ML18011A349

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Re Cycle 6 Fuel Transition
ML18011A349
Person / Time
Site: Harris Duke Energy icon.png
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)
v • d • e


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 TECHNICAL SPECIFICATION PAGES q0050400 Bg qp0217 05000000 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 D

for Specification 3/4.2.1, V

e. Heat Flux Hot Channel Factor, F<" , K(Z), and Pf(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.

'.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 and one approve rats(on pucnbcr Sha(l bc identified s

(~S<~STATEMC~ 2 HERE)

I g WCAP-9272-P-A, "WESTINGHOUSE RELO July 1985 (W Proprietary) ~

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 ~

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 AXIAL OFFSE 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' Statement g

-2V~

~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 Thermal Performance Fuel," Siemens Nuclear Power Corporation, Richland MA 99352.

(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~

Small Break Model," Exxon "Exxon Nuclear Company Evaluation Model EXEM PMR Nuclear Company, Richland MA 99352.

- 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).

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 CORE OPERATING LIMITS REPORT (Continued)

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.

(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

k. 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).

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.

(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

Retrieved from "https://kanterella.com/w/index.php?title=ML18011A349&oldid=2421473"