ML20198L343

Forwards Insp Repts 50-317/98-10 & 50-318/98-10 on 980706-10 & 1118.Insp Rept Documents App R Issues Which Constituted Violations of NRC Requirements.Nov Not Issued Because, Violations Identified by Licensee Staff as Part of C/A

ML20198L343
Person / Time
Site:	Calvert Cliffs
Issue date:	12/12/1998
From:	Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Cruse C BALTIMORE GAS & ELECTRIC CO.
Shared Package
ML20198L349	List: ML20198L343 ML20198L362
References
50-317-98-10, 50-318-98-10, EA-98-570, NUDOCS 9901040173
Download: ML20198L343 (3)

See also: IR 05000317/1998010

Text

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December 12, 1998

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EA 98-570 '

l Mr. Charles H. Cruse

! Vice President - Nuclear Energy

Baltimore Gas and Electric Company

y Calvert Cliffs Nuclear Power Plant

1850 Calvert Cliffs Parkway

Lusby, MD 20657- 4702

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- SUBJECT: NRC INSPECTION REPORT NOS. 50-317/98-10 AND 50-318/98-10 AND i

EXERCISE OF DISCRETION

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Dear Mr. Cruse:  :

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This letter refers to an inspection conducted from July 6 to 10,1998, at Calvert Cliffs

Nuclear Power Plant and further review of issues continuing through December 3,1998.

The areas examined during this inspection included: 1) your corrective actions in response

to the identification of Appendix R program issues; and 2) your evaluations of previously

identified inspection items. Additional inspection included a meeting held at NRC

headquarters on November 18,1998, with NRC staff, to discuss issues identified in an

October 22,1998, letter to BG&E. The enclosed report presents the results of this

inspection. At the July 10,1998, exit meeting and the supplemental exit meeting on

December 3,1998, the inspection findings were discussed with your staff members.

Your Appendix R self-assessment was of good quality and was eifactive in identifying non-

compliances and areas for enhancement. Your corrective actions to identified non .

I compliances were appropriate and included plant modifications to motor operated valve

circuits and Appendix R hand switch circuits, and enhancements to your abnormal

operating procedures (AOPs). Your effort to enhance the fire protection program was a

good initiative. An example of an appropriate enhancement you made, was the decision to

perform a cable to cable hot short analysis for all cables that could affect the ability of the

plant to reach safe shutdown conditions.

The enclosed report documents Appendix R issues which constituted violatioris of NRC

requirements.' These violations included the following: (1) Safe shutdown Appendix R

emergency lighting was inadequate in the Unit 1 main steam isolation valve (MSIV) room

and in the area of the Unit 2 emergency shutdown panel; (2) Portable air bottles used to

l l operate the auxiliary spray valve was stored in a room where their availability would be in

question in the event a fire were to occur in that room; (3) Appendix R isolation hand

switches were single fused; (4) A hot short could occur in MOV control cables that could

. bypass MOV limit switches, cause spurious operation, and potentially damage the valve;

L and (5) Identification of a condition in which RCS/LPSI suction valves (MOV-651 and 652)

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could'open based on a postulated fire. These violations could be considered for escalated

enforcement and subject to civil penalties. However, after consultation with the Director, g

9901040173 981212

PDR ADOCK 05000317

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Mr. Charles H. Cruse 2

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Office of Enforcement, and the Regional Administrator, Region I, I have been authorized to

not issue Notices of Violations on those items specifically noted in the enclosed rr port and

not propose a civil penalty in those cases in accordance with the provisions provided in

l Section Vll.B.4 of the NRC's Enforcement Policy. This decision was made after

consideration that: (1) the violations were identified by your staff as part of the corrective

l action for previous Appendix R related issues; (2) they had the same root cause as the

previous issues; (3) they did not substantially change the safety significance or the I

character of the regulatory concern arising out of those findings; and (4) corrective actions,

both taken and planned, were comprehensive and reasonable.

No reply to this report is necessary and your cooperation with us is appreciated.

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Sincerely, l

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ORIGINAL SIGNED BY: i

James T. Wiggins, Director

Division of Reactor Safety

Docket Nos. 50-317,50-318

Enclosures:

1. NRC Inspection Report No. 50-317,318/98-10

2. BG&E Response to NRC Questions Concerning Appendix R Self-Assessment

cc w/encls:

B. Montgomery, Director, Nuclear Regulatory Matters (CCNPP)

R. McLean, Administrator, Nuclear Evaluations

J. Walter, Engineering Division, Public Service Commission of Maryland

K. Burger, Esquire, Maryland People's Counsel

R. Ochs, Maryland Safe Energy Coalition

State of Maryland (2)

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Mr. Charles H. Cruse 3

Distribution w/encls:

H. Miller, RA/W. Axelson, DRA (1)-

D. Screnci, PAO

Nuclear Safety Information Center (NSIC)

PUBLIC

NRC Resident inspector

Region i Docket Room (with concurrences)

L. Doerflein, DRP

W. Cook, DRP

R. Junod, DRP

J. Wiggins, DRS

L. Nicholson, DRS

B. Fewell, ORA

J. Lieberman, OE (2)'

C. Miskey, DRS

Distribution w/encts: (VIA E MAIL)

G. Shear, RI EDO Coordinator

S. Stewart - Calvert Cliffs

S. Bajwa, NRR

A. Dromerick, NRR

M. Campion, RI

Inspection Program Branch, NRR (IPAS)

R. Correia, NRR

DOCDESK

R. Zimmerman, ADPR, NRR

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F. Davis, OGC

A. Nicosia, OGC

J. Lieberman, OE (OEMAIL) )

D. Holody, EO, RI 1

T. Walkar, ORA, RI l

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DOCUMENT NAME: G:\EEB\ YOUNG \CC9810.lNS

T3 receive a copy of thie document, indicate in the box: *C* = Copy without attachment / enclosure 'E' = Copy with attachment / enclosure 'N'=

No copy

OFFICE Rl/DRS l Rl/DRS l Rl/ ORA 7l Al/DRS j RI/DRP

NAME KYoung jfy DLew ()(/ - T W alk JWiggins('yv/ LDoerfleinjit f

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DATE 12/18/98 12/l[/98 12/$/98 12/7]/98 1 12/2)/98 bt_

OFFICIAL RECORD C0pY

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