ML18031B133
| ML18031B133 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/14/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Muller D NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation |
| References | |
| GL-83-28, NUDOCS 8701210253 | |
| Download: ML18031B133 (8) | |
Text
ACCESSION NBR FAC IL: 50-259'0-2SO 50-29m AUTH. NAME QRI DLEY> R.
RECIP. NAME MULLER> D. R.
REGULATOR NFORMATION DISTRIBUTION 'S EM (RIDS) 8701210253 DOC. DATE: 87/01/14 NOTARIZED:
NO DOCKET Brains Ferry Nuclear Pouer Station>
Unit 1>
Tennessee 05000259 Brogans Ferry Nuclear Pouer Station>
Unit 2.
Tennessee 05000260 Brogans Ferry Nuclear Pouer Station>
Unit 3>
Tennessee 0500029lI>
AUTHOR AFFILIATION Tennessee Valley Authority RECIPIENT AFFILIATION Record Services Branch (Document Control Desk)
Office of Nuclear Reactor Regulation>
Director (post 851125
SUBJECT:
Fortoards response to 861107 request for addi info re Items
- 2. 2. 1. 3 Zc 2. 2. 1. 5 of Generic Ltr 83-28. Util nuclear review program currently being upgraded to resolve Item 2. 1.
Responses to Item 2. 1 vill be provided blj 870330.
DISTRIBUTION CODE:
AOBBD COPIES RECEIVED: LTR ~ ENCL J SIZE:
TITLE: OR/Licensing Submittal:
Salem ATWS Events GL-83-28 NOTES: NMSS/FCAF ice.
NMSS/FCAF/PM 1c g.
OIA 1 cg.
NMSS/FCAF icy.
NMSS/FCAF/Pl'l icy. OI* icy.
NMSS/FCAF ice.
NMSS/FCAF/PM 1 c g.
OIA 1 cg.
0500025'7 05000260 05000296 RECIPIENT ID CODE/NAME BNR *DTS BNR ElCSB BNR PD2 LA QROTENHUl8> M BNR RSB INTERNAL: ACRS ELD/HDS4 IE/DGAVT NRR PWR-A ADTS NRR TOALSTON A NRR/TAMB Cor IES LTTR ENCL 1
1 2
2 1
0 1
1 1
6 6
1 0
1 1
1 1
1 1
1 REC IP IENT ID CODE/NAME BWR EB BWR FOB BWR PD2 PD 01 BNR PSB ADN/LFMB IE/DI NRR LASHER> D NRR P WR-B ADTS NR ~AS SIR G F 04 COPIES LTTR ENCL
~ 1 1
1 1
3 3
1 1
0 1
1 1
1 1
EXTERNAL: LPDR NSIC NOTES:
03 05 1
1 1
1 NRC PDR 02 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 36 ENCL 33
r
~
I t
I IH t'
TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 57B Lookout Place JAM 14587 U.S. Nuclear Regulatory Commissi n Attn:
Document Control Desk Office of Nuclear Reactor Regulat on Washington, D.C.
20555 Attention:
Mr. D. R. Muller In the Matter of Tennessee Valley Authority Docket Nos. 50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) REQUEST FOR ADDITIONAL INFORMATION GENERIC LETTER 83-28 As requested by letter from M. Grotenhuis to S. A. White dated November 7,
- 1986, we are submitting the enclosed information regarding Generic Letter 83-28 for BFN.
The above letter requested additional information on responses transmitted in TVA's letter dated November 7, 1983 to items 2.1 (part 2),
2.2.1.3 and 2.2.1.5.
TVA's Nuclear Experience Review program is currently being upgraded which is intended to resolve item 2.1 (part 2).
Therefore, responses to questions regarding this item will be provided when this program is finalized.
This additional information will be provided by March 30, 1987.
Very truly yours, TENNESSEE VALLEY AUTHORITY R.
- ridley, rector Nuclear Safety and Licensing Enclosure cc:
See page 2
8701210253 8701140 DR ADOCK 05000259 P D~R
. 'n Equal Opportunity Employer
U.S. Nuclear Regulatory Commission JAN 1C )887 cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II Attn:
Dr. J.'elson
- Grace, Regional Administrator 101 Marietta Street, NM, Suite 2900 Atlanta, Georgia 30323 Mr. G. E. Gears Browns Ferry Project Manager U.S, Nuclear Regulatory Commission 7920 Norfolk Avenue
- Bethesda, Maryland 20814 Mr. G.
G. Zech, Director TVA Projects U.S. Nuclear Regulatory Commission 101 Marietta St.,
NM, Suite 2900 Atlanta, Georgia 30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant P.O.
Box 311
- Athens, Alabama 35611
ENCLOSURE
RESPONSE
TO REQUEST FOR INFORMATION DATED NOVEMBER 7, 1986 Generic Letter 83-28 ITEM 2.2.1.3 A description of the process by which station personnel use this information handling system to determine that an activity is safety-related and what procedures for maintenance, surveillance, parts replacement, and other activities defined in the introduction of 10 CFR 50, Appendix B, apply to safety-related components.
RE UEST FOR ADDITIONALINFORMATION We request that the licensee describe in detail the procedural path that leads all personnel involved in any safety-related activity to the identification of that activity as safety-related and also the appropriate instructions to be followed in performing the activity.
Describe each of the different procedural paths required for different types of safety-related activities.
RESPONSE
Before the start of an activity station personnel would routinely utilize the CSSC list or a specific analysis to determine whether the activity affects safety-related equipment.
From that point, an appropriate procedure (e.g.,
maintenance, procurement, modifications, etc.) is required to carry out the activity if it affects such equipment.
This requirement. is contained in BFN Quality Assurance Program and the technical specifications and encompasses the activities listed in the introduction to 10 CFR 50 Appendix B.
When applied to CSSC components these procedures would specify the applicable requirements or other procedures unique to activities affecting CSSC components.
This basic path does not vary substantively among different types of activities.
~ e J
I
ITEM 2.2.1.5 A demonstration that appropriate design verification and qualification testing is specified for procurement of safety-related components.
The specifications shall include qualification testing for expected safety service conditions and provide support for the licensees'eceipt of testing documentation to support the limits of life recommended by the supplier.
RE VEST FOR ADDITIONAL INFORMATION We request that the licensee confirm that the specifications for safety related components contain appropriate requirements for design verification, qualification testing and testing documentation.
f ll A.
RESPONSE
II
'8 BFN procurement procedures require that CSSC,.components (critical systems, structures, and components) be procured to the original design specifications or an approved revision to those specifications to obtain the appropriate technical and quality requirements for inclusion in a procurement request.
These procedures also require various contract and engineering reviews be performed after a request is originated to ensure the proper technical and quality requirements are specified.
These specifications 'would~-as appropriate, include design verification, qualification testing for expected safety service conditions, and documentation to support the vendor's compliance with these requirements.-.-