland WA 99352.
Advanced Nuclear Fuels Corporation, Richland WA 99352.
(Methodology   for Specification     3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel   Factor).
(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel
C. XN-NF-82-21(A),   latest Revision, "Application of       Exxon Nuclear Company   PWR Thermal Margin Methodology to Mixed Core         Configurations,"
: Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
Exxon Nuclear Company, Richland WA 99352.
C.
(Methodology   for Specification 3.2.3       - Nuclear Enthalpy Rise Hot Channel   Factor).
XN-NF-82-21(A), latest Revision, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,"
SHEARON HARRIS     -'NIT 1                 6-24                           Amendment No.
Exxon Nuclear
: Company, Richland WA 99352.
(Methodology for Specification 3.2.3
- Nuclear Enthalpy Rise Hot Channel Factor).
SHEARON HARRIS -'NIT 1 6-24 Amendment No.


ADMINISTRATIVE CONTROLS 6:9.1.6 CORE OPERATING   LIMITS REPORT (Continued)
ADMINISTRATIVE CONTROLS 6:9.1.6 h.
: h. ANF-88-054(A),   latest Revision, "PDC-3: Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2," Advanced Nuclear Fuels Corporation, Richland     WA   99352.
k.
n.
CORE OPERATING LIMITS REPORT (Continued)
ANF-88-054(A), latest Revision, "PDC-3:
Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2," Advanced Nuclear Fuels Corporation, Richland WA 99352.
(Methodology for Specification 3.2. 1,- Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor).
(Methodology for Specification 3.2. 1,- Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor).
WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",
WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",
July 1985 (W Proprietary).
July 1985 (W Proprietary).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
(Methodology for Specification 3.2.2
WCAP-10266-P-A, Rev. 2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).
- Heat Flux Hot Channel Factor and 3.2.3
(Methodology for Specification 3.2.2 -     Heat Flux Hot Channel Factor).
- Nuclear Enthalpy Rise Hot Channel Factor).
I
WCAP-10266-P-A, Rev.
: k. WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", January 1990 (W Proprietary).
2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).
(Methodology for Specification 3.2.3 - Nuclear Enthalpy       Rise Hot Channel Factor).
(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).
EMF-92-081(A),   latest Revision   and Supplements,   "Statistical Setpoint/Transient Methodology for Westinghouse       Type Reactors,"
I WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", January 1990 (W Proprietary).
(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
EMF-92-081(A), latest Revision and Supplements, "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors,"
Siemens Power Corporation, Richland WA 99352.
Siemens Power Corporation, Richland WA 99352.
(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3.1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel   Factor,   and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5
EMF-92-153(A), latest Revision and Supplements, "HTP: Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"
- Shutdown Bank Insertion Limits, 3.1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel
: Factor, and 3.2.3
- Nuclear Enthalpy Rise Hot Channel Factor).
EMF-92-153(A), latest Revision and Supplements, "HTP:
Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"
Siemens Nuclear Power Corporation, Richland WA 99352.
Siemens Nuclear Power Corporation, Richland WA 99352.
(Methodology for Specification 3.2.3     - Nuclear Enthalpy Rise Hot Channel Factor).
(Methodology for Specification 3.2.3
: n. XN-NF-82-49(A),   latest Revision and Supplements, "Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model," Exxon Nuclear Company, Richland WA 99352.
- Nuclear Enthalpy Rise Hot Channel Factor).
(Methodology for Specification 3.2. 1     - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).
XN-NF-82-49(A), latest Revision and Supplements, "Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model," Exxon Nuclear
SHEARON HARRIS - UNIT 1               6-24b                         Amendment No.
: Company, Richland WA 99352.
(Methodology for Specification 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel
: Factor, and 3.2.3
- Nuclear Enthalpy Rise Hot Channel Factor).
SHEARON HARRIS - UNIT 1 6-24b Amendment No.


ATIACHMENT3       SERIAL: HNP-94-013 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TRANSITION REVISED PAGE CHANGE INSTRUCTIONS REMOVED PAGE                      INSERTED PAGE 3/4 2-1                           3/4 2-1 3/4 2-2                            3/4 2-2 3/4 2-4                            3/4 2-4 3/4 2-6                            3/4 2-6 3/4 2-7a                          3/4 2-7a 3/4 2-7b                          3/4 2-7b 3/4 2-7c                          DELETED 3/4 2-7d                          DELETED 3/4   10-2                        3/4 10-2 B 3/4 2-1                          B 3/4 2-1 B 3/4 2-2                         B 3/4 2-2 B 3/4 2-4                          B 3/4 2-4 6-24                              6-24 6-24a                             6-24a 6-24b                              6-24b 6-24c}}
ATIACHMENT3 SERIAL: HNP-94-013 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TRANSITION REVISED PAGE CHANGE INSTRUCTIONS REMOVED PAGE 3/4 2-1 3/4 2-2 3/4 2-4 3/4 2-6 3/4 2-7a 3/4 2-7b 3/4 2-7c 3/4 2-7d 3/4 10-2 B 3/4 2-1 B 3/4 2-2 B 3/4 2-4 6-24 6-24a 6-24b INSERTED PAGE 3/4 2-1 3/4 2-2 3/4 2-4 3/4 2-6 3/4 2-7a 3/4 2-7b DELETED DELETED 3/4 10-2 B 3/4 2-1 B 3/4 2-2 B 3/4 2-4 6-24 6-24a 6-24b 6-24c}}

Latest revision as of 06:31, 7 January 2025

Proposed Tech Specs Re Cycle 6 Fuel Transition
ML18011A349
Person / Time
Site: Harris 
Issue date: 02/17/1994
From:
CAROLINA POWER & LIGHT CO.
To:
Shared Package
ML18011A348 List:
References
HNP-94-013, HNP-94-13, NUDOCS 9403040084
Download: ML18011A349 (9)
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Text

Attachment o SERIAL: HNP-94-013 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TIMNSITION-SUPPLEMENTAL INFORMATION TECHNICALSPECIFICATION PAGES q0050400 05000000 Bg qp0217 pgR ADQC pDR P

ADMINISTRATIVE CONTROLS 6

9 1

6 CORE OPERATING LIMITS REPORT 6.9.1.6.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106, prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

a.

Moderator Temperature Coefficient Positive and Negative Limits and 300 ppm surveillance limit for Specification 3/4.1.1.3, b.

Shutdown Bank Insertion Limits for Specification 3/4.1.3.5, c.

Control Bank Insertion Limits for Specification 3/4.1.3.6, d.

Axial Flux Difference Limits t and APL for D

Specification 3/4.2.1, V

and Pf(Z) e.

Heat Flux Hot Channel Factor, F<"

, K(Z),

for Specification 3/4.2.2, f.

Enthalpy Rise Hot Channel Factor, FaH and Power Factor Multiplier, PFoH for Specification 3/4.2.3.

g.

Boron Concentration for Specification 3/4.9.1.

(Methodolo for S ecification 3 - Moderator Temperat Coefficient, 3.1.3.5 own Bank Insertion Lim'

.3.6 Control Bank tion Limit 3.2.1-c 3.2.2 Heat Flux Hot Channel Factor,

.2.3

- Nuclear Enthalpy Rise Hot and Channel Factor an 3.0

~

'.9.1.6.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and a roved b the NRC

~

a<

c me, c reload anaiySn are. per orgcd s

(~S<~STATEMC~ 2 HERE) and one approve rats(on pucnbcr Sha(l bc identified Ig WCAP-9272-P-A, "WESTINGHOUSE RELO SAFETY EVALUATION METHODO July 1985 (W Proprietary)

~

b.

WCAP-11914, "SAFETY EV UATION SUPPORTING A MORE N IVE EOL MODERATOR TEMPERA OEFFICIENT TECHNICAL SP ICATION FOR THE SHEARON

.HARRIS LEAR POWER PIANT", Augus 88 (W Proprietary).

Approved C Safety Evaluation date ay 22, 1989.

ethodology for Specification

..1.3

- Moderator Temperature Coefficient).

c ~

WCAP-10216-P-A, TION OF CONSTANT AXIALOFFSE ONTROL Fq SURVEILLANCE T ICAL SPECIFICATION", JUNE 1983 Proprietary).

(Metho ogy for Specifications 3.2.1

'al Flux Difference (Re ~ed Axial Offset Control) and 3.

- Heat Flux Hot Channel actor (Fo Methodology for W(Z) su illance requirements) ).

SHEARON HARRIS

- UNIT 1 6-24 Amendment No. ~

ADMINISTRATIVE CONTROLS j

WCAP-10266-P-A, Rev. 2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).

(Methodology Eor Specification 3.2.2 - Heat Flux Hot Channel.

Factor).

WCAP"8385, "POWE STRIBUTION CONTROL AND FOLLOWING PROCEDUR

- TOPICAL R

T", September 1974 (W

P rietary).

odology Eor Specificat'.2.1

- Axial Flux DifE ence Consr ant Axial Offset troL ) ).

e WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", Jynuary 1990 (W Proprietary).

(Methoclolog'/ +or Speci<<ca+'nn 3.2,3-uuclsaiE~l py Siss, Hc+ Qhanncl Fackr).

6.9.1.6.3 The core operating limits shall be determined so that all Thing~ ~applicable limits (e.g.,

fuel thermal-mechanical limits, core thermal-hydraulic l,imits, nuclear L.imits such as shutdown margin, and transient and accident, analysis limits) oE the safety analysis are met.

6 ~ 9 ~ 1.6.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements, shall be provided, upon issuance Eor each reload cycle, to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspecror.

SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the NRC in accordance with 10CFR50.4 within the time period specifi'ed for each report.

6.10 RECORD RETENTION 6.10.1 In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.

6.10.2 The following records shall be retained Eor at least 5 years:

a ~

Records and Logs of unit operation covering time intervaL at each power level; b.

Records and Logs of principal maintenance activities, inspections,

repair, and replacement of principal items oE equipment reLated to nuclear safety; C ~

All REPORTABLE EVENTS; d ~

Records of surveillance activities, inspections, and'alibrations required by these Technical Specifications; SHEARON HARRIS - UNIT 1

6"24a Amendment No.

(zNacT 7o Fige'

-2V~

Statement g

~A) lakes%

f4is,ion a,nd Juppk,we.efg>

E<F-gg-gal&

"Statistical Setppint/Transient Mettpdpipgy fpr Westinghouse Type Reactors.,"

Siemens Power Corporation, Richland MA 99352.

(Methodology for Specification

3. 1. 1.3 Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3e6

- Control Bank Insertion Limits, 3.2. 1 - Axial Flux Oifference, 3.2.2

- Meat Flux Mot Channel

Factor, and 3.2.3

- Nuclear Enthalpy Rise Hot Channel Factor).

Jafesi.

PeVisioA and $ gpp'rernehks>

EMF-92-153+/,

"HTP: Departure from Nucleate Boiling Correlation for High 99352.

Thermal Performance Fuel," Siemens Nuclear Power Corporation, Richland MA (Methodology for Specification 3.2.3

- Nuclear Enthalpy Rise Hot Channel Factor}.

/a~esy Revision and SUpptemt'.nts, XN-NF-82-49(A)

A~uniate~

"Exxon Nuclear Company Evaluation Model EXEM PMR Small Break Model," Exxon Nuclear

Company, Richland MA 99352.

(Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel

Factor, and 3.2.3

- Nuclear Enthalpy Rise Hot Channel Factor).

ADMINISTRATIVE CONTROLS 6.9. 1. 6 CORE OPERATING LIMITS REPORT 6.9. 1.6. 1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR), plant procedure PLP-106, prior to each reload cycle, or prior to any remaining portion of a reload cycle, for the following:

a.

Moderator Temperature Coefficient Positive and Negative Limits and 300 ppm surveillance limit for Specification 3/4. 1. 1.3, b.

Shutdown Bank Insertion Limits for Specification 3/4. 1.3.5, c.

Control Bank Insertion Limits for Specification 3/4. 1.3.6, d.

Axial Flux Difference Limits for Specification 3/4.2. 1, e.

Heat Flux Hot Channel

Factor, F,"~, K(Z), and V(Z) for Specification 3/4.2.2, f.

Enthalpy Rise Hot Channel

Factor, F~R~,

and Power Factor Multiplier, PF~ for Specification 3/4.2.3.

g.

Boron Concentration for Specification 3/4.9. 1.

6.9. 1.6.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC at the time the reload analyses are performed, and the approved, revision number shall be identified in the COLR.

a ~

XN-75-27(A), latest Revision and Supplements, "Exxon Nuclear Neutronics Design Methods for Pressurized Water Reactors,"

Exxon Nuclear

Company, Richland WA 99352.

(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5

- Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel Factor, 3.2.3

- Nuclear Enthalpy Rise Hot Channel

Factor, and 3.9. 1 - Boron Concentration).

b.

ANF-89-151(A), latest Revision, "ANF-RELAP Methodology for Pressurized Water Reactors:

Analysis of Non-LOCA Chapter 15 Events,"

Advanced Nuclear Fuels Corporation, Richland WA 99352.

(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5 - Shutdown Bank Insertion Limits, 3. 1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel

Factor, and 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

C.

XN-NF-82-21(A), latest Revision, "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,"

Exxon Nuclear

Company, Richland WA 99352.

(Methodology for Specification 3.2.3

- Nuclear Enthalpy Rise Hot Channel Factor).

SHEARON HARRIS -'NIT 1 6-24 Amendment No.

ADMINISTRATIVE CONTROLS 6:9.1.6 h.

k.

n.

CORE OPERATING LIMITS REPORT (Continued)

ANF-88-054(A), latest Revision, "PDC-3:

Advanced Nuclear Fuels Corporation Power Distribution Control for Pressurized Water Reactors and Application of PDC-3 to H. B. Robinson Unit 2," Advanced Nuclear Fuels Corporation, Richland WA 99352.

(Methodology for Specification 3.2. 1,- Axial Flux Difference, and 3.2.2 - Heat Flux Hot Channel Factor).

WCAP-9272-P-A, "WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY",

July 1985 (W Proprietary).

(Methodology for Specification 3.2.2

- Heat Flux Hot Channel Factor and 3.2.3

- Nuclear Enthalpy Rise Hot Channel Factor).

WCAP-10266-P-A, Rev.

2, "The 1981 Version of the WESTINGHOUSE ECCS EVALUATION MODEL USING THE BASH CODE", March 1987 (W Proprietary).

(Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor).

I WCAP-11837-P-A, "EXTENSION OF METHODOLOGY FOR CALCULATING TRANSITION CORE DNBR PENALTIES", January 1990 (W Proprietary).

(Methodology for Specification 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor).

EMF-92-081(A), latest Revision and Supplements, "Statistical Setpoint/Transient Methodology for Westinghouse Type Reactors,"

Siemens Power Corporation, Richland WA 99352.

(Methodology for Specification 3. 1. 1.3 - Moderator Temperature Coefficient, 3. 1.3.5

- Shutdown Bank Insertion Limits, 3.1.3.6-Control Bank Insertion Limits, 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel

Factor, and 3.2.3

- Nuclear Enthalpy Rise Hot Channel Factor).

EMF-92-153(A), latest Revision and Supplements, "HTP:

Departure from Nucleate Boiling Correlation for High Thermal Performance Fuel,"

Siemens Nuclear Power Corporation, Richland WA 99352.

(Methodology for Specification 3.2.3

- Nuclear Enthalpy Rise Hot Channel Factor).

XN-NF-82-49(A), latest Revision and Supplements, "Exxon Nuclear Company Evaluation Model EXEM PWR Small Break Model," Exxon Nuclear

Company, Richland WA 99352.

(Methodology for Specification 3.2. 1 - Axial Flux Difference, 3.2.2-Heat Flux Hot Channel

Factor, and 3.2.3

- Nuclear Enthalpy Rise Hot Channel Factor).

SHEARON HARRIS - UNIT 1 6-24b Amendment No.

ATIACHMENT3 SERIAL: HNP-94-013 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TRANSITION REVISED PAGE CHANGE INSTRUCTIONS REMOVED PAGE 3/4 2-1 3/4 2-2 3/4 2-4 3/4 2-6 3/4 2-7a 3/4 2-7b 3/4 2-7c 3/4 2-7d 3/4 10-2 B 3/4 2-1 B 3/4 2-2 B 3/4 2-4 6-24 6-24a 6-24b INSERTED PAGE 3/4 2-1 3/4 2-2 3/4 2-4 3/4 2-6 3/4 2-7a 3/4 2-7b DELETED DELETED 3/4 10-2 B 3/4 2-1 B 3/4 2-2 B 3/4 2-4 6-24 6-24a 6-24b 6-24c

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