ML19209B725
| ML19209B725 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/26/1979 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910100360 | |
| Download: ML19209B725 (6) | |
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s TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II September 26, 1979 TVA BFNP TS 127 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Washington, DC 20555
Dear Mr. Denton:
In the Matter of the
)
Docket No. 50-296 Tennessee Valley Authority
)
As a supplescent to the requested amendment to license DPR-68 submitted by my letter to you dated August 6, 1979 (TVA BFNP TS 127),
we are enclosing 40 copies of an additional requested C mge to the Technical specifications of Browns Ferry Nuclear Plant unit 3 (Enclosure 1). Also enclosed are 60 copies of the justification for the proposed changes (Enclosure 2).
Approval of this proposed change is requested on a schedule consistent with TVA BFNP TS 127.
Because this single additional requested change is directly connected with the modification work to be done as part of requested technical specification change TVA BFNP TS 127, we believe that the license review fees of $4,000 submitted with that request adequately covers any review of this supplement found to be necessary. Accordingly, we are not forwarding any additional fees with this supplement.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Subscribed and sworn to before me this 06 day ol M /j - 1979.
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Notary Public
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My Comission Expires k.
/O Enclosures j l } L(
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cc See page 2 An Equal Opportumty Employer 7 910100
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s Mr. Harold R. Denton September 26, 1979 cc '.Pelosures):
Mr. Charles R. Christopher Chairman, Limestone County Commission P.O. Box 188 Athens, Alabama 35611 Dr. Ira L. Myers State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36104 i135 354
4 ENCLOSURE 1 1135 355
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TABLE 3 7.0 CHECK VALVES 0:1 DRrJELL II.7LUE:IT LII SS Valve Test Valves Identification Medium 3-554 Feedwater Air 3-558 Feedaater Air 3-568 Feed,mter Air 3-572 Feedwater Air 63-525 Standby Liquid Control Air Discharge 63-526 Standby Liquid Control Air Discharge 69-579 m:CU Return (Feedwater Line E)
Air l 69-624 miCU Return (Feedwater Line A)
Air 71-40 RCIC Pump Discharce Air 73-45 HPCI Pu=p Liccharge Air 85-576 CRD Hydraulic Return Air 281
ENCLOSURE 2 1135 357
JUSTIFICATION FOR ADDITIONAL REQUESTED CHANGE TO BROWNS FERRY NUCLEAR PLANT UNIT 3 TECHNICAL SPECIFICATIONS In Reference 1, General Electric (GE) discusses several mechanisms responsible for initiation and growth of cracks in BWR vessel feedwater nozzles and presents recommendations to provide increased margin against such crack initiation and proparation. One recommendation is to modify the Reactor Water Cleanup (RWCU) System return piping so that the return flow is distributed equally among the feedwater lines. This modification will allow feedwater at low flow rates to be mixed with the higher temperature EWCU return water, thereby lessening the thermal cycling on the feedwater nozzle and the consequent thermal fatigue.
TVA plans to perform this modification on Browns Ferry unit 3 during its current major maintenance and refueling outage. Because this modification entails the addition of a check valve, this technical specification change request is needed to revise Table 3.7.G to include the required check valve.
L 9
Reference:
1.
General Electric Company Service Information Letter No. 208, Revision 1,
" Minimizing Feedwater Nozzle Thermal Duty," dated October 1978.
5 358
4 ENCLOSURE 1 1135 359
TABLE 3.7.G CHECK VALVES C:I LPJn' ELL 1:r/LUE:IT LI!iES Valve Test Valves Identification Medium 3-554 Feednter Air 3-558 Feedwater Air 3-568 Feedwater Air 3-572 Feedvater Air 63-525 Standby Liquid Control Air Discharge 63-526 standby Liquid Control Air Discharge 69-579 wCU Return (Feedwater Line E)
Air l 69-624 E'dCU Return (Feedwater Line A)
Air 71-40 RCIC Pu=p Diccharge Air 73-45 HPCI Pump Liccharge Air 85-576 CRD Hydraulic Return Air 281 1135 360
0 ENCLOSURE 2 1135 361
JUSTIFICATION FOR ADDITIONAL REQUESTED CHANGE TO BROWNS FERRY NUCLEAR PLANT UNIT 3 TECHNICAL SPECIFICATIONS In Reference 1, General Electric (CE) discusses several mechanisms responsible for initiation and growth of cracks in BWR vessel feedwater nozzles and presents recommendations to p rovide increased margin against such crack initiation anJ propagation. One recommendation is to modify the Reactor Water Cleanup (RWCU) System return piping so that the return flow is distributed equally among the feedwater lines. This modification will allow feedwater at low flow rates to be mixed with the higher temperature RWCU return water, thereby lessening the thermal cycling on the feedwater nozzle and the consequent thermal fatigue.
TVA plans to perform this modification on Browns Ferry unit 3 during its current major maintenance and refueling outage. Because this modification entails the addition of a check valve, this technical specification change request is needed to revise Table 3.7.G to include the required check valve.
Reference:
1.
General Electric Company Service Information Letter No. 208, Revision 1,
" Minimizing Feedwater Nozzle Thermal Duty," dated October 1978.
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