ML20082V210
| ML20082V210 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/15/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8312200020 | |
| Download: ML20082V210 (2) | |
Text
_ _ _ _ _ _ _
~
TENNESSEE VALLEY AUTHORITY CH ATTANOOG A, TENNESSEE 374ot 400 Chestnut Street Tower II l
December 15, 1983 Director of Nuclear Reactor Regulation j
Attention:
Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mu. Adensam:
In the Matter of
)
Docket No.
50-327 Tennessee Valley Authority
)
Please refer to my letter to you dated March 15, 1982 which responded to the Sequoyah Nuclear Plant unit 1 operating license condition 2.C(24) and provided to you a final instrumentation list and the design criteria for SNP postaccident monitoring instrumentation.
The enclosed information is provided as additional information to this previous submittal and should clarify any misinterpretation of TVA's position on Regulatory Guide 1.97, In addition, please refer to R. H. Shell's letter to you dated December 1, 1983 which provided the most recent schedules for compliance with Regulatory Guide 1.97.
As indicated, TVA now expects to provide a Regulatory Guide 1.97 implementation date by February 15, 1984.
If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2676.
Very truly yours, TENNESSEE VALLEY AUTHORITY 0312200020 7
DR ADOCK 0 PDR g
L. M. Mills, nager Nuclear Licensing Sworn po ppd subscr ed before me y
1983 this [O m day of e
Di l
Notary Public l
My Commission Expires 5-#
Enclosure oc:
U.S. Nuclear Regulatory Commission (Enclosure)
Region II g
Attn:
Mr. James P. O'Reilly Administrator I
101 Marietta Street, NW, Suite 2900 l
If Atlanta, Georgia 30303 i
1983-TVA 5OTH ANNIVERSARY An Equal Opportunity Employer
~
f ENCLOSURE Amendment to the March 15, 1982 submittal from L.M. Mills to E.Acensam concerning Sequoyah Nucicar Plant unit 1 operating license condition 2.C(24) 1.
Identification Postaccident monitoring (PAM) shall consist of a set of process variables along with the instrumentation necessary to monitor the variables in the control room required to ensure safety during and following an accident. Support instrumentation (called category 3 in our March 15, 1982 submittal) may provide additional information to the operator during and following an accident, but this information is not required.
2.
Definitions a.
PAM Instrumentation - A sec of process variables along with the instrumentation necessary to monitor these variables in the control room required to ensure safety during and following an accident (i.e., category 1).
b.
Support Instrumentation (referred to as category 3 in our March 15, 1982 submittal) - A set of process variables, along with the instrumentation necessary to monitor these variables, which may provide additional information to the operaton.
c.
Type A, B, and C Variables - Type A, B, and C variables comprise the complete set of variables for PAM instrumentation by the functional definition of these variable types. Type D.
and E variables are not part of the set of variables which comprise the set of variables for PAM instrumentation. Type D and E variables are _ support instrumentation by the functional definition of the variable types.
3 selection of oualification Level Type A, B, and C variables are monitored by category 1 instrumentation. Type D and E variables are monitored by good quality utility grade instrumentation.
a
- a.
Category 1 Instrumentation - Instrumentation monitoring these variables serves a primary safety function; therefore, indication of these variables is required during and following an accident. 'These variables are considered the complete set of PAM variables. They are used by the operator to ensure (1) the capability to ehut down the reactor and maintain it in a safe shutdown condition, (2) the integrity of the fission product boundaries, and (3) the capability to mitigate the consequences of accidents "hich could result in potential offsite exposures comparable to the exposure guidelines of 10 CFR 100.
Instrumentation used to indicate the need for required operator actions that ensure design basis behavior for the design basis events (accidents) shall be category 1 instrumentation.
b.
Support Instrumentation - Instrumentation monitoring these variables does not serve a primary safety function; therefore, indication of these variables is not required during and following an accident. These variables are not considered PAM instrumentation, and they only pecvide additional information by indicating system operating status, diverse variables, and radiation releases.
The variables can be used to enhance safety, if the instrumentation is available, by allowing the operator to improve the system operation over the minimum required for design basis'aehavior or determine what system has failed. The instrumentation to indicate these variables is not essential for the safety functions provided by PAM.
O Nd -
m s g h.= )
g@, n,1 ]