ML18283B721
| ML18283B721 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/16/1976 |
| From: | Purple R Office of Nuclear Reactor Regulation |
| To: | Gerald Williams Tennessee Valley Authority |
| References | |
| Download: ML18283B721 (22) | |
Text
Docket iioe. (~A and 50-260 fennossce Valley Authority A'1TN:
Mr. Godwin 17illiams, Jr..
Manager of Power 818 Po>>'cr Building Chattanooga, Tcnncssce 37201 Gentlemen:
April 16, 1976 DISTRIBUTION:
Docket File (2)
ORB¹l Rdg RAPurple TV!(ambach SMSheppard KRGoller TJCarter OELD OI 444E (3)
ACRS (16)
BJones (8)
BScharf (10)
JMCGough JSaltzman OTBr. Chiefs 8
- CMiles, OPA TBAbernathy JRBuchanan The Commission has issued tho enclosed Amendments No.21 and 18 to Facility Licenses No. DPR-33 and DPR-5 for the Bro>nis Ferr>
Nuclear Plant, U>>its 1 and 2.
These anendme>>ts consist of cl)angcs to the Tcchnical Specifications and are in response to your roquest of April 9,'976.
'1'hcse arne>>dments revise the Interin Technical Specifications to allo@
renioval of thc canal gate and throe canal blocks in order to allow safo transfer of the neutron sources from the rc"ctor vessel to t!~e fuel storago pool.
Alternate methods to protect against possible loss of spent fuel pool >>ater through a leak in thc primary coolant system or in other systems connected thereto are required by these amendments when the canal gates a>>d plugs are not in place.
Copies of the Safety Evaluation and thc Fcdcral Register Notice are also enclosed.
Sincerely,
/s/
R. A. Purple Robert A. Purple, Chief.
Operating Reactors Branch ¹I Division of Operating Pcactors Enclosuros:
l.
Amcndmc>>t No. 21 to DPR-33 2.
'GlaendmIcnt No. 18 to Dpi 52 3.
Safety Evaluation 4.
Federal Register Notice n ~oz.o~yo /vs iI /( I.'5C A" OTFICK+
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Tennessee Valley Authority April 16, 1976 cc w/enclosures:
H. S. Sanger
'eneral Counsel 629 New Sprankle Building Knoxville, Tennessee 37919 Athens Public Library South and Forrest
- Athens, Alabama 35611 her. william E. Garner Route 4, Box 354 Scottsboro, Alabama 3576S blr. Thomas Lee Hammons
- Chairman, Limestone County Board of Revenue
- Athens, Alabama
. 35611 cc w/enclosures and incoming:
Ira L. ltyers,
<f.D.
State Health OfEicer State Department oE Public Health State Office Building Montgomery, Alabama 36104
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 I. ~ ~
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BRONNS FERRY NUCLEAR PLANT UNIT 1 AtIENRIENT TO FACILITY OPERATING LICENSE Amendment No. 21 License No.
DPR-33 1.
The Nuclear. Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 9,
- 1976, complies with the standards and requirements of the Atomic Energy Act of
- 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
An environmental statement or negative declaration need not be prepared in connection with the issuance of this amendment.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment.
3.
This license amendment is effective as of the date of issuance.
FOR %K NUCLEAR REGULATORY COi~MISSION Robert A. Purple, Chief Operating Reactors Branch Pl Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 16, 1976
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UNITED STATES NUCLEAR REGULATORY COMMISSlON WASHINGTON, D. C. 20555
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TENNESSEE VALLEY AUTHORITY DOCKET NO.
SO-260 BR01@fS FERRY NUCLEAR PL%MT UNIT 2 AhKNDbiENT TO FACILITY OPERATING LICENSE Amendment No. 18 License No.
DPR-S2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated April 9,
- 1976, complies with the standards and requirements of the Atomic Energy Act of
- 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities >>ill be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
An environmental statement or negative declaration need not be prepared in connection with the issuance of this amendment.
2.
Accordingly, the license is amended by a change to the Technical Specifications as indicated in the attachment to this license amendment.
2-3.
This license amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COh&fISSION Robert A. Purple, Chief Operating Reactors Branch tl Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 16, 1976
ATTACHMENT TO LICENSE fQKNDMENTS AMENDMENT NO.
21 TO FACILITY LICENSE NO.
DPR-33 AhKNRFNT NO.
18 TO FACILITY LICENSE NO.
DPR-S2 DOCKET NOS.
50-259 6 50-260 Revise Appendix A as follows:
Remove pages
- 131a, 133, 133a and 146 and insert revised identically numbered pages.
'IIMITING CONDITIONS FOR OPERATION SURVEI LLAYCE REOUIREME'TS fied in 3.5.C.1.
01han a fuel pool cooling pump is required to bc. opera-ting or as a backup, the associated RBCCWS loop and service water system must be functi.onal.
3.
Whenever irradiated fuel is stored in the fuel pool, the gates on the fuel transfer canal between unit 1 and unit 2 shall be left in place and the transfer canal drain valves 1-78-561 and 1-78-562 shall be shut.
The fuel pool gates between the fuel pools and the reactor cavities shall be installed with the canal blocks in place, except as specified in 3.5.C.4.
4.
i&en it is necessary to transfer radioactive components through the canal, the fuel pool gate and three canal blocks may be temporarily removed from between the reactor vessel and the fuel pool, provided at least one block is left in the canal and the over-head crane is available and rigged to the second canal block of the affected unit. If at any time when the canal blocks are removed, the fuel pool level drops to the low level alarm, all canal blocks and the fuel pool gate shall be reinserted and normal SFSP water level reestablished and the cause of the low level determined and corrected.
Amendment iVos. 21, 18 April 16, 1976
l t.Z><ITrhc CONOrrZONS FOR OPERATZO, SUr.VETLLANCr. PZ";i Vr, EATS g,5 CORl'.
CONTATt,"MENT AND FUEL POOE COOLTNC SYSTE~tS 4.5 CORi~ CO'TAC:nrNT AN@ FU~'.L POO COOLING SYSTPifS Each pump muat run continuouzly with its loss ox voltage'trips deactivated or it shall be cap-able of automatic start in its normal D/G load sequencing mode of operation.
Each pump on the same header shall be assigned to a separate diesel power supply.
3,'outine surveillance for an
'tem a,
Fump opera-bility
~Fre uencv Upon resto=.
tion:
and monthly thc:
after if no'.
in continuo:
service.
operating or backup RHR or fuel pool cooling pump is as follows:
b, Motor-oper-ated valve operability Upon restor-tion and monthly thc.
after 4
whenever the fuel pool gate is removed from the canal, an operator will'e stationed on the reruel floor to continu-ously observe the fuel pool level.
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Hhenever irradiated fuel is stored in the spent fuel pool, two independent flow paths for
. water mal;e up to the spent fue1'ool will be available from two RHRSff pumps, capable of being supplied by separate dies 1
. power.
Amendment Nos.
21, 18 April 16, 1976
LZIITZfG CONDXTlOIJS =OR OPERATZOI'I SK3VETLLVICE REQ'L~~
TFiS RHR Service Mater Svstem (RIIR~SHS And Emer enc Eouinment Coolin~
Mater S stem EECWS 1.
RIIR Service Mater System
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Each oZ the required RIIRSM pumps and associated essential control valves on the RIIR heat exchanger head rs shall be demonstrated to be functional upon restoration and once every month thereafter if not in continuous service.
333a Amendment Nos.
21, 18 April 16 1976
GASES:
CORE Cpt;TAImf nrm FUl:.L r 0nL CnnLt;Ã; SYST 3 5 C
S ent Fuel Pool Coolin continued The gates and all the blocks except one may be removed from the canal between the spent fuel storage pool and the reactor cavity to allow transfer of the sources from the cavity into the pool.
When the blocks and gates are removed, the overhead crane will be rigged to the second block ready to install it into the canal in the unlikely event that a low level in the spent fuel storage pool occurs.
The addition of the second block will prevent the water level from dropping to within 8 1/2 feet of the top of the fuel.
(Refer to Bases 3.10/4.10).
The decay heat removal requirements for. a full core stored in the fuel pool can be conservatively met by the operation of one RHR pump and its associated"RHR heat exchanger in the fuel pool cooling mode.
The total heat load for this mode is estimated to be less than 20 percent of the heat exchanger capability under the required flow and temperature conditions.
Amendment Nos. 21,. 18 April 16, 1976
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
21 TO FACILITY LICENSE iNO. DPR-33 AND A&lENzDilENT NO. 18 TO FACILITY LICENSE NO DPR-52 TENNESSEE VALLEY AUTHORITY BROlPiJS FERRY NUCLEAR PLAiNT UNITS 1
AND 2 DOCKET NOS.
50-259 AND 50-260 Introduction By letter dated April 9,
(BFNP), applied for amendments to licenses DPR-33 and DPR-52 to change the Technical Specifications for Units 1 and 2 'to allow removal of three canal blocks and the canal gate bet>>cen the spent fuel pool and the reactor vessel.
Subsequent to the March 22, 1975 fire, the Technical Specifications for Units 1 and 2 were changed to take into account the conditions of equ'p-ment and systems at the plant and specified requirements to ensure that the fuel would be safely maintained in a stored,
- shutdown, cooled condi-tion (Ref.
1, 2 and 3).
Because of the conditions in the. plant at that time and the planned activities to return the plant to an operable status, additional precautionary measures were required by these Interim Technical Specifications.
Among these was the requirement to have the canal gate and the canal shield blocks in place between the spent fuel pool and the reactor vessel to prevent loss of pool water through drainage or leakage during restoration and testing of systems connected to the primary coolant system.
The licensee now must remove. the neutron sources from the Unit 1 reactor to send them to Oak Ridge National Laboratory for reactivation.
In order to accomplish this the sources must be transferred from the vessel to the spent fuel pool where the shipping cask is located.
The sources must be kept under water to shield the operator.
This requires use of the transfer canal.
2-Evaluation
+a Whenever the canal gate and blocks are not in place, the licensee proposes to station an operator on the refuel SI'oor to continuously observe the water level in the fuel pool and to immediately take corrective action if the water level should start decreasing.
A canal block will be rigged to the overhead crane and can be lo>>ered into place in a Sew minutes.
Even if the water level should drop to the top of this canal block, it would still be above the 8-1/2 feet of water required over the top of the stored fuel. If this canal block were not put in place, at least 5 feet of water would remain above the spent fuel and at least 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> >>ould be available to install the blocks and gate or provide supplemental cooling before the spent fuel pool water >>ould reach the boiling point.
Ye find that this alternative method for preventing excessive loss of spent fuel pool water through leakage or drainage from the primary coolant system during the limited time needed to pass radioactive components through the canal satisfactorily compensates Sor the removal of canal blocks and canal gate and allo>>'s the neutron sources to be safely handled for offsite shipment.
4'e have determined that the amendments do not authorize a change in effluent typos or total amounts nor an increase in power lovel and >>ill not, result in any significant environment"1 impact.
slaving made this determination, we have further concluded that the amendmcnts involve an action >>hich is insignificant from the standpoint of environmental impact a>>d pursuant to 10 CFR 551.5(d)(0) that an environmental statement, negative declaration, or environmental impact appraisal need not he prepared in connection with the issuance of the amendments.
Conclusion ice have concluded, based on the consideratons discussed above, that:
(1) because the change does not involve a significant increase in the probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin, the change does not involve a significant ha"ards consideration, (2) there is reasonable assurance that the health and safety of the public >>ill not be endangered by operation in'he proposed
- manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments >>ill not be inimic"1 to the common defense and security or to the health and safety of the public.
References (1) Amendments 9 to DPR-33 and 6 to DPR-52 dated May 9, 1975 and accompanying
7 to DPR-52 dated June 13, 1975 and accompanying SER.
(3) Amendments 18 to DPR-33 and 15 to DPR-52 dated December 19, 1975 and accompanying SER.
Date..April 16, 1976
UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NOS.
50-259 AND 50-260 TENNESSEE VALLEY AUTiiORITY NOTICE OF ISSUANCE OF AMENDiEATS TO FACILITY OPERATING LICENSES Notice is hereby given that the U. S. Nuclear".,Regulatory Commission (the Commission) has issued Amendment No. 21 to Facility Operating License V
No.
DPR-33 and Amendment No,'18 to Facility Operating License No.
DPR-52 issued to Tennessee Valley Authority (the licensee) which revised the Technical Specifications of the Browns Ferry Nuclear Plant, Units 1 and 2, located in Limestone County, Alabama.
The amendments are effective as of the date of issuance.
These amendments revise the interim Technical Specifications to allow removal of the canal gate and three canal blocks in order to allow safe transfer of the neutron sources from the reactor vessel to the fuel storage pool.
Alternate methods to protect against possible loss of spent fuel pool water through a leak in the primary coolant system or in other systems connected thereto are required by these amendments when the canal gates and plugs are not in place.
The application for these amendments complies with the standards and "
requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.
Prior public notice of these amendments was not required since the amendment do not involve a significant hazards consideration.
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The Commission has determined that the issuance of these amendments
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will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental statement, negative declaration, or environmental impact appraisal need not be prepared in connection with issuance of these amendments.
For further details with 'respect to this action, see (1) the application f
for amendments dated April 9,
- 1976, (2) Amendment No. 21 to License No.
DPR-33 and Amendment No.
18 to License No. DPR-52, and (3) the Commission's related Safety Evaluation.
All of these items are available for public inspection at the Commission's Public Document
- Room, 1717 H Street, N. N.
1'tashington, D.
C.
- 20555, and at the Athens Public Library, South and
- Forrest, Athens, Alabama 35611.
A copy of items (2) and (3) may be obtained upon request addressed to the U. S. Nuclear Regulatory Commission, ii'ashington, D. C.
- 20555, Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, bfaryland, this 16th day of April 1976 FOR THE NUCLEAR REGULATORY CO:D/lSSION 4 ~
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Robert A. Purple, Chi f Operating Reactors Branch
~1 Division of Operating Reactors