IR 05000546/1980045
| ML19341C180 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 01/07/1981 |
| From: | Fiorelli G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19341C176 | List: |
| References | |
| 50-546-80-45, 50-547-80-45, NUDOCS 8103020240 | |
| Download: ML19341C180 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-546/80-45; 50-547/80-45 Docket Nos. 50-546; 50-547 Licenses No. CPPR-170; CPPR-171 Licensee:
Public Service of Indiana P. O. Box 190
,New Washington, IN 47162 Facility Name: Marble 11111 Nuclear Generating Station, Units 1 and 2 Meeting At: Marble 11111 Site, Jefferson County, IN
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. Meeting Conducted: December.9, 1980
'NRC Personnel Present:
J. G. Keppler, Director RIII G. Fiorelli, Chief, Reactor Construction and
. Engineering Support Branch
C. C. Williams, Chief, Project Section 2
'J.-J. Ilarrison, Resident' Inspector g
E. R. Schweibinz, Project Inspector
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Approved By:
_G.
Fiorelli, Chief, 54/Ahd2 Reactor Construction and f/g j
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Engineering Support' Branch
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cMeeting" Summary Management Meeting on' December 9, 1930 (Reports No. 50-546/80-45; 50-547/80-45)
Areas Discussed: Management meeting held at the'NRC's request to discuss the regulatory performance.of _ the activities at the Marble liill. Nuclear Generating
. Station as-concluded in the Systematic Assessment of Licensee Performance (SALP)
Program.
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Results: i A summationLof the licensee's performance evaluation was' presented.
~ Areas _ of concern were discussed with corporate -management.
In view of the.
- fact ?that. safety related construction work' was suspended by an NRC Order for
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Emost of theLappraisal period, there was_no basis to compare the 1icensee's
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regulatory ~ performance with other plants tutder construction in Region III.
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I DETAILS 1.
Persons Contacted Public Service of Indiana (PSI)
- D. V. Menscer, President S. W. Shields, Senior Vice President - Nuclear Division L. O. Ramsett, Quality Assurance Manager W.'M. Petro, Project Director J. U. Bott, Nuclear Regulation and Affairs Manager
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M. L. Morris, Executive Assistant
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- Denotes that the individual attended part of the meeting. -
2.
Areas Discussed A summary of the SALP program was presented, including the development,
.a.
-the-basis for evaluation, and its purpose.
-b.
The results of the~NRC's. evaluation of the licensee's performance were discussed.
(A copy of the evaluation is attached.)
c.
Several' topics related to enforcement, the inspection program, and regulatoryLplanning were discussed.
3.
Major Observation Within the areas reviewed during this evaluation period of July 1, a.
1979 through June 30, 1980, the noncompliance history was of some concern, in that the number and severity of noncompliances were above
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. average relative to other comparable construction sites in Region III.
-It.was noted however,. that the number of-inspector hours on site was 3also the highest of any construction site-in Region III.
In regard to the number of items of noncampliance:it is the Region III opinion that the: corrective actions that the licensee has taken in the past year with regard to-their QA. program, and the staf fing and manning of site organizations, can effe'ctively minimize the number of noncompliances
- receivedfin the-future, if these. programs are rigorously implemented.
b.-
Nineteen construction' deficiency reports of problems 'were reported
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by the' licensee in accordance with 10 CFR 50.55(e) during this evaluation period; Eight of these were retracted.
Of_the remaining
- eleven: deficiencies :
six:were generated for items which Westinghouse controlled;'one item was under the control of the poiar crane manu-
- facturer; ~ arid. four deficiencies-were generated. for items under PSI's
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control.
0f' these four, three were identified during the construction
- verification program. No instances'were identified by. Region III.in which an item'which should havelbeen reported, was not.
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Management efforts need to be increased in the area of self-evaluations (audits and surveillances).
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Additional improvement is needed in communications and interfacing between the various site organizations.
4.
Overall Assessment In view of the fact that safety related construction work was suspended by an NRC Order for most of the appraisal period, no overall assessment of licensee regulatory performance is meaningful. The conditions of the Order were complied with during this period.
5.
Planned NRC Actions The licensee's performance to date, and the status of Region III inspections are such that the present increased frequency of inspections will be con-tinued until the licensee has adequately demonstrated the implementation of his QA program.
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APPENDIX B
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REGION III
1.ICENSEE PERFORMANCE EVALUATION (CONSTRUCTION)
Facility: bbrble Hill Nuclear Station, Units 1 and 2 Licensee: Public Service of Indiana Unit Identification:
Docket No.
CP No./Date of Issuance Unit No.
50-546 CPPR-170/04-04-78
50-547 CPPR-171/04-04-/8
Rcactor Information:
Unit 1 Unit 2 Unit 3 NSSS Westinghouse Westinghouse
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MWe 1130 1130
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Appraisal Period:
July 1, 1979 to June 30, 1980 Appraisal Completion Date:
December 5, 1980 Review Board Members:
E. R. Schweibinc, Project Inspector, RC&ES, RIII J. J. Harrison, Resident Inspector, RC&ESB, RIII J. N. Wilson, Project Manager, NRR G. Fiorelli, Chief, RC&ESB, RIII C. C. Uilliams, Chief, Project Section 2, RC&ESB, RIII D. W. Hayes, Chief, Engineering Support Section 1 P. Barrett, Reactor Inspector, RC&ESB, RIII C. M. Erb, Reactor Inspector, RC&ESB, RIII E. Gallagher, Reactor Inspector, RC&ESB, RIII F. Hawkins, Reactor Inspector, RC&ESB, RIII J. Hughes, Reactor Inspector, RC&ESB, RIII F. J. Jablonski, Reactor Inspector, RC&ESB, RIII C. E. Jones, Resctor Inspector, RC&ESB, RIII J. E. Konklin, Reactor Inspector, RC&ESB, RIII K. Naidu, Reactor Inspector, RC&ESB, RIII J. H. Neisler, Reactor Inspector, RC&ESB, RIII
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MC 2955 (App. B)
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A.
Number and Nature of Noncompliance Items Noncompliance category:
Unit 1 Unit 2 Unit 3
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Violations ~
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Infractions -
25
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Deficiencies
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Areas of Noncompliance:
Unit 1 Unit 2 Unit 3
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(Points)
(Points)
(Points)
Lack of adequate training and
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-failure to significantly implenent the QA program
20 Inadequate design contrel
30 Failure to include quality requirements in procurement documents-
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Lack of or failure-to follov -
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60 precedures Failure to assure purchased services
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10 Failure to assure the-special process-
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Inadequate inspection program 20-
Failure to provide proper storage and instructions for maintenance of materials
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Failure.to-properly control material-
'which did not conform to requirements and failure to-
- adequately identify. storage nonconformances
20 Failure to take. adequate corrective'
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action Failure.to maintain sufficient records-Lto ' furnish evidence of activites
'affecting; quality.10-250;
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B.
Nurber and Unture of Peficiency Reports
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Repair of polar crane coatings.
08/02/79 Use of Hilti " shot-on" studs to hane, temporary lighting en safety related entednent plates.
03/06/79 Potential Westinghouse control problens.
(Interaction of non-safety with safety related controls. ) 03/31/79 Improper bolting of Catecory I structural steel in auxiliary building (vashers).
12/28/79 Lack of test or equirnent to detect failure of Westinghouse pernissive P-b which could lead to loss of safety functicn.
01/11/80 Fotential for erronous stean generator water level indicaticn during high enercy line break.
01/16/80 Non-conservative rod drop analysis by Westinghouse.
01/16/80 Questionable veld filler material in Categcry I pipe.
03/26/80 Westinghouse scenario which could result in the failure of the charging purps during safety injection.
05/09/80 Westinghouse reported a problen concerning the inproper functioning of type W-2 switches.
06/19/80 SPP-2 reinspecticn of reinforcing steel has identified cases of inproper rebar sise, number, spacing, and cicar cover.
06/27/80 C.
Escalated Enforcenent Actions Civil Penalties - None Orders OS/15/79 - Order confirning suspensien of all safety related verk Innediate Action Lette,r 07/23/79 - Innediate Acticn Letter stcpping the placement of concrete for safety related structures D.
Management Conferences Held During Past Twelve Months Nunerous managenent conferences were held during this evaluation period both prior to and after the Order. These conferences all involved dis-cussions in connection with the various ccnstructicn problems identi-fied at the site as addressed in the IAL or the Order. They occurred on the folleving dates:
07/07/79 08/01/79 12/10/79 02/27/80 07/10/79 08/15/79 01/21/80 03/31/60 07/20/79-11/08/79 02/20/80 OL/30/80 06/27/80
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On March 25, 1980 a public neeting was held in Madison, Indiana to discuss' the licensee's response to the August 15, 1979 " Order Confirning Suspension of Constructien".
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E.
Justification of Evaluations of function _al Areas Categorized _ as Requiring an increase in Inspection Frequency / Scope (See evaluation sheet)
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The present increased frequency of inspections will be continued until the licensee has adequately demonstrated the implementation of his QA program.
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MC 2955 (App. B)
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Inspection
Frequency and/or Scope FUNCTIONAL AREA Increase No. Change Decrease 1_
Quality Assurance, Management & Training l 2.
Substructure & Foundations X
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Concrete X
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Liner (Containment & Others)
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Safety-Related Structures I
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- Piping & Hangers (Reactor Coolant l
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& Others)
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Safety-Related Components (Vessel, I,
Internals & HVAC)
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Electrical Equipment I
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Electrical (Tray & Wire)-
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Instrumentation l
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Fire Protection X
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Preservice Inspection
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Reporting l
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(Designated Regional Manager)
Date
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-2955-B-4-4/15/80
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