ML20234D186
| ML20234D186 | |
| Person / Time | |
|---|---|
| Site: | River Bend, 05000000 |
| Issue date: | 05/21/1985 |
| 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 8707070128 | |
| Download: ML20234D186 (24) | |
Text
{{#Wiki_filter:<- . s g o , MAY 211985 I 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 SU8 JECT: STATUS OF FACILITY COMPLETION FOR RIVER BEND STATION l DOCKET NO. 50-458, REVISION 2 l This forwards the status of facility completion report for the River Bend Station in accordance with Inspection Procedure 943008. It is the second revision of this report. The licensee's projected fuel load date is June 1985. In addition to the completion of specific tests and inspectims delineated in the enclosures, the licensee must also resolve thousands of open punch list items. There are two punch lists involved. One is the system punch list, and the other is the building punch list. Open punch list items will be resolved to the Region's satisfaction prior to fuel load. Resolved means that an item is either cleared or determined to have no safety significance. Although individual items may . have little safety significance alone, the total number of them may have a l synergistic effect. Inspections conducted in late April and early May defined two problems. The ) first of these was that safety-related raceways were not ready for final { walkdown inspections. The second problem was that the licensee did not yet i have a complete set of surveillance procedures for technical specification l implementation in a state that would support licensing. Region IV advised the { licensee of these deficiencies by two letters, both dated May 10, 1985, in l advance of the inspection report issucnce. In the case of the surveillance j procedures, over 300 open items were identified. It is not clear whether procedural problems or as built verification is the actual critical path. There are no outstanding escalated enforcement issues at this time. There are, however, many open inspection items (i.e., violations, deviations, and open items) resulting from inspections. These items must be resolved prior to l fuel load. The open items list attached to Enclosure 1 is not all inclusive, for it does not include open items from ynspections for which reports have not yet been issued. This report will be updated at intervals not to exceed 30 days. f ( v' RPB1 g1
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DRSP RPB1/" JPJ n b k EHJohnson 7PDenise f /9 /85 /p/85 $ /85 8707070128 870512 PDR FOIA GRABER87-279 PDR
l If you have any questions, please contact either Johns Jaudon (FTS 728-8140) or myself. Original Signed By: Richard P. Denise R. P. Denise, Director Division of Reactor Safety , and Projects j
Enclosures:
- 1. Items to be Completed Prior to Fuel Load
- 2. Preoperational Test Status
- 3. Construction Status I'
- 4. Status of Inspections Required by MC 2512, MC 2513, and MC 2514
- 5. Status of Allegations
- 6. Status of SER Open and Confirmatory Items Affecting Region IV cc w/ enclosures:
R. Martin, RIV J. Taylor IE S. Stern, NRR K. Kniel, NRR R. Bangart, RIV E. Johnson, RIV I J. Jaudon, RIV j R. Taylor, RIV R. Bennett, RIV i R. Caldwell, RIV D. Chamberlain, SRI R. Farrell, SRI i bec w/ enclosures: RPB1 RIV File
I 1 ENCLOSURE 1 ITEMS TO BE COMPLETED PRIOR TO FUEL LOADING l 1 I. 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 l Performance Category Performance Category ] Functional Area (8/1/83 to 12/31/84) (9/1/82 to-7/31/83) Notes j A. Soils and Founda- Not Assessed (NA) NA 1 ) tions d B. Containment and 1 2 1 Other Safety-Related Structures C. Piping Systems and 2 2 2 ) Support l D. Support Systems 2 2 1 E. Electrical Power and 2 2 1 Supply and Distribution F. Instrumentation and 2 2 3, 12 i Control Systems I G. Safety-Related 2 2 4, 12 i Components H. Corrective Action and 1 2 1 . Reporting , l I. Quality Assurance 2 2 5, 12 (Construction J. Quality Assurance 2 NA 6 (Operations) K. Design Contr. 2 1 7 L. Preoperational Testing 2 NA 1 Alb
. , . . . . . . . , . .. . l
\
Latest Previous Performance Category Performance Category Functional Area (8/1/83 to 12/31/84) (9/1/82 to-7/31/83) Notes M. Plant Operations 2 NA 8 Preparation N. Emergency Preparedness 2 NA 9
- 0. Radiological Controls 2 NA 10 I
P. Security 2 NA 1 Q. Training 2 NA 11, 12 i 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. ;
1 I
- 2. Additional management attention should be directed toward as-built verification and drawing resolution.
- 3. Additional attention and resources may be needed to accomodate 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 perfonning document reviews and other i 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 permanent plant positions should be filled.
f . . . .. .~. . . . . .. I i
- 9. Emphasis should be given to the timely correction of deficiencies identified during the emergency preparedness preoperational !
I 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 l releases, effluent monitoring, and transportation activities are l l
completed in a timely manner. l 1
- 11. Complete the definition of job qualifications and clearly define training and training requirements.
- 12. The Region is satisfied with licensee progress in this functional I area and the functional area is currently satisfactory for fuel load. ,
l II. NRC Region IV is continuing its review of licensee action on NRC f 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 9
" Ready to Clene" by the Licensee o Number of Items Determined by the Licensee 5 to be Nonreportable and which the Region has not yet reviewed o Number not Reported Ready to Close by the 32 !
Licensee , 1 IV. The licensee will resolve to the satisfaction of Region IV the open inspection items delineated in Appendix A to this enclosure. V. Compliance to Appendix R requirements was inspected by a team during the I 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 minor items. VI. Followup to the CAT inspection 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 were:
. i l
1 o Deficiency D4.3-3, Effect of Torsion / Rocking in Amplified Response Spectra o Unresolved Item U.14-1, Recoupling of Control Rod Drive Piping and l Supports o Unresolved Item 4.5.12-1, Standby Diesel Generator Lubricating 011 { Circulating Pump Motor Qualification { l o Unresolved Item U.6.7-1, Periodic Test of the Standby Service Water ' System VII. The final draft of the Technical Specifications was checked against installed equipment by a Region IV inspection team April 29-May 3, q 1985. Minor problems regarding requirements have been referred to NRR I for resolution. This inspection found that many licensee procedures were l not completed or had errors in them. It was concluded that the licensee's procedures to implement Technical Specifications would require an in-depth reinspection. The inspection report for this inspection is still under preparation, but the licensee was advised of the extent of the l i problems found by the exit meeting and a Region IV letter dated May 10, 1985. Appendix: A List of Open Inspection Items I l
.. Appendix m * . . 9 D h 'I4
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l ENCLOSURE 2 PRE 0PERATIONAL 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 48 Number of tests completed but not 18 22 reviewed Number of tests started 41 20 Number of tests not started 29 17 The licensee's review of data from the primary hydrostatic test indicated that some pressure vessel welds had not been witnessed by the ANI. This test was conducted again May 16, 1985. Additionally, the same contractor and 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: Previous Report Current Report Total number of tests 86 97* Number of tests completed and reviewed 42 68 Number of tests completed but not 8 5 reviewed Number of tests stai ted 10 8 Number of tests not started 26 16 l
*Previously combined tests have been separated.
)
I i
ENCLOSURE 3 CONSTRUCTION STATUS As of May 17, 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 112 systems identified by the licensee as needed to support a license to load fuel, 33 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, 18 systems have completed l the approval process. A completion date has not been established for the l remaining systems. l l l
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 ' 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 applicable. The list of remaining MC 2512 modules is as J follows: 1 Module Number Description Percent Complete {
*TI-2512/11 New Initiatives 30% l I
l
- 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 NA 70312 Preop Test Witnessing NA 70317 Reactor Protection Sys Test Witness 30% 70322 ESF Test Evaluation 0% (IntegratedECCS) 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 Procedure Witness 70% 70452 Remote Reactor SD-Witness 20% 70532 CROM Test Evaluation 0% 70541 Emergency Standby Power-Evaluation 0% 70552 Remote Reactor SD-Evaluation 0%
?5742 QA Program-Document Control 50%*
l I Module Number Description Percent Complete 35743 QA program-Maintenance 50%* 35744 QA Program-Design Changes 50%* , 35745 QA Program-Surveillance Test 50%* I 35750 QA Program MT&E 50%* l 42450 Operations Procedures 90% 42451 Maintenance Procedures 50% 42452 Emergency Procedures 30% 71301 Technical Specifications Review 90% 83522 Rad Protection-Preoperational 90% q 83523 Rad Protection-Preoperational 90% i 83524 External Exposure Control 80% 83525 Internal Exposure Control 80% 83526 Cont. of Radioactive Material 80% 83527 Facilities and Equipment 80% 83528 Maintaining Occupational Exposure 80% 84522 Solid Wastes 60% 84523 Liquids and Liquid Waste 60% 84524 Gaseous Waste System 60% 84525 Radiological and Chemical Confirm Meas. 75% TI2512/55 Emergency Preparedness 90% 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%** 81064 Compensatory Measures 0%** 81072 Access Control Packages 0%** 81074 Access Control-Vehicles 0%** 81080 Detection Aids 0%**
? . . . .. . . 4 1 Module Number Description Percent Complete 81084 Alarm Stations 0%** l 81088 Communications 0%** 81810 Physical Protection, S/G Info. 0%**
*The remaining 50% of these QA modules is done after implementation (i.e.,
af ter licensing). . 1
** Preliminary inspections of security have been completed; however, modules are carried at 0% complete pending lock down.
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 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% l 72509 Power Assession Procedure Review (B) 0% I 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% TI2500-11 Emergency Preparedness 80%
l l l ENCLOSURE 5 STATUS OF ALLEGATIONS RECEIVED BY NRC FOR RIVER BEND A total of 32 allegations have been received. Twenty-six of these have been closed and six are still open. The status of the six open allegations is as follows: Subject Source Status l
- 1. Sensitive 01 lead
- 2. Sensitive OI lead
- 3. Cable Trays Anonymous RIV lead
- 4. HVAC Testing Anonymous Violations to be issued in inspection report 85-23; this will close t this allegation
- 5. Harrassment of Eng. Anonymous GSU lead; RIV monitor Staff (S&W)
- 6. Control Room Circuitry Craft Worker GSU lead; RIV monitor Problems to GSU 1
l l t i
l 1 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 , confinnatory actions assigned to RIV for closure and still open: l 57 Licensed operator experience 62 ESF functioning J l e i I i
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