ML18031A974
| ML18031A974 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 11/07/1986 |
| From: | Grotenhuis M Office of Nuclear Reactor Regulation |
| To: | White S TENNESSEE VALLEY AUTHORITY |
| References | |
| GL-83-28, NUDOCS 8611120368 | |
| Download: ML18031A974 (6) | |
Text
November 7, 1986 Dockets Nos. 50-259/260/296 Mr. S. A. White Manager of Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
Dear Mr. White:
Distribution OG.
LSpesserd GZech, RII NRC 8
LPDRs SNorris RBernero OIA EJordan MGrotenhuis BGrimes
- SPWeise, RII ACRS (10)
Plant'ile HThompson HDenton JPartlow SRichardson,IE RClark
- JTaylor, IE SRConnelly,
- BHayes, OI NGrace, RII WECampbell BJYoungblood JHolonich CStahle TKenyon WLong TAlexion FCantrell RWessman AToalston DLasher MSrinivasan RE:
BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2, AND 3 By letter dated November 7, 1983 you responded to Generic Letter 83-28.
We have completed our review for items 2. 1 (Part 2) Vendor Interface Program and 2.2. 1 (Part 1) Equipment Classification (Program for All Safety Related Components).
Based on our review we find that we need the additional information described in the enclosure to this letter.
Please respond to the request for information in the enclosure or provide a
schedule for your response within 60 days of the receipt of this letter.
The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.
Sincerely,
Enclosure:
As stated cc w/enclosure:
See next page marshall Grote uis, Project Manager BWR Project Directorate ¹2 Division of BWR Licensing DB :PD¹2 SN is 10/cP+86 DBL:PD¹2 MGrotenhuis;jch 1$/ ) /86 D
PD¹2 G
s
/86 MN'~
18/7 /86 Sb111203ba Sbii07 PDR ADOCK 05000259 P
f 1
Mr. S. A. White Tennessee Valley Authority Browns Ferry Nuclear Plant Units 1, 2, and 3
CC:
General Counsel Tennessee Valley Authority 400 Commerce Avenue
- E 11B 330 Knoxville, Tennessee 37902 W. C. Drotleff ATTN:
J. A. Raulston Tennessee Valley Authority 400 West Summit Hill Dirve, W12 A12
. Knoxville, Tennessee 37902 R. L. Gridley Tennessee Valley Authority 5N 1578 Lookout Place Chattanooga, Tennessee 37402-2801 M. J.
May Tennessee Valley Authority Browns Ferry Nuclear Plant Post Office Box 2000
- Decatur, Alabama 35602
- Chairman, Limestone County Commission Post Office Box 188
- Athens, Alabama 35611 Ira L. Meyers, M.D.
State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36130 Regional Administrator, Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Mr. Steven Roessler U. S. Nuclear Regulatory Commission Reactor Training Center Osborne Office Center, Suite 200 Chattanooga, Tennessee 37411 Resident Inspector U. S. Nuclear Regulatory Commission Route 2, Box 311 Athens,,Alabama 35611
Request for Additional Information Browns Ferry Nuclear Plant Units 1, 2, and 3
Dockets Nos. 50-259,
- 260, 296 Generic Letter 83-28 A.
Item 2.1 Part 2
The staff is aware that the large majority of the reactor trip system components and equipment are supplied as part of the NSSS and would be covered under an existing interface program with the NSSS Vendor.
Accordingly, the staff review guideline now requires that the response include a brief description of the interface program between the licensee and'is NSSS vendor that is sufficient to confirm that (a) the program is currently in place and functioning; (b) the program will continue throughout the life of the plant; (c) periodic contact is made with the vendor to assure that all applicable information has been received; (d) a system of positive feedback is used with the vendor such as written licensee verification of receipt of mailed technical information; and (e) confirmation that applicable vendor.information is incor-porated or referenced into appropriate plant instructions and procedures.
Our evaluation of the licensee's submittal indicates:
(a)
A vendor interface exists with the NSSS vendor but go description of how it functions is presented.
(b)
No information is presented that would indicate that the NSSS vendor interface program will continue throughout the plant life.
I (c)
The submittal states that NSSS vendors supply information but does not indicate that periodic contact is initiated and maintained which assures that all applicable information is received.
(d)
No information is presented regarding positive feedback means used with
,the vendor to assure licensee receipt of mailed vendor technical information.
(e)
Information supplied in the submittal of November 7, 1983 demonstrates that an acceptable procedure for handling, evaluating and incorporating or referencing reviewed vendor technical information into plant instructions and procedures exists.
We request that the licensee supplement its response to include a brief description of the functioning of NSSS vendor interface program; to confirm that the program will remain functional throughout the plant life; to confirm that periodic contact with the vendor is initiated and maintained which assures that all applicable information is received; and to describe a
positive feedback method that is applied to assure licensee receipt of technical information issued by the vendor.
tA I,
0
~
h
> gib
)
IA ~
\\
I h
P J
AA 0
~
B.
Item 2.2 Part I 2.
With respect to Item 2.2.1.3 of Generic Letter 83-28, the licensee states that plant activities that could affect equipment on the list of critical
- systems, structures or components (CSSC) are prescribed by the instructions appropriate to the circumstances.
However, it is not clear that these instructions, or similar instructions, apply to all activities defined in the introduction of 10 CFR 50, Appendix B, and not just to those activities that affect equipment.
Also, in response to Item 2.1 of Generic Letter 83-28, the licensee refers to documentation that is required prior to performing maintenance or modification activities.
The relationship of this documentation to the instructions described above is not clear.
Nor is it clear how the instructions identify a safety-related activity as safety-related.
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.
With respect to Item 2.2.1.5, the licensee's response indicates that design specifications are used in the procurement of CSSC Components; however it is not stated that these specifications require appropriate
'esign verification, qualification testing for the expected safety service conditions, or testing documentation to support the limits of 1'ife recommended by the supplier.
We request that the licensee confirm that the specifications for safety related components contain appropriate requirements for design verification, qualification testing and testing documentation.
I
'