IR 05000373/1980052
| ML20003A684 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, LaSalle  |
| Issue date: | 12/18/1980 |
| From: | Fiorelli G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20003A680 | List: |
| References | |
| 50-373-80-52, 50-374-80-33, 50-454-80-22, 50-455-80-21, 50-456-80-14, 50-457-80-13, NUDOCS 8102040713 | |
| Download: ML20003A684 (16) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No.
50-373/80-52; 50-374/80-33 50-454/80-22; 50-455/80-21 50-456/80-14; 50-457/80-13 Docket Nos.
50-373; 50-374 Licenses No. CPPR-99; CPPR-100 50-454; 50-455 CPPR-130; CPPR-131 50-456; 50-457 CPPR-132; CPPR-133 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name:
Byron Units 1 and 2, Braidwood Units 1 and 2, La Salle County, Units 1 and 2 Meeting At: Chicago, IL Meeting Conducted: November 25, 1980 RIII h3C Personnel Present:
J. G. Keppler, Director G. Fiorelli, Chief, Reactor Construction and Engineering Support Branch (RC&ESB)
C. C. Williams, Chief, Projects Section 2, RC&ESB R. L. Spessard, Chief Projects Section 1, RONS C. E. Jones, Project Inspector, Byron Station E. R. Schweibinz, Project Inspector, Braidwood Station J. H. Neisler, Project Inspector, La Salle County Station R. D. Walker, Senior Resident Inspector, La Salle County Station J. E. Konklin, Project Inspector, Byron Station 8.C.9K W ~ V:
' Approved By:
G. Fiorelli, Chief
/8 ~- / E ' 84 Reactor Construction and Engineering Support Branch 81020407 h
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Meeting Summary Management Meeting on November-25, 1980 (Reports No. 50-373/80-52; 50-374/80-33; 50-454/80-22; 50-455/80-21; 50-456/80-14; 50-457/80-13)
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Areas Discussed: Management meeting held at the NRC's request to discuss the regulatory performance of the activities at Byron, Braidwood, and La Salle County Stations as concluded in the Systematic Assessment of Licensee Performance (SALP) program.
Results: A summation of the licensee evaluation was presented. Areas of concern were discussed with corporate management. The licensee's performance was rated as follows:
Braidwood Units 1 and 2: Average Byron Units 1 and 2: Average La Salle County Units 1 and 2: Average t
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DETAILS 1.
Persons Contacted
Commonwealth Edison Personnel Byron Lee Jr., Executive Vice President C. Reed, Vice President (Part Time)
A. W. Kleinrath, Manager of Construction W. Shewski, Manager of Quality Assurance B. Stephenson, Project Manager, La Salle J. J. Maley, Manager of Projects V. I. Schlosser, Project Manager, Byron /Braidwood T. R. Tram, PWR Nuclear License Administrator J. D. Deress, Project Engineering Manager, Byron /Braidwood B. R. Shelton, Project Engineering Manager, La Salle J. P. Woods, Station Construction Department L. J. Burke, Site Project Manager, La Salle L. C. Bird, Station Construction Department D. E. O'Brien, Assistant Superintendent, Braidwood R. E. Querio, Station Superintendent, Byron R. H. Holyoak, Station Superintendent, La Salle G. P. Wagner, Assistant Department Head, Station Nuclear Engineering D. Galle, Operations Manager, Nuclear Station Division L. O. Del George, Nuclear Licensing Administrator, La Salle R. Cosaro, Construction Site Superintendent, Braidwood 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 for each facility is enclosed).
c.
Several topics related to enforcement, the inspection program, and regulatory planning were discussed.
3.
Major Observations a.
Within the areas reviewed during the past year, the noncompliance history is not of significant regulatory concern. The number and severity of noncompliances relative to other comparable construction sites in Region III were low at Braidwood and average at Byron and La Salle.
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.b.
Only one of the construction deficiency reports of problems reported by the licensee pursuant to 10 CFR 50.55(e) was considered to be within the control of the licensee. The number of construction deficiencies reported by the licensee's 1.cilities-is considerably less than the; average for construction. sites in Region III.
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c.
Management efforts need to be increased in the areas of design controls, and in the establishment and implementation of procedural controls for pre-operational testing and startup.
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Additional improvement is needed in communications and interfacing between station construction department and the groups responsible for preoperational testing.
e.
Audits of vendor facilities should be improved both in audit scope and timeliness to identify and correct deficiencies in design control activities.
f.
Overall quality attitude can be improved, The organizations actually doing the work have the first responsibility to assure conformance to quality requirements and should implement more timely and effective corrective action to resolve nonconformances identified by quality assurance audits.
4.
Overall Assessment The overall regulatory performance of.ommonwealth Edison Company during the period July 1, 1979 through June 30, 1980, as related to the Byron, Braidwood, and La Salle facilities, is considered to be Average when com-pared with other comparable facilities in Region III.
5.
Planned NRC Action The licensee's performance to date, and the status of Region III inspec-tions, are such that no changes are planned in the routine inspection programs at Byron, Braidwood and La Salle.
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APPENDIX 8
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REGION.III
LICENSEE PERFORMANCE EVALUATION (CONSTRUCTION)
Facility: Braidwood Station Units 1 and 2 Licensee: Commonwealth Edison
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Unit Identification:
Docket No.
CP No./Date of Issuance Unit No.
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50 h56 CPPR-132/12-31-75
50-h57 CPPR-133/12-31-75
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Reactor Information:
Unit 1 Unit 2 Unit 3 NSSS Westinghouse Westinghouse
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gg, 1120 1120
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Appraisal Period:
July 1,1979 to June 30, 1980 Appraisal Completion Date:
November 17, 1980
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Rcview Board Members:
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E. R. Schweibinz, Project Inspector, RC&ES, RIII C. W. Moon, Project Manager, NRR C. C. Williams, Chief, Project Section 2, RC&EEB, RIII G. Fiorelli, Chief, RC&ESB, RIII J. G. Keppler, Director, RIII J. E. Konklin, Reactor Inspector, RC&ESB, RIII (C. E. Jones, Reactor Inspector, RC&ESB, RIII C. M. Erb, Reactor Inspector, RC&ESB, RIII E. J. Gallagher, Reactor Inspector, RC&ESB, RIII K. Naidu, Reactor Inspector, RC&ESB, RIII
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2955-B-1 4/15/80
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MC 2955 (App. B)
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A.
Number and ' Nature of Noncompliance Items t
Noncompliance category:
Unit 1 Unit 2 Unit *-
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Violations
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Infractions
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Deficiencies
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Areas of Noncompliance:
Unit 1 Unit 2 Unit 3 (List Areas as Required)
(Points)
(Points)
(Points)
Inadequate storage of records
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and equip =ent Inadequate procedures and storage
20
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conditions during shutdown
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Inadequate procedures for the
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control of IE Bulletins and Circulars
Inadequate design control
10
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Failure to follow procedures
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Total Points B.
Number and Nature of Deficiency Reports Defective trip breakers for safety injection signals. 11/29/79 Deficient Westinghouse rod drop analyses.
11/29/79 Intemittent contact operation of W-2 switches.
6/20/80 Part 21 Report - Leakage of Jamesbury valves.
h/18/80
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Escalated Enforcement Actions C.
Civil Penalties NONE
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Orders NONE
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Immediate Action Letters NONE
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2955-B-2 4/15/80
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MC 2955 (IPP. i,
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D.
Management Conferences Held During Past Twelve Months u
A meeting was held on March 28, 1980 at the Byron Nuclear Plant Site,
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among CECO corporate management and RIII managenent, to review the
, overall status of the Byron, Braidwood and LaSalle construction activities and to discuss specific technical areas of i'nterest.
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E.
Justification of Evaluations of Functional Areas Categorized as Requiring an increase in Inspection Frequency / Scope (See evaluation sheet)
The licensee's performance to date, and the completion of RIII inspections, are sucM that no changes are required in the routine inspection program at Braidwood.
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MC 2955 (App. B)
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Inspection
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Frequency and/or Scope
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FUNCTIONAL AREA Increase No. Change Decrease
Quality Assurance, Management & Training
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Substructure & Foundations X
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Concrete X
4.
Liner (Containment & Others)
y 5.
Safety-Related Structures
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y
6.
Piping & Hangers (Reactor Coolant
& Others)
X j
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Safety-Related Components (Vessel,
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Internals & HVAC)
l X
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Electrical Equipment
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Electrical (Tray & Wire)
X
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Instrumentation k
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11. Fire Protection X
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Reporting l
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CM:
5 NNxN'e v x
(Designated Regi'o6al Manager)
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Date
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2955-B-4 4/15/80
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1II 1 lcr;;SEE PEEFOE".A!;CE EVALUATIO!; (CO!;, SIP.UCTIO!i)_
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Tacility: Eyron Ststion Ur its 1 nnd 2
Licensee: Corr.snveelth Tdison Unit Identi-ation:
Docket !!o.
CP !!o./Date of Ir.suance Unit !'o.
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50-L5L CPPR-130/12-31/75
50-L55 CPPR-131/12-31-75
Ecactor Inforratien:
Unit l-
, Unit 2 Unit'3
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L'e 1120 1120
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A; praisal Period:
July 1, 1979 to June 30, 1930
/.ppraisal Co pletion Date:
- !yhtber IL, 1950
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Tcricw Eoard !!er.bers:
C. E. Jcnes, Troject Ir.spector, RCLES, RIII
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C. W. ;'aen, ' reject *:anscer, ::RR.
C..C.-Wi]I! us, Treject Secticn Chief, ROLES,;RIII-
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G. Ticrelli, Chief ECLES, RIII-J. G. l'eppler, Director, RIII J. E. Ecnklin, Eeacter Ir.cpector, ECLES, EIII_
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E. W. F. Lee, Fesetcr I:.crector, ECLES, RIII-
P. A. F.arrett, Feactor'Incpector. ECLES, PIII E. - J. Ca112cher, Ecactor Inspector, ECLES, -RIII
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T. C. Hawkins, Ecactor' Inspector, RC&ES, RIII
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E. "aidu, Ecactor Incrector, RCLES,.RIII_
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. J. Ccha,Wer, Ecactor Inspector, ECLES, RIII
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- I. 'I'. Yin, ?cactor In:pe: tor, ROLES, h1II:'
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D)l]30 X f
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A.
Nar5mr e nd Na t ure of No.iconn1 f anc e T t c.r.s Nonconpliance Category:
1* nit 1 Unit 2 Unit 3
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Violations
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Infra etions
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Deffefencies
1 Areas of Nonconpifance:
Unit 1 Unit 2 Unit 3.
(List Areas as Rec,ufred)
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,@ints)
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Inadequate Design Control
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Inadequate Procedures and
30 Failure to follow Procedures Inadequate Docunent Control
32 Inadequate Program for Inspection 20
of Sa fety-Related Work Inadequate Measures to Protect
10 Equipment failure to Audit Contractor's
10 Perforr.ance Total Foints 144 132 B.
Nusber and Nature of Def f ef ency Report s Defective trip breakers for safety injection signals. 11/2?/79 Failure of post-tensioning anchor-heads.
11/29/79 Deficient Uestinghouse rod drop analyses.
11/29/79 Internittent contact operation of W-2 switches.- 6/20/80 Part 21 Report - Leakage of Janesbury valves.
4/18/80.
C.
Escalated Enforce:ent-Actions
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Civil Pensities fDNE
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' t:ONE Itrediate Action Letters
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NONE --
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(*iP. B)
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it w rj r.ent,_ Conf c r c :::c :, Iteld Dgr ing Pa st T-cive Ibntig A n:eting t;as held on farch 28,1930 at the P ron f!sclear Pbnt S it e, i
a.mang Ceco corporate rsr.3;cecnt and RIII rir.agenc-nt, to review the overall status of t he nsraa craid.,ood and I 3Salle construct ion activities and to discuss sp:cific tect.aical areas of interest.
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E.
Justification of Evaluations of runctier.a) Areas cateoorized as recairi_ng
]ncrcase in Inspection f recuency/ Scope {See evaluation st.eet]
an The licensee's perforr.ance to date, and the completion of RIII insrections, are su:h that no changes are required in the routine
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inspection program at Byron.
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[D*"l0o o A\\ o m A llNct
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Intpection
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Treqtjency_ and/or Scope _ _, _
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fDNCIl0.'ML AREA Increase lio. Chang'e Decrtat.c I
1.
Quality Assurance, l'anager.ent & Training l
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X l
2.
Suh tructure & Foundations l
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X i
Concrete X
4.
'Lir.er (Contain:. ant & Others)
y 5.
Safety-Related Structures
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X 6.
Piping & !! angers (Reactor Coolant
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& Others)
l X
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Safety-Related Components (Vessel,
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'I Interr.als & liVAC)
X
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Electrical Fquipr.ent
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X
Electrical (Tray & k' ire)
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I ns trar.enta tion s.
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X
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31.
Fire Protection i
i X
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Preservice Inspection l
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X 13.
T.cporting
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.(D ignated RegidhPI itanager)
1-=L ik i <;se
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Date
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D**]O * 30TT $
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s sau 295.5 -E -4 4/15/c,0
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APPENDIX B
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REGION III LICENSEE PERFORMANCE EVALUATION (CONSTRUCTION)
Facility:
LaSalle County Station Licensee:
Cor=cnvealth Edison Company Unit Identification:
Docket No.
CP No./Date of Issuance Unit No.
50-373 CPPR 99/9-10-73
50-37h CPPR 100/9-10-73
Reactor Information:
Unit 1 Unit 2'
Unit 3 NSSS.
GE GE MWt 3293 3293 Appraisal Period: July 1, 1979 through June 30, 1980;
.Appraisa; Completion Date:
November 1, 1980-Review Board Members:
P. A. Barrett, Reactor. Inspector, RC&ESB, RIII A. Sournia, Project Manager, NRR'
'C. Erb, Reactor Inspector, RC&ESB,;RIII
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G. Fiore111,. Chief, RC&ESB,'RIII F. Rawkins, Reactor-Inspector, RC&ESB, RIII.
-C. Jones, Reactor Inspector, RC&ESB, RIII
'J.' Keppler, Director, RIII E. Lee, Reactor Inspector, RC&ESB,'RIII-F. Maura, Reactor Inspector, RO&NSB,.RIII
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'J. Neisler, Project Inspector,.LaSalle RC&ESB, RIII-
- M. 0estmann, Environmental (Inspector, FF&MSB, RIII,,_
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R. Walker, Resident ' Inspector, LaSa13e, RO&NSB, RIII ~
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4/15/80 I. Yin, Reactor Inspector,.RC&ESB, Rill
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MC 2955 (App. B)
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A.
Number and Nature of Noncompliance Items
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Noncompliance ratenorv:
Unit 1 Unit 2 Unjt_3 Violations
0 Infractions lh
Deficiencies
0 Areas of Noncompliance:
Unit 1 Unit 2 Unit 3 (List Areas as Required)
(Points)
(Points)
(Points)
Management Controls
(11h)
Audits
(30)
(10)
Qualification and Training
(10)
of Personnel (10)
Design Control
1 (10)
(10)
Total Points lhh
B.
Number and Nature of Deficiency Reports 1 - 10 CFR 50 55(e) report involving cracks in containment stub colurn cap plates. Deficiency corrected during report period by replacing defective cap plates with suitable material.
C.
Escalated Enforcement Actions Civil Penalties NONE NOE Orders Immediate Action Letten NONE
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2955-B-2-4/15/80
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M: 2955 (APP. B)
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D.
Manacecant Centerences Held Du _rin_o Past Twe_.l_ve Months
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A r.cetinc vnr held cn arch 28, 1930 at the 1yren rite, tetween CE:o
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corp: rate.inscenent and Eecicn :::
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.t 1: review the cverall statur of c.structicn activitier at r~ raidwacd and :yron site ana the ecnetructic n and precy rations; activitier at t he L12s11e site.
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E.
Justification of Evaluations of Functional Areas Catecorized as Requiring an increase in Inspection frecuency/ Scope (See evaluation sheet)
The licensee's perforr.ance is such that no chancer tre re uired in the routine inspection ;tegran at LaSalle.
2955-E-3 4/15/E3 0**]O *]O
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MC 2955 (App. B)
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Inspection
Frequency and/or Scope m
TUNCTIONAL AREA Increase No. Change Decrease
Quality Assurance, Management & Training j y
l 2.
Substructure & Foundations
,j 3.
Concrete y
4.
Liner (Containment & Others)
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5.
Safety-Related Structures f
y 6.
Piping & Hangers (Reactor Coolant l
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& Others)
X j
7.
Safety-Related Components (Vessel, j
X Internals & HVAC)
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X
8.
Electrical Equipment g
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9.
Electrical (Tray & Wire)
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j s
3.
Instrumentation l
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x 11.
Fire Protection
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x
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12.
Preservice Inspection l
X 13.
Reporting I
X
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I W,,an %lbnAe-(D,%dignatedRegioni4*anager)
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Date l
2955-B-4
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