ML18037A495
| ML18037A495 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/30/1993 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18037A494 | List: |
| References | |
| NUDOCS 9310050182 | |
| Download: ML18037A495 (18) | |
Text
ENCLOSURE 1
PROPOSED TECHNICAL SPECIFICATION CHANGE BROWNS FERRY NUCLEAR PLANT UNIT 1 TVA BFN TECHNICAL SPECIFICATION N00 337 9310050182 930930 PDR ADOCK 05000259
. P PDR
I N
il
(ll)
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions" of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
"Browns Ferry Physical Security Plan", with revisions submitted through May 24, 1988; "Browns Ferry Security Personnel Training and Qualification Plan", with revisions submitted through April 16, 1987; and "Browns Ferry Safeguards Contingency Plan", with revisions submitted through June 27, 1986.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
(12)
The licensee is authorized to temporarily store low-level radioactive waste in an existing covered pavilion that is situated outside the security fence, as presently located, but inside the site exclusion area.
The total amount of low-level waste to be stored shall not exceed 1320 curies of total activity.
This authorization expires two years from the effective date of this amendment and is subject to all the conditions and restrictions in TVA's application dated January 21, 1980.
(13)
Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated December 8, 1988, March 6, 1991, March 31, 1993
(
) and Supplement dated November 3, 1989 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
D.
This amended license is effective as of the date of issuance and shall expire midnight on December 20, 2013.
FOR THE ATOMIC ENERGY COMMISSION S/
A Giambusso A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing Date of Issuance:
PROPOSED TECHNICAL SPECIFICATION CHANGE BROWNS FERRY NUCLEAR PLANT UNIT 2 TVA BFN TECHNICAL SPECIFICATION NO 337
(12)
The licensee is authorized to temporarily store low-level radioactive waste in an existing covered pavilion that is situated outside the security fence, as presently located, but inside the site exclusion area.
The total amount of low-level waste to be stored shall not exceed 1320 curies of total activity.
This authorization expires two years from the effective date of this amendment and is subject to all the conditions and restrictions in TVA's application dated January 21, 1980.
(13)
Commission Order dated March 25, 1983 is modified as follows:
in Attachment 1, for item II.F.1.1 and II.F.1.2 change "12/31/84" to "Prior to startup in Cycle 6."
(14)
Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated December 8, 1988, March 6, 1991, March 31, 1993 (
) and Supplement dated November 3,
1989 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
D.
This amended license is effective as of the date of issuance and shall expire midnight on June 28, 2014.
FOR THE ATOMIC ENERGY COMMISSION S/
A Giambusso A. Giambusso, Deputy Director for Reactor Projects Directorate of Licensing
Attachment:
Appendices A 6 B Technical Specifications Date of Issuance:
JUN 28, 1974 BFN Unit 2
Cont'd HH.
A endix Sa e Shutdown ro r BFH has developed an Appendix R Safe Shutdown Program.
This Program is to ensure that the equipment required by the Appendix R Safe Shutdown Analysis"is maintained and demonstrated functional as follows:
1.
The functional requirements of the Safe Shutdown systems and equipment, as well as appropriate compensatory measures should these systems/components be unable to perform their intended function are outlined in Section III of the Program.
2.
Testing and monitoring of the Appendix R Safe Shutdown systems and equipment are defined in Section V of the Program.
00, CORE OPERATI G LIMITS REPORT COLR The COLR is the unit-'specific document that provides the core operating limits for the current operating cycle.
These cycle-specific core operating limits shall be determined for each operating cycle in accordance with Specification 6.9.1.7.
Plant operation within these limits is addressed in individual specifications.
BFH Unit 2 1.0-12a
PROPOSED TECHNICAL SPECIFICATION CHANGE BROWNS FERRY NUCLEAR PLANT UNIT 3 TUA BFN TECHNICAL SPECIFICATION NO ~
337
(4) The licensee shall maintain in effect and fully implement all provisions of the Commission approved physical security plan including amendments made pursuant to the authority of 10 CFR 50.54(p).
The approved plan, which contains information protected under 10 CFR 73.21, is entitled "Browns Ferry Nuclear Plant Physical Security Plan," dated May 15, 1982 (TVA letter dated June ll, 1982) and revisions submitted by TVA letters dated August 31, 1982 and October 19, 1982.
Notwithstanding the statement in Section 9.1 of the physical security plan, the licensee shall maintain positive access control over containment in accordance with the requirements of 10 CFR 73.55(d)(8).
(5) The licensee shall follow all provisions of the NRC approved Guard Training & Qualification Plan, including amendments and changes made pursuant to 10 CFR 50.54(p).
The approved Guard Training &
Qualification Plan is identified as "Browns Ferry Nuclear Power Station Guard Training & Qualification Plan," dated August 17,
- 1979, as revised by pages dated January 24,
- 1980, May 21, 1980, October 1,
- 1980, and March 9, 1981 and as may subsequently be revised in accordance with 10 CFR 50.54(p).
The Guard Training & Qualification Plan shall be followed, in accordance with 10 CFR 73.55(b),
60 days after the date of this amendment.
(6) The licensee sh'all fully implement and maintain in effect all provisions of the Commission-approved physical security, guard training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, which contain Safeguards information protected under 10 CFR 73.21, are entitled:
"Browns Ferry Physical Security Plan", with revisions submitted through May 24, 1988; "Browns Ferry Security Personnel Training and Qualification Plan", with revisions submitted through April 16, 1987; and "Browns Ferry Safeguards Contingency Plan", with revisions submitted through June 27, 1986.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
(7)
Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in the SEs dated December 8, 1988, March 6, 1991, March 31,
- 1993,
(
),
a
~
Supplement dated November 3, 1989 subject to the following provision:
The licensee may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
BFN Unit 3
1.0 D
I 0
S Cont'd NN.
endi Sa e
S utdown Pro r BFN has developed an Appendix R Safe Shutdown Program.
This program is to ensure that the equipment required by Appendix R Safe Shutdown Analysis is maintained and demonstrated functional as follows:
1.
The functional requirements of the Safe Shutdown Systems and equipment, as well as appropriate compensatory measures should these systems/components be unable 'to perform their intended function are outlined in Section III of the program.
2.
Testing and monitoring of the Appendix R Safe Shutdown systems and equipment are defined in Section V of the Program.
00.
CO OPE G L M S
REPORT COLR The COLR is the unit-specific document that provides the core operating limits for the current operating cycle.
These cycle-specific core operating limits shall be determined for each operating cycle in accordance with Specification 6.9.1.7.
Plant operation within these limits is addressed in individual specifications.
BFN Unit 3 1.0-12a
ENCLOSURE 2
PROPOSED TECHNZCAL SPECZFZCATZON (TS)
BROWNS FERRY NUCLEAR PLANT (BFN)
UNITS 1q 2q AND 3 (TVA BFN TECHNICAL SPECIFICATION NO ~ 337)
REASON FOR THE CHANGE DESCRZPTION AND i7USTIFICATZON Reason for Chan e
BFN Units 1, 2, and 3, TSs were revised to implement the guidance set for the in Generic Letters (GL) 86-10 "Implementation of Fire Protection Requirements" and 88-12 "Removal of Fire Protection Requirement from Technical Specifications."
During the review of the Fire Protection Program, it was recognized that the Appendix R Safe Shutdown Program was for Unit 2 operation only.
The proposed administrative change will revise the license condition for the Fire Protection Program to reflect the NRC approval for the combined Unit 2 and 3 Appendix R Safe Shutdown Program, and for Unit 3, add the definition of the Appendix R Safe Shutdown Program.
Descri tion of the Pro osed Chan e
For Units 1, 2, and 3, license condition number (13),
(14),
and (7), respectively, presently read as follows:
Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Final Safety Analysis Report for BFN as approved in SEs dated December 8,
- 1988, March 6,
- 1991, March 31,
- 1993, and Supplement dated November 3,
1989, subject to the following provision:
The licensee may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
The proposed change to the license condition for Units 1, 2, and 3 (13),
(14),
and (7) reads as follows:
Browns Ferry Nuclear Plant shall implement and maintain in effect all provisions of the approved Fire Protection Program as described is the Final Safety Analysis Report for BFN as approved in SEs dated December 8,
- 1988, March 6,
- 1991, March 31,
- 1993,
(
) and Supplement dated November 3,
- 1989, subject to the 'following provision:
The licensee may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
2.
Change existing definition NN to 00 for Unit 3 only:
3.
Add definition NN as follows to Unit 3 only:
NN.
A endix R Safe Shutdown Pro ram BFN has developed an Appendix R Safe Shutdown Program.
This program is to ensure that the equipment required by Appendix R Safe Shutdown Analysis is maintained and demonstrated functional as follows:
The functional requirements of the Safe Shutdown systems and equipment, as well as appropriate compensatory measures should these systems/components be unable to perform their intended function are outlined in Section III of the program.
2.
Testing and monitoring of the Appendix R Safe Shutdown systems and equipment are defined in,Section V of the program.
4.
Delete the following from definition NN, for Unit 2 only:
"3.
Deleted."
Justification of Chan e
The current license condition issued by the April 1, 1993 letter, reflects a Units 1, 2, and 3, Fire Protection Program and Unit 2 Appendix R Safe Shutdown Program.
The proposed administrative change to the BFN license will allow BFN to implement and NRC approved Appendix R Safe Shutdown Program in accordance with the guidance set forth in GLs 86-10 and 88-12 for a combined Unit 2 and 3 operation.
k I
ENCLOSURE 3
BROWNS FERRY NUCLEAR PLANT (BFN)
PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION UNITS 1p 2i AND 3 (TVA BFN TECHNICAL SPECIFICATION NO 337)
DESCRIPTION OF PROPOSED TECHNICAL SPECIFICATION CHANGE The proposed technical specification changes revise the Fire Protection Program license condition for Units 1, 2, and 3, and adds the Appendix R Safe Shutdown Program definition "NN" to Section 1.0 in the Unit 3 TSs.
Furthermore, for consistency, the current definition "NN" in the Unit 3 TSs was relettered "OO".
BASIS FOR PROPOSED NO SIGNIFICANT HAZARDS CONSZDERATZON DETERMINATION NRC has provided standards for determining whether a significant hazards consideration exists as stated in 10 CFR 50.92(c).
A proposed amendment to an operating license involves no significant hazards considerations 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 the margin of safety.
1 ~
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
This proposed change is administrative in nature.
The proposed change is being made to revise the license condition to reflect a combined Unit 2 and 3 Appendix R Safe Shutdown Program following NRC approval.
Compliance with the applicable Appendix R requirements is ensured through implementation of the Fire Protection Program and the Appendix R Safe Shutdown Program.
The change does not affect any design bases accident or the ability of any safe shutdown equipment to perform its function.
Also, there are no physical modifications required to implement this TS change.
Therefore, these proposed administrative changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change is administrative in nature.
The proposed change is being made to revise the license condition to reflect a combined Unit 2 and 3 Safe Shutdown Program following NRC approval.
Compliance with the applicable Appendix R requirements is ensured through implementation of the Fire Protection Program and Appendix R Safe Shutdown Program.
This change does not affect any design basis accident or the ability of any safe shutdown equipment, to perform its function.
Also, there are no physical modifications required to implement this TS change.
Therefore, these proposed administrative changes do not create the possibility of a new or different, kind of accident from an accident previously evaluated.
3.
This change does not involve a significant reduction in the margin of safety.
The proposed changes are administrative in nature.
Compliance with the applicable Appendix R requirements is ensured through the implementation of the Fire Protection Program and Appendix R Safe Shutdown Program.
The proposed change does not affect any design basis accident and does not reduce or adversely affect the capability to achieve and maintain safe shutdown in the event of a fire.
Furthermore, no reductions to the requirements for equipment operability, surveillance requirements or setpoints are being made which could result in reduction in the margin of safety.
Therefore, these proposed administrative changes will not result in a reduction in the margin of safety.
CONCLUSION TVA has evaluated the proposed amendment described above against the criteria given in 10 CFR 50.92(c) in accordance with the requirements of 10 CFR 50.91(a)(1).
This evaluation has determined that the proposed amendment will not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility for a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety.
- Thus, TVA has concluded that the proposed amendment does not involve a significant hazards consideration.