ML20234D136
| ML20234D136 | |
| Person / Time | |
|---|---|
| Site: | River Bend, 05000000 |
| Issue date: | 03/22/1985 |
| From: | Denise R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Thompson H Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20234D050 | List: |
| References | |
| FOIA-87-279 NUDOCS 8707070111 | |
| Download: ML20234D136 (12) | |
Text
-
NER 2 2 $85 MEMORANDUM FOR:
Hugh L. Thompson, Director, Division of Licensing, Office of Nuclear Reactor Regulation l
FROM:
Richard P. Denise, Director, Division of Reactor Safety and Projects, Region IV 3
SUBJECT:
STATUS OF FACILITY COMPLETION FOR RIVER BEND STATION DOCKET NO. 50-458, INITIAL SUBMITTAL j
This forwards the status of facility completion report for the River Bend
)
Station in accordance with Inspection Procedure 943008.
It is the initial submittal of this report.
The licensee's projected fuel load date is April 15, 1985.
This date is based on the projected date of the completion of the last major preoperational test.
It does not consider such items as the completion of mandatory test data review. Moreover, there are other inspection activities such as the final as-built and walkdown inspection which are dependent upon the status of system completion and turnover.
Since all systems have not been turned over and there are currently several thousand open items, it is not clear whether testing or as-built verification will become the actual critical path.
There are no outstanding escalated enforcement issues at this time.
The information herein is current as of March 20, 1985.
This report will be uodated as required and the update intervals will not exceed 30 days.
If you have any questions, please contact ef;her Johns Jaudon or myself.
nd By:
n-b nise R. P. Denise, Director Division of Reactor Safety and Projects
Enclosures:
1.
Items To Be Completed Prior To Fuel Load 2.
Preoperational Test Status 3.
Construction Status 4.
Status of Inspections Required by MC 2512, MC 2513, and MC 2514 l
5.
Status of Allegations 6.
Status of SER Open and Confirmatory Items Affecting Region IV cc:
3 See attached l
RIV-RPB1/A RPB1 h DRSP JPJaudon:vs EHJohnson RPDenise v8,
- eve, y,
8,y 8707070111 870512 PDR FOIA GRABER87-279 PDR
e.
cc w/ enc 1:
R. Martin, RIV J. Taylor, IE
R. Taylor, RIV R. Bennett, RIV R. Bangart, RIV E. Johnson, RIV D. Chamberlain, SRI R. Farrell, SRI l
i i
D z.h-ge..
- r. -
?.h. '
OirI *- '
(.
~.
r ENCLOSURE 1 ITEMS TO BE COMPLETED PRIOR TO FUEL LOADING I.
The licensee will demonstrate to the satisfaction of Region IV that l
management attention has been satisfactorily directed to those areas t
identified in the last SALP report as requiring either specific or general improvement or continued activity in a specific area.
Previous SALP Evaluations Latest Previous Performance Category Performance Category Functional Area (8/1/83 to 12/31/84)
(9/1/82 to 7/31/83) Notes A.
Soils and Foundations Not Assessed (NA)
NA 1
B.
Containment and Other Safety-Related Structures 1
2 1
C.
Piping Systems and Support 2
2 2
D.
Support Systems 2
2 1
E.
Electrical Power and Supply and Distribution 2
2 1
F.
Instrumentation and Control Systems 2
2 3
G.
Safety-Related Components 2
2 4
H.
Corrective Action and Reporting 1
2 1
I.
Quality Assurance (Construction) 2 2
5 J.
Quality Assurance (Operations) 2 NA 6
K.
Design Control 2
1 7
L.
Preoperational Testing 2
NA 1
r
., M.
Plant Operations Preparation 2
NA 8
N.
NA 9.
O.
Radiological Controls 2
NA 10 P.
Security 2
NA 1
Q.
Training 2
NA 11 R.
Management Control 1
1 1
S. Licensing Activity 2
2 1
Notes 1.
No additional need for management attention was identified for this functional area.
2.
Additional management attention should.be directed toward as-built veri.fication and drawing resolution.
3.
Additional attention and resources may be needed to accommodate increased activity.
4.
Source inspection should be improved to suppoit spare parts procurement.
5.
Quality assurance personnel should provide greater surveillance of actual construction.
Staff should be provided to accomplish this surveillance in addition to performing document reviews and other activities.
6.
There should be aggressive recruiting to fill positions within the QA organization.
7.
There should be aggressive closecut of all IDI findings and monitoring of as-built verification.
8.
Evaluate completed walkthroughs of procedure in order to develop confidence in the internal procedure review and approval process.
Open permanent plant positions should be filled, 9.
Emphasis should be given to the timely correction of deficiencies icentified during the emergency preparedness preoperational inspection.
l
c I
i 10.
Increased management attention is needed to assure that NRC identified concerns in the areas of radwaste systems, effluent releases, effluent i
monitoring, and transportation activities are completed in a timely manner.
II.
Complete the definition of job qualifications and clearly define training and training requirements.
II.
NRC Region IV is continuing its review of licensee action on NRC Bulletins and Circulars.
III. NRC Region IV is continuing its review of Construction Deficiency Reports (10 CFR Part 50.55(e)) and Part 21 items.
The licensee has reported approximately 280 items, including potentially reportable items.
The current status of open reports is:
No. of Reportable Items Reported as
" Ready to Close" by the Licensee 45 No. of Items Determined by the Licensee to be Nonreportable 50 No. Not Reported Ready to Close by the Licensee 37 IV.
The licensee will complete to the satisfaction of Region IV the following open inspector items:
(List will be supplied in a future report.)
V.
Compliance to Appendix R requirements will be inspected by a team during the week of April 1, 1985.
Since the licensee has an open item requesting postponement until first refueling of the safe / alternate shutdown (main control fire)-SER Outstanding Issue 13, this inspection may result in some open items. Additionally, as of March 13, 1985, Region IV inspectors noted that many fire stops and fire tray wraps had not yet been installed.
VI.
Open items resulting from the CAT and IDI inspections must be resolved.
Followup on the CAT issues has been addressed in Inspection Reports 50-458/84-36, 50-458/85-01, and 50-458/85-10.
Items remaining are being tracked as open items.
There are still two issues for which followup action is not documented in an inspection, but these will be documented within 1 month.
Followup on the IDI inspection is still under the control of IE.
l l
r
- q l
PREOPERATIONAL TESTING STATUS The status of the licensee's preoperational tests is as follows:
Total number of tests 107
)
Number of tests completed and reviewed 19 j
Number of tests completed but not reviewed 6
Number of tests started 48 i
Number of tests not started 34 Additionally, the same contractor ar.d licensee test organizations which perform preoperational tests-also accomplish acceptance tests. Acceptance tests are essentially preoperational tests on balance of plant systems; however, these tests compete for manpower with the preoperational tests.
The status of acceptance tests is as follows:
Total number of tests 97
)
\\
Number of tests completed and reviewed 42
{
Number of tests completed but not reviewed 1
Number of tests started 27 Number of tests not started 27
)
i 1
r CONSTRUCTION STATUS As of March 13, 1985, construction was 96 percent completed.
The licensee has been releasing equipment by " Boundary Identification Packages" (BIP) to the plant staff.
Review of the current status by whole systems instead of BIPs indicates that out of 102 systems identified by the licensee as needed to support a license to load fuel, only 18 have been turned over to the plant staff as of this report.
However, BIPs which contain portions of other required systems have been turned over also.
Of the 41 systems requiring N5 stamp certification, 6 systems have completed the approval process.
A completion date has not been determined for the remaining systems.
4 i
i t
i l
1 STATUS OF INSPECTIONS REQUIRED BY MC 2512, MC 2513, and MC 2514 l
The MC 2512 inspection program and all completed NRC construction inspections
)
performed to date have been reviewed.
Credit for the inspection efforts done by the Independent Design Inspection group and the Construction Assessment Team has been taken where apolicable.
The list of remaining MC 2512 modules to be performed are as follows:
Module No.
Description Percent Comolete 50071 Mech. Comp-Procedures 50%
50073 Mech. Comp-Observation 50%
50075 Mech. Comp-Records 30%
53051 Cont. Penetrations-Procedures 0%
53055 Cont. Penetrations-Records 0%
35020 Surveillance of Contractor QA/QC 0%
35060 Lic. Mgt, of QA Activities 0%
35061 QA Performance 50%
37055 Onsite Design Activities 50%
51055 Elect. Comp-Records 90%
52053 Instr. Comp-Observation 75%
52055 Instr. Comp-Records 75%
51065 Elect. Cables-Record 3 75%
52061 Instr. Cables-Procedures 75%
52063 Instr. Cables-Observation 75%
52065 Instr. Cables-Records 75%
49051 RCP Boundry Piping-Procedures 50%
49053 RCP Boundry Piping-Observation 50%
49055 RCP Boundry Piping-Records 50%
49061 SR Piping-Procedures 50%
49063 SR Piping-Records 50%
- TI-2512/11 New Initiatives 0%
l
- Completion of this inspection and of Procedure 37301 (MC 2513) are dependent upon completion of construction, N5 certifications, availability of as-built l
drawings, and the clearing of open items.
These inspections are scheduled to be completed by fuel load.
f The status of MC 2513 inspections is as follows:
Module No.
Description Percent Complete
.70302 Preop Test Program Implementation 40%
70329 Preop Test Evaluation Verification 10%
70312 Preop Test Witnessing NA 35301 QA for Preop Testing.
70%
70307 Cont. Sys. ILRT-Procedure 0%
70313 Cont. Syst ILRT Witness 0%
70315 ESF Test Witness 70%
70316 Loss of Offsite Power Test Witness 0%
70317 Reactor Protection Sys Test Witness 0%
70322 ESF Test Evaluation 0%
70325 Reactor Prot Sys-Test Evaluation 0%
70326 Loss of Offsite Power-Evaluation 0%
70323 ILRT-Test Witness 0%
70t,J2 Reactor Hydro-Evaluation 0%
70370 Testing of Pipe Supports 0%
70434 EST Test Procedures Review 90%
70432 CRDM Test Procedure Review 70%
70452 Remote Reactor SD-Witness 0%
70532 CRDM Test Evaluation 0%
70534 ESF Test Evaluation 0%
70541 Emergency Standby Power-Evaluation 0%
70552 Remote Reactor SD-Evaluation 0%
70556 Standby Liquid Cont-Evaluation 0%
35740 QA Progrm-Administration 0%
35742 QA Program-Document Control 0%-
35743 QA Program-Maintenance 0%
35744 QA Program-Design Changes 0%
35745 QA Program-Surveillance Test 0%
35750 QA Program MT&E 0%
40301 Safety Committee 0%
42450 Operations Procedures 60%
42451 Maintenance Procedures 50%
42452 Emergency Procedures 30%
71301 Technical Specifications Review 0%
83522 Rod Protection-Preoperational 90%
83523 Rod Protection-Preoperational 90%
83524 External Exposure Control 50%
83525 Internal Exposure Control 40%
83526 Cont. of Radioactive Material 50%
83527 Facilities and Equipment 75%
r
,'s, !
Module No.
Description Percent Complete
-n 83528 Maintaining Occupational Exposure 80%
L 84522 Solid Wastes 40%.
1 84523 Liquids and Liquid Waste 40%
i 84524 Gaseous Waste System 40%
84525 Radiological & Chemical Confirm Meas.
50%
TI2512/55 Emergency Preparedness 80%
{
The status of MC 2514 inspections is as follows:
i Module No.
Description Percent Complete 35501 QA for SU Test Program 0%
72400 Overall Startup Test Log 0%
{
72500 Initial Fuel Loading Procedures Review 0%
72524 Initial Fuel Loading-Witness 0%
83521 Rad Protection-SU 0%
84521 Radwaste-SU 0%
72502 Int. Crit-Procedures Review 0%
72504 Heatup Phase Procedure Review 0%
72508 Power Assession Procedure Review (A) 0%
72509 Power Assession Procedure Review (B) 0%
72510 Power Assession Procedure Review (C) 0%
72512 SU Test Procedure Review (B) 0%
72514 SU Test Procedure Review (A & B) 0%
72516 SU Test Procedure Review (A) 0%
72517 SU Test Procedure Review (A & B) 0%
72518 SU Test Procedure Review 0%
72526 Initial Criticality-Witness 0%
72532 Power Level Data Review & Evaluation 0%
TI2514/01 Confirmation of TMi Items 40%
4
i
.I
^
~
f i
1 STATUS OF ALLEGATIONS RECEIVED BY NRC FOR RIVER BEND' A total of 31 allegations have been received.
Twenty of these have been closed I
and 11 are still open.
The status of the 11 open arlegations is as follows:
Subject Source Stftus 1.
Sensitive 01' lead 2.
~
3.
HVAC Construction Anonymous GSU lead, RIV monitoring, data in IR 50-458/84-06 sufficient to close
\\
4.
Improper Thermocouple i
Connection Anonymous RIV lead; ready to close in next SRI (const.) IR 5.
Suppression of Lawsuit by Letter sent 3/11/85'to Nonconformance Reports R. H. Teunisin Teunisin requesting i
that he contact NRC~
6.
Druns Confidential GSU lead; RIV monitor 7.
Improper N&D Disp.
Allegation to GSU_
GSU lead; RIV monitor 8.
Cable Trays Anonymous RIV lead 9.
HVAC Testing Anonymous RIV lead l
10.
Drugs Anonymous GSU lead; RIV monitor l
11.
Harassment of Anonymous GSU lead; RIV monitor Eng. Staff (S&W) r i
=,
i Enclosure'6 I
STATUS OF SER OPEN AND CONFIRMATORY ITEMS i
AFFECTING REGION IV The licensee will complete to the satisfaction of Region IV the following SER confirmatory actions assigned to RIV for closure and still open:
56 Personnel resumes 57 Licensed operator experience 63 ESF functioning 64 Procedures for removal and return to service of safety-related equipment Additionally, GSU has made several organizational changes which must be documented in an SER supplement.
GSU also has discussed changes in the procedure review methods that they desire to use and in the onshift requirements for operators, but these are not yet documented as an FSAR change.
This proposed change, when made, will also require a supplemental SER input.
'