HNP-93-826, Application for Amend to License NPF-63,revising TS 3/4.2.1, 3/4.2.2,6.9.1.6 & Associated Bases Re Transition from Nuclear Fuel Supplied by Westinghouse to Nuclear Fuel Supplied by Siemens Power Corp Beginning W/Cycle 6
| ML18010B140 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/16/1993 |
| From: | Robinson W CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18010B141 | List: |
| References | |
| HNP-93-826, NUDOCS 9307270189 | |
| Download: ML18010B140 (16) | |
Text
.ACCEI.ERA <9 DOCUMXNTDIST UTION SYSTEM
,L REGULA Y INFORMATION DISTRIBUTI.
SYSTEM (RIDS)
ACCESSION NBR:9307270189 DOC.DATE: 93/07/16 NOTARIZED: YES DOCKET N
FACIL:50-400 Shearon Harris Nuclear Power Plant, Unit 1, Carolina 05000400 AUTH.NAME AUTHOR AFFILIATION ROBINSON,W.R.
Carolina Power a Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amend to License NPF-63,revising 3/4.2.2,6.9.1.6 a associated bases re transition nuclear fuel supplied by Westinghouse to nuclear supplied by Siemens Power Corp beginning w/Cycle DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL TITLE: OR Submittal: General Distribution NOTES:Application for permit renewal filed.
TS 3/4.2.1, from fuel 6.
SIZE:
05000400 RECIPIENT ID CODE/NAME
'PD2-1 LA LE,N INTERNAL: ACRS NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS1 EXTERNAL: NRC PDR COPIES LTTR ENCL 1
1 2
2 6
6 1
1 1
1 1
1 1
0 1
1 RECIPIENT ID CODE/NAME PD2-1 PD NRR/DE/EELB NRR/DRPW/OTSB NRR/DSSA/SRXB O~CZDZB REG Il~E 01 NSIC COPIES LTTR ENCL 1
1' 1
1 1
1 1
1 0
1 1
1 1
NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE %ASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DONT NEEDI TOTAL NUMBER OF COPIES REQUIRED:
LTTR 21 ENCL 19
@ME Carolina Power 8 LightCompany JUL 16 1S93 SERIAL:
HNP-93-826 10 CFR 50.90 Letter Number:
HO-930124 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 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TRANSITION Gentlemen:
In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, Carolina Power
& Light Company (CP&L) hereby requests a revision to the Technical Specifications (TS) for the Shearon Harris Nuclear Power Plant (SHNPP).
The proposed amendment revises Technical Specifications 3/4.2.1, 3/4.2.2, 6.9.1.6 and associated Bases related to the transition from nuclear fuel suppliedby Westinghouse to nuclear fuel supplied by Siemens Power Corporation (SPC) beginning with Cycle No.
6.
Specifically, the proposed changes will incorporate references to the SPC methodologies that will support the transition.
Enclosure 1 provides a detailed description of the proposed changes and the basis for the changes.
Enclosure 2 details, in accordance with 10 CFR 50.91(a),
the basis for the Company's determination that the proposed changes do not involve a significant hazards consideration.
Enclosure 3 provides an environmental evaluation which demonstrates that the proposed amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b),
no environmental assessment needs to be prepared in connection with the issuance of the amendment.
Enclosure 4 provides page change instructions for incorporating the proposed revisions.
Enclosure 5 provides the proposed Technical Specification pages.
In accordance with 10 CFR 50.91(b),
CP&L is providing the State of North Carolina with a copy of the proposed license amendment.
-" ~oo.o'-'O 9307~7 pgpppppp Sq 930716 pDR ADOCK
@DR P
oo/
(2020HHP) l
t Y
A "a
I I
'u V
8 1
'1
'>'> u', <<r,
>'ocument Control Des~
HN(43-826 / Page 2
CP&L requests approval of the proposed amendment by March 1, 1994 in order to support the next SHNPP refueling outage, currently scheduled to begin in March 1994.
In order to allow time for procedure revision and orderly incorporation into copies of the Technical Specifications, CP&L requests that the proposed amendment, once approved by the NRC, be issued such that implementation will occur within 60 days of issuance of the amendment.
Please refer any questions regarding this submittal to Mr. D.
C. McCarthy at (919) 362-2100.
Yours very truly,
'I W. R. Robinson General Manager
- Harris Plant LSR/smh
Enclosures:
1.
Basis for Change Request 2.
10 CFR 50,92 Evaluation 3.
Environmental Considerations 4.
Page Change Instructions 5.
Technical Specification Pages cc:
Mr. Dayne H. Brown Mr. S.
D. Ebneter Mr. N.
B.
Le Mr. J.
E. Tedrow W. R. Robinson, 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
& Light Company.
My commission expires: g -K-9E Notary eal)
@': "@>o 4
+o NOTARY PUOLfC (2020HNP)
ENCLOSURE TO SERIAL:
HNP-93-826 Page 1 of 2 SHEARON. HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TRANSITION.
BASIS FOR CHANGE RE UEST
~Back round Beginning with Cycle No.6, the Shearon Harris Nuclear Power Plant (SHNPP) will begin transitioning from nuclear fuel supplied by Westinghouse Electric Corporation to nuclear fuel designed and fabricated by Siemens Power Corporation (SPC).
The SPC-designed fuel will be supported by SPC design methodology, while the Westinghouse fuel (allowed peaking and burnup limits) will continue to be supported by the original Westinghouse calculations.
Plant response will be supported by SPC methodology.
The transition to SPC fuel will require Technical Specification changes in the following areas:
reactor core safety limits, reactor trip system instrumentation setpoints, power distribution limits, and Core Operating Limits Report (COLR) reEerences.
Since some of these changes are dependent upon plant-specific analyses that are currently underway, but not complete, CP6L will submit the Cycle No.
6 Technical Specification changes in two parts.
As discussed at a meeting between CP&L and the NRC in White Flint, Maryland on April 22, 1993 and at SHNPP on June 28,
- 1993, the changes submitted herein are proposed references to NRC-approved methodologies or methodologies which are currently under review by the NRC for approval.
Any necessary plant-specific changes will be submitted separately by September 1993.
Pro osed Chan e
The proposed amendment revises Technical Specifications 3/4.2.1, 3/4.2.2, 6.9.1.6, and associated Bases to incorporate references to the Siemens Power Corporation (SPC) methodologies that will support the transition from Westinghouse-supplied fuel to SPC-supplied fuel.
Specifically:
Changes are proposed to Technical Specification 3/4.2.1, Axial Flux Difference, Technical Specification 3/4.2.2, Heat Flux Hot Channel Factor (F<), and associated Bases to incorporate the use of the Siemens PDC-3 methodology for power distribution control.
The speciEic Technical Specification changes reElect the manner in which Target Axial Flux Difference (AFD) will be controlled and how the associated penalties to the measured F< are applied.
Technical Specification 6.9.1.6 will be revised to update the Core Operating Limits Report (COLR) reference section to incorporate the appropriate SPC generic methodology used to establish the limits provided in the COLR.
This revision incorporates references to three SPC methodologies that are currently under review by the NRC staff (EMF-92-081, EMF-92-153, and XN-NF-,82-49).
(2020HNP)
C f
C L
ENCLOSURE TO SERIAL:
HNP-93-826 Page 2 of 2 Basis 1.
The accidents previously evaluated in the Final Safety Analysis Report (FSAR) are unchanged by the proposed revisions to Technical Specifications 3/4.2.1 and 3/4.2.2.
The plant'ystems, including excore and incore hardware and general methods of operation (i.e., axial power distribution control) are not affected by the proposed changes; plant procedures (except that Base Load is no longer an option) and allowed action times for limiting conditions for operation are also unchanged.
Therefore, there is no increase in the probability or consequences of any accident previously evaluated in the FSAR.
The proposed amendment does not involve any modifications or additions to.plant equipment;- therefore, there is no increase 'in the probability or consequences of a malfunction of equipment important to safety as evaluated previously in the FSAR.
The proposed amendment replaces one approved methodology with another (PDC-3).
These methodologies are designed to provide the same function, control of axial flux difference, so that existing analyses remain valid.
Therefore, this change does not create the possibility of a new or different kind of accident.
Additionally, the proposed amendment does not change those parameters which relate to the margin of safety as determined by safety evaluation.
Therefore, there is no reduction in the margin of safety as defined in the Technical Specifications.
2.
The proposed incorporation of reference changes in the Core Operating Limits Report (COLR) does not involve changes or additions to plant equipment.
The referenced.methodologies are used to evaluate the consequences of the changes in fuel design according to NRC-approved requirements.
These consequences must satisfy the specified acceptable fuel design limits, the radiological limits, and the loss of coolant limits as defined by the NRC.
These limits continue to be met.
Therefore, there is no increase in the probability or consequences of an accident previously evaluated in the FSAR.
Since there is no change to any postulated causes for equipment malfunction and since all applicable design limits continue to be.met, there is no increase in the probability or consequences of a malfunction of equipment important to safety as previously evaluated in the FSAR.
The'ncorporation of references in the COLR does not create precursors to a new kind of accident.
Therefore, the proposed change does not create the possibility of a new or different type of accident than any previously evaluated in the FSAR. Additionally, the proposed amendment does not change those parameters which relate to the margin of safety as determined by safety evaluation.
Therefore, there is no reduction in the margin of safety as defined in the Technical Specifications.
(2020HNP)
0' I
ENCLOSURE TO SERIAL:
HNP-93-826 Page 1 of 2 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TRANSITION 10 CFR 50.92 EVALUATION The Commission has provided standards in 10 CFR 50.92(c) for determining whether a significant hazards consideration exists.
A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
(1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
Carolina Power 6 Light Company has reviewed this proposed license amendment request and determined that its adoption would not involve a significant hazards determination.
The bases for this determination are as follows:
Pro osed Chan e
The proposed amendment revises Technical Specifications 3/4.2.1, 3/4.2.2, 6.9.1.6, an'd associated Bases to incorporate references to the Siemens Power Corporation (SPC) methodologies that will support the transition from Westinghouse-supplied fuel to SPC-supplied fuel.
Specifically:
Changes'are pr'oposed to Technical Specification 3/4.2.1, Axial Flux Difference, and Technical Specification 3/4.2.2, Heat Flux Hot Channel Factor (F<),
and associated.
Bases to incorporate the use of the Siemens PDC-3 methodology for power distribution control.
~ The specific Technical Specification changes reflect the manner in which Target Axial Flux Difference (AFD) will be controlled and how the associated penalties to the measured F< are applied.
Technical Specification 6.9.1.6 will be revised to update the Core Operating Limits Report (COLR) reference section to incorporate the appropriate SPC generic methodology used to establish the limits provided in the COLR. This revision incorporates references to three SPC methodologies that are currently under review by the NRC staff (EMF-92-081,.
EMF-92-153, and XN-NF-82-49).
~
Basis This change does not involve a significant hazards consideration for the following reasons:
1.
The proposed amendment does not involve a significant increase in the probability or consequences of. an accident previously evaluated.
(a)
The accidents previously evaluated in the Final Safety Analysis Report (FSAR) are unchanged by the proposed revisions to Technical Specifications 3/4.2.1 and 3/4.2.2.
The plant systems, including excore and incore hardware and general methods of operation (i.e.,
axial power distribution control) are not affected by the proposed (2020HNP)
A
)
ENCLOSURE TO SERIAL:
HNP-93-826 Page 2 of 2 changes; plant procedures (except that Base Load is no longer an option) and allowed action times for limiting conditions'for operation are unchanged.
(b)
The proposed incorporation of reference changes in the Core Operating Limits Report (COLR) does not involve changes or additions to plant equipment.
The referenced methodologies are used to evaluate the consequences of the changes in fuel design according to NRC approved requirements.
These consequences must satisfy the specified acceptable fuel design limits, the radiological limits, and the loss of coolant limits as defined by the NRC.
These limits continue to be met.
2.
The proposed amendment does not create the possibility of a new or different kind of accident from any accident'reviously evaluated.
(a)
The proposed amendment replaces one approved methodology with another (PDC-3).
These methodologies are designed to provide the same function, control of axial flux difference, so that existing analyses remain valid.
(b)
The incorporation of references in the COLR does not create precursors to a new kind of accident.
3.
The proposed amendment does not involve a significant reduction in the margin of safety.
(a)
The proposed changes to Technical Specifications 3/4.2.1, 3/4.2.2, and associated Bases do not affect, parameters that relate to the margin of safety as defined in the Technical Specifications.
(b)
The incorporation of references in the Core Operating Limits Report (COLR) does not impact the parameters that relate to the margin of safety as defined in the Technical Specifications.
(2020HNP)
l r
I C
I C
ENCLOSURE TO SERIAL:
HNP-93-826 Page 1 of 2 SHEARON HARRIS-NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TRANSITION ENVIRONMENTAL CONSIDERATIONS 10 GFR 51.22(c)(9) provides criterion for and identification of licens'ing and regulatory actions eligible for categorical exclusion from performing an environmental assessment.
A proposed amendment to an operating license for a facility requires no environmental assessment if operation of the facility in accordance with the proposed amendment would. not:
(1) involve a significant hazards consideration; (2) result in a significant change in the types or significant increase in the amounts of any effluents that may be released off-site; (3) result in an increase in. individual or cumulative'ccupational radiation exposure.
Carolina Power
& Light Company has reviewed this request and determined that the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of the amendment.
The basis for this determination'follows:
Pro osed Chan e
The proposed amendment revises Technical Specifications 3/4.2.1, 3/4.2.2, 6.9.1.6, and associated Bases to incorporate references to the Siemens Power
'Corporation (SPC) methodologies that will support the transition from Westinghouse-supplied fuel to SPC-supplied fuel.
Specifically:
Changes are proposed to Technical Specification 3/4.2.1, Axial Flux Difference, and Technical Specification 3/4.2.2, Heat Flux Hot Channel Factor (F<),
and associated Bases to incorporate the use of the Siemens PDC-3 methodology for power distribution contiol.
The specific Technical Specification changes reflect the manner in which Target Axial Flux Difference (AFD) will be controlled and how the associated penalties to the measured F< are applied.
Technical Specification 6.9.1.6 will be revised to update the Core Operating Limits Report (COLR) reference section to, incorporate the appropriate SPC generic methodology used to establish the limits provided in the COLR. This revision incorporates references to three SPC methodologies that are currently under review by the NRC staff (EMF-92-081, EMF-92-153, and XN-NF-82-49).
Basis The change meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) for the following reasons:
1.
As demonstrated in Enclosure 2, the proposed amendment does not involve a significant hazards consideration.
(2020HHP)
4
'I g
r.
I
ENCLOSURE TO SERIAL:
HNP-93-826 Page 2 of 2 2.
The proposed amendment does not result in a significant change in the types or significant increase in the amounts of any. effluents that may be released off-site.
The proposed amendment
'does not introduce any new equipment, nor does it require existing systems to perform a different type of function than they are currently designed to perform.
As such, the change can not affect the types or amounts of any effluents that may be released off-site.
3.
The propo'sed amendment does not result in an increase in individual or cumulative occupational radiation exposure.
"The proposed revisions do not result in changes to Technical Specification surveillance requirements and does not affect personnel radiation exposure.
Therefore, the amendment has no affect on either individual or cumulative occupational radiation exposure.
(2020HNP)
ENCLOSURE TO SERIAL:
HNP-93-826 Page 1 of 1 SHEARON HARRIS NUCLEAR POWER PLANT NRC DOCKET NO. 50-400/LICENSE NO. NPF-63 REQUEST FOR LICENSE AMENDMENT CYCLE 6 FUEL TRANSITION PAGE CHANGE INSTRUCTIONS Removed Pa e
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 Inserted Pa e
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 (2020HNP)
I C