IR 05000354/1981006
| ML20004B997 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 05/20/1981 |
| From: | Bateman W, Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20004B993 | List: |
| References | |
| 50-354-81-06, 50-354-81-6, 50-355-81-06, 50-355-81-6, NUDOCS 8106010392 | |
| Download: ML20004B997 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCIMENT Region I 50-354/81-06 Report Nc. 50_-355/81-06 5C-354 Occket No. 50-355 CPPR-120
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License No. CPPR-121 Priority Category A
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Licensee:
Public Service Electric and Gas Comoany 80 Park Plaza - 17C Newark, New Jersey 07101 Facility Name: Hope Creek Generating Station, Units 1 and 2 Meeting at: Hancock s Bridge, New Jersey Meeting conducte :
April 0, 1981 9 d-I Znspectors:
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W. H. Bateman, Senior Resident Inspector
' 'dard signed date signed cate signed Approved by:
M20~ N
% G. Ereenm, Chie Reactor Projects date signed Section 2A Meeting Summary:
Meeting on April 30_,'1981 (Combined Report Nos_. 50-354/81-06 and 50_-355/8_1-06)_
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Scope:
Special, announcec' management meeting to discuss the results of the Region I co board convened to evaluata the licensee's performance from November.1,1979 to October l
31, 1980 as part of the NRC's SALP program. Areas addressed included but, were not limited,to Quality Assurance; Piping and Hangers; Reporting; and Management.
Results: A summary of the licensee performance evaluation was presented. Areas of concern were discussed with corporate and site management. No new enforcement actions were identified, however, two areas where improvement is necessary were identified.
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Region I Form 12 8106010$2 (Rev. April 77)
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DETAILS _
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Attendees Public Service Electric and Gas Company (PSE&Gl
J. T. Boettger, General Manager, Corporate QA A. E. Giardino, Project QA Engineer P. J. Kudless, Project Construction Manager A. Nassman, Manager, QA Engineering and Construction B_echtel Power Cor3 oration _ (Bech_tel)
D. L. Long, 3roject Superintendent G. Moulton, Prcject QA Engineer United State Nuclear Regulatory Comis_sion (_USNRC)
W. H. Bateman, Senior Resident Inspector, Hope Creek
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E. J. Brunner, Acting Director, ORPI E. G. Greenman, Chief, Reactor Projects 2A, DRPI 2.
Discussfon
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A brief summary of the Systematic Assessment of Licensee Performance (SALP) Program was presented to explain the basis and purpose of the evaluation.
The NRC Region I evaluation board meeting was discussed, including the
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appraisal period, performance data and the results of the board's evaluation. (See Appendix 1 and Attachments 1 and 2.)
The licensee's overall performance was considered acceptable although two areas will receive increased inspection effort by Region I to
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I detennine the effectiveness of the licensee's program improvements in those areas. These two areas of concern were identified to corporate and site management.
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Appendix 1
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SYSTEMATIC ASSESSMENT OF LICENSEE PERFORMANCE HOPE CREEK GENERATING STATION REGION I EVALUATION BOARD MEETING Facility:
Hope Creek Generating Station Units 1 and 2 Licensee:
Public Service Electric and Gas Company Unit Identification:
Docket No_.
Licensee No./Date of Issuance Unit No.
50-354 CPPR-120 November 4, 1974 Unit 1 50-355 CPPR-121 November 4, 1974 Unit 2
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Reactor Information:
Unit 1 Unit _2 NSSS General Electric General Electric MWt 3293 3293 Assessment Period:
November 1, 1979 to October 31, 1980 Evaluation Soard Meeting Data:
January 19, 1981 Evaluation Board Members:
B. J. Grier, Director, Region I J. M. Allan, Deputy Director, Region I E. J. Brunner, Acting Director, Division of Resident and Project Inspection i
R. T. Carlson, Director, Enforcement and Investigation Staf-W. G. Martin, Assistant to the Director
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R. J. Bores, Chief, Independent and Environmental l
Protection Section J. Kerrigan, Licensing Project Manager (Salem 2), NRR Other NRC Attendees:
W. H. Bateman, Senior Resident Inspector, Region I
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Attachm:nt 1
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BASIC PERFORMANCE DATA Hope Creek Generating Station Assessment Period:
November 1, 1979 to October 31, 1980 A.
Number _and Nature of Noncomo11ance Items 1.
Nonccmpliance category:
Unit 1-Unit 2 Violations
0 Infractions 10 + (4)
1 + (4)
Deficiencies
0 2.
Areas of Noncompliance:
(Vio/Inf/0ef)
(Vio/Inf/Def)
Quality Assurance 0/2+(1)/0 0/0+(i)/0 Concreta 0/1+(1)/0 0/1+(1)/0 Safety-Related Structures 0/2+(2)/0 0/0+(2)/0 0/4/0 0/0/0 Pip (ing and HangersReactorCoolantandOthers)
Safety-Related Cc=ponents 0/1/1 0/0/0 (Vessel, Internals,andHVAC)
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B.
Number and Nature _of Construction Deficiency Recorts
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Type of Events:
Unit 1_
Unit 2
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Personnel Error
2 S.
Design / Fabrication Error
1 C.
External Cause
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Causally-Linked Events:
None identified.
C.
_ Escalated __ Enforcement Actions
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Civil Penalties l
None l
2.
Orders.
None 3.
Immediate_ Action Letters None 4.
Other Escalated Enfercement l
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None
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D.
Manacement Conferences Held Ourine past Twelve Months
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No enforcement related management conferences were held during the assessment period.
There was, however, a routine meeting held with the licensee management at the licensee corporate office to discuss the following:
(a) Hope Creek project status, (b) status of FSAR, (c) resident inspection program, (d) NRC independent measurements program, (e) NRC programs underway to evaluate licensee performance, (f) 10 CFR 50.55(e) *eporting, and (g) enforcement policy.
E.
Licensee Activities Activity on both units varied extensively over the evaluation period because of a strike by the pipefitters local in May of 1980 ind cubse-quent large scale layoffs of other trades.
Prior to the strike the total site work force was approximately 3000.
During the strike period the work force dropped to approximately 200. After settlement of the strike in early June, 1980, the work force gradually increased to approximately 1400 by the end of the evaluation period.
Prior to the strike there was extensive activity in the areas of con-crete placement, containment erection, structural steel erection, and reactor pressure vessel (RPV) noztle modification for both Units 1 and 2.
Unit 1 piping installation was also in progress.
Simultaneously with the strike, the licensee announced a delay in the commercial operation dates of Units 1 and 2 frem May,1985 and May,1987
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to December,1986 and December,1989, respectively.
As a result of this delay, resumption of work activity, post strike settlement, was limited on Unit 1 and nearly non-existent on Unit 2.
Unit 1 activity
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was in the same areas as before the strike but limited to safety related work and Unit 2 activity involved minor concrete placements.
Milestones accomplished during the evaluation period included completion of erection and overpressure testing of Unit 1 containment, commencement of work on service water intake structure, completion of Unit 1 RPV nozzle modification, and connencement of Unit 2 containment erection.
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F.
Insoection Activities The construction resident inspection program was implemented in February, 1980.
Resident inspector activities involved acccmplishment of assigned inspection requirements including observation of work in progress-and evaluation of licensee responses to outstanding items. Nine inspection reports were issued by the resident inspector for each of the 2 units.
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Prior to implementation of the construction resident program, three inspections of Unit I and two inspections of Unit 2 were conducted by project inspectors during the assessment period.
These inspections involved observation of work in progress, ccmpleted work, records review, and resolution of outstanding items.
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Nine inspections were performed by regionally based specialist in-spectors.
The particular activities inspected were concrete, non-destructive examination, pipe welding, RPV roz le replacement, records,
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QA/QC procedures, site work procedures, cat' e tray installation, and resolution of outstanding items.
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Attachment 2
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HOPE CREEK GENdRATING STATION INSPECTION PROGRAM CHANGES INSPECTION TIME AND/0R SCOPE CHANGE FROM PRESCRISED INSPECTION PROGRA FijNCTIONAL AREA INCREASE NO CHANGE DECREASE
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1.
Quality Assurance 2.
Substructure and Foundations X
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x
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Concreta
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Steel Containment X
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Safety-Related Structures X
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Piping and Hangers (Reactor Coolant and Others)
X 7.
Safety-Related Ccmponents X
(Vessel, Internals, and HVAC)
X j
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Electrical Equip =ent X
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9.
Electrical (Tray and Wire)
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X 10.
Instrumentation
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X 11.
Fire Protection 12.
Preservice Inspection l
X X
13.
Reporting
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Environmental X
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Training X
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Management X
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Regt nalD{ector l$ l0b ww Date y n
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