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{{#Wiki_filter:'ACCELERATED L4TRIBUTION DEMONSalhTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8904210035 DOC.DATE: 88/04/13 NOTARIZED:
{{#Wiki_filter:'                                           DEMONSalhTION            SYSTEM ACCELERATED           L4TRIBUTION REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
YES FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina AUTH.NAME AUTHOR AFFILIATION EURY,L.W.Carolina Power 6 Light Co.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)SUMECT: Supplemental application for amend to License NPF-63 re Cycle 2 operation.
ACCESSION NBR:8904210035       DOC.DATE: 88/04/13   NOTARIZED: YES       DOCKET FACIL:50-400 Shearon Harris Nuclear Power     Plant, Unit 1, Carolina   05000400 AUTH. NAME           AUTHOR AFFILIATION EURY,L.W.           Carolina Power 6 Light Co.
DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR J ENCL$SIZE: TITLE: OR Submittal:
RECIP.NAME           RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
General Distribution DOCKET 05000400 R I NOTES:Application for permit renewal filed.05000400 8 RECIPIENT ID CODE/NAME PD2-1 LA BUCKLEY,B INTERNAL: ACRS NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E S/ILRB12 I BEG FI 01 EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 0 1 1 6 6 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD2-1 PD ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DOEA/TSB 11 OGC 15-B-18 RES/DE/EIB NRC PDR COPIES LTTR ENCL 5 5 1 0 1 1 1 1 1 1 1 0 1 1 1 1 j D D 8'A TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 24 RL Carolina Power 8 Ught Company P.O.Box 1551~Ratelgh.N.C.27602 LYNN W.EURY Senior Vice President Operations Support APR 13~B SERIAL: NLS-88-089 10CFR50.90 United States Nuclear Regulatory Commission ATTENTION:
SUMECT: Supplemental application for amend to License NPF-63 re Cycle 2 operation.                                                       R DISTRIBUTION CODE: AOOID TITLE:  OR COPIES RECEIVED:LTR Submittal: General Distribution J   ENCL
Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO.50-400/LICENSE NO.NPF-63 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT CYCLE 2 OPERATION Gentlemen:
                                                              $   SIZE:               I NOTES:Application for permit renewal filed.                               05000400 8
ID RECIPIENT CODE/NAME PD2-1 LA BUCKLEY,B COPIES LTTR ENCL 1
1 0
1 ID RECIPIENT CODE/NAME PD2-1 PD COPIES LTTR ENCL 5    5 j
INTERNAL: ACRS                    6    6    ARM/DAF/LFMB         1    0            D NRR/DEST/ADS 7E      1    1    NRR/DEST/CEB 8H       1    1 NRR/DEST/ESB 8D      1    1    NRR/DEST/MTB 9H       1    1 D
NRR/DEST/RSB 8E      1    1    NRR/DOEA/TSB 11       1    1 S/ILRB12      1    1    OGC 15-B-18         1    0 I BEG  FI        01    1    1    RES/DE/EIB           1   1             8 EXTERNAL: LPDR                    1     1   NRC PDR              1     1 NSIC                  1     1
                                                                                    'A TOTAL NUMBER OF COPIES REQUIRED: LTTR       27   ENCL   24
 
RL Carolina Power 8 Ught Company P. O. Box 1551 ~ Ratelgh. N. C. 27602 APR     13   ~B SERIAL: NLS-88-089 10CFR50.90 LYNN W. EURY Senior Vice President Operations Support United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington,       DC   20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT CYCLE 2 OPERATION Gentlemen:


==SUMMARY==
==SUMMARY==
On February 1, 1988, Carolina Power&Light Company (CP&L)requested a revision to the Technical Specifications for the Shearon Harris Nuclear Power Plant (SHNPP).The proposed amendment contained four groups of Technical Specification changes which are required to support Harris Cycle 2 operation.
 
This supplement revises the proposed wording for Technical Specification 5.3.1, Fuel Assemblies, included in Enclosure 4 of the February 1, 1988 submittal.
On   February 1, 1988, Carolina Power & Light Company (CP&L) requested a revision to the Technical Specifications for the Shearon Harris Nuclear Power Plant (SHNPP).           The proposed amendment contained four groups of Technical Specification changes which are required to support Harris Cycle 2 operation. This supplement revises the proposed wording for Technical Specification 5.3.1, Fuel Assemblies, included in Enclosure 4 of the February 1, 1988 submittal. In addition, revised 10 CFR 50.92 evaluations for each of the four groups and for the Company's February 8, 1988 submittal regarding Boron Dilution/Sliding Shutdown Margin are included. The attached significant hazards evaluations supplement those submitted by our February 1 and 8, 1988 submittals and have been formatted such that they incorporate both previous information and supplemental information; Enclosures 2 through 6 of this letter are intended as stand alone documents which replace the significant hazards evaluations of the earlier submittals.
In addition, revised 10 CFR 50.92 evaluations for each of the four groups and for the Company's February 8, 1988 submittal regarding Boron Dilution/Sliding Shutdown Margin are included.The attached significant hazards evaluations supplement those submitted by our February 1 and 8, 1988 submittals and have been formatted such that they incorporate both previous information and supplemental information; Enclosures 2 through 6 of this letter are intended as stand alone documents which replace the significant hazards evaluations of the earlier submittals.
DISCUSSION The change       to the fuel assembly description in Technical Specification 5.3.1 proposed in Enclosure 4 of CP&L's February 1, 1988 submittal would allow for replacement of damaged fuel rods with filler rods or vacancies in a fuel assembly provided the replacement is justified by a cycle specific evaluation. Based on recent conversations with the Staff, the Company is revising the proposed change to include a provision to notify the Commission       if more than 30 fuel rods total or more than 10 fuel rods in any one assembly are replaced during a refueling outage. This notification will be accomplished via a Special Report, submitted in accordance with Technical Specification 6.9.2 within 30 days after cycle startup. The Company understands that submittal of a Special Report 8804210035 880413 PDR ADOCK 05000400                   i~
DISCUSSION The change to the fuel assembly description in Technical Specification 5.3.1 proposed in Enclosure 4 of CP&L's February 1, 1988 submittal would allow for replacement of damaged fuel rods with filler rods or vacancies in a fuel assembly provided the replacement is justified by a cycle specific evaluation.
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Based on recent conversations with the Staff, the Company is revising the proposed change to include a provision to notify the Commission if more than 30 fuel rods total or more than 10 fuel rods in any one assembly are replaced during a refueling outage.This notification will be accomplished via a Special Report, submitted in accordance with Technical Specification 6.9.2 within 30 days after cycle startup.The Company understands that submittal of a Special Report 8804210035 880413 PDR ADOCK 05000400 P DCD i~
 
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/Page 2 based on the number of rods replaced during a refueling outage is an administrative requirement intended to alert the NRC of above normal failed fuel conditions.
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The number of replaced rods required to initiate the report is an administrative limit established for convenience and does not represent a restriction on the total number of rods which may be replaced during a refueling outage.Enclosure 1 contains the revised Technical Specification page.This page supersedes the page included in the February 1, 1988 submittal.
 
Note that Enclosure 4 of the February 1, 1988 submittal also proposed changes to Technical Specification Table 4.3-1 which are still applicable and are not affected by the enclosed change to Technical Specification 5.3.1.Carolina Power 6 Light Company has reviewed and revised the 10 CFR 50.92 Evaluations provided in the February 1 and 8, 1988 submittals.
Document Control Desk NLS-88-089   / Page 2 based on the number   of rods replaced during a refueling outage is an administrative requirement intended to alert the NRC of above normal failed fuel conditions. The number of replaced rods required to initiate the report is an administrative limit established for convenience and does not represent a restriction on the total number of rods which may be replaced during a refueling outage. Enclosure 1 contains the revised Technical Specification page. This page supersedes the page included in the February 1, 1988 submittal. Note that of the February 1, 1988 submittal also proposed changes to Technical Specification Table 4.3-1 which are still applicable and are not affected by the enclosed change to Technical Specification 5.3.1.
These revised evaluations are included in Enclosures 2 through 6~The February 1 and 8, 1988 submittals also included a"Basis for Change Request" section for each proposed change.These sections as well as the marked up Technical Specification pages remain applicable and are not affected by this letter with the only exception being the revision to Technical Specification 5.3.1 discussed above.The required license amendment application fee has been submitted by our previous correspondence.
Carolina Power 6 Light Company has reviewed and revised the 10 CFR 50.92 Evaluations provided in the February 1 and 8, 1988 submittals. These revised evaluations are included in Enclosures 2 through 6 The~
Please refer any questions regarding this submittal to Mr.Leonard I.Loflin at (919)836-6242.Yours very truly, L.W.E LWE/MAT L.W.Eury, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief;and the sources of his information are officers, employees, contractors, and agents of Carolina Power 6 Light Company.My commission expires://4 P J tary (Seal)~%l~gyltttltg~
February 1 and 8, 1988 submittals also included a "Basis for Change Request" section for each proposed change. These sections as well as the marked up Technical Specification pages remain applicable and are not affected by this letter with the only exception being the revision to Technical Specification 5.3.1 discussed above.
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The required license amendment application fee has been submitted by our previous correspondence. Please refer any questions regarding this submittal to Mr. Leonard I. Loflin at (919) 836-6242.
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Yours very truly, L. W. E LWE/MAT L. W. Eury, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power 6 Light Company.
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Document Control Desk NLS-88-089   / Page 3


==Enclosures:==
==Enclosures:==
: 1. Proposed Revision to Technical Specification 5.3.1
: 2. 10 CFR 50.92 Evaluation, D-Bank Reconfiguration - Control Rod Insertion Limits
: 3. 10 CFR 50.92 Evaluation, F~  Increase From 2.28 To 2.32, RAOC/
Base Load Operation and  FQ Surveillance
: 4. 10 CFR 50.92 Evaluation, Increased F-Delta-H Multiplier
: 5. 10 CFR 50 '2 Evaluation, Miscellaneous Technical Specification Changes
: 6. 10 CFR 50.92 Evaluation, Boron  Dilution/Sliding Shutdown Margin CC:  Mr. Dayne H. Brown w/a Mr. B. C. Buckley w/a Dr. J. Nelson Grace w/a Mr. G. F. Maxwell w/a


1.Proposed Revision to Technical Specification 5.3.1 2.10 CFR 50.92 Evaluation, D-Bank Reconfiguration
ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400 OPERATING LICENSE NPF-63 REVISION TO REQUEST FOR LICENSE AMENDMENT MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES PROPOSED REVISION TO TECHNICAL SPECIFICATION 5 3 1}}
-Control Rod Insertion Limits 3.10 CFR 50.92 Evaluation, F~Increase From 2.28 To 2.32, RAOC/Base Load Operation and FQ Surveillance 4.10 CFR 50.92 Evaluation, Increased F-Delta-H Multiplier 5.10 CFR 50'2 Evaluation, Miscellaneous Technical Specification Changes 6.10 CFR 50.92 Evaluation, Boron Dilution/Sliding Shutdown Margin CC: Mr.Dayne H.Brown w/a Mr.B.C.Buckley w/a Dr.J.Nelson Grace w/a Mr.G.F.Maxwell w/a ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO.50-400 OPERATING LICENSE NPF-63 REVISION TO REQUEST FOR LICENSE AMENDMENT MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES PROPOSED REVISION TO TECHNICAL SPECIFICATION 5 3 1}}

Revision as of 05:56, 22 October 2019

Supplemental Application for Amend to License NPF-63, Revising Proposed Wording for Tech Spec 5.3.1, Fuel Assemblies & 10CFR50.92 Evaluations of Tech Specs Re Boron Dilution/Sliding Shutdown Margin in 880201 Application
ML18005A392
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 04/13/1988
From: Eury L
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18005A393 List:
References
NLS-88-089, NLS-88-89, NUDOCS 8804210035
Download: ML18005A392 (7)
v • d • e


Text

' DEMONSalhTION SYSTEM ACCELERATED L4TRIBUTION REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8904210035 DOC.DATE: 88/04/13 NOTARIZED: YES DOCKET FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH. NAME AUTHOR AFFILIATION EURY,L.W. Carolina Power 6 Light Co.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUMECT: Supplemental application for amend to License NPF-63 re Cycle 2 operation. R DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution J ENCL

$ SIZE: I NOTES:Application for permit renewal filed. 05000400 8

ID RECIPIENT CODE/NAME PD2-1 LA BUCKLEY,B COPIES LTTR ENCL 1

1 0

1 ID RECIPIENT CODE/NAME PD2-1 PD COPIES LTTR ENCL 5 5 j

INTERNAL: ACRS 6 6 ARM/DAF/LFMB 1 0 D NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 D

NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB 11 1 1 S/ILRB12 1 1 OGC 15-B-18 1 0 I BEG FI 01 1 1 RES/DE/EIB 1 1 8 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1

'A TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 24

RL Carolina Power 8 Ught Company P. O. Box 1551 ~ Ratelgh. N. C. 27602 APR 13 ~B SERIAL: NLS-88-089 10CFR50.90 LYNN W. EURY Senior Vice President Operations Support United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT DOCKET NO. 50-400/LICENSE NO. NPF-63 SUPPLEMENT TO REQUEST FOR LICENSE AMENDMENT CYCLE 2 OPERATION Gentlemen:

SUMMARY

On February 1, 1988, Carolina Power & Light Company (CP&L) requested a revision to the Technical Specifications for the Shearon Harris Nuclear Power Plant (SHNPP). The proposed amendment contained four groups of Technical Specification changes which are required to support Harris Cycle 2 operation. This supplement revises the proposed wording for Technical Specification 5.3.1, Fuel Assemblies, included in Enclosure 4 of the February 1, 1988 submittal. In addition, revised 10 CFR 50.92 evaluations for each of the four groups and for the Company's February 8, 1988 submittal regarding Boron Dilution/Sliding Shutdown Margin are included. The attached significant hazards evaluations supplement those submitted by our February 1 and 8, 1988 submittals and have been formatted such that they incorporate both previous information and supplemental information; Enclosures 2 through 6 of this letter are intended as stand alone documents which replace the significant hazards evaluations of the earlier submittals.

DISCUSSION The change to the fuel assembly description in Technical Specification 5.3.1 proposed in Enclosure 4 of CP&L's February 1, 1988 submittal would allow for replacement of damaged fuel rods with filler rods or vacancies in a fuel assembly provided the replacement is justified by a cycle specific evaluation. Based on recent conversations with the Staff, the Company is revising the proposed change to include a provision to notify the Commission if more than 30 fuel rods total or more than 10 fuel rods in any one assembly are replaced during a refueling outage. This notification will be accomplished via a Special Report, submitted in accordance with Technical Specification 6.9.2 within 30 days after cycle startup. The Company understands that submittal of a Special Report 8804210035 880413 PDR ADOCK 05000400 i~

P DCD

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Document Control Desk NLS-88-089 / Page 2 based on the number of rods replaced during a refueling outage is an administrative requirement intended to alert the NRC of above normal failed fuel conditions. The number of replaced rods required to initiate the report is an administrative limit established for convenience and does not represent a restriction on the total number of rods which may be replaced during a refueling outage. Enclosure 1 contains the revised Technical Specification page. This page supersedes the page included in the February 1, 1988 submittal. Note that of the February 1, 1988 submittal also proposed changes to Technical Specification Table 4.3-1 which are still applicable and are not affected by the enclosed change to Technical Specification 5.3.1.

Carolina Power 6 Light Company has reviewed and revised the 10 CFR 50.92 Evaluations provided in the February 1 and 8, 1988 submittals. These revised evaluations are included in Enclosures 2 through 6 The~

February 1 and 8, 1988 submittals also included a "Basis for Change Request" section for each proposed change. These sections as well as the marked up Technical Specification pages remain applicable and are not affected by this letter with the only exception being the revision to Technical Specification 5.3.1 discussed above.

The required license amendment application fee has been submitted by our previous correspondence. Please refer any questions regarding this submittal to Mr. Leonard I. Loflin at (919) 836-6242.

Yours very truly, L. W. E LWE/MAT L. W. Eury, having been first duly sworn, did depose and say that the information contained herein is true and correct to the best of his information, knowledge and belief; and the sources of his information are officers, employees, contractors, and agents of Carolina Power 6 Light Company.

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Document Control Desk NLS-88-089 / Page 3

Enclosures:

1. Proposed Revision to Technical Specification 5.3.1
2. 10 CFR 50.92 Evaluation, D-Bank Reconfiguration - Control Rod Insertion Limits
3. 10 CFR 50.92 Evaluation, F~ Increase From 2.28 To 2.32, RAOC/

Base Load Operation and FQ Surveillance

4. 10 CFR 50.92 Evaluation, Increased F-Delta-H Multiplier
5. 10 CFR 50 '2 Evaluation, Miscellaneous Technical Specification Changes
6. 10 CFR 50.92 Evaluation, Boron Dilution/Sliding Shutdown Margin CC: Mr. Dayne H. Brown w/a Mr. B. C. Buckley w/a Dr. J. Nelson Grace w/a Mr. G. F. Maxwell w/a

ENCLOSURE 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400 OPERATING LICENSE NPF-63 REVISION TO REQUEST FOR LICENSE AMENDMENT MISCELLANEOUS TECHNICAL SPECIFICATION CHANGES PROPOSED REVISION TO TECHNICAL SPECIFICATION 5 3 1

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