ML20211Q560

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Forwards Insp Rept 50-412/99-07 on 990720-29.Three Apparent Violations Noted & Being Considered for Escalated Ea. Violations Involve Failure to Implement C/As to Prevent bio- Fouling of Svc Water Sys
ML20211Q560
Person / Time
Site: Beaver Valley
Issue date: 09/07/1999
From: Lanning W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Cross J
DUQUESNE LIGHT CO.
Shared Package
ML20211Q563 List:
References
50-412-99-07, EA-99-212, NUDOCS 9909150093
Download: ML20211Q560 (4)


See also: IR 05000412/1999007

Text

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September 7, 1999

EA 99-212

Mr. J. E. Cross

Generation Group

Duquesne Light Company

Post Office Box 4

Shippingport, Pennsylvania 15077

SUBJECT:

NRC SPECIAL INSPECTION REPORT 50-412/99-07

Dear Mr. Cross:

From July 20 - 29,1999, the NRC conducted a special team inspection at Beaver Valley Unit 2

to evaluate a diesel generator failure that occurred on July 16,1999. The circumstances of this

event, and in particular questions regarding the operators' response to the loss of all seal

cooling for two reactor coolant pumps, resulted in this special team inspection. This inspection

also reviewed the macro biological fouling (biofouling) problems which affected the service water

supply to both diesel generators.

The NRC concluded that immediate operator actions to reduce the likelihood of seal failures

during a loss of all seal cooling were not adequately incorporated into plant procedures, operator

training, or the human factoring of control room alarms. The failure of your organization to

provide the foundations for consistent operator respense to this event is of significant concem,

especially because reactor coolant pump seal failures are the predominant risk contributor in

your probabilistic safety assessment. Additionally, we concluded the response of your

organization to the service water biofouling issue was not commensurate with the potential for a

common mode failure of the emergency diesel generators. This event had a significantly higher

risk potential because both diesel generators would have become biofouled if the chemical

treatment procedure had been followed, as planned. Other aspects of the operating crew's

response were appropriate. Effective actions were taken to protect safety related equipment

from the under-voltage condition created when the diesel generator's voltage regulator failed.

The NRC concluded that a careful assessment and good corrective actions were developed by

your Event Response Team for the electrical aspects of the event.

Three apparent violations were identified and are being considered for escalated enforcement

action in accordance with the " General Statement of Policy and Procedure for NRC Enforcement

,

Actions"(Enforcement Policy), NUREG-1600. The apparent violations involve the failure to

implement corrective actions to prevent biofouling of the service water system, the failure to

provide adequate acceptance criteria for chemical treatment of the service water system, and

the failure to meet Technical Specification requirements for diesel generator operability. The

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circumstances surrounding these apparent violations, the significance of the issues, and the

need for lasting and effective corrective action were discussed with members of your staff during

the special team inspection and at the inspection exit meeting on July 29,1999. The service

water heat exchanger cleaning and inspection efforts completed while the plant was shut down

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were adequate to support a safe restart. An evaluation to assess why the biofouling program

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9909150093 990907

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Mr. J. E. Cross

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failed to prevent this problem was initiated after a preliminary exit meeting with the special

inspection team. As a result, it may not be necessary to conduct a predecisional enforcement

conference in order to enable the NRC to make an enforcement decision.

1

Because you identified the violation, and based on our understanding of your corrective actions,

a civil penalty may not be warranted in accordance with Section VI.B.2 of the Enforcement

Policy. The final decision will be based on your confirming on the license docket that the

corrective actions previously described to the staff have been or are being taken.

In addition, the NRC has also determined that three Severity Level IV violations of NRC

requirements occurred. These violations are being treated as Non-Cited Violations (NCVs),

consistent with Appendix C of the Enforcement Policy. These NCVs involved the failure to

develop a procedure for loss of emergency power, the failure of operators to implement an

alarm response procedure, and the failure to follow the procedure for chemical sampling of the

service water system. These NCVs are further described in the subject inspection report.

Before the NRC makes its enforcement decision conceming the apparent violations, we are

providing you an opportunity to either (1) respond to the apparent violations addressed in this

inspection report within 30 days of the date of this letter or (2) request a predecisional

enforcement conference. If a conference is held, it will be open for public observation. Please

be advised that the number and characterization of apparent violations described in the

enclosed inspection report may change as a result of further NRC review. You will be advised

by separate correspondence of the results of our deliberations on this matter.

In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter, its

enclosure, and your response (if you choose to provide one) will be placed in the NRC Public

Document Room (PDR). To the extent possible, your response should not include any personal

privacy, proprietary, or safeguards information so that it can be placed in the PDR without

redaction. Please contact Mr. Peter Eselgroth at (610)337-5234 within seven days of the date of

this letter to notify the NRC of your intended response.

Sincerely,

ORIGINAL SIGNED BY:

BRIAN E. HOLIAN FOR

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Wayne D. Lanning, Director

Division of Reactor Safety

Docket No. 50-412

Enclosure:

NRC Special inspection Report 50-412/99-07

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Mr. J. E. Cross

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cc w/ encl:

Sushil C. Jain, Senior Vice President, Nuclear Services Group

Mr. L. W. Myers, Executive Vice President, Generation Group

K. Ostrowski, Vice President, Nuclear Operations Group and Plant Manager

B. Tuite, General Manager, Nuclear Operations Unit

W. Kline, Manager, Nuclear Engineering Department

M. Pearson, Manager, Quality Services Unit

M. Ackerman, Manager, Safety & Licensing Department

J. Macdonald, Manager, System and Performance Engineering

J. A. Hultz, Manager, Projects and Support Services, FirstEnergy

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M. Clancy, Mayor, Shippingport, PA

(

Commonwealth of Pennsylvania

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State of Ohio

State of West Virginia

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Mr. J. E. Cross

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Distribution w/ encl:

Region't Docket Room (with concurrences)

Nuclear Safety information Center (NSIC)

PUBLIC

NRC Resident inspector

H. Miller, RA/J. Wiggins, DRA

P. Eselgroth, DRP

N. Perry, DRP

C. O'Daniell, DRP

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W. Kane NRR

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8. Sheron, NRR

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D. Dambly, OGC

D. Holody, EO, RI

T. Walker, ORA, RI

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Distribution w/enct NIA E-MAIL):

M. Tschiltz, OEDO

E. Adensam, PD1, NRR

S. Bajwa, NRR

D. Collins, NRR

V. Nerses, NRR

R. Correia, NRR

DOCDESK

Inspection Program Branch, NRR (IPAS)

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"N" = No copy

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