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Malling Addrsss Alabama Power Company 600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291                                                             A Telephone 205 783-6081 F. L Clayton, Jr.
Malling Addrsss Alabama Power Company 600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291 A
Rn"$3%",*"'                                                       AlabamaPower the Southern electrC SyStern November 24, 1982 i
Telephone 205 783-6081 F. L Clayton, Jr.
Docket No. 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention:           Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Unit 2 Technical Specification Amendment to Incorporate License Condition Requirements Gentlemen:
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On October 22, 1982, Joseph M. Farley Nuclear Plant - Unit 2 shut down for the first refueling outage. In accordance with the operating license, NPF-8, some design changes and submittal of additional information prior to startup following the first refueling outage are required.         Specifically, the requirements that affect the technical specifications are:           the addition of containment penetration overcurrent protection devices, license condition 2.C.(19)(b); replacement of tne containment vent valves, license condition 2.C.(17); and tabulation of a list of safety-related mechanical snubbers, Technical Specification Table 3.7-4b. Therefore, proposed technical specification changes, as contained herein, are respectfully requested to provide conformance with the aforementioned license conditions.
AlabamaPower the Southern electrC SyStern November 24, 1982 i
Docket No. 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Unit 2 Technical Specification Amendment to Incorporate License Condition Requirements Gentlemen:
On October 22, 1982, Joseph M. Farley Nuclear Plant - Unit 2 shut down for the first refueling outage.
In accordance with the operating license, NPF-8, some design changes and submittal of additional information prior to startup following the first refueling outage are required.
Specifically, the requirements that affect the technical specifications are:
the addition of containment penetration overcurrent protection devices, license condition 2.C.(19)(b); replacement of tne containment vent valves, license condition 2.C.(17); and tabulation of a list of safety-related mechanical snubbers, Technical Specification Table 3.7-4b.
Therefore, proposed technical specification changes, as contained herein, are respectfully requested to provide conformance with the aforementioned license conditions.
l License Condition 2.C.(19)(b)
l License Condition 2.C.(19)(b)
License condition 2.C.(19)(b), as amended, requires the modifica-tion of circuit protection devices in the containment penetration circuits.         The modifications are described in the Alabama Power Company letter of November 17, 1980, and were approved in the NRC Safety Evalua-tion Report, Supplement No. 5, dated March 1981.
License condition 2.C.(19)(b), as amended, requires the modifica-tion of circuit protection devices in the containment penetration circuits.
l Many of the required circuit modifications will be completed during the first refueling outage while the remainder of the modifications will be completed no later than the second refueling outage. Since it will not be known exactly how many of the modifications will be completed until just prior to startup from the first refueling outage, all of the 4d
The modifications are described in the Alabama Power Company letter of November 17, 1980, and were approved in the NRC Safety Evalua-tion Report, Supplement No. 5, dated March 1981.
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l Many of the required circuit modifications will be completed during the first refueling outage while the remainder of the modifications will be completed no later than the second refueling outage.
                                                              \ %g\T
Since it will not be known exactly how many of the modifications will be completed until just prior to startup from the first refueling outage, all of the 4d 8211290658 821124
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Mr. S. A. Varga                                         November 24, 1982 Director Nuclear Reactor Regulation                     Page 2 U.S. Nuclear Regulatory Commission circuit modifications are included in the proposed technical specifica-tion table change (Table 3.8-1) with a footnote stating that only the installed protection devices will be covered by the requirements of section 3/4.8.3.1 until the second refueling, at which time all protec-tion devices listed will be covered. This approach allows early submit-tal of the proposed technical specification table change and eliminates the need for a subsequent technical specification change during the second refueling outage.
Mr. S. A. Varga November 24, 1982 Director Nuclear Reactor Regulation Page 2 U.S. Nuclear Regulatory Commission circuit modifications are included in the proposed technical specifica-tion table change (Table 3.8-1) with a footnote stating that only the installed protection devices will be covered by the requirements of section 3/4.8.3.1 until the second refueling, at which time all protec-tion devices listed will be covered.
This approach allows early submit-tal of the proposed technical specification table change and eliminates the need for a subsequent technical specification change during the second refueling outage.
Some changes to the November 17, 1980 proposed design have been made and are reflected in the proposed technical specification change.
Some changes to the November 17, 1980 proposed design have been made and are reflected in the proposed technical specification change.
All of the changes are in accordance with licensing requirements and these changes are described in detail in Attachment 1.
All of the changes are in accordance with licensing requirements and these changes are described in detail in Attachment 1.
This proposed change to Technical Specification Table 3.8-1 is in accordance with license condition 2.C.(19)(b) as described in Attachment
This proposed change to Technical Specification Table 3.8-1 is in accordance with license condition 2.C.(19)(b) as described in Attachment 1.
: 1. This change is made to bring the Unit 2 Technical Specifications into conformance with previously approved plant design changes such that no technical or safety issues are involved. Therefore, this change is administrative in nature per 10CFR170.22 and does not involve an unreviewed safety question.
This change is made to bring the Unit 2 Technical Specifications into conformance with previously approved plant design changes such that no technical or safety issues are involved.
Therefore, this change is administrative in nature per 10CFR170.22 and does not involve an unreviewed safety question.
License Condition 2.C.(17)
License Condition 2.C.(17)
License condition 2.C.(17) requires the installation of a modified vent valve system prior to startup following the first refueling.     The modified system is described in the Alt.bama Power Company letters of September 30 and October 30, 1981.
License condition 2.C.(17) requires the installation of a modified vent valve system prior to startup following the first refueling.
The modified design involves replacing the existing 18" mini-purge valve with an 8" vent valve. This change affects the description of the containment ventilation system in Technical Specification 3/4.6.1.7 but does not affect the technical requirements for the ventilation system.
The modified system is described in the Alt.bama Power Company letters of September 30 and October 30, 1981.
The modified design involves replacing the existing 18" mini-purge valve with an 8" vent valve.
This change affects the description of the containment ventilation system in Technical Specification 3/4.6.1.7 but does not affect the technical requirements for the ventilation system.
As stated in the September 30 and {{letter dated|date=October 30, 1981|text=October 30, 1981 letter}}s, the modified design complies with the requirements of Branch Technical Position CSB-6-4.
As stated in the September 30 and {{letter dated|date=October 30, 1981|text=October 30, 1981 letter}}s, the modified design complies with the requirements of Branch Technical Position CSB-6-4.
This proposed change to Technical Specification 3/4.6.1.7 is in accordance with license condition 2.C.(17) as described in Attachment
This proposed change to Technical Specification 3/4.6.1.7 is in accordance with license condition 2.C.(17) as described in Attachment 1.
: 1. This change is made to bring the Unit 2 Technical Specifications into conformance with a previously approved plant design change such that no technical or safety issue is involved. Therefore, this change is administrative in nature per 10CFR170.22 and does not involve an unreviewed safety question.
This change is made to bring the Unit 2 Technical Specifications into conformance with a previously approved plant design change such that no technical or safety issue is involved.
Therefore, this change is administrative in nature per 10CFR170.22 and does not involve an unreviewed safety question.
1
1


Mr. S. A. Varga                                             November 24, 1982 Director Nuclear Reactor Regulation                         Page 3 U.S. Nuclear Regulatory Commission Technical Specification Table 3.7-4b Unit 2 Technical Specification Table 3.7-4b contains a requirement that the list of safety-related mechanical snubbers be provided prior to startup following the first refueling outage.         The required list is contained in Attachment 2 to this letter.
Mr. S. A. Varga November 24, 1982 Director Nuclear Reactor Regulation Page 3 U.S. Nuclear Regulatory Commission Technical Specification Table 3.7-4b Unit 2 Technical Specification Table 3.7-4b contains a requirement that the list of safety-related mechanical snubbers be provided prior to startup following the first refueling outage.
This proposed change to Technical Specification Table 3.7-4b is in accordance with the technical specification requirement as described in . This change adds the list of mechanical snubbers to the technical specifications and does not involve a plant design change.
The required list is contained in Attachment 2 to this letter.
This proposed change to Technical Specification Table 3.7-4b is in accordance with the technical specification requirement as described in.
This change adds the list of mechanical snubbers to the technical specifications and does not involve a plant design change.
Therefore, this change is administrative in nature per 10CFR170.22 and does not involve an unreviewed safety question.
Therefore, this change is administrative in nature per 10CFR170.22 and does not involve an unreviewed safety question.
Conclusion The above described changes have been reviewed by Alabama Power Company's Plant Operations Review Committee and it has been concluded that the proposed changes do not involve an unreviewed safety question. A detailed safety evaluation is contained in Attachment 1 and the proposed technical specification changes are contained in Attachment
Conclusion The above described changes have been reviewed by Alabama Power Company's Plant Operations Review Committee and it has been concluded that the proposed changes do not involve an unreviewed safety question.
: 2. The Nuclear Operations Review Board will review this proposed change during its next meeting.
A detailed safety evaluation is contained in Attachment 1 and the proposed technical specification changes are contained in Attachment 2.
This amendment is designated as Class II in accordance with 10CFR170.22 requirements, since it is administrative in nature and does not involve a safety issue (i.e., all of the change are in accordance with NRC imposed license conditions). Enclosed is a check for $1,200 to cover the total amount of fees required.
The Nuclear Operations Review Board will review this proposed change during its next meeting.
This amendment is designated as Class II in accordance with 10CFR170.22 requirements, since it is administrative in nature and does not involve a safety issue (i.e., all of the change are in accordance with NRC imposed license conditions).
Enclosed is a check for $1,200 to cover the total amount of fees required.
In accordance with 10CFR50.30(c)(1)(f), three signed originals and forty (40) additional copies of the proposed changes are enclosed.
In accordance with 10CFR50.30(c)(1)(f), three signed originals and forty (40) additional copies of the proposed changes are enclosed.
Yours very truly,
Yours very truly,
                                    . L. Cl ayton , J r.
. L. Cl ayton, J r.
FLCJ r/GGY : jc-D31                 SWORN TO AND SUBSCRIBED BEFORE ME Attachments                         THIS d?dC DAY OF A/nfly[1/U ,1982.
FLCJ r/GGY : jc-D31 SWORN TO AND SUBSCRIBED BEFORE ME Attachments THIS d?dC DAY OF A/nfly[1/U,1982.
cc: Mr. R. A. Thomas Mr. G. F. Trowbridge                           OnN(t> ktux/dd Mr. J. P. O'Reilly                           Notary Public Mr. E. A. Re:ves Mr. W. H. Bradford           My Commission Expires:
cc:
Il- L9 - 8:L-
Mr. R. A. Thomas OnN(t> ktux/dd Mr. G. F. Trowbridge Mr. J. P. O'Reilly Notary Public Mr. E. A. Re:ves Mr. W. H. Bradford My Commission Expires:
Il-L9 - 8:L-


ATTACHMENT 1 Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications I. Background On October 22, 1982, Joseph M. Farley Nuclear Plant - Unit 2 shut down for the first refueling outage.     In accordance with the operating license, NPF-8, some design changes and submittal of additional information prior to startup following the first refueling outage are required. Specifically, the requirements that affect the technical specifications are:   the addition of containment penetration overcurrent protection devices, license condition 2.C.(19)(b);
ATTACHMENT 1 Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications I.
 
===Background===
On October 22, 1982, Joseph M. Farley Nuclear Plant - Unit 2 shut down for the first refueling outage.
In accordance with the operating license, NPF-8, some design changes and submittal of additional information prior to startup following the first refueling outage are required.
Specifically, the requirements that affect the technical specifications are:
the addition of containment penetration overcurrent protection devices, license condition 2.C.(19)(b);
replacement of the containment vent valves, license condition 2.C.(17);
replacement of the containment vent valves, license condition 2.C.(17);
and tabulation of a list of safety-related mechanical snubbers, Technical Specification Table 3.7-4b. Therefore, proposed technical specification changes, as contained in Attachment 2, are necessary to provide conformance with the aforementioned license conditions.
and tabulation of a list of safety-related mechanical snubbers, Technical Specification Table 3.7-4b.
II. References Operating License NPF-8 as amended FNP-2 Technical Specifiations III. Bases License Condition 2.C.(19)(b)
Therefore, proposed technical specification changes, as contained in Attachment 2, are necessary to provide conformance with the aforementioned license conditions.
II.
References Operating License NPF-8 as amended FNP-2 Technical Specifiations III.
Bases License Condition 2.C.(19)(b)
License condition 2.C.(19)(b), as amended, requires the modification of circuit protection devices in the containment penetration circuits.
License condition 2.C.(19)(b), as amended, requires the modification of circuit protection devices in the containment penetration circuits.
The modifications are described in the Alabama Power Company letter of November 17, 1980, and were approved in the NRC Safety Evaluation Report, Supplement No. 5, dated March 1981.
The modifications are described in the Alabama Power Company letter of November 17, 1980, and were approved in the NRC Safety Evaluation Report, Supplement No. 5, dated March 1981.
l     Many of the required circuit modifications will be completed during the first refueling outage while the remainder of the modifications will be completed no later than the second refueling outage.     Since it will not be known exactly how many of the modifications will be completed until just prior to startup from the first refueling outage, all of the circuit nodifications are included in the proposed technical
l Many of the required circuit modifications will be completed during the first refueling outage while the remainder of the modifications will be completed no later than the second refueling outage.
,      specification table change (Table 3.8-1) with a footnote stating that only the installed protection devices will be covered by the l
Since it will not be known exactly how many of the modifications will be completed until just prior to startup from the first refueling outage, all of the circuit nodifications are included in the proposed technical specification table change (Table 3.8-1) with a footnote stating that l
requirements of section 3/4.8.3.1 until the second refueling, at which time all protection devices listed will be covered.     This approach allows early submittal of the proposed technical specification table change and eliminates the need for a subsequent technical specification change during the second refueling outage.
only the installed protection devices will be covered by the requirements of section 3/4.8.3.1 until the second refueling, at which time all protection devices listed will be covered.
;      Some changes to the November 17, 1980 proposed design have been made l     and are reflected in the proposed technical specification change. All l     of the changes are in accordance with licensing requirements.       The specific changes to the modifications detailed in the {{letter dated|date=November 17, 1980|text=November 17, 1980 letter}} are:
This approach allows early submittal of the proposed technical specification table change and eliminates the need for a subsequent technical specification change during the second refueling outage.
 
Some changes to the November 17, 1980 proposed design have been made l
Attachment 1 Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 2
and are reflected in the proposed technical specification change.
: 1. These circuits were categorized as "maybe occasionally required for shorc periods of time" and were therefore not listed as needing backup protection. Since then, Alabama Power Company has decided to provide both primary and backup protection to this category of circuits as follows:
All l
A. Table 2 - 600V AC Load Centers Reactor Polar Crane, powered from 600V L/C Breaker EA04, has been provided with backup protection MSCP Type "X" fuse in the Penetration Protection Cabinet.
of the changes are in accordance with licensing requirements.
B. Table 3 - 600V AC Motor Control Centers These circuits have been provided with backup protection by adding MSCP fuses in the circuits.
The specific changes to the modifications detailed in the {{letter dated|date=November 17, 1980|text=November 17, 1980 letter}} are:
Service                   Feecer Compartment         Type of Fuse CTMT Gib-Crar.e                   FC-M4L                     S CTMT Gib-Crane                   FC-S3R                     S CTMT Elev. #3                     FB-A4R                     S Controller CTMT Gib-Crane                   FD-H7R                     S Reactor Cavity Coo 1*             FB-02                     S Fan MOV 3310-B
Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 2 1.
* Not included in original study
These circuits were categorized as "maybe occasionally required for shorc periods of time" and were therefore not listed as needing backup protection.
: 2. These circuits were categorized as not neeJing backup protection since the existing breakers were determined to be adequate.
Since then, Alabama Power Company has decided to provide both primary and backup protection to this category of circuits as follows:
A.
Table 2 - 600V AC Load Centers Reactor Polar Crane, powered from 600V L/C Breaker EA04, has been provided with backup protection MSCP Type "X"
fuse in the Penetration Protection Cabinet.
B.
Table 3 - 600V AC Motor Control Centers These circuits have been provided with backup protection by adding MSCP fuses in the circuits.
Service Feecer Compartment Type of Fuse CTMT Gib-Crar.e FC-M4L S
CTMT Gib-Crane FC-S3R S
CTMT Elev. #3 FB-A4R S
Controller CTMT Gib-Crane FD-H7R S
Reactor Cavity Coo 1*
FB-02 S
Fan MOV 3310-B
* Not included in original study 2.
These circuits were categorized as not neeJing backup protection since the existing breakers were determined to be adequate.
However, due to a review of the design calculations, backup protection was determined to be needed as follows:
However, due to a review of the design calculations, backup protection was determined to be needed as follows:
Table 4 - 208V AC Motor Control Centers These circuits have been provided with backup protection by adding MSCP fuses in circuit.
Table 4 - 208V AC Motor Control Centers These circuits have been provided with backup protection by adding MSCP fuses in circuit.
Service                   Feeder Compartment         Type of Fuse Reactor Cavity                 HA-03                         N H2 Dil. Fan 2A Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 3 Service                 Feeder Compartment           Type of Fuse Reactor Cavity                 HB-N7                       N H2 Dil. Fan 2B
Service Feeder Compartment Type of Fuse Reactor Cavity HA-03 N
: 3. These circuits were proposed to be protected by MSCP fuses.
H2 Dil. Fan 2A Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 3 Service Feeder Compartment Type of Fuse Reactor Cavity HB-N7 N
H2 Dil. Fan 2B 3.
These circuits were proposed to be protected by MSCP fuses.
However, due to design changes in the circuits, other backup protection has been provided by circuit breakers.
However, due to design changes in the circuits, other backup protection has been provided by circuit breakers.
A. Table - 3 600V AC Motor Control Centers The following backup protection is provided instead of MSCP Type "U" fuses:
A.
Backup Service                 Feeder Compartment         Protection Accumulator 2A               FU-Z2                 Q2R18B032-A Discharge Valve                                     (HE63-8050)
Table - 3 600V AC Motor Control Centers The following backup protection is provided instead of MSCP Type "U" fuses:
Accumulator 2C               FU-Z3                 Q2R18B031-A Discharge Valve                                       (HE63-8050)
Backup Service Feeder Compartment Protection Accumulator 2A FU-Z2 Q2R18B032-A Discharge Valve (HE63-8050)
Accumulator 2B               FV-S2                 Q2R18B035-B Discharge Valve B. Table - 10 Lighting Panels The MSCP Type "Y" fuses proposed for lighting panels have been deleted as a result of modifications that introduce a local control panel outside containment for each lighting panel.
Accumulator 2C FU-Z3 Q2R18B031-A Discharge Valve (HE63-8050)
Accumulator 2B FV-S2 Q2R18B035-B Discharge Valve B.
Table - 10 Lighting Panels The MSCP Type "Y" fuses proposed for lighting panels have been deleted as a result of modifications that introduce a local control panel outside containment for each lighting panel.
These local control panels have a breaker to provide backup protection.
These local control panels have a breaker to provide backup protection.
Backup Service                 Feeder Compartment         Protection LTG. PNL. 20                   EB09                 N2T51L003D-N LTG. PNL. 2R                   EB09                 N2T51 LOO 3A-N LTG, PNL. 2P                   EC13                 N2T51L003C-N LTG. PNL. 2Q                   EC13                 N2T51 LOO 3B-N
Backup Service Feeder Compartment Protection LTG. PNL. 20 EB09 N2T51L003D-N LTG. PNL. 2R EB09 N2T51 LOO 3A-N LTG, PNL. 2P EC13 N2T51L003C-N LTG. PNL. 2Q EC13 N2T51 LOO 3B-N 4.
: 4. The primary and backup protection for the Digital Rod Position Control and Indication were not included in the original Table -4, 208 VAC Motor Control Centers. Due to a review of the tables, this situation was identified and these protection circuits are now included in the technical specifications.
The primary and backup protection for the Digital Rod Position Control and Indication were not included in the original Table
-4, 208 VAC Motor Control Centers.
Due to a review of the tables, this situation was identified and these protection circuits are now included in the technical specifications.


!                          Attachment 1 Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 4 l                                                                                                                                                                                                                     t Additionally, the primary protection trip setpoints and response times have been changed to reflect actual test procedures. -The changes do not represent changes in the operating characteristics of the circuit breakers nor in the analysis of the breakers performance. The changes are in accordance with the original analysis and reflect margins included per the manufacturers recommendations / time current characteristic curves.
Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 4 l
In conclusion, this proposed change to Technical Specification Table 3.8-1 is in accordance with license condition 2.C.(19)(b) and does not raise any new technical or safety issues.                                                                                         This change is made to bring the Unit 2 Technical Specifications into conformance with previously l                                                   approved plant design changes.                                                         No unreviewed safety question is i n vol ved.
t Additionally, the primary protection trip setpoints and response times have been changed to reflect actual test procedures. -The changes do not represent changes in the operating characteristics of the circuit breakers nor in the analysis of the breakers performance.
The changes are in accordance with the original analysis and reflect margins included per the manufacturers recommendations / time current characteristic curves.
In conclusion, this proposed change to Technical Specification Table 3.8-1 is in accordance with license condition 2.C.(19)(b) and does not raise any new technical or safety issues.
This change is made to bring the Unit 2 Technical Specifications into conformance with previously l
approved plant design changes.
No unreviewed safety question is i n vol ved.
License Condtion 2.C.(17)
License Condtion 2.C.(17)
!                                                    License condition 2.C.(17) requires the installation of a modified
License condition 2.C.(17) requires the installation of a modified vent valve system prior to startup following the first refueling.
;                                                    vent valve system prior to startup following the first refueling.                                                                                           The t i                                                    modified system is described in the Alabama Power Company letters of i                                                   September 30 and October 30, 1981.
The t
The modified design involves replacing the existing 18" mini-purge
modified system is described in the Alabama Power Company letters of i
;                                                    valve with an 8" vent valve. This change affects the description                                                                                           of the containment ventilation system in Technical Specification 3/4.6.1.7
i September 30 and October 30, 1981.
!                                                    but does not affect the technical requirements for the ventilation
The modified design involves replacing the existing 18" mini-purge valve with an 8" vent valve.
!                                                    system.       As stated in the September 30 and {{letter dated|date=October 30, 1981|text=October 30, 1981 letter}}s, the modified design complies with the requirements of Branch Technical l
This change affects the description of the containment ventilation system in Technical Specification 3/4.6.1.7 but does not affect the technical requirements for the ventilation system.
As stated in the September 30 and {{letter dated|date=October 30, 1981|text=October 30, 1981 letter}}s, the modified design complies with the requirements of Branch Technical l
Position CSB-6-4.
Position CSB-6-4.
In conclusion, this proposed change to Technical Specification i
In conclusion, this proposed change to Technical Specification 3/4.6.1.7 is in accordance with license condition 2.C.(17) and is being i
3/4.6.1.7 is in accordance with license condition 2.C.(17) and is being l
l made to bring the Unit 2 Technical Specifications into conformance with i
made to bring the Unit 2 Technical Specifications into conformance with i                                                   a previously approved plant design change.                                                                                           No unreviewed safety j                                                   question is involved.
a previously approved plant design change.
i                                                                       Technical Specification Table 3.7-4b
No unreviewed safety j
!                                                    Unit 2 Technical Specification Table 3.7-4b contains a requirement that
question is involved.
!                                                    the list of safety-related mechanical snubbers be provided prior to startup following the first refueling outage.                                                                                           The required list is contained in Attachment 2.
i Technical Specification Table 3.7-4b Unit 2 Technical Specification Table 3.7-4b contains a requirement that the list of safety-related mechanical snubbers be provided prior to startup following the first refueling outage.
This proposed change to Technical Specification Table 3.7-4b is in accordance with the Technical Specification requirement and simply adds i                                                   the list of mechanical snubbers. A plant design change is not involved
The required list is contained in Attachment 2.
!                                                    nor is an unreviewed safety question involved.
This proposed change to Technical Specification Table 3.7-4b is in accordance with the Technical Specification requirement and simply adds i
s
the list of mechanical snubbers.
 
A plant design change is not involved nor is an unreviewed safety question involved.
Attachment 1 Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 5 IV.         Conclusion
s Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 5 IV.
Conclusion Alabama Power Company respectfully requests the proposed technical i
~
~
i Alabama Power Company respectfully requests the proposed technical specification changes contained in Attachment 2 to provide conformance with the above described license conditions.                 This proposed change does not involve an unreviewed safety question as defined by 10CFR50.59.
specification changes contained in Attachment 2 to provide conformance with the above described license conditions.
This proposed change does not involve an unreviewed safety question as defined by 10CFR50.59.
j
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Latest revision as of 11:46, 16 December 2024

Application for Amend to License NPF-8,incorporating Design Changes & Addl Info Prior to Startup Following First Refueling Outage.Changes Concern Containment Penetration Overcurrent Protection.Safety Evaluation Encl
ML20066K812
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 11/24/1982
From: Clayton F
ALABAMA POWER CO.
To: Varga S
Office of Nuclear Reactor Regulation
Shared Package
ML20066K814 List:
References
NUDOCS 8211290658
Download: ML20066K812 (8)
v • d • e


Text

.

Malling Addrsss Alabama Power Company 600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291 A

Telephone 205 783-6081 F. L Clayton, Jr.

Rn"$3%",*"'

AlabamaPower the Southern electrC SyStern November 24, 1982 i

Docket No. 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention:

Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Unit 2 Technical Specification Amendment to Incorporate License Condition Requirements Gentlemen:

On October 22, 1982, Joseph M. Farley Nuclear Plant - Unit 2 shut down for the first refueling outage.

In accordance with the operating license, NPF-8, some design changes and submittal of additional information prior to startup following the first refueling outage are required.

Specifically, the requirements that affect the technical specifications are:

the addition of containment penetration overcurrent protection devices, license condition 2.C.(19)(b); replacement of tne containment vent valves, license condition 2.C.(17); and tabulation of a list of safety-related mechanical snubbers, Technical Specification Table 3.7-4b.

Therefore, proposed technical specification changes, as contained herein, are respectfully requested to provide conformance with the aforementioned license conditions.

l License Condition 2.C.(19)(b)

License condition 2.C.(19)(b), as amended, requires the modifica-tion of circuit protection devices in the containment penetration circuits.

The modifications are described in the Alabama Power Company letter of November 17, 1980, and were approved in the NRC Safety Evalua-tion Report, Supplement No. 5, dated March 1981.

l Many of the required circuit modifications will be completed during the first refueling outage while the remainder of the modifications will be completed no later than the second refueling outage.

Since it will not be known exactly how many of the modifications will be completed until just prior to startup from the first refueling outage, all of the 4d 8211290658 821124

\\ g\\T PDR ADOCK 05000364 p

PDR

Mr. S. A. Varga November 24, 1982 Director Nuclear Reactor Regulation Page 2 U.S. Nuclear Regulatory Commission circuit modifications are included in the proposed technical specifica-tion table change (Table 3.8-1) with a footnote stating that only the installed protection devices will be covered by the requirements of section 3/4.8.3.1 until the second refueling, at which time all protec-tion devices listed will be covered.

This approach allows early submit-tal of the proposed technical specification table change and eliminates the need for a subsequent technical specification change during the second refueling outage.

Some changes to the November 17, 1980 proposed design have been made and are reflected in the proposed technical specification change.

All of the changes are in accordance with licensing requirements and these changes are described in detail in Attachment 1.

This proposed change to Technical Specification Table 3.8-1 is in accordance with license condition 2.C.(19)(b) as described in Attachment 1.

This change is made to bring the Unit 2 Technical Specifications into conformance with previously approved plant design changes such that no technical or safety issues are involved.

Therefore, this change is administrative in nature per 10CFR170.22 and does not involve an unreviewed safety question.

License Condition 2.C.(17)

License condition 2.C.(17) requires the installation of a modified vent valve system prior to startup following the first refueling.

The modified system is described in the Alt.bama Power Company letters of September 30 and October 30, 1981.

The modified design involves replacing the existing 18" mini-purge valve with an 8" vent valve.

This change affects the description of the containment ventilation system in Technical Specification 3/4.6.1.7 but does not affect the technical requirements for the ventilation system.

As stated in the September 30 and October 30, 1981 letters, the modified design complies with the requirements of Branch Technical Position CSB-6-4.

This proposed change to Technical Specification 3/4.6.1.7 is in accordance with license condition 2.C.(17) as described in Attachment 1.

This change is made to bring the Unit 2 Technical Specifications into conformance with a previously approved plant design change such that no technical or safety issue is involved.

Therefore, this change is administrative in nature per 10CFR170.22 and does not involve an unreviewed safety question.

1

Mr. S. A. Varga November 24, 1982 Director Nuclear Reactor Regulation Page 3 U.S. Nuclear Regulatory Commission Technical Specification Table 3.7-4b Unit 2 Technical Specification Table 3.7-4b contains a requirement that the list of safety-related mechanical snubbers be provided prior to startup following the first refueling outage.

The required list is contained in Attachment 2 to this letter.

This proposed change to Technical Specification Table 3.7-4b is in accordance with the technical specification requirement as described in.

This change adds the list of mechanical snubbers to the technical specifications and does not involve a plant design change.

Therefore, this change is administrative in nature per 10CFR170.22 and does not involve an unreviewed safety question.

Conclusion The above described changes have been reviewed by Alabama Power Company's Plant Operations Review Committee and it has been concluded that the proposed changes do not involve an unreviewed safety question.

A detailed safety evaluation is contained in Attachment 1 and the proposed technical specification changes are contained in Attachment 2.

The Nuclear Operations Review Board will review this proposed change during its next meeting.

This amendment is designated as Class II in accordance with 10CFR170.22 requirements, since it is administrative in nature and does not involve a safety issue (i.e., all of the change are in accordance with NRC imposed license conditions).

Enclosed is a check for $1,200 to cover the total amount of fees required.

In accordance with 10CFR50.30(c)(1)(f), three signed originals and forty (40) additional copies of the proposed changes are enclosed.

Yours very truly,

. L. Cl ayton, J r.

FLCJ r/GGY : jc-D31 SWORN TO AND SUBSCRIBED BEFORE ME Attachments THIS d?dC DAY OF A/nfly[1/U,1982.

cc:

Mr. R. A. Thomas OnN(t> ktux/dd Mr. G. F. Trowbridge Mr. J. P. O'Reilly Notary Public Mr. E. A. Re:ves Mr. W. H. Bradford My Commission Expires:

Il-L9 - 8:L-

ATTACHMENT 1 Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications I.

Background

On October 22, 1982, Joseph M. Farley Nuclear Plant - Unit 2 shut down for the first refueling outage.

In accordance with the operating license, NPF-8, some design changes and submittal of additional information prior to startup following the first refueling outage are required.

Specifically, the requirements that affect the technical specifications are:

the addition of containment penetration overcurrent protection devices, license condition 2.C.(19)(b);

replacement of the containment vent valves, license condition 2.C.(17);

and tabulation of a list of safety-related mechanical snubbers, Technical Specification Table 3.7-4b.

Therefore, proposed technical specification changes, as contained in Attachment 2, are necessary to provide conformance with the aforementioned license conditions.

II.

References Operating License NPF-8 as amended FNP-2 Technical Specifiations III.

Bases License Condition 2.C.(19)(b)

License condition 2.C.(19)(b), as amended, requires the modification of circuit protection devices in the containment penetration circuits.

The modifications are described in the Alabama Power Company letter of November 17, 1980, and were approved in the NRC Safety Evaluation Report, Supplement No. 5, dated March 1981.

l Many of the required circuit modifications will be completed during the first refueling outage while the remainder of the modifications will be completed no later than the second refueling outage.

Since it will not be known exactly how many of the modifications will be completed until just prior to startup from the first refueling outage, all of the circuit nodifications are included in the proposed technical specification table change (Table 3.8-1) with a footnote stating that l

only the installed protection devices will be covered by the requirements of section 3/4.8.3.1 until the second refueling, at which time all protection devices listed will be covered.

This approach allows early submittal of the proposed technical specification table change and eliminates the need for a subsequent technical specification change during the second refueling outage.

Some changes to the November 17, 1980 proposed design have been made l

and are reflected in the proposed technical specification change.

All l

of the changes are in accordance with licensing requirements.

The specific changes to the modifications detailed in the November 17, 1980 letter are:

Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 2 1.

These circuits were categorized as "maybe occasionally required for shorc periods of time" and were therefore not listed as needing backup protection.

Since then, Alabama Power Company has decided to provide both primary and backup protection to this category of circuits as follows:

A.

Table 2 - 600V AC Load Centers Reactor Polar Crane, powered from 600V L/C Breaker EA04, has been provided with backup protection MSCP Type "X"

fuse in the Penetration Protection Cabinet.

B.

Table 3 - 600V AC Motor Control Centers These circuits have been provided with backup protection by adding MSCP fuses in the circuits.

Service Feecer Compartment Type of Fuse CTMT Gib-Crar.e FC-M4L S

CTMT Gib-Crane FC-S3R S

CTMT Elev. #3 FB-A4R S

Controller CTMT Gib-Crane FD-H7R S

Reactor Cavity Coo 1*

FB-02 S

Fan MOV 3310-B

  • Not included in original study 2.

These circuits were categorized as not neeJing backup protection since the existing breakers were determined to be adequate.

However, due to a review of the design calculations, backup protection was determined to be needed as follows:

Table 4 - 208V AC Motor Control Centers These circuits have been provided with backup protection by adding MSCP fuses in circuit.

Service Feeder Compartment Type of Fuse Reactor Cavity HA-03 N

H2 Dil. Fan 2A Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 3 Service Feeder Compartment Type of Fuse Reactor Cavity HB-N7 N

H2 Dil. Fan 2B 3.

These circuits were proposed to be protected by MSCP fuses.

However, due to design changes in the circuits, other backup protection has been provided by circuit breakers.

A.

Table - 3 600V AC Motor Control Centers The following backup protection is provided instead of MSCP Type "U" fuses:

Backup Service Feeder Compartment Protection Accumulator 2A FU-Z2 Q2R18B032-A Discharge Valve (HE63-8050)

Accumulator 2C FU-Z3 Q2R18B031-A Discharge Valve (HE63-8050)

Accumulator 2B FV-S2 Q2R18B035-B Discharge Valve B.

Table - 10 Lighting Panels The MSCP Type "Y" fuses proposed for lighting panels have been deleted as a result of modifications that introduce a local control panel outside containment for each lighting panel.

These local control panels have a breaker to provide backup protection.

Backup Service Feeder Compartment Protection LTG. PNL. 20 EB09 N2T51L003D-N LTG. PNL. 2R EB09 N2T51 LOO 3A-N LTG, PNL. 2P EC13 N2T51L003C-N LTG. PNL. 2Q EC13 N2T51 LOO 3B-N 4.

The primary and backup protection for the Digital Rod Position Control and Indication were not included in the original Table

-4, 208 VAC Motor Control Centers.

Due to a review of the tables, this situation was identified and these protection circuits are now included in the technical specifications.

Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 4 l

t Additionally, the primary protection trip setpoints and response times have been changed to reflect actual test procedures. -The changes do not represent changes in the operating characteristics of the circuit breakers nor in the analysis of the breakers performance.

The changes are in accordance with the original analysis and reflect margins included per the manufacturers recommendations / time current characteristic curves.

In conclusion, this proposed change to Technical Specification Table 3.8-1 is in accordance with license condition 2.C.(19)(b) and does not raise any new technical or safety issues.

This change is made to bring the Unit 2 Technical Specifications into conformance with previously l

approved plant design changes.

No unreviewed safety question is i n vol ved.

License Condtion 2.C.(17)

License condition 2.C.(17) requires the installation of a modified vent valve system prior to startup following the first refueling.

The t

modified system is described in the Alabama Power Company letters of i

i September 30 and October 30, 1981.

The modified design involves replacing the existing 18" mini-purge valve with an 8" vent valve.

This change affects the description of the containment ventilation system in Technical Specification 3/4.6.1.7 but does not affect the technical requirements for the ventilation system.

As stated in the September 30 and October 30, 1981 letters, the modified design complies with the requirements of Branch Technical l

Position CSB-6-4.

In conclusion, this proposed change to Technical Specification 3/4.6.1.7 is in accordance with license condition 2.C.(17) and is being i

l made to bring the Unit 2 Technical Specifications into conformance with i

a previously approved plant design change.

No unreviewed safety j

question is involved.

i Technical Specification Table 3.7-4b Unit 2 Technical Specification Table 3.7-4b contains a requirement that the list of safety-related mechanical snubbers be provided prior to startup following the first refueling outage.

The required list is contained in Attachment 2.

This proposed change to Technical Specification Table 3.7-4b is in accordance with the Technical Specification requirement and simply adds i

the list of mechanical snubbers.

A plant design change is not involved nor is an unreviewed safety question involved.

s Safety Evaluation for Proposed Changes to the FNP-2 Technical Specifications Page 5 IV.

Conclusion Alabama Power Company respectfully requests the proposed technical i

~

specification changes contained in Attachment 2 to provide conformance with the above described license conditions.

This proposed change does not involve an unreviewed safety question as defined by 10CFR50.59.

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