ML19331C618

Submits Response to IE Bulletin 80-06 Re Engineered Safety Features Reset Controls.Components Which Do Not Remain in Emergency Mode Have Been Modified

ML19331C618
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/18/1980
From:	Cavanaugh W ARKANSAS POWER & LIGHT CO.
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
1-060-17, 2-060-22, IEB-80-06, IEB-80-6, NUDOCS 8008190179
Download: ML19331C618 (5)

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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK. ARKANSAS 72203 [501) 371-442; .. .. <

June 18, 1980 WILUAM CAVANAUGH 111 Vice Preedent .

Genersoon & Construccon 1-060-17 2-060-22 Mr. K. V. Seyfrit, Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Comission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011

Subject:

Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 IE Bulletin 80 Engineered Safety Features (ESF) Reset Controls (File: 1510.1, 2-1510.1)

Gentlemen:

In response to the subject bulletin, the following is provided in accordance with 10 CFR 50.54(f).

Item 1:

Review the drawings for all systems r.erving safety-related functions at the schematic level to determine whether or not upon the reset of an ESF actuation signal, all associated safety-related equipment re-mains in its emergency mode.

Response

A review of the schematic drawings for ESF components has been com-pleted for both ANO-1 and ANO-2. From this review it was determined that 1ot all ESF associated safety-related equipment remained in its emergency mode upon ESF activation signal reset.

Item 2:

Verify the actual installed instrumentation and controls at the facility are consistent with the schematics reviewed in Item 1 above by conduct-ing a test to demonstrate that all equipment remains in its emergency mode upon removal of the actuating signal and/or manual resetting of the various isolation or actuation signals. Provide a schedule for the perfonnance of the testing in your response to this bulletin.

8008190 799 -_

l Mr. K. V. Seyfrit June 18, 1980 1

Response

ANO As a result of design changes made late last year and early this year, a test was conducted of all ESF components. This test checked removal of the ES signal to each component and operator action to position the component after an ES actuation. We feel that this test, in addition to tests conducted as a result of design changes made in response to Item 3, is sufficient to ver-ify that the actual installed instrumentation and controls are consistent with the schematics reviewed in response to Item 1.

ANO A test has been completed to verify that the actual installed instrumentation and controls are consistent with the schematics reviewed in resp]nse to Item 1. In all cases, the schematics and test results agreed as tc which components would remain or change upon removal of the ESF signal.

Item 3:

If any safety-related equipment does not remain in its emergency mode upon :eset of an ESF signal at your facility, describe proposed system modification, design change, or other corrective action planned to re-solve the problem.

Response

ANO All components identified in response co Item 1 which did not remain in their emergency mode upon ESF actuation signal reset have been modified. Attachment 1 is a listing of these compo-nents.

ANO As per our review of the systems schematics as required by Item 1, those components which we have identified as requiring modi-fications will be modified prior to startup from the next refuel-ing outage (currently scheduled for early 1981). These components are listed in Attachment 2.

Very truly yours,f William Cavana69h, III b WC: MAS:skm Attachments cc: Mr. Victor Stello, Jr., Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20$55

STATE OF ARKANSAS )

) SS COUNTY OF PULASKI )

William Cavanaugh III, being duly sworn, states that he is Vice President, Generation & Construction, for Arkansas Power & Light Company; that he is authorized on the part of said Ccmpany to sign and file with the Nuclear Regulatory Consnission this Supplementary Information; that he has reviewed or caused to have reviewed all of the statements contained in such information, and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, informa-tion and belief.

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William Ca(anaugh II SUBSCRIBED AND SWORN TO before me, a Notary Public in and for the County and State above named, this /Nay of ' HLD 1980.

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My Comission Expires:

My Commissica Expires 9/1/,81

2 ATTACHMENT 1 The following ANO-1 components did not remain in their emergency mode upon removal of an ES signal:

CV-2214 Letdown Cooler Isolation Valve CV-6203 Reactor Bldg. Chilled Water Isolation Valve CV-2100 Penetration Room Isolation Valve CV-2101 Penetration Room Isolation Valve CV-2102 Penetration Room Isolation Valve CV-2103 Penetration Room Isolation Valve CV-2104 Penetration Room Isolation Valve CV-2105 Penetration Room Isolation Valve -

CV-2106 Penetration Room Isolation Valve CV-2107 Penetration Room Isolation Valve CV-2108 Penetration Room Isolation Valve CV-2111 Penetration Room Isolation Valve CV-2112 Penetration Room Isolation Valve CV-2113 Penetration Room Isolation Valve -

CV-2114 Penetration Room Isolation Valve CV-2115 Penetration Room Isolation Valve CV-2116 Penetration Room Isolation Valve

_ - . _ _ . _ _ _ . - _ . _ _ _ . . ~ . ._ . . _ - . . _ _ , _ _ . _

ATTACHMENT 2 The following ANO-2 components will return to normal mode upon removal of ES actuation and are to be modified:

2CV-5001-1 SIT Drain Valve 2CV-5021-1 SIT Drain Valve 2CV-5041-2 SIT Drain Valve 2CV-5061-2 SIT Drain Valve 2CV-5628-2 S.I. Recirculation Valve 2CV-5672-1 C.S.S. Recirculation Valve 2CV-5673-1 C.S.S. Recirculation Valve 2CV-5126-1 HPSI Recirculation Valve 2CV-5127-1 HPSI Recirculation Valve 2CV-5128-1 HPSI Recirculation Valve 2CV-5123-1 LPSI Recirculation Valve 2CV-5124-1 LPSI Recirculation Valve 2CV-5647-1 Containment Sump Isolation Valve 2CV-5648-2 Containment Sump Isolation Valve 2CV-5649-1 Containment Sump Recirculation Valve 2CV-5650-2 Containment Sump Recirculation Valve 2CV-0714-1 E.F.W. Flush Isolation Valve 2CV-0798-1 E.F.W. Flush Isolation Valve l

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