ML20206A725

Forwards Request for Addl Info Re Util Response to IE Bulletin 85-003, Motor Failures During Plant Transients Due to Improper Switch Settings

ML20206A725
Person / Time
Site:	Cooper
Issue date:	11/09/1988
From:	Callan L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:	Trevors G NEBRASKA PUBLIC POWER DISTRICT
References
IEB-85-003, IEB-85-3, NUDOCS 8811150228
Download: ML20206A725 (4)

Text

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NOV 9 IllBB in Reply Refer To:

Docket: 50-298 Nebraska Public Pcwer District ATTh: George A. Trevors Division Manager - huclear Support P.O. Box 499 Colurnbus, NE 6P602-0499 Gentlerren:

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION CONCERilING COOPER NUCLEAR STATION RESPONSE TO IEC 05-03 Your letters of !!ay 15 end Noveitber 26, 1986, contained a response to IE Bulletin 85-03, "Potor Failures During Plant Transients Due to Iriproper Switch Settings." The review of the responses indicates the need for additional information before the progran can be approved. Enclosure 1 provides the specific infonration necessary for revicw corrpletion.

Please provide the additional requested information within 2 ranths of the date of this letter.

Sincerely.

Original Signuf Bp A.B. BEACH L. J. Callan, Director Division of Reactor Projects

Enclosure:

As stated bcc to DMS (ll-11) bec distrib. by RIV:

RRI R. D. Martin, RA Section Chief (DRP/C) Lisa Shea, RM/ALF RPB-DRSS MIS Systen RIV File Project Engiu cr, DRP/C RSTS Operatcr CFP P. O'Connor, hRR Project l'anager (MS: 13-D-18)

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[' h bb APR 5 900 Pal 0 I Of 3 REQUEST POR ADDITIONAL INFORMATION (RAI) RE:

F Review of Responses to Action Item e of IE Bulletin 85-03 e

Unit (s): Cooper Station Licensees Date of Response 05-15-86 Nebraska Public Power District 11-26-86 P. O. Box 499 Respondents Columbus, Nebraska 68601-0499 Jay M. Pilant, Technical Staff Manager Nuclear Power Group l

The inforastion provided in your response deficient to Action in some areas.ItemProvide e of IE Bulletin 85-03 was found to btthe additional inforastion necessary to consents and questions:

1 of the response dated 11-26-86

1. Revise to includeTable the2-1 of Enclosure following MOVs, or justify their exclusion.

According to pages 55 and 59 of BWROG Report NEDC-31322 dated September 1986, these valves do not have any safety actionst  :

however, utilities are expected to report differentialAlso address the i

, pressures for testing, per Note o on Page 66. discrepa

(

(a) BPCI MO 24 is shown normally open in Zone E-2 of the BWROC Report.

i (b) RCIC MO 33 is shown normally open in Zone E-1 i

of the BWROC Report.

, 11-26-86 l

2. Revise Table 2-1 of Enclosure 1 of the response dated d s

to include values of differential pressure for open

• exclusion of these pressures.

l MOV 5 and RCIC MOV 5 on pages 68 and 72 of the BVROG Report.

Note o mentioned in Iten 1 above applies here also.

11-26-86 h

3. Revise Table 2-1 of Enclosure 1 of the response As

following MOVs, or justify exclusion of these pressuros. assume inadvertent required by Action Ites a of the bulletin, equipment operations.

L

- o o

APR 5 1988 Page 2 of 3 RAI for Cooper Station 7

(a) HPCI NOV MO 17 is shown normally open in Zone J-3 of Drawing 2041 Revision N18, and as MOV 3 on Page 68 of the BWROG How would suction from the CST be ensured if this Re7 M0/ ort. were to be (a) actuate ( inadventently to the closed position upon intended iniciation of the nystem or (b) left closed inadvertently?

(b) HPCI MOV MO 20 is shown normally open i's Zone C-8 of Drawing 2044 Revision N18, and as MOV 8 on Past 68 of the SWROG Report. How would injection to the reactor vessel be ensured if this MOV were to be (a) ac'susted inadvertently to the closed position upon intended initiation of the system or (b) left closed inadvertently?

(c) RCIC MOV MO 18 la shown normally open in Zone J-3 of Drawing' ,

2043 Revision N10, and as MOV 3 on Page 72 of the BVROG Report. The question in Item 3(a) above applies here also.

I (d) RCIC MOV MO 20 is shown normally open in Zone C-8 of Drawing 2043 Revision N10, and as MOV 8 on Page 72 of the BWROC Report. The question in Item 3(b) above appliec here stro.

4. HPCI Injection Valve MO 19 is shown normallynormally open in Zone C-8 of Drawing 2044 Revision N18. It is shown Explain this closed as MOV 1 on Page 68 of the BWROC Report.

descrepancy.

j 1 of the response dated 11-26-86

5. Revise Table 2-1 of Enclosure to change the required active operation of RCIC MOV-MO 131 from l

As shown "Open" to "Open/Close", or justify the present entry.

for Steam Admission Valve MOV I on Page 61 of the BWR00 Report, both opening and closing are safety actions.

6. Revise Table 2-1 of Enclosure 1 of the response dated 11-26-86 to include the following MOVs in injection lines to the reactor ,

vessel, or justify their exclusion.

(a) HPCI Valve MO 57 (2-inch) is shown normally open in Zone C-9 of Drawing 2044 Revision N18, in parallel with air-operated r Valve A0 18 (14-inch).

(b) RCIC Valve MO 17 (1-inch) is shown norss11y open in Zone C-9 of Drawing 2043 Revision N10, in parallel with air-operated Valve A0 22 (4-inch).

7. The proposed progras forProvide action items b, e anddetails the following d of the as a bulletin is incomplete. ,

' minimum (a) commitment to a training program for setting switches, t

maintaining valve operators, using signature testing i

equipment and interpreting signatures.

7._

1 LT9 5 588 y!.3.g3for RA Cooper Station

'(b) commitment to justify continued operation of a va lve determined to be inoperable.

(c) description of a method possibly needed to extrapolate valve stes thrust determined by testing at less than anximum differential pressure, (d) justification of a possible siternative to testing at maximum differential pressure at the plant, (e) consideretion of pipe break conditions as required by the bulletin, and (

t (f) stroke testing when necessary to meet bulletin requirements.

e

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