ML20215C444
| ML20215C444 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/12/1987 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8706180123 | |
| Download: ML20215C444 (9) | |
Text
n e
TENNESSEE VALLEY AUTHORITY CH ATTANOOGA, TENNESSEE 374o1 SN 157B Lookout Place j
MAY 121987 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk j
Washington, D.C.
20555 Gentlemen:
In the Matter of
)
Docket Nos. 50-327 Tennessee Valley Authority
)
50-328 SEQUOYAH NUCLEAR PLANT - POSTRESTART SCOPE AND SCHEDULE FOR THE DESIGN BASELINE AND VEPIFICATION PROGRAM (DBVP)
Reference:
TVA letter from R. Gridley to NRC dated April 28, 1987 In accordance with a TVA commitment within the reference, enclosed is the DBVP scope and schedule for Phase II (postrestart) of Sequoyah unit 2.
Please note that implementation of DBVP activities for the Phase II scope of systems differs, in some cases, from Phase I.
For example, procedures for Phase II may be revisions of Phase I procedures or may be newly-developed.
Also, a System Modification Summary Report will be issued for each system or portion thereof in lieu of a System Evaluation Report (SYSTER). Under the Phase II scope of systems, only implemented changes will be reviewed using the updated design criteria; however, unimplemented and partially implemented changes for this scope of systems were evaluated as part of a procedurally controlled portion cf the prerestart program.
TVA believes that these differences from Phase I have been justified by the results of the Phase I effort, in that the DBVP processes will be optimized while retaining the most valuable aspects of Phase I activities. consists of new commitments made within this submittal.
If you have any questions concerning this issue, please call Beth L. Hall, of the Sequoyah Site Licensing Staff, at (615) 870-7459.
Very ttvly yours, TENNESSEE VALLEY AUTHORITY i. Gridley, Director Nuclear Safety and Licensing
'll Enclosures cc:
see page 2 O
I B706180123 070512 I )
PDR ADOCK 05000027 P
PDR An Equal Opportunity Ernployer
. U.S. Nuclear Regulatory Commission cc (Enclosures):
Mr. G. G.'Zech, Assistant Director j
for Inspection Programs Office of Special Projects
'U.S.-Nuclear Regulatory Commission 101.Marietta Street, NW, suite 2900 Atlanta, Georgia 30323 l
Mr. J. A. Zwolinski, Assistant Director For Projects Division of TVA Projects Office of Special Projects U.S. Nuclear. Regulatory Commission 4350 East West Highway-EWW 332-Bethesda, Maryland 20814 Sequoyah Resident Inspector Sequoyah Nuclear. Plant 2600 Igou Ferry Road.
l-Soddy Daisy, Tennessee 37379 L..................__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___
i ENCLOSURE 1 POSTRESTART PHASE (PHASE II)
DESIGN BASELINE AND VERIFICATION PROCRAM (DBVP)
INTRODUCTION 1
This discussion provides the information describing the postrestart phase of the DBVP. It defines the specific systems that are included, attributes of the Phase I scope that are applied, and a schedule for completion.
Phase II will establish the functional baseline for the remaining safety-related systems or portions of systems (see attachment 1 for list).
Verification will be performed for Postoperating License (OL) changes to these systems. The Transitional Design Change Control process will be utilized in preparation for the Permanent Design Change Control System.
~
SCOPE The scope of the program is divided into design control activities and baseline and verification activities.
Design Control Implementation of improved design control practices which began in Phace I will continue. The Transitional Design Control System will be utilized during Phase II until the Permanent Design Change, Control System is fully
(
implemented. The Permanent Design Control program will be put into effect j
during Phase II.
Implementation of this program will begin by December 31, 1987, and requires developing and implementing new design control i
procedures.
The Change Control Board will remain in effect to assist in controlling the i
change process.
Baseline and Verification A.
Safe Shutdown and Accident Mitigation (SS/MA) Systems i
I These systems or portions of systems were the subject of Phase I.
Work in Phase II to complete this scope is as follows:
1.
The C/R data base will be reviewed, updated, and maintained.
i 2.
The Restart Design Basis Document (RDBD) design criteria will be revised as appropriate to incorporate additional C/Rs as required.
They will also be revised considering the INPO Design Criteria audit recommendations and testing requirements.
3.
The postrestart modifications and documentation corrections identified in Phase I will be completed.
4 Configuration Control Drawings (CCDs) for primary Control Room As-Constructed Drawings (CRADs) reviewed in Phase I will be issued.
^
..B.
Remaining Safety-Related Systems l
This scope covers the remaining safety-related systems and the safety-related portions of the SS/MA systems excluded in Phase I.
)
The' remaining safety-related systems or portions of safety-related systems are shown on attachment 1.
A new system boundary calculation will be prepared to define in detail the review boundaries.
For this' scope, the following four major activities will be carried out:
1.
Design Criteria / Design Basis Review, update, and maintain the existing C/R data base.
Develop new or expand existing design criteria to cover this system scope.
~
2.
System Walkdown/ Tost System walkdowns will be performed to verify the functional configuration of the process flow for mechanical and fluid systems.
Instrumentation and control (I&C) systems will include confirmation by walkdown/ tests that the control device functions and that its associated-root valve is verified.
s
~
For electrical and I&C modifications, results from preoperational tests, postmodification tests, su_rveillance instructions, special tests, and engineering reviews will be evaluated to establish proper function of modifications since OL.
Dimensional data will be obtained, as required, for input to engineering evaluations needed to technically justify the modifications.
3.
Evaluation of Engineering Change Notices (ECNs) and Other System Changes A technical review will be conducted of implemented changes against the updated design criteria.
The evaluation process will determine if the modifications affect the system's capability to operate safely and meet the design basis.
This evaluation will be based upon documented engineering a.nalysis.
i 1
n --
b The evaluation of other change documents such as Nonconformance Reports /Significant Condition Reports (NCRs/SCRs), Temporary Alteration Control Forms (TACFs),' Local Design Change Requests (LDCRs) Field Change Requests (FCRs), and Field Change Notices (FCNs), ensures that engineering evaluations have been performed, that appropriate corrective actions have been taken, and that the related documentation is in order.
4.
System Evaluations and Corrective Actions The following items will be issued before completion of the program for each system or portion thereof:
o Design Criteria o CCDs required for operations o. System Modification Summary Report Corrective actions required to resolve discrepancies identified in the change document evaluation and/or technical review will be taken.
This may require drawing changes, Design Basis Document changes, and/or licensing commitment changes.
Findings will be
~~
identified and reported, and corrective action will be scheduled based on above reviews.
SCHEDULE
~The overall schedule for Phase II is shown on attachment 2.
The program is scheduled to run until January 1990. The schedule is based on the refueling / outage schedule for unit 2 as a controlling factor. Attachment 2 shows the major interfaces between program elements and the refueling / outage schedule.
ORGANIZATION i
~A program team will be organized under a Sequoyph Engineering Project (SQEP)
Assistant Project Engineer to carry out the program. Liaison with the plant, Quality Assurance (QA), Licensing, and Nuclear Construction will be established.
ENGINEERING ASSURANCE (EA)
EA will review engineering activities.
An EA oversight team will independently review program activities on a sample basis. A separate program plan will be prepared to define the details of this activity.
PROGRAM PROCEDURES
- Procedures required to assign specific responsibilities, define methods, and establish documentation requirements will be developed or revised, based on Phase I experience.
l 1
i
,1 4
_4_
FINAL REPORT The results and conclusions of the program (Phase I and Phase II) will be documented in a final report for submission to the Director of Nuclear
- Engineering. Based upon a review of the report, the director will determine if the stated objectives of. the program have been met or if additional actions are required.
ATTACHMENTS. - Remaining Safety-Related Systems - Schedule for Design Baseline and Verification Program Phase II I
i I
1 i
+
y.
ENCLOSURE 2 LIST OF NEW COMMITMENTS FOR SEQUOYAH NUCLEAR PLANT 1.
Issue site procedures for Phase 1[I and conduct training for'their use by.
December 31, 1987.
2.
Develop Configuration Control Drawings (CCDs)'for Control Room As-constructed Drawings (CRADs) for Phase II by December 31, 1989.
3.-
Evaluate change documents and testing for Phase II scope of systems by April 1, 1989.
4.
Issue Phase II final report by October 1, 1989.
4
)
)
1 e
r-
)
ATTACHMENT 1 REMAINING SAFETY-RELATED SYSTEMS SYSTEM NO, NAME
- 68 Reactor Coolant System - including Reactor Vessel Level Indication System (RVLIS)
- 77 Waste Disposal - Effluent Monitoring
- 78 Spent Fuel Pool Cooling - Pumps, Heat Exchangers, and Associated Equipment 79 Fuel Handling.and Storage - Fuel Handling Accident 84 Flood Mode Boration
- 90 Radiation Monitoring - Effluent Monitoring 94 In-Core Flux Monitoring
- This system is also in Phase I, and this scope consists of remaining
' safety-related portions.
O
T,7 s
e ga Wg Bil
_ _ _ _ _ _ _b _ _ a.
li 1
8 n
gga
. g
{
i j g_a_
EL L
pg 6
St El de
~
6 h.
e f
-5 gg e
W a
dg s
s N
5 2,.
a i
4 9
8 i
g
_w 13 g
m x
W 9
k s
p*
vi i
ll l
()<
s t
s g
!E B
GL 6
8v's l
C e
E{$
E g
_b,____t _H A ___l b,E E
u
~
N 2
I g
~
s a
i 8
g 9
e
~;
I
$a 2
D Bn s
E w
8 GL L
L L 5
=
w m
at N
g)
W 5-W t
El l
l
.b1 69 67 b7 b1 Li
__ g_g g _ _ __. _ _ _ _.__
g
_ g_. _ _ _ ps n-g__.
utts a
l 8
88 ss 54d?
~
4 mm awam