ML15224A712

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Discusses Insp Repts 50-269/90-17,50-270/90-17 & 50-287/90-17 on 900520-0616 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000
ML15224A712
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 08/16/1990
From: Ebneter S
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Tucker H
DUKE POWER CO.
Shared Package
ML15224A713 List:
References
EA-90-119, GL-88-14, NUDOCS 9008270246
Download: ML15224A712 (6)


See also: IR 05000269/1990017

Text

AUG 16 1990

Docket Nos. 50-269, 50-270, and 50-287

License Nos.

DPR-38, DPR-47, and DPR-55

EA 90-119

Duke Power Company

ATTN:

Mr. H. B. Tucker, Vice President

Nuclear Production Department

Post Office Box 1007

Charlotte, North Carolina 28201-1007

Gentlemen:

SUBJECT:

NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY - $25,000

(INSPECTION REP.ORT NOS. 50-269/90-17, 50-270/90-17 AND 50-287/90-17)

This refers to the Nuclear Regulatory Commission (NRC) inspection conducted by

the Resident Inspectors at the Oconee Nuclear Station during the period May 20

June 16, 1990. The inspection included a review of the circumstances surrounding

the apparent design error in the Reactor Building Penetration Room Ventilation

System (PRVS) that could render the system inoperable under specific conditions

that were identified by the NRC during a detailed walkdown of the PRVS. The

report documenting this inspection was sent to you by letter dated June 27, 1990.

As a result of this inspection, a significant failure to comply with NRC regula

tory requirements was identified, and accordingly, NRC concerns relative tothe

inspection findings were discussed in an Enforcement Conference held on July 12,

1990. The letter summarizing this Conference was sent to you on July 18, 1990.

The two violations in the enclosed Notice of Violation and Proposed Imposition

of Civil Penalty (Notice) involve the issues surrounding your failure to ensure

that an Engineered Safeguards (ES) system (the PRVS) would be able to perform

its intended safety function and your failure to respond completely and

accurately to an NRC Generic Letter (GL).

Violation I in the Notice deals with an NRC Resident Inspector's discovery on

June 12, 1990, (with Unit 1 at 97 percent and Units 2 and 3 at 100 percent full

power) that two pneumatic throttle valves on each unit would fail closed on a

loss of instrument air versus failing open as indicated in the FSAR. It appears

that this condition has existed since before the plant was licensed in 1973. The

NRC believes the root cause of this problem was an original design deficiency,

including deficient documentation, and that it was compounded by your failure

to recognize the significance of the problem and to take appropriate corrective

action. Specifically, in 1982 in a document titled, "Loss of Instrument Air,"

you identified that for instrument air pressure dropping from 100 to 70 psig,

"PR-13 (PR Fan "A" Inlet Control) closes and PR-17 (PR Fan "B" Inlet Control)

closes which prevents operation of the Penetration Room Ventilation System."

However, despite this observation, you failed to recognize the significance of

.

the problem and correct it. Furthermore, in another instrument air study in

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Duke Power Company

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AUG 1 6 70

1984, you referenced the 1982 document and reiterated that a loss of instrument

air would prevent operation of the PRVS. In this case, the report was routed

to high level management at Duke and the significance of the issue was still

not recognized and corrective action was still not taken. In addition, you had

at least two other opportunities in which you should have recognized and

corrected this problem. Specifically, in 1987 during a design study initiated

to identify active valves, you should have recognized that valves PR-13 and

PR-17 were active valves in that they would need to be repositioned after a

loss of instrument air to enable the PRVS to perform its intended function. The

NRC believes that if you had properly classified these valves during this

review, you should then have been able to subsequently identify the deficiency

of the system configuration and the discrepancy with the FSAR. In August 1988,

during your review in response to NRC Generic Letter 88-14 (GL 88-14), "Instru

ment Air Supply System Problems Affecting Safety-Related Equipment," a review

directed at identifying this type of discrepancy, you should have recognized

that these two valves are considered safety-related and that, per the instruc

tions in GL 88-14, should have been verified as being able to function as

intended on a loss of instrument air.

Although from a technical standpoint, the resulting dose from the unavailability

of the PRVS may not have been above the 10 CFR Part 100 limit, the ventilation

system was clearly degraded. From a regulatory standpoint, the NRC considers

this problem to be a serious regulatory concern because of your failure to take

appropriate corrective action despite the numerous opportunities you had to

.recognize

the significance of this problem. Therefore, in accordance with the

"General Statement of Policy and Procedure for NRC Enforcement Actions,"

(Enforcement Policy) 10 CFR Part 2 Appendix C (1990), Violation I has been

categorized at Severity Level III.

The staff recognizes that you took prompt action and declared both trains of the

PRVS inoperable on all three units upon the NRC Resident Inspector's identifica

tion of the problem and placed all three units in a Technical Specification

action statement requiring the units to be shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. We were

informed promptly of your temporary modifications to the valves and of your

ongoing review of the issue. The staff also recognizes the promptness of your

corrective actions with respect to your incomplete response to GL 88-14,

including your review of the responses to GL 88-14 for both the McGuire and

Catawba facilities. In addition, the staff commends you for your thorough and

frank Licensee Event Report (LER) 269/90-10, to the extent that it clarified and

traced the history of this issue.

However, to emphasize the importance of taking prompt corrective action, I have

been authorized, after consultation with the Director, Office of Enforcement,

and the Deputy Executive Director for Nuclear Reactor Regulation, Regional

Operations and Research, to issue the enclosed Notice of Violation and Proposed

Imposition of Civil Penalty (Notice) in the amount of $25,000 for Violation I.

The base value of a civil penalty for a Severity Level III violation is $50,000.

The escalation and mitigation factors in the Enforcement Policy were considered.

Escalation of the base penalty was considered for Violation I because the NRC

identified the problem and because of the numerous opportunities you had to

identify and recognize the significance of the problem. However, the NRC

Duke Power Company

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- AUGI 8

y

considered your thorough investigation into the issue after it was identified,

and determined that on balance, the base penalty was neither escalated nor

mitigated for identification and reporting. The base penalty was mitigated by

50 percent for your prompt and extensive corrective action once you fully recognized

the problem, including your subsequent review of all air operated safety-related

valves. Several issues were considered with respect to your past performance.

On December 13, 1988, you received a civil penalty for a Severity Level III

violation associated with the high pressure injection "piggyback" mode of

operation. This violation was compounded by a breakdown in your communications

that hindered the resolution of the problem once it was already identified.

However, your past performance in this area has been satisfactory, as evidenced

by your SALP Category 2 ratings in the areas of engineering/technical support

and safety assessment/quality verification. Therefore, on balance, the base

civil penalty was neither escalated nor mitigated for your past performance.

The multiple occurrences factor was considered, but was not deemed applicable

to the circumstances of this case. Escalation for both the prior notice and

duration factors was considered, but was not applied because the duration of

the violation and the prior notice (including GL 88-14 and the numerous oppor

tunities you had to recognize and correct the problem) were considered in

categorizing the violation at Severity Level III.

Violation II in the Notice involves your response to GL 88-14. The generic

letter requested, in part, that verifications be performed to ensure that all

safety-related equipment will function as intended on loss of instrument air

.and

components be identified that cannot accomplish their intended safety

function as a result of this review. Your responses to this generic letter,

dated May 8, 1989 and July 20, 1989, did not completely address this request in

that your review only considered "active" valves rather than all safety-related

valves. Furthermore, your responses did not identify valves PR-13 and PR-17 as

being active valves, even though they would need to be repositioned (throttled

open) to enable the PRVS to perform its intended function on loss of instrument

air. The NRC considers this oversight to be more than a minor regulatory

concern and therefore, in accordance with the Enforcement Policy, this violation

is categorized at Severity Level IV.

You are required to respond to this letter and should follow the instructions

specified in the enclosed Notice when preparing your response. In your response,

you should document the specific actions taken and any additional actions you

plan to prevent recurrence. After reviewing your response to this Notice,

including your proposed corrective actions and the results of future inspections,

the NRC will determine whether further NRC enforcement action is necessary to

ensure compliance with NRC regulatory requirements.

In accordance with 10 CFR 2.790(a), a copy of this letter and its enclosure

will be placed in the NRC Public Document Room.

Duke Power Company

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AUG

The responses directed by this letter and its enclosure are not subject to the

clearance procedures of the Office of Management and Budget as required by the

Paperwork Reduction Act of 1980, Pub. L. No.96-511.

Should you have any questions concerning this letter, please contact us.

Sincerely,

Stewart D. Ebneter

Regional Administrator

Enclosure:

Notice of Violation and Proposed

Imposition of Civil Penalty

Duke Power Company

-

5 -

AUG 1

.0

cc w/encl:

H. B. Barron

Station Manager

Oconee Nuclear Station

P. 0. Box 1439

Seneca, SC 29679

A. V. Carr, Esq

Duke Power Company

P. 0. Box 1007

Charlotte, NC 28201-1007

County Supervisor of Oconee County

Walhalla, SC

29621

Robert B. Borsum

Babcock and Wilcox Company

Nuclear Power Generation Division

Suite 525, 1700 Rockville Pike

Rockville, MD 20852

J. Michael McGarry, III, Esq.

Bishop, Cook, Purcell and Reynolds

1400 L Street, NW

Washington, 0. C. 20005

Office of Intergovernmental Relations

116 West Jones Street

Raleigh, NC 27603

Heyward G. Shealy, Chief

Bureau of Radiological Health

South Carolina Department of Health

and Environmental Control

2600 Bull Street

Columbia, SC 29201

Manager, LIS

NUS Corporation

2536 Countryside Boulevard

Clearwater, FL 33515

Paul Guill

Duke Power Company

P.O. Box 1007

Charlotte, NC 28201-1007

Karen E. Long

Assistant Attorney General

N. C. Department of Justice

.P.O.

Box 629

Raleigh, NC

27602

State of South Carolina

Duke Power Company

-

6 -AUG

161990

DISTRIBUTION:

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LPDR

SECY

CA

HThompson, DEDS

'JSniezek, DEDR

JLieberman, OE

SEbneter, RII

JGoldberg, OGC

TMurley, NRR

JPartlow, NRR

Enforcement Coordinators

RI, RII, RIII, RIV, RV

RPedersen, OE

-Resident Inspector

FIngram, GPA/PA

BHayes, 01

DWilliams, OIG

EJordan, AEOD

Pay File

EA File

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