ML17179A722

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Discusses Insp Rept 50-237/92-35 on 921019-1215 Re Circumstances Surrounding Identification That Reactor Vessel pressure-temp Curve in TS Figure 3.6.1 Was Nonconservative. NOV Re Failure to Provide Complete & Accurate Info Encl
ML17179A722
Person / Time
Site: Dresden 
Issue date: 02/12/1993
From: Davis A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Delgeorge L
COMMONWEALTH EDISON CO.
Shared Package
ML17179A723 List:
References
EA-92-253, NUDOCS 9302220016
Download: ML17179A722 (5)


See also: IR 05000237/1992035

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UNITED STATES

NUq..EAR REGULATORY COMMISSION.

Docket No.

50-237

License No .. DPR~19

EA 92-253

REGION.Ill.

799 ROOSEVELT ROAD

GLEN EL.LYN, ILLINOIS 60137

February 12, 1993.

Commonwealth Edison Company

ATTN:

Mr.-L. o. DelGeorge, Vice President,

Nuclear Oversight and Regulatory

Services

Ex~cutive T6wers Wes~ III *

1400 Opus Place Suite 300

60515

Dear Mr. DelGeorge:

SUBJECT:*

NOTICE OF VIOLATION

(NRC INSPECTION REPORT NO. 50-237/92035(DRP))

.This refers to the inspection conducted during the period of

October 19 thr6ugh December 15, 1992, ~t Dresden Statioh, Unit 2,

to.review the circumstinces surrounding your identification th~t

the reactor vessel pressure-temperature.curve .. in Technical

Specification Figure 3.6.1 w~s honconservative.

During this*

inspection a violation o~ NRC.requirements was identified.

The

report documenting the inspe6tion was ~ent to you by letter dated

December .24, 1992.

On January 22, 1993, **an enforce.ment

conference was held in the Region III off ice to discus~ the

~iolation~ .its cause and your corrective action~.

The re~ott

summarizing the conference ~as sent to you by letter dated

January 28, 1993.

On October 23, *1989, you submitted a Unit 2 Technical

specification amendment request to revise the pressure-

temperature curve to reflect the guidance in Regulatory

Guide 1.99, Revision 2.

Subsequently, on September 5, 1991,

Technical Specification Amendment No .. 114 was issued.

On

June 26, 1992, you identified that the Unit 2 reactor-pressure

temperature curve was nonconservative as a result of a review of

the data for the vessel beltline welds and made a one hour

telephone report.

During this revie~ you determined that the

material properties and the initial reference nil~ductility

temperature that were ~sed to develop the curve were based on

data ftom weld procedure qualification te~ting rather. than data

from the Unit 2 vessel materia~.

You subsequently submitted a

written licerisee event report pn July 16, 1992.

CERTIFIED -MAIL .

RETURN RECEIPT REQUESTED

  • ~----~

9302220016 930212

PDR

ADOCK 05000237

G

PDR

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190043

,*

Commonwealth Edison Company

_February 12, 1993

The violation,. which is described in the. enclosed Notice. of ..

  • Viola~ion (Notice) , concerhs a failure to provid~ complete and
  • accurate information in the Technical-Specification amendment

request.

The root cause of the violation was Cornrno'nwea1th Edison's

inadequate v~rification of contractor assumptions and erigineering

judgments which allowed an initial personnel.error to be

trarislated into* an inac~ur~te Technical Specification.

In

October 1988, a contractor employe~ incorrectly concluded that

the Unit 2 reactor vessel could be considered separately from

Unit 3 due to a personnel etror in his interpretation of a

summary table of-reacto~vessel material "and fabrication

information.

This conclusion was accepted by your ISI &

Materials Group Super~isor ind was subsequently used by General .

Electric in developing the new pressure-temperature curves.

In this particul~i case you have demonstrated tha~ reactor ~essel

in'tegrity was not* impacted and adequate margin against crack

. initiation existed at all times.

However, the sequence of events

which allowed you' to submit an inaccurate Technical Specitication

amendment request-is* a significant regulatory concern.

Further,

had the amendment request been.accurate at the time of submittal,

it would have resulted in a different NRC regulatory- position.

Theref_ore, in accordance: with the "General Statement of Policy * *

and Procedure for NRC Ehforce~ent Actions, (Enforcement Policy)

10 CFR Part 2, Appendix c, the violation has been categorized at

Severity Level III.

We acknowledge your immediate correctiv~ acti6ns which included

  • directing Operations to use the Unit 3 curve for Unit 2

operations and temporary procedure changes.

Additionally, on

September 16, ,1992, an amendment request was submitted to the NRC

to correct Figure 3.6.1~

We also acknowledge your long-term corrective.actions which

included an architectural-engineering guidebook to provide

specific requirements for selecting.design inputs for

calculations and otner design products, an agreement with your

reactor vendor which calls fo~ vendor engineering output

documents to contain certain information, guidance to your

erigineering personnel to.clarify ~anagement expectations for the

review of calculations and other design products, and procedural

improvel'[lents in the processes for ensuring the.quality of*

engineering: documents prepared internally.

In accordance with the Erifbrcement Policy a civil penalty is

considered for a Severity Le~el III violation.

However, after

consul tati,Oh _with. the "Dire-C-tor I -Off ice of Enf orcernen~t ,** and. th,f

Deputy Execritive Director for Nuclear Reactor Regulation, .

Regional Ope.rations and Research, I have decided that a civil

Commonwealth Edison Company

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February 12, 1993

penalty will not be proposed in this case.

In reachin~ this

  • decision, the st~ff considered the. adjust~ent ~actors in th~ NRC

Enforcement Policy.

We d~termined that full mitigation of the base civil penalty was

appropriate due to your identification of the nonconservative

pressure-temperatur~ curves, and your good corrective-actions.

The remaining factors in the Enforcement Policy were considered

and no further* adjustment to the base civil penalty was.

considered appropriate.

YoU are r~qrii~ed t6 respond to this letter and should foll6w the

instructions ~~ecified in th~ enclosed Notice when*pr~p~rin~ your

response.

In your respons~, you shbuld document the specific

actions taken and any additional actions you plan to prevent

recurrence.

After reviewing your re~pcinse to this Notice, *

  • including your proposed corrective actions and the results of

future inspections, the NRC will d~termine whether further NRC

enforcement action is* nebessa~y to ensrire cbmpliance with NRC

regulatory requirements.

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In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice,"-

a copy of this letter ~nd its enclosur~ will be placed in.the:N~C

Public Document Room.

The response directed by this lett~r and the enclosed Notice are

n6t subject to t~e clearance procedures of the Off ice of

Management ?nd Budget as required by the Paperwork Reduction Act .

9f 1980, PL 96-511.

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Sincerely,

lfflt~--- /J~

-A. Bert Davis

Regional Administrator

Enclosure:

Notice of Violation

See Attached Distribution:

Commonwealth Edison Company

Distribution:

cc w/enclosure:

,iFocD/DCB (RIDS) .

M:

Ly~ter, Site Vice President

c. Schr6eder, Station

Manager

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J. Shields, Regulatory Assurance

Supervisor

D. Farrar, Nuclear Regulato~y

Service~ Manager

OC/LFDCB

Resident Inspectors LaSalle,

Dreiden; Quad Cities, Clint6n

Richard Hubbard

J. W.

McC~ffrey, Chief, Public

Counsel, State of Illinois Center*

B. Siegel, Licensing Project Manager, NRR

T. Martin, Region III

J. Dyer, NRR

E. J. Leeds, NRR

M. t. Jor~an, RLII *

C. D. Pederson, RIII

S. Stasek, SRI, Davis Besse

. February 12, 1993

Commonwealth Edison Company

DISTRIBUTION:

PDR

.. SECY

CA

JTaylor, EDO

HThornpson, DEDS

.JSniezek, DEDR .

JLieberman, OE

WTros~oski, . OE *

LChandler, OGC

JGoldberg, OGC

TMurley, NRR

.JJ>artlow, NRR

Enforcement Coordinators

RI, RII, RIV, RV

Fingra:m, GPA/PA

DWilliams~ OIG

BHaye~, or

EJordan, AEOD

Day File

EA File

DCS

State of Illin~is

RAO:RIII

SLO:RIII

PAO:RIII

IMS:RIII

5

February 12, 1993