ML20080M007
| ML20080M007 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/27/1983 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8310030414 | |
| Download: ML20080M007 (22) | |
Text
Memng Address Alabama Power Company 600 North 18th Street
. Post Offica Box 2641 Birmingham. Alabama 35291 Telephone 205 783-6081 F. L Clayton. Jr.
gg;;gy"'
AlabamaPbwer the southern ekt rc system September 27, 1983 Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. S. A. Varga 10CFR50.49 - Environmental Qualification of Regulatory Guide 1.97 Equipment - Units 1 and 2 Gentlemen:
In letters dated May 20 and August 24, 1983, Alabama Power Company requested that the, schedule provided in 10CFR50.49(g) for identifying accident monitoring equipment (Regulatory Guide 1.97) and upgrading its environmental qualification be extended to November 30, 1985.
In I
subsequent conversations with the NRC Farley Nuclear Plant Project Manager, Mr. E. A. Reeves, Alabama Power Company has been informed that equipment items should be identified for which an extension is requested.
As a supplement to letters dated May 20 and August 24, 1983, Alabama Power herein identifies the specific Regulatory Guide 1.97 accident monitoring equipment items for which an extension is requested.
In addition, schedules are provided for upgrading the subject equipment along with bases for the extension request.
10CFR50.49 establishes a goal of final environmental qualification of electrical equipment within the scope of the rule "by the end of the second refueling outage after March 31, 1982."
To comply with 10CFR50.49, such equipment would require qualification by the end of the present Unit 2 second refueling outage scheduled for completion in October 1983 and the Unit 1 fif th refueling outage scheduled to start in February 1984.
Alabama Power Company has determined that the schedule of 10CFR50.49 is impractical and can not be satisfied based on the time needed to complete proper engineering evaluations, the current schedule for refueling outages and procurement lead times. presents the current schedule for refueling outages at Farley Nuclear Plant.
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Mr. S. A. Varga September 27, 1983 U. S. Nuclear Regulatory Commission Page 2 Alabama Power Company stated in letter dated November 16, 1981 that ef forts to address Regulatory Guide 1.97, SPDS, emergency operating procedures, emergency response facilities and control room desi gn review would not commence until the NRC finalized all criteria.
Following issuance of Supplement 1 to NUREG-0737, Alabama Power Company made specific commitments for Regulatory Guide 1.97 in letter dated April 15, 1983.
At the date these commitments were made, only seven months for Unit 2 and ten months for Unit 1 were available to evaluate the appropriate Farley Nuclear Plant instrumentation to the provisions of Regulatory Guide 1.97, complete design, procure equipment and perform modifications to comply with the 10CFR50.49 implementation dates.
Alabama Power Company's April 15, 1983 letter included a preliminary schedule for implementing all twelve Regulatory Guide 1.97 criteria.
This schedule was based on upgrading instrumentation to satisfy all twelve Regulatory Guide 1.97 criteria with a single coordinated modification per instrument, rather than a series of modifications addressing only individual criteria such as environmental qualification.
In order to comply with the extension schedules of 10CFR50.49, Alabama Power Company must now make modifications solely to resolve environmental qualification concerns and potentially implement additional modifications at a later date to resolve discrepancies based on the remaining Regulatory Guide 1.97 criteria.
The R.G. 1.97 Cempliance Report will identify modifications needed to establish compliance with R.G.1.97 including those associated with environmental qualificaton.
The R.G.1.97 Compliance Report will be submitted in June 1984 and March 1984 for Units 1 and 2, respectively.
Consequently, Alabama Power Company requests, pursuant to 10CFR50.49(g), that the schedule to upgrade the environmental qualification of accident monitoring equipment (Regulatory Guide 1.97) as described in 19CFR50.49(b)(3) be extended to the Unit I sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985. identifies the specific equipment items for which the extension is requested including bases for this extension.
Also included in Attachment 2 is a schedule with expected dates for satisfying this extension request.
This schedule is based on preliminary design evaluations, estimates of procurement lead tima, and tentati ve planning for implementation and testing.
Such preliminary information was prepared to satisfy the schedule of 10CFR50.49 without integrating the evaluations and potential overlapping modifications to satisfy all twelve R.G. 1.97 criteria.
During the course of implementing this schedule, Alabama Power Company will make every effort to compress the R.G. 1.97 schedule included in the April 15, 1983 letter and will notify the appropriate NRC management if it is unable to satisfy this extension request.
4 Mr. S. A. Varga September 27, 1983 U. S. Nuclear Regulatory Commission Page 3 In letter dated May 20, 1983, Alabama Power Company emphasized that to the certain post-accident the extension request applied only(b)(3) and that the 1,378 equipment monitoring equipment of 10CFR50.49 items within the scope of b(1) and b(2) are environmentally qualified.
Certain equipment items within the scope of 10CFR50.49(b)(1) and (b)(2) and the TM1 Action Plan are environmentally qualified and are also within the scope of 10CFR50.49(b)(3).
These equipment items are identi fied in Attachment 3.
As stated in Alabama Power Company's letter dated April 15, 1983, the provisions of Supplement 1 to NUREG-0737 are to enhance the present emergency response capabilities and are not intended to provide the sole safety function.
Currently, the Farley Nuclear Plant computer and main control board are being utilized to monitor parameters necessary for normal and emergency conditions.
The safe operation of the Farley Nuclear Plant will not be jeopardized during the upgrades of equipment within the scope of Regulatory Guide 1.97 to comply with 10CFR50.49.
It is requested that this extension request to the schedule of 10CFR50.49(g) be provided by October 14, 1983.
This requested date is approximately two weeks prior to return to power from the present Unit 2 refueling outage, which is the date for compliance to 10CFR50.49.
Granting this proposed extension by October 14, 1983 would prevent unnecessary loss of power generation from the extended outage required to design, procure and install equipment necessary to comply with 10CFR50.49.
Such equipment installation could extend the next Unit 1 and 2 outages by twelve months.
If there are any questions, please contact this office.
Yours very truly, 8
F. L. Clayton !Jr.
FLCJ r/BDM:l sh-D1 cc:
Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O 'Reilly Mr. E. A. Reeves Mr. W. H. Bradford Dr. I. L. Myers
ATTACR1ENT 1 Schedule To Upgrade R.G.1.97 Equipment Not Presently Qualified To 10CFR50.49 Extension Request 01/84 01/85 11/30/85 R.G. 1.97 Supplenent 1 Unit 2 Conpliance Unit 2 Schedule 2nd Refueling Report 3rd Refueling Unit 2 -
04/.5/83 09/16 Note 1 10/30 03/84 02/85 Note 2 04 85 Note 3 R.G. 1.97 Supplenent 1 Unit 1 Conpliance Unit 1 Schedule 5th Refueling Report 6th Refueling Unit 1 -
04/15/83 02/84 Note 1 05/85 06/84 09/85 Note 211/35 Note 3 Note 1: Design and Vendor Walkdowns For Inaccessible Equipnent Note 2: Conpletion of Inaccessible R.G.1.97 Equipnent Upgrade for Environnental Qualification Note 3: Conpletion of Accessible R.G.1.97 Equipnent Upgrade For Environnental Qualification
Accident Monitoring Equipment Potentially Requiring Environmental Qualification
Explanation 10CFR50.49 establishes a goal of final environmental qualification of electrical equip.nent within the scope of the rule "by the end of the second refueling outage after March 31, 1982." The second refueling outage after March 31, 1982 is the Unit 1 fifth refueling outage and the Unit 2 second refueling outage. The anticipated completion dates discussed herein are based on currently scheduled refueling outages.
The current refueling outage schedule for Units 1 and 2 is shown in of this letter and is summarized as follows:
Scheduled Refueling Outage End Dates Unit 1 Unit 2 5th Refueling Outage - April 1984 2nd Refueling Outage - Oct.1983 (second refueling (second refueling outage after outage after March 31, 1982)
March 31, 1982) 6th Refueling Outage - Nov.1985 3rd Refueling Outage - April 1985 f
s i
A.
Parameter:
Core Exit Thermocouples Anticipated Completion Dates:
Unit 1 Unit 2 Walkdown 5th Refueling Outage (R.0.)
2nd R.0.
Installation 6th Refueling Outage (R.0.)
3rd R.0.
Discussion: Walkdowns of the installed core exit thermocouple instrumentation are necessary in order to develop the design and determine procurement requirements prior to the installation cf any environmental qualification modifications. Major components of this system, such as the thermocouple connectors, junctiots boxes and cabling, are located in the containment and are not accessible during power operation. These walkdowns are not anticipated to be completed until the 5th refueling outage of Unit 1 and the 2nd refueling outage of Unit 2, both of which are the second outages after March 31, 1982.
Therefore, the design and equipment, based on current procurement lead-times, will not be available within the schedule established in 10CFR50.49.
The core exit thermocouple system is needed for power operation of Farley Nuclear Plant and to satisfy the Technical Specifications. No modifications to the existing system can be performed during power operation.
Installation of modifications is scheduled to be completed during the first occurring refueling outage following the development of design and completion of procurement. These refueling outages for installation are anticipated to be the 6th refueling outage of Unit 1 and the 3rd refueling outage of Unit 2.
Extension Request: The end of the Unit 1 sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
A-1
B.
Parameter: Containrent Pressure - Extended and Narrow Range Anticipated Completion Dates:
Unit 1 Unit 2 R.G.1.97 Compliance Report June 1984 March 1984 Installation 6th R.0.
3rd R.O.
Discussion:
Environmental qualification test documentation exists for various components of this installed accident monitoring instrumentation. These test documents will be evaluated to determine the qualification of the associated components to the Farley specific accident environment. Upon completion of the evaluation, the instrumentation may be determined to be environmentally qualified. However, any unqualified equipment will be replaced or nodified (e.g., relocation or shielding) to establish its qualificaton. The need for modifications will be identified in the R.G.1.97 Compliance Reports.
The R.G.1.97 Compliance Report and resulting design and procurement will not be completed within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G.1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984.
The extended and narrow ranga containment pressure instrumentation is needed to satisfy the Technical Specifications and can not be removed from service during power operation. The R.G.1.97 Compliance Report will identify the need for modifications that could be performed at power or during scheduled refueling outages.
Any inodification requiring an outage will be implemented at the first occurring refueling outage following the completion of the necessary design and procurement. These refueling outages are anticipated to be the Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Any modifications that could be performed at power will be implemented within 6 months after the completion of design and procurement but no later than the Unit 1 sixth refueling outage and the Unit 2 third refueling OLcage.
i Extension Request: The end of the Unit 1 sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
B-1
C.
Parameter:
Neutron Monitor Anticipated Completion Dates:
Unit 1 Unit 2 Walkdowns 5th R.0.
2nd R.0.
Installation 6th R.0.
3rd R.0.
Discussion:
Walkdowns of the installed components may be necessary in order to develop the design and determine procuremant for the environmental qualification modifications. Major components of this system, such as the detectors and cabling, are located in the containraent and are not accessible during power operation. Alabama Power Company is presently working with vendors and designers to determine the need for walkdowns.
In order to preclude any delays in the design and procurement, walkdowns are presently scheduled for the Unit 1 fifth refueling outage and the Unit 2 second refueling outage. Walkdowns during these outages will provide for the design and procurement during the subsequent fuel cycles in preparation for installation during the Unit 1 sixth and Unit 2 third refueling outages.
The neutron monitor instrumentation is needed for power operations of Farley Nuclear Plant and to satisfy the Technical Specifications. No modifications to the existing instrumentation can be performed during power operation.
Installation of modifications is scheduled for the first occurring refueling outage following the development of design and completion of procurement.
These refueling outages for installation are anticipated to be the Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Requested Extension: The end of the Unit I sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
J i
C-1
D.
Parameters: Residual Heat Removal System / Low Head Safety Injection Flow Containnent Spray Flow Component Cooling Water Heat Exchanger Outlet Temperature Residual Heat Removal Heat Exchanger Inlet and Outlet Temperature Containnent Cooler Service Water Outlet Temperature Flow to Component Cooling Water Heat Exchanger Tenperature of Service Water to Auxiliary Building Anticipated Completion Dates:
Unit 1 Unit 2 R.G. 1.97 June 1984 March 1984 Compliance Report Installation 6th R.0.
3rd R.0.
Discussion: Alabama Power Company has performed an evaluation of the areas in which certain components of this instrumentation are located and has determined that these areas would be exposed to a radiation dose from post-accident recirculating fluids. APCo is determining the availability of environmental qualification test documentation and the total integrated radiation dose to which the component would be exposed based on its post-accident operating time. APCo will evaluate the available test data and determine the qualification status of the inst rumentati on.
It is expected that certain components of the instrumentation will be determined to be environmentally qualified. Any components that are determined not to be environmentally qualified will be replaced or modified (e.g., relocation or shielding) to establish its qualification. The need for modifications will be identified in the R.G.1.97 Compliance Reports.
The R.G.1.97 Compliance Report and resulting design and procurement will not be completed within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G.1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984.
D-1
These instruments are used in systems which are needed to satisfy the Technical Specifications and perform safety
. related functi ons.
The R.G.1.97 Compliance Report may outline modifications that could be performed at power or during scheduled refueling outages. Any modification requiring an outage will be implemented at the first occurring refueling outage following'the conpletion of the necessary design and procurement, These refueling outages are anticipated to be
,the Unit 1 sixth refueling outage and the Unit ? third refueling outage. Any modifications that could be performed at power will be implemented within 6 months after the completion of design and procurement' but no later than the Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Extension Request: The end of the Unit 1 sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
i D-2
E.
Parameters: Boric Acid Charging Flow Letdown Flow Anticipated Completion Dates:
Unit 1 Unit 2 R.G. 1.97 Compliance Report June 1984 March 1984 Installation 6th R.0.
3rd R.0.
Discussion: Alabama Power Company has performed an evaluation of the areas in which certain components of this instrumentation are located and has determined that these areas would be exposed to a radiation dose from post-accident recirculating fluids. APCo is determining the availabilityof environmental qualification test documentation and the total integrated radiation dose to which the component would be exposed based on its post-accident operating time. APCo will evaluate tne available test data and determine the qualification status of the instrumentation.
It is expected that certain components of this instrumentation will be determined to be located in a mild environment and will not be within the scope of 10CFR50.49. Any components that are determined not to be environmentally qualified will be replaced or modified (e.g., relocation or shielding) to establish its qualification. The need for modifications will be identified in the R.G.1.97 Compliance Reports.
The R.G.1.97 Compliance Report and resulting design and procurement will not be completed within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G. 1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984 This instrumentation is a portion of the Chemical and Volume Control System which is needed for power operation.
The R.G.1.97 Compliance Repnrt may outline modifications that could be performed at power or during scheduled refueling outages. Any modification requiring an outage will be implemented at the first occurring refueling outage following the completion of the necessary design and procurement. These refueling outages are anticipated to be the Unit I sixth refueling outage and the Unit 2 third refueling outage. Any modifications that could be performed at power will be implemented within 6 months after the completion of design and procurement but no later than the Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Extension Request: The end of the Unit 1 sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
E-1
F.
Parameters:
High Head Safety Injection System Flow Containment Hydrogen Concentration Auxiliary Feedwater Flow Reactor Coolant Pump Seal Injection Flow Anticipated Comnletion Dates:
Unit 1 Unit 2 R.G. 1.97 Compliance Report June 1984 March 1984 Installation 6th R.0.
3rd R.0.
Discussion: Alabama Power Company is performing an evaluation of the areas in which certain components of this instrumentation are located to determine if these areas would be exposed to a radiation dose from post-accident recirculating fluids.
If there is the potential for a barsh environment, Alabama Power Company will determine the availability of environmental qualification test documentation and the total integrated radiation dose to which the component would be exposed based on its post-accident operating time. The available test data will be evaluated to determine the qualification status of the i nst rumentation.
It is expected that certain components will be located in a mild environment and not subject to a post-accident radiation dose. The need for modifications will be identified in the R.G.1.97 Compliance Reports.
The R.G.1.97 Compliance Report and resulting design and procurement will not be completed within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G. 1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984.
The instrumentation is a portion of systems which are needed to satisfy the Technical Specifications and perform safety related functions.
ihe R.G.1.97 Compliance Report may outline modifications that could be performed at power or during scheduled refueling outages. Any modification requiring an outage will be implemented at the first occurring refueling outage following the completion of the necessary design and procurement. These refueling outages are anticipated to be the Unit 1 sixth refueling outage and the Unit 2 third refueling outage. Any modifications that could be performed at power will be implemented within 6 months after the completion of design and procurement but no later than the Unit I sixth refueling outage and the Unit 2 third refueling outage.
Extension Request: The end of the Unit 1 sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
F-1
G.
Parameter:
Charging System Flow Volume Control Tank Level Anticipated Completion Dates:
Unit 1 Unit 2 R. G. 1.97 Compliance Report June 1984 March 1984 Installation 6th R.0.
3rd R.O.
Discussion: Alabarea Power Company is performing an evaluation of the areas in which certain components of this instrumentation are located to determine if these areas would be exposed to a radiation dose from post-accident recirculating fluids.
If there is the potential for a harsh environment, Alabana Power Company will determine the availability of environmental qualification test documentation and the total integrated radiation dose to which the component would be exposed based on its post-accident operating ti me. The available test data will be evaluated to determine the qualification status of the instrumentation.
It is expected that certain components will be located in a mild environment and will not be within the scope of 10CFR50.49. The need for modifications will be identified in the R.G. 1.97 Compliance Reports.
The R.G.1.97 Compliance Report and resulting design and procurement will not be completed within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G. 1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984.
This instrumentation is a portion of Chemical and Volume Control System which is needed for power operation. The R.G.1.97 Compliance Report may outline modifications that could be perforned at power or during scheduled refueling outages. This instrumentation cannot be removed from service during power operation. Any modification requiring an outage will be implemented at the first occurring refueling outage following the completion of the necessary design and procurement. These refueling outages are anticipated to be the Unit 1 sixth refueling outage and the Unit 2 third refueling outage. Any modifications that could be performed at power will be implemented within 6 months after the completion of design and procurement but no later than Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Extension Request: The end of the Unit I sixth refueling outage and Unit 2 third refueling outage but no later than November 30, 1985.
G-1
H.
Parameter: Vent Radiation from Steam Generator Safety Valves and Atmospheric Relief Valves Vent Radiation from Turbine-Driven Auxilt.y Feedwater Pump Condenser Exhaust Radiation Plant Vent Effluent Radiation Plant Vent Effluent Flow Anticipated Completion Dates:
Unit 1 Unit 2 R. G.1.97 Compliance Report June 1984 March 1984 Installation 6th R.0.
3rd R.0.
Discussion: Alabama Power Company is performing an evaluation of the areas in which certain components of these instrumemtation are located to determine if these areas would be exposed to a radiation dose from post-accident recirculating fluids.
If there is the potential for a harsh environment, Alabama Power Company will determine the availability of environmental qualification test documentation and the total integrated radiation dose to which the component would be exposed based on its post-accident operating time. The available test data will be evaluated to determine the qualification status of the instrumentation.
It is expected that certain conponents will be located in a mild environment and will not be within the scope of 10CFR50.49. The need for modifications will be identified in the R.G. 1.97 Compliance Reports.
The vent radiation and flow instrumentation is needed to satisfy the Technical Specifications. This instrumentation can not be r_rraved from service during power operation.
The R.G.1.97 Compliance Report may outline modifications that could be performed at power or duririg scheduled refueling outages. Any modification requiring on outage will be implemented at the first occurring refueling outage following the completion of the necessary design and p rocurement. These refueling outages are anticipated to be the Unit 1 sixth refueling outage and the Unit 2 third refueling outage. Any modifications that could be performed at power will be implemented within 6 months after the completion of design and procurement but no later than Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Extension Request: The end of the Unit 1 sixth refueling outage and Unit 2 third refueling outage but no later than November 30, 1985.
H-1
r I.
Parameter:
Position of Emergency Vent Dampers Anticipated Completion Dates:
Unit 1 Unit 2 R.G.1.97 Compliance Report June 1984 March 1984 Installation 6th R.O.
3rd R.0.
Discussion:
Certain emergency damper position indicators are environmentally qualified and satisfy 10CFR50.49. This equipment is identified in previous submittals regarding environmental qualification. For other emergency vent damper position indicators, Alabama Power Company is performing an evaluation of the areas in which certain components of this instrumentation are located to determine if these areas would be exposed to a radiation dose from post-accident recirculating fluids.
If thera is the potential for a harsh environnent, Alabaco Power Company will determine the avcilability of environmental qualification test documentation and the total integrated radiation dose to which the component would be exposed based on its post-accident operating tine. The available test data will be evaluated to determine the qualification status of the instrumentation.
It is expected that certain components will be located in a mild environment and will not be within the scope of 10CFR50.49. The need for modifications will be identified in the R.G.1.97 Compliance Reports.
The R.G.1.97 Compliance Report and resulting design and procurement will not be completed within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G. 1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984.
This instrumentation forms a portion of the Containnent Ventilation and Penetratior. Roon Filtration Systems. These systems are addressed by Techncial Specifications and perform safety related functions. This instrumentation can not be removed from service during power operation. The R.G.1.97 Compliance Report nay outline modifications that could be performed at power or during scheduled refueling outages. Any modification requiring an outage will be implemented at the first occurring refueling outage following the completion of the necessary design and procurement. These refueling outages are anticipated to be the Unit 1 sixth refueling outage and the Unit 2 third refueling outage. Any modifications that could be performed at power will be implemented within 6 months after the completion of design and procurement but no later than Unit I sixth refueling outage and the Unit 2 third refueling outage.
i Extension Request:
The end of the Unit 1 sixth refueling outage and l
Unit 2 third refueling outage but no later than November 30, 1985.
1-1 i
J.
Parameter: Accumulator Tank Level Accumulator Tank Pressure Accumulator Tank Isolation Valve Position Anticipated Completion Dates:
Unit 1 Unit 2 R.G.1.97 Compliance Report June 1984 March 1984 Installation 6th R.0.
3rd R.0.
Discussion: Major conponents of this instrumentation, such as transmitters and cabling, are located in the containment.
Alabama Power Company is determining the availability of environmental qualification test documentation. Alabama Power Company will evaluate the available test data and determine the qualification status of the instrumentation.
It is 9xpected that certain compor.ents of the instrumentation will be determined to be located in a mild environrent and excluded for tne scope of 10CFR50.49. Any components that are determined not be be environmentally i
quaMfied will be replaced or modified (e.g., relocation or i
shielding) to establish its qualification. The R.G. 1.97 Compliance Reports will identify the need for any modifications.
The R.G.1.97 Compliance Report and resulting design and procurenent will not be conpleted within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G. 1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984.
This instrumentation is a portion of a system which is needed to satisfy the Technical Specifications and perform a safety function. No modifications to the existing system can be performed during power operation.
Installation of modifications is scheduled to be completed during the first occuring refueling outage following the development of design and completion of procurement. These refueling outages for installation are anticipated to be the Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Extension Request:
The end of the Unit 1 sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
J-1
K.
Parameter: Containment Atmosphere Temperature Anticipated Completion Dates:
Unit 1 Unit 2 R.G. 1.97 Ccmpliance Report June 1984 March 1984 Installation 6th R.0.
3rd R.0.
Discussion: Major ccmponents of this instrumentation are located in the contai nment. Alabama Power Company is determining the availability of environmental qualification test documentation. Alabama Power Company will evaluate the available test data and determine the qualification status of the instrunnntation.
It is expected that certain components of the instrumentation will be determined to be located in a mild environment and excluded for the scope of 10CFR 50.49. Any components that are determined not be be environmentally qualified will be replaced or modified (e.g., relocation or shielding) to establish its qualification. The R.G. 1.97 Compliance Reports will identify the need for any modifications.
The R.G.1.97 Compliance Report and resulting design and procurement will not be completed within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G.1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984.
This intrumentation is needed to satisfy the Technical Specifications during power operation. No modifications to the existing system can be performed during power operation.
Installation of any modifications is scheduled to be completed during the first occurring refueling outage following the development of design and completion of procurement. These refuelirg outages for installation are anticipated to be the Unit I sixth refueling outage and the Unit 2 third refueling outage.
Extension Request: The end of the Unit 1 sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
K-1
L.
Parameters:
Containment Isolation Valve Position Anticipated Completion Dates Unit 1 Unit 2 R.G.1.97 Compliance Report June 1984 March 1984 Installation 6th R.0, 3rd R.0.
Discussion: Certain containment isolation valve position indicators are environmentally qualified and satisfy 10CFR50.49. This equipment is identified in previous submittals regarding environmental qualification. Alabama Power Company is performing an evaluation of these areas in which certain components of this instrumentation are located to determine if these areas would be exposed to a radiation dose from post-accident recirculating fluids.
If there is the potential for a harsh environment, Alabama Power Company will determine the availability of environmental qualification test documentation and the total integrated radiation dose to which the component would be exposed based on its post-accident operating time. The available test data will be evaluated to determine the qualification status of the instrumentation.
It is expected that certain components will be located in a mild environment and not subject to a post-accident radiation dose. The need for modifications will be identified in the R.G.1.97 Compliance Reports.
The R.G.1.97 Compliance Report and resulting design and procurement will not be completed within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G.1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984.
The instrumentation is a portion of systems which are needed to satisfy the Technical Specifications and perform a safety related function. This instrumentation can not be removed from service during pwer operation. The R.G. 1.97 Compliance Report may outline modifications that could be performed at power or during scheduled refueling outages.
Any modification requiring an outage will be implemented at the first occurring refueling outage following the completion of the necessary design and procurement. These refueling outages are anticipated to be the Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Any modifications that could be performed at power will be implemented within 6 months after the completion of design and procurement but no later than the Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Extension Request: The end of the Unit 1 sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
L-1
~
M.
Parameter:
Post-Accident Sampling System to Determine Reactivity Concentration of Reactor Coolant Anticipated Completion Dates:
Unit 1 Unit 2 R.G.1.97 Compliance Report June 1984 March 1984 Installation 6th R.0.
3rd R.0.
Discussion:
Certain components of the post-accident sampling system are environmentally qualified and satisfy 10CFR50.49. This qualified equipment is identified in previous submittals regarding environmental qualification. For the other components of the post-accident sampling system, Alabama Power Company is performing an evaluation of the area in which certain components of this instrumentation are located to determine if this area would be exposed to a harsh environment.
If there is the potential for a harsh environment, Alabama Power Company will determine the availability of environmental qualification test documentation. The available test data will be evaluated to determine the qualification status of the 1
inst rumentation.
It is expected that certain components will be located in a mild environment and not excluded from 10CFR50.49. The need for modifications will be identified in the R.G. 1.97 Compliance Reports.
The R.G.1.97 Compliance Report and resulting design and procurement will not be completed within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G. 1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984.
The instrumentation is a portion of equipment which is needed to satisfy the Technical Specifications and perform a safety related function. The R.G.1.97 Compliance Report may outline modifications that could be performed at power or during scheduled refueling outages. Any modification requiring an outage will be implemented at the first occurring refueling outage following the completion of the necessary design and procurement. These refueling outages are anticipated to be the Unit I sixth refueling outage and the Unit 2 third refueling outage. Any modifications that could be performed at power will be implemented within 6 months after the completion of design and procurement but no later than the Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Extension Request: The end of the Unit 1 sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
M-1
N.
Parameter:
Steamline Pressure Anticipated Completion Dates:
Unit 1 Unit 2 R.G.1.97 Compliance Report June 1984 March 1984 Installation 6th R.0.
3rd R.0.
Discussion: Alabama Power Company is performing an evaluation of the aria in which certain components of this instrumantation are located to der. ermine if this area would be exposed to a harsh environment.
If there is the potential for a harsh environment, Alabama Power Company will determine the availability of environmental qualification test documentation. The available test data will be evaluated to determine the qualification status of the instrumentation.
It is expected that certain components will be located in a mild environment and excluded from 10CFR50.49. The need for modifications will be identified in the R.G.1.97 Compliance Reports.
The R.G.1.97 Compliance Report and resulting design and procurement will not be completed within the schedule of 10CFR50.49 for Units 1 and 2.
The R.G. 1.97 Compliance Report will be prepared in March 1984 for Unit 2 and June 1984 for Unit 1.
The "second refueling outage after March 31, 1982" specified by 10CFR50.49 is the Unit 2 second refueling outage scheduled to end October 1983 and the Unit 1 fifth refueling outage scheduled to end April 1984 The instrumentation is needed to satisfy the Technical Specifications. The R.G. 1.97 Compliance Report may outline modifications that could be performed at power or during scheduled refueling outages. Any modification requiring an outage will be implemented at the first occurring refueling outage following the completion of the necessary design and procurement. These refueling outages are anticipated to be the Unit 1 sixth refueling outage and the Unit 2 third refueling outage. Any modifications that could be performed at power will be implemented within 6 months after the completion of design and procurement but no later than the Unit 1 sixth refueling outage and the Unit 2 third refueling outage.
Extension Request: The end of the Unit I sixth refueling outage and the Unit 2 third refueling outage but no later than November 30, 1985.
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Accident Monitoring Equipment Presently Environmentally Qualified Steam Generator Level Main Steam Flow Narrow and Wide Range Containment Sung Level Pressurizer Level Narrow Range Containment ECCS Sump Level Pressurizer PORV Position Wide Range Indication Pressurizer Safety Valve Reactor Coolant System Hot Position Indication Leg Temperature Wide Range Emergency Damper Position Indication Reactor Coolant System Cold 4
i Leg Temperature Wide Range Containment Area Radiation Reactor Coolant System Extended Range Pressure Wide and Narrow Range Containnent Isolation Valve Position Indication n
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