ML20148C538

Forwards Request for Addl Info on IE Bulletin 85-003 to Evaluate Valve Operability Considerations Per IE Bulletin 85-005, Motor-Operated Valve Common Mode Failures During Transient Due to Improper Switch Setting

ML20148C538
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/18/1988
From:	Bettenhausen L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Mroczka E CONNECTICUT YANKEE ATOMIC POWER CO.
Shared Package
ML20148C542	List: ML20148C538 ML20149M430
References
IEB-85-003, IEB-85-005, IEB-85-3, IEB-85-5, NUDOCS 8803220433
Download: ML20148C538 (4)

Text

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s MAR 181988 Docket No. 50-213 Connecticut Yankee Atomic Power Company ATTN: Mr. E. J. Mroczka Senior Vice President - Nuclear Engineering and Operations Group P. O. Box 270 Hartford, Connecticut 06141 Gentlemen:

Subject:

Additional Information on IEB 85-03 l This transmits an identification of the additional information needed by the NRC to evaluate valve operability considerations in accordance with IEB 85-05, "Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper Switch Settings."

To f acilitate NRC review, we are requesting that you supplement your June 11, 1986 response to IEB 85-03 with the information identified in the enclosure to this letter. Please make that submittal within one month of the date of this letter, if oracticable. If development and submittal of the information will take longer, plevse make an interim submittal in one month, including the considerations in and tim ng for providing the remaining information.

Yove submittal should be make to the NRC Document Control Desk, with copies to this office and the NRR Division of Operational Events Assessment.

Thank you for your cooperation.

Sincerely, Ortaina181gned tys LeeH. Dettenhauses Lee H. Bettenhausen, Chief Projects Branch No. 3 Division of Reactor Projects

Enclosure:

Request for Additional Information (RAI)

Contact:

R. J. Kiessel, NRR (301) 492-1154 89032204:t3 880318 PDR ADOCK 05000213 G PDR OFFICIAL RECORD COPY 29/MCCABE/3/2/88 - 0001.0.0 jp5l\

03/02/88 I JON!

Connecticut Yankee Atomic Power Company 2 000118 Hgg cc w/ enc 1:

- D. B. Miller, Station Superintendent D. O. Nordquist, Manager of Quality Assurance R. M. Kacich, Manager, Generation Facilities Licensing W. D. Romberg, Vice President,- Nuclear Operations

- Gerald Garfield, Esquire Public Document-Room (PDR)

- Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Inspector State of Connecticut bec w/ encl:

Region I Docket Room (with concurrences)

Management Assistant, DRMA (w/o enc 1)

Section Chief, DRP W. Raymond, SRI, Millstone 1&2 A. Wang, LPM. NRR R. Bores, DRSS R. J. Kiessel, NRR 4

RI:DRP RI DRP e ettenhausen McCabe/meo 5/)/88 f//f/ff

, 6 0FFICIAL RECORD COPY 29/MCCABE/3/2/88 - 0002.0.0 03/02/88

.c Request for Additional Information Enclosure 1 Page 1 of 2 Haddam Neck (50-213)

REQUEST FOR ADDITIONAL INFORMATION (RAI) RE:

Review of Responses to Action Item e of IE Bulletin 85-03 The information provided in your response to Action Item e of IE Bulletin 85-03 needs supplementation in some areas. Please provide additional information to resolve the following comments and questions:

1. Has water hammer due to valve closure been considered in the determination of pressure differentials? If not, please explain.

2. Unlisted MOV SI-MOV-24 is shown locked open in Zone G-3 of Drawing 16103-26010, Revision 25, in the suction line from the RWST to the centrifugal charging pumps and to the HPSI pumps. Is power removed from the motor in addition to

-locking this MOV open? If not, what is the effect of inadvertent equipment operations as specified in Action Item a of the bulletin? Please revise At-tachment 1 of the 6/11/86 response to include this valve.

3. Revised Attachment 1 of the 6/11/86 response to include the following MOVs, or justify their exclusion. As specified in Action Item a of the bulletin, assume inadvertent equipment operations,

a. Valve FW-MOV-344 (2-inch) is shown normally closed in Zone G-4 of Drawing 16013-26018, Sheet 4, Revision 3. It is in parallel with normally closed air-operated Valve FW-FCV-295 (3-inch). These valves control flow from the charging pumps to the 2-inch header for lines leading to cold leg loops 1 through 4. How would opening of this MOV from the normally closed position be ensured?

b. Valves FH-MOV-578, -535, -522, and -508.(1 1/2-inch) are shown normally open on Drawing 16103-26007, Sheet 1, Revision 7. They are located in lines leading from the header mentioned in Item 3.a above to cold leg loops 1 through 4. How would discharge to the cold legs be ensured if these MOVs were inadvertently left closed?

4. Valve FW-MOV-35 is called normally closed in the response, but it is shown normally open on Drawing 16103-26013, Sheet 1, Revision 40. Please correct this discrepancy. Also further explain the fix described for FW-MOV-35 in Attachment 1 of the response. This MOV is in a line leading from the turbine-driven AFW pumps to all four steam generators. Verify that the time delay caused by either shutting down the AFW pumps or shutting the manual valves before operating this valve does not exceed the time limits assured in the design analyses.

5. The propcsed program for Action Items b, c, and d of the bulletin is incom-i n!ete. Please provide the following details.

OFFICIAL RECORD COPY 29/MCCABE/3/2/88 - 0003.0.0 03/02/88

Request for Additional Information Enclosure 1 Page 2 of 2

a. Commitment to a training program for setting switches and maintaining valve operators,

b. Commitment to justify continued operation if a valve is determined to be inoperable,

c. Description of the method for extrapolating valve stem thrust determined by testing at less than maximum differential pressure.

d. Justification of a possible alternative to testing at maximum differen-tial pressure at the plant.

e. Consideration of applicable industry recommendations in the preparation of procedures to ensure maintenance of correct switch settings.

OFFICIAL RECORD COPY 29/MCCABE/3/2/88 - 0004.0.0 03/02/88