IR 05000458/1980010
| ML19351D842 | |
| Person / Time | |
|---|---|
| Site: | River Bend |
| Issue date: | 10/03/1980 |
| From: | Beach A, Crossman W, Seidle W, Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19351D837 | List: |
| References | |
| 50-458-80-10, NUDOCS 8011200102 | |
| Download: ML19351D842 (10) | |
Text
.
.
.
O U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-458/80-10 Docket No.
50-458 Category A2 Licensee: Gulf States Utilities Post Office Box 2951 Beaumont, Texas 77704 Facility Name: River Bend Station, Unit No. 1 Meeting at:
Baton Rouge, Louisiana (September 17, 1980)
.
'
/LIjl.y
!
NRC Participants:
c _
4,
'
K. V. Seyfrit, Dir or,' Region IV Date
.
.
/
//
A/ Llw
/
,, ig.
W.C.Seid{6eringSupportBranch e, Chief, Reactor Construction Date and Engiu
_-
-
/d/4/d!Po W. A. Crossman, Chief, Projects Section Date M ou S L
ro/alo A. B. Beach, Reactor Inspector, Projects Section Date Approved by:
m; -
/O/S[8o V. A. Crossman, Chief, Projects Section Date Meeting Summarv Meeting on September 17, 1980 (Recort No. 50-458/80-10)
Meeting Topics: Announced meeting with GSU corporate management concerning the evaluation of the licensee's performance.
.
8011200/#
.
.
DETAILS SECTION 1.
Persons Contacted Principal Licensee Employees L. Humphreys, Senior Vice-President, Engineering and Construction W. J. Cahill, Jr., Senior Vice-President, River Bend Nuclear Group T.'C. Crouse, Director, Quality Assurance J. E. Wimberly, Superintendent, Site Construction K. C. Hodges, Quality Assurance Engineer P. D.-Graham, Supervisor, Quality Engineering J. E. Booker, Manager, Technical Programs NRC Participants K. V. Seyfrit, Director, Region IV Office of Inspection and Enforcement W. C. Seidle, Chief, Reactor Construction and Engineering Support Branch W. A. Crossman, Chief, Projects Section A. B. Beach, Future Resident Reactor Inspector, River Bend Station 2.
Meeting Vith Gulf States Utilities Management A.
Purpose of Meeting The purpose of this meeting was to describe the regional evaluation for the systematic appraisal of licensee perfonnance. This evalua-tion is an integral part of the Systematic Assessment of Licensee Perfocmance (SALP) Program which is to be implemented in accordance with the commitments of the " Action Plan for Implementing Recommenda-tions of the President's Commission and Other Studies of TM1-2 Acci-dent."
The attached Appendix A is the performance evaluation for the River Bend facility for the period September 1, 1979, through August 31, 1980, compiled by the NRC participants and a Regional Review Board.
To begin the meeting, the Regional Director outlined the following objectives for a systematic appraisal of licensee performance:
Identify exceptional or unacceptable licensee performance
-
Improve licensee performance
-
-
Improve the IE inspection program Provide and achieve a means of regional consistency in
-
evaluating licensee performance B.
Enforcement History The enforcement history for the River Bend facility was reviewed. The j
following noncompliances were issued during the period of September 1, 1979, through August 31, 1980, by NRC, Region IV IE Inspectors
'
__
.
.
Failure to control ordering of safety-related concrete
-
' Failure to follow manufacturer's instructions for the storage
-
of reinforcing steel mechanical splice sleeves Failure to provide required information in a petrographic report
-
Failure to pecvide timely notification of construction deficiencies
-
Deletion of and failure to specify acceptance criteria
-
'ailure to identify unsatisfactory test results and follow
-
construction specifications Failure to perform and failure to identify inadequate
-
aggregate tests Failure to follow procedures for certification of FQC inspection
-
personnel Failure to follow procedures for utilization of qualified inspec-
-
tion personnel for the performance in site inspection activities Failure to meet specification requirements for the qualificatica
-
of No. 67 and No. 8 coarse aggregates Failure to follow procedures for the identification of training
-
needs Failure to follow procedural requirements for good housekeeping
-
I Inappropriate accept / reject criteria for total air content in
-
an exterior wall The following deviations were issued during this same time period:
Qualification of individuals as Level II inspectors who do not
-
meet the ANSI N45.2.6 experience qualifications for a Level II capability Performance of QC inspection activity reviews by inspection
-
personnel not in accordance with the ANSI N45.2.6 requirements
,
Use of air entrainment admixture in Category I concrete
-
Hot weather concreting
-
Concrete placement
-
i
,
Y
.
.
-.~
.
-
-.
_-
_
_
_.
.
,
,
,
.
.
,
These eighteen enforcement actions (noncompliances and deviations)
were issued during 603 man-hours of direct inspection at the site
~during nine routine NRC inspections. Special inspections and investi-gations stre not considered in these calculations.
,
The NRC participants determined that had better corrective action been taken to the problems addressed in the enforcement actions, especially in the area of concreting activities, the number of
enforcement actions could have been substantially lessened. The licensee attendees agreed and stated that in the future they would try to make improvements in this area.
C.
Construction Deficiency Reports The following construction deficiencies were reported by the licensee during the period September 1, 1979,- through August 31, 1980:
i Irregularities of concrete materials testing
-
Low yield of tensile test of mat anchor steel ring
-
,
ASTM C227 mortar bar tests
-
NDE performed during fabrication of primary shield wall by CBI
-
-
Miscellaneous steel deficiency provided by Cives Steel Reinforcing steel surface imperfections
-
"
~ Improper repair of rejectable cadweld
-
Misalignment of computer data for safety relief valve setting
-
.
Cold joint in Diesel Generator Building foundation slab
-
f Improperly qualified No. 8 and No. 67 aggregates
-
.
Stop work Category 1 concrete-form displacement, cold joint
-
1 Error in calculation of modulus of elasticity in shield wall
-
The NRC participants concluded that the threshold of reportability
established by the licensee was adequate, and that the performance I
of reporting the deficiencies by the licensee was in accordance with the imposed requirements (reportability of construction deficiencies was discussed with the licensee in a management meeting i
held November 2,1979, in Inspection Report 50-458/79-07).
!
!
l
.
a
.
- - -
-
rn
.
.
,
_
_
_
.
.
f
.
D.
' Escalated Enforcement Actions An tamediate action letter was issued on November 6,1979, concerning the verification of concrete ingredients used in Category I concrete placements. This was the only escalated enforcement action taken by the NRC during the evaluation period.
E.
Licensee's Responsiveness and Ability to take Meaningful Corrective Action The NRC participants discussed the licensee's responsiveness to IE Bulletins, IE Circulars, and IE Information Notices.
It was found to be rompt and adequate to meet the necessary requirements.
Responses to NRC inspection reports and enforcement actions were
.
then discussed. Basically, as stated earlier in this report, responses
'
to enforcement actions need to be improved. These responses need to specifically address the problem involved, and the corrective action taken in response to the identified problems needs to be re-evaluated.
Specific examples of inadequate responses to NRC identified items of noncompliance were demonstrated in Inspection Reports No. 458/80-05, 458/80-06, and 458/80-07. Additional information was requested re-garding t.he responses to Inspection Report No. 458/80-05 in our letter.
of -ugust 15, 1980. The licensee was informed that similar requests for additional information concerning the responses in Inspection Reports No. 458/80-06 and 458/80-07 will be forthcoming.
F.
Effectiveness and Attitudes in Complying with NRC Regulatory Requirements
The identification of significant trends that may be adverse to the
,
i construction of the facility or that may impair compliance with NRC
[
regulatory requirements must be an important part of the licensee's
quality assurance program. A significant trend that was observed over the evaluation period was an excessive number of specification changes deleting requirements after i problem was identified. Most
<
of these changes were made in the aciconservative direction.
Specific examples discussed were as follows:
g False set test of cement (ASTM C451)
-
Heat of hydration tests
-
Correlation tests of ASTM Cl38 and ASTM C567
-
-
Minimum concrete density of 135 pounds per cubic foot ASTM C227 mortar bar tests
-
t
-.
_. - _-.
.
-. -
_
-
..
.
I Air entrainstat. requirements
-
Excessive gradation failures
-
Control of concrete by " fear of rejecting" trucks
-
G.
Summa ry The Region IV Director, at the conclusion of the meeting, emphasized that the licensee has principal and legal responsibility for all matters associated with the construction of the nuclear power plant as specified in applicable regulations. Corporate management involve-ment is essential in all phases of the project to assure appropriate execution of the licensee's responsibilities.
The NRC participants stressed the importance of adequate responses to NRC enforcement actions, and emphasized the importance of specifi-cation changes and their relation to NRC commitments.
It was re-emphasized that these two areas needed improvement.
3.
Site Tour Various NRC participants toured the site and observed activities in pro-gress. On September 18, 1980, two IE inspectors observed concrete place-ment activities in progress. Air entrainment limits were noted to be well within acceptable industry _ standards, and slump adjustments were being mac * according to the immediate placement conditions.
No items of noncompliance or deviations were identified.
.
-
-
,
-
...
.. - -.
._, _.
.
-
_ _ _
.
. -.
-
._
.
.
APPENDIX A
i LICENSEE PERFORMANCE EVALUATION (CONSTRUCTION)
Facility: River. Bend Nuclear Station
'
Licensee: Gulf States Utilit'ies Company Unit Icentification:
Doc.ket No.
CP No./Date of Issuance Unit No.
50-458 CPPR-145/ March 1977-
!
-
.
Reactor Information:
Unit 1 Unit 2*
Unit 3 NSSE-General Electric X
X
MWe 934 X
X
- Unit 2 is on an fndefinite hold at the time of this inspection Appraisal Period:
September 1,1979 through August 31, 1980 Accraisal Comoletion Date:
September 30, 1980
>
,
Review Board Memeers:
W. C. Seidle W. A. Crossman A. B. Beach C. R. Oberg
,
L. D. Gilbert
.
-,w w
w
-
ww-w-
~
w,
-, - -
w w->
-
y
.-
,,,e-,
.
_
_ _ _.
.
.
.
.
.
.
-2-A Number and Nature of Noncemoliance Items Noncompliance Category:
Unit 1-Unit 2 Unit 3 Violations
X X
Infractions
X X
Deficiencies
X X
Areas of Noncompliance:
Unit 1 Unit 2 Unit 3 (List Areas as Required)
(Points)
(Points)
(Points)
Concreting Activities
X X
QA Management
X X
Reporting
X X
t Deviations (5)
,
Total Points i
132 X
X l
S.
Number and Nature of Deficiency Recorts
1. Irregularities concrete materials testing 7. Improper repair Cadweld
2. Low yeild tensile strength mat ring 8. Relief valve setting 3. ASTM C227 mortar bar tests 9. Cold joint Diesel Generator Bldg.
4. NDE Shield Building CBI 10. Improper qualified #8 & #67 aggre-5. Cives miscellaneous steel gate
.
6. Reinforcing steel surface imperfections 11. Stop work on Category I concrete
!
12. Modulus of elasticity error
.
,
C.
Escalated Enforcement Actions
Civil Penalties None Orders
.
None
Immediate Action Letters November 6,1979: Halt placement of concrete in safety-related structures until-verification of qualification tests of concrete ingredients is assured.
.
,
,
-
--..--e m
w.
-
,.
.
~
.
-
-
-
-
'
.
t-3-D.
Management' Conferences Held During past Twelve Months i
November 2, 1979: Discuss 50.55(e) reporting requirements and discussion of Part 21 requirements (Inspection Report No. 50-458/79-07)
September 17, 1980: Corporate management meeting held to discuss the regional evaluation of licensee performance during the period September 1, 1979, through August 31, 1980. This meeting was also held to discuss signi-cant trends identified in the previous inspections and to re-emphasize the importance to the licensee of meeting their comnitments to the NRC require-ments (Inspection-Report No. 50-458/80-10)
E.
Justification of Evaluations of Functiont.' Areas Categorized as Requiring an Increase in Inspection Frequency / Scope (see evaluation sheet)
The area of Quality Assurance, Management and Training is a functional
area where 'an increase.in inspection, both in frequency and scope, will be required. The review board unanimously agreed tnat an increase in inspection in this area was justified in that the corrective action by the licensee taken in response to NRC identified problems needs to be improved.
The functional area of tP.e Suostructure and Foundations is an area where the inspection effort will be decreased in that much of the safety-related work in this area is completed.
The area of Concrete is a functional area where the review board again unanimously agreed that an increase in the scope of the inspection
.
effort would be necessary. Although the amount of inspection effort
'
already perfonned in this area is substantial, more inspection time must be expended until the placeability problems, discussed during the management meeting on September 17, 1980, are solved.
l
.
,
, _ _,
-..
,_
._
._
.
_
m
_
m.__ ;.
--..
.
..
,
,
.
.+
E e-4-
!
.
J Inspection
'
Frecuency and/or Sccoe
,
FUNCTIONAL AREA INCREASE.
NO. CHANGE DECREASE
.l.
Quality Assurance, Management & Training X
-
2.
Substructure.1 Foundations y
3.
Concrete 4.
Liner (Containment & Others)
X 5.
Safety-Related Structures X
6.
Piping & Hangers (Reactor Coolant
.'
& Others)
x
,
Safety-RelatedCompon$nts(Vessel, 7.
Internals & HVAC)
.
y
[
3.
Electrical -Equipment y
9.
Electrical (Tray & Wire)
Y
!
10.
Instrumentation i
Y 11.
Fire Protection Y
I 12.
Preservice Inspection Y
i
-
l 13.
Reporting X
r i
I I
l I
!
I i
l l
l
,
.
.
i
,
l
'
i
,
1
!
.
_
,.
..
.
-
. - -, _., _ -. - - - _...
-
- -. _, - - - -, - __
.
_. _ _., - _ - - -. _ - _