ML20039D567
| ML20039D567 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/29/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8201050216 | |
| Download: ML20039D567 (2) | |
Text
._
r TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 4
400 Chestnut Street Tower II g
December 29, 1981 ggg Director of Licensing JAN 5 198 > F
( $N"g
'8 Attention:
Mr. Thomas A. Ippolito, Chier Operating Reactors Branch No. 2 U.S. Nuclear Regulatory Commission 710C g
Washington, DC 20555
Dear Mr. Ippolito:
In the Matter of the
)
Docket Nos. 50-259 Te.nnessee Valley Authority
)
50-260 By letter from T. A. Ippolito to H. G. Parris dated September 3, 1981, NRC issued Amendment Nos. 75 and 72 to licenses DPR-33 and DPR-52 for the Browns Ferry Nuclear Plant units 1 and 2.
These amendments were issued in response to TVA request for license amendment TVA BFNP TS 156 concerning undervoltage corrective modifications at Browns Ferry units 1 and 2.
During review of TS 156, the NRC staff raised a concern regarding the testing of the diesel generator load sequencers associated with loads from unit 2.
Information intended to resolve that concern was submitted by my letter to H. R. Denton dated July 2, 1981. However, that information did not resolve the NRC staff's concern since it was reflected in the Safety Evaluation Report accompanying the subject license amendments.
The enclosure provides additional information which we believe will resolve that concern. The additional information consists of clarification of the surveillance testing presently done on the Browns Ferry diesel generators. In view of the enclosed clarification it is TVA's firm position that we meet the intent and requirements of 10 CFR Part 50 Appendix A, General Design Criteria 18.
Very truly yours, TENNESSEE VALLEY AUTHORITY LTM.Mi).1lls,l M 3
4anager Nuclear Regulation and Safety SubscribeAgnd worn to ber ce
.me this o(7 day of 1981.
Bankfe 2. %dux Notary Public
~
My Commission Expires Enclosure L
'8201050216 811229 g, g PDR ADOCK 05000259
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PDR An Equal Opportunity Employer
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ENCLOSURE RESPONSE TO NRC STAFF CONCERNS REGARDING TESTING OF UNIT 2 DIESEL GENERATOR LOAD SEQUENCERS BROWNS FERRY NUCLEAR PLANT UNITS 1 AND 2 (DOCKET NOS. 50-259 AND 50-260)
It is TVA's opinion that the intent of General Design Criteria '(GDC)-18 is to demonstrate the operability of the electric power system as a whole and under conditions as close to design as practical. GDC-18 does not address the systems which are powered by the electric power system. Our Surveillance Instruction (SI) 4.9.A.1.b meets the intent and requirements of GDC-18.
SI 4.9.A.1.b provides verification that each diesel generator will start and accept its assigned load when called upon by a simultaneous loss of shutdown. power.and an accident signal. This test concerns only the operation of the diesel generators and is not intended to prove.
operability of any of the emergency core cooling system equipment. This test for units 1 and 2 diesel generators uses, unit 1 equipment only as loads.
The unit 1 equipment used as the loads during SI 4.9.A.1.b are the residual heat removal (RHR) pumps, core-spray pumps, and RHR service water pumps. This equipment is not tested during the SI.
Only the diesel generator is tested.
The equipment is tested under SI's 4.2.B.39, 4.2.B.45, 4.5.B.1.a, 4.9.A.3.a, 4.5.A.1.a, and 4.2.B.14, previously described in TVA letter from L. M. Hills to H. R. Denton dated July 2, 1981. These tests also verify the operability of all load sequencing relays. These SI's are performed on both unit 1 and unit 2 equipment.
In view of the clarification provided that only the diesel generator load acceptance is tested by SI 4.9.A.1.b and that units 1 and 2 safety systems loads are tested independently, TVA's position remains firm that we meet the intent and requirements of GDC-18.