ML20234D160
| ML20234D160 | |
| Person / Time | |
|---|---|
| Site: | River Bend, 05000000 |
| Issue date: | 04/22/1985 |
| 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 8707070118 | |
| Download: ML20234D160 (14) | |
Text
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1 APH 2 2 FJ65 MEMORANDUM FOR:
Hugh L. Thompson, Director, Division of Licensing, Office of Nuclear Reactor Regulation FROM:
Richard P. Denise, Director, Division of Reactor Safety and Projects, Region IV
SUBJECT:
STATUS OF FACILITY COMPLETION FOR RIVER BEND STATION DOCKET N0. 50-458, REVISION 1 This forwards the status of facility completion report for ths River Eend Station in accordance with Inspection Procedure 943008.
It is the first revision of this report.
The licensee's projected fuel load date has been char:ged to June 1985 from April 1985. This change was the result of some slippage in the test completion schedule.
It also allowed some time for final walkdown and as-built inspections.
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 April 15, 1985. This report will be updated as required and the update intervals will not exceed 30 days.
If you have any questions, please contact either Johns Jaudon or myself.
f 1
o w! Eiar.cd By:
- Wd P. Denite 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 HC 2512, MC 2513, and MC 2514 5.
Status of Allegations 6.
Status of SER Open and Confirmatory Items Affecting Region IV cc:
(cont. on next page) bcc:
RIV File RP81 RPB1/A RPB1 i DRSP JPJaudcn/1k EHJohnson RPDenise Q/gb/85 Q/g/85 g
/85 i
8707070110 870512 chBE
-279 PDR
i Hugh L. Thompson cc w/ enclosures:
R. Martin,-RIV J. Taylor, IE S. Stern, NRR K. Kniel, NRR R. Bangart, RIV E. Johnson, RIV J. Jaudon, RIV R. Taylor, RIV R. Bennett, RIV R. Caldwell, RIV D. Chamberlain, SRI R. Farrell, SRI bcc w/ enclosures:
RPB1 RIV File i
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ENCLOSURE 1 ITEMS TO BE COMPLETED PRIOR TO FUEL LOADING 4
1.
The licensee will demonstrate to the satisfaction of Region IV that management attention has been satisfactorily directed to those areas j
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 Perfonnance Category Functional Area (8/1/83 to 12/31/84)
(9/1/82 to-7/31/83)
Notes A.
Soils and Founda-Not Assessed (NA)
NA 1
tions B.
Containment and 1
2 1
Other Safety-Related Structures j
C.
Piping Systems and 2
2 2
Suppert D.
Support Systems 2
2 1
E.
Electrical Power and 2
2 1
Supply and Distribution F.
Instrumentation and 2
2 3
Control Systems G.
Safety-Related 2
2 4
Components H.
Corrective Action and 1
2 1
Reporting I.
Quality Assurance 2
2 5
(Construction J.
Quality Assurance 2
NA 6
(Operations)
K.
Design Control 2
1 7
L.
Preoperational Testing 2
NA 1
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. t Latest Previous Perfonnance Category Perfonnance Category Functional Area (8/1/83 to 12/31/84)
(9/1/82 to-7/31/83)
Notes M.
Plant Operations 2
.NA 8
i Preparation i
N.
NA 9
l 0.
Radiological Controls 2'
NA 10 i
f P.
Security 2
NA 1
Q.
Training 2
NA 11
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R.
Management Control 1
1 1
t S.
Licensing Activity 2
2 1
Notes 1.
No additional need for management attention has identified for this functional area.
2.
Additional management attention should be directed toward as-built.
verification and drawing resolution.
3.
Additional attention and resources may be needed to accommodate increased activity.
4.
Source inspection should be improved to support spare parts procurement.
5.
Quality assurance personnel should provide greater surveillance of actual construction.
Staff should be provided to accomplish this i
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 closeout 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 pennanent plant positions should be filled.
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9.
Emphasis should be given to the timely correction of deficiencies identified during the emergency preparedness preoperational
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inspection.
(This will be inspected by an NRC inspection team May 6-10, 1985.)
10.
Increased management attention is needed to assure that NRC identified concerns in the areas of radwaste systems, effluent releases, effluent monitoring, and transportation activities are completed in a timely manner.
- 11. 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.
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 300 items, including potentially reportable items. The current status of open reports is:
o Number of Reportable Items Reported as 8
" Ready to Close" by the Licensee o
Number of Items Determined by the Licensee 2
to be Nonreportable o
Number not Reported Ready to Close by the 65 Licensee 1
IV. The licensee will complete to the satisfaction of Region IV the following open inspector items:
o (List will be supplied in a future report.)
V.
Compliance to Appendix R requirements was inspected by a team during the week of April 1, 1985.
The most significant inspection finding was that the licensee had not analyzed effects of fire induced spurious signals outside of the control room. A followup by Region IV will also be required to verify completion of fire stops and cable tray wraps and other i
minor items.
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, 50-458/85-10, and 50-458/85-21.
Items remaining are being tracked as open items. Followup on the IDI inspection has been completed except for four issues referred to the Office of Nuclear Reactor Regulation by IE. These four items are:
a 1
I Deficiency D4.3-3, Effect of Torsion / Rocking in Amplified Response o
Spectra Unresolved Item U.14-1, Recoupling of Control Rod Drive Piping and o
Supports Unresolved Item 4.5.12-1, Standby Diesel Generator Lubricating 011 o
Circulating Pump Motor Qualification 1
o Unresolved Item U.6.7-1, Periodic Test of the Standby Service Water System J
VII. The final draft of the Technical Specifications is scheduled for issue l
April 22.
If this occurs, the onsite verification of these draft Technical Specifications will be checked by an onsite, team iraspection commencing April 29, 1985.
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ENCLOSURE 2 l
PREOPERATIONAL TESTING STATUS The status of the licensee's preoperational tests is as follows:
Previous Report Current Report Total number of tests 107 107 Number of tests completed and reviewed 19 19 Number of tests completed but not 6
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reviewed j
Number of tests started 48 41 Number of tests not started 34 29 Additionally, the same contractor and licensee test organizations which perfonn 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 i
acceptance tests is as follows:
Previous Report Current Report Total number of tests 97 86*
Number of tests completed and reviewed 42 42 Number of tests completed but not 1
8 reviewed Number of tests started 27 10
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Nunber of tests not started 27 26
- Total changed because some tests have been combined.
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ENCLOSURE 3 CONSTRUCTION STATUS As of April 15, 1985, construction was approximately 97 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 19 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, 9 systems have completed the approval process.
A completion date has not been established for the remaining systems.
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ENCLOSURE 4 STATUS OF INSPECTIONS REQUIRED BY MC 2512, MC 2513, AND MC 2514 The MC 2512 inspection program and all completed NRC construction inspections
- perfomed 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 applicable. The list of remaining MC 2512 modules is as follows:
Module Number Description Percent Complete 50071 Mech. Com-Procedures 90%
50073 Mech. Comp-Observation 90%
50075 Mech. Comp-Records 90%
53051 Cont. Penetrations-Procedures 60%
53055 Cont. Penetrations-Records 60%-
35020 Surveillance of Contractor QA/QC 0%
35060 Lic. Mgt. of QA Activities 30%
35061 QA Performance 50%
37055 Onsite Design Activities 80%
51065 Elect. Cables-Records 75%
52061 Instr. Cables-Procedures 75%
52063 Instr. Cables-Observation 75%
52065 Instr. Cables-Records 75%-
- TI-2512/11 New Initiatives 10%
- Completion of this inspection and of Procedure 37301 (MC 2513) are dependent upon completion of construction, N5 certifications, availability of as-built drawings, and the clearing of open items.
These inspections are scheduled to be completed by fuel load.
The status of MC 2513 inspections is as follows:
Module Number Description Percent Complete 70329 Preop Test Evaluation Verification 10%
70312 Preop Test Witnessing NA-70315 ESF Test Witness 20%
70316 Loss of Offsite Power Test Witness 0%
70317 Reactor Protection Sys Test Witness 0%
. Module Number Description Percent Complete 70322 ESF Test Evaluation 0%
70325 Reactor Prot Sys-Test Evaluation 0%
70326 Loss of Offsite Power-Evaluation 0%
70323 ILRT-Test Evaluation 30%
70562 Reactor Hydro-Evaluation 0%
70370 Testing of Pipe Supports 0%
70432 CRDM Test Proc 2 dure Witness 70%
70452 Remote Reactor SD-Witness 20%
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%
35742 QA Program-Document Control 25%
35743 QA program-Maintenance 25%
35744 QA Program-Design Changes 25%-
35745 QA Program-Surveillance Test 25%
35750 QA Program MT&E 25%
42450 Operations Procedures 90%
42451 Maintenance Procedures 50%
42452 Emergency Procedures 30%
71301 Technical Specifications Review 0%
83522 Rad Protection-Preoperational 90%
83523 Rad Protection-Precperational 90%
83524 External Exposure Control 50%
83525 Internal Exposure Control 40%
83526 Cont. of Radioactive Material 50%
83527 Facilities and Equipment 75%
83528 Maintaining Occupational Exposure 80%
84522 Solid Wastes 40%
84523 Liquids and Liquid Waste 40%
84524 Gaseous Waste System 40%
84525 Radiological and Chemical Confirm Meas.
50%
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' Module Number Description Percent Complete TI2512/55 Emergency Preparedness 80%
81018 Management Effectiveness 0%
81038 Records and Reports 0%
81042 Testing and Maintenance 0%
81046 Locks, Keys, Combinations 0%
81054 Physical Barriers 0%
81058 Security System Power Supply 0%
f 81064 Cortpensatory Measures 0%
81072 Access Control Packages 0%
81074 Access Control-Vehicles 0%
81080 Detection Aids 0%
81084 Alann Stations 0%
81088 Communications 0%
81810 Physical Protection, S/G Info.
0%
The status of MC 2514 inspections is as follows:
Module Number Description Percent Complete 35501 QA for SU Test Program 0%
72400 Overall Startup Test Log Of 72500 Initial Fuel Loading Procedures Review 0%
72524 Initial Fuel Loading-Witness 0%
83521 Rad Protection-SU 0%
B4521 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 SUTestProcedureReview(A) 0%
72517 SU Test Procedure Review (A&B) 0%
4 Module Number Description Percent Complete 72518 SU Test Procedure Review 0%
72526 Initial Criticality-Witness 0%.
72532 Power Level Data Review & Evaluation 0%
T12514-01 Confirmation of TMI Items 40%
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ENCLOSURE 5 STATUS OF ALLEGATIONS RECEIVED BY NRC FOR RIVER BEND A total of 32 allegations have been received. Twenty-three of these have been closed and nine are still open. The status of the nine open allegations is as follows:
Subject Source Status 1.
Improper Thermocouple Anonymous RIV lead; ready to Connection close in inspection repcrt 85-22 4.
Improper N&D Disp.
Allegation to GSU lead; RIV monitor GSU 5.
Cable Trays Anonymous RIV lead 6.
HVAC Testing Anonymous Violations to be issued in inspection report 85-23; GSU doing j
followup 7.
Drugs Anonymous GSU lead; RIV monitor 8.
Harrassment of Eng.
Anonymous GSU lead; RIV monitor Staff (S&W) 9.
Control Room Circuitry Craft Worker GSU lead; RIV monitor Problems to GSU
ENCLOSURE 6 STATUS OF SER OPEN AND CONFIRMATORY ITEMS 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:
57 Licensed operator experience 63 ESF functioning 64 Procedures for removal and return to service of safety-related equipnent i
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