ML17298B611

Confirms That Seismic Qualification Program Complete W/ Exception of Encl Justifications for Interim Operation Re Equipment Not Expected to Be Qualified Prior to Fuel Load, Per Sser 5 (NUREG-0857)

ML17298B611
Person / Time
Site:	Palo Verde
Issue date:	12/07/1984
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G Office of Nuclear Reactor Regulation
References
RTR-NUREG-0857, RTR-NUREG-857 ANPP-31380-EEVB, NUDOCS 8412110316
Download: ML17298B611 (14)

Text

REGULATOR INFORMATION DISTRIBUTION TEM (RIDS)

ACCESSION NBR:8412110316.

DOC ~ DATE: 84/12/07 NOTARIZED: YES DOCKET FAOIL;STN"50 528 Palo Verde Nuclear Station~

Unit li Arizona Publi 05000528 STN.50-529 Palo Verde Nuc'lear Station~

Unit 2'i Arizona Publi 05000529 "STN-50 530 Palo Verde Nuclear Station~

Unit 3~ Arizona Publi 05000530 AUTH~ NAME, AUTHOR AFFILIATION.

VAN BRUNT'iE'6'i Arizona Public Service Co ~

RECIP ~ NAME RECIPIENT AFFILIATION KNIGHTONg G ~ I'I ~

Licensing Branch 3-

SUBJECT:

Confirms that seismic qualification program complete w/

exception of encl Justifications for interim ojeration re equipment not expected to be qualified prior to fuel load/

per SSER,5 (NUREG"0857) ~

DISTRIBUTION CODE:

B001D COPIES" RECEIVED:LTR ENCL.

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T'ITLE; Licensing Submittal:

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Arizona Public Service Company ANPP-31380-EEVB/MFQ/Mt<H December 7,

1984 Director of Nuclear Reactor Regulation Attention: Mr. George W. Knighton, Chief Licensing Branch No.

3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3

Docket Nos. STN-50-528/529/530 Seismic Qualification Program File: 84-056-026; G.l.01.10

Reference:

(A) NUREG-0857, Supplement No.

5 "Safety Evaluation Report" Related to the Operation of Palo Verde Nuclear Generating Station, Units 1, 2 and 3, dated

November, 1983.

Dear Mr. Knighton:

As required by Section 3.11 of Reference (A), Arizona Public Service Company hereby confirms that the PVNGS Seismic Qualification Program is complete with the exception of the Justifications for Interim Operation (JIO) provided in Attachment 1 of this letter.

Attachment 1 contains JIO's not previously supplied for each piece of equipment which is not expected to be qualified prior to fuel load.

If you have any questions, please contact me.

Very truly your EEVBJr/MWH/no Attachment cc:

E. A. Licitra w/a H. Garg w/a A. C. Gehr w/a R.

P.

Zimmerman w/a E. E.

Van Brunt, Jr.

APS Vice President Nucl ear Producti on ANPP Project Director ol Bi12110316 500052 g1207 pDR PDOC pD E

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ANPP-31380 STATE OF ARIZONA

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) ss.

COUNTY OF MARICOPA)

I, Edwin E.

Van Brunt, Jr.,

represent that I am Vice President, Nuclear Production of Arizona Public Service

Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority to do so, that I have read such document and know its

contents, and that to the best of my knowledge and belief, the statements made therein are true.

Edwin E.

Van Brunt, Jr.

Sworn to before me this H

day o 1984.

Notary Public My Commission Expires:

, /Ay ComNIsslon Expires April 6, 1987

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Attachment 1

Justifications for Interim Operation

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PURCHASE ORDER NUMBER:

13-NM-001 DESCRIPTION:

Remote shutdown panel seismic PROJECTED QUALIFICATION COMPLETION DATE April 15, 1985 TAG NUMBER 1-J-ZJA-E01 ENVI.

DESIGN.*

SAFETY FUNCTION IV The safety function of the remote shutdown panels is to provide an alternate means to perform safe plant shutdown.

1-J-ZJB-EOl IV Same as above.

HISTORY:

These cabinets and internals have been demonstrated to be seismically qualified to PVNGS Plant requirements as documented in Qualification Program 814273-1CE-3531.

Subsequently, alarm annunciators-and transfer switches have been added to these cabinets to satisfy human factors and Appendix R (fire protection) concerns.

Seismic integrity verification of these components and an assessment of the impact of these additions on the qualification of the RSPs remains to be completed.

This activity is now underway.

JUSTIFICATION FOR INTERIM OPERATION:

Based on current schedule estimates it is expected that the seismic qualification assessment will be fully resolved after Unit 1 fuel loading, and no later than initial criticality.

Prior to this time, the remote shutdown panel serves no safety function.

Prior to initial criticality there is no fission product inventory that would produce decay heat and require an alternate (remote) shutdown capability.

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PURCHASE ORDER NUtEER:

13-kK-721B DES CRIPTION:

Temperature Elements PROJECTED QUALIFICATION COMPLETION DATE:

April 15, 1985 TAG NUMBER:

J-HFA-TE-73A J-HFA-TE-73B J-HFB-TE-74A J-HFB-TE-74B ENVI.

DES IG.*

SAFETY FUNCTION VI VI VI VI Each pair of temperature elements provides for temperature differential measurement across the fuel building air handling unit charcoal filter of each train.

The temperature elements provide no safety or accident mitigation function themselves but alert the control room operator of potential filter fires.

HISTORY:

American Air Filter (AAF),

who was the supplier of the fuel building air handling units, went out of business before completion of all required qualification

work,

- prior to which they had either slowed or cancelled activities without notifying customers.

Once it was determined that AAF had no intention of completing the qualification of the temperature

elements, a design change package was initiated to replace the existing elements with a qualified model.

JUSTIFICATION FOR INTERIM OPERATION:

The fuel building air handling units* are used to remove airborne radioactivity in the event of a fuel handling accident or LOCA.

Therefore, these units are not required until there is a fission product inventory in the plant.

+alified temperature elements will be installed prior to initial criticality, which is expected to occur on or about April 15, 1985.

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<<Environmental Designations (FSAR Section 3.11)

I Components Inside Containment The temperature,

pressure, humidity, and chemical environment inside containment after a LOCA or HSLB.

II Irr Components inside containment which are required after a design basis LOCA.

Components outside containment.

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