ML17299B243

Application for Amend to License NPF-41,changing Tech Spec Section 3/4.8.1 AC Sources & Table 4.8-1 Re Diesel Generator Test Schedule,Per Generic Ltr 84-15.Fee Paid

ML17299B243
Person / Time
Site:	Palo Verde
Issue date:	05/14/1986
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Knighton G Office of Nuclear Reactor Regulation
Shared Package
ML17299B244	List: ML17299B243 ML17299B245
References
ANPP-36587-EEVB, ANPP-36857-EEVB, GL-84-15, TAC-61750, NUDOCS 8605200277
Download: ML17299B243 (8)

Text

REGULA. Y INFORMATION DIBTRIBUTI YBTEN (RXDB>

ACCESSION NBR: 8605200277 DOC. DATE: 86/05/14 FACIL:STN-50-528 Palo Vev de Nuclear Station. Uni NOTARXZED: YES t ii Arizona Pub li DOCKET 05000528 I

AUTH. NAI"1E AUTHOR AFFXLIATIQN VAN BRUNT.E. E. Arizona Nucleav'ower Pv object (formerly Av zona i Public Sevv RECIP. MANE RECIPIENT AFFXLI*TIQN KNXQHTQN, Q. M. PMR Pv object Div ectov ate 7

SUBJECT:

Application fov amend to License NPF-41> changing Tech Spec Section 3/4. 8. 1 "AC Souv ces" 5 Table 4. 8. 1 v e diesel genevatov test schedule. per Genev ic Ltv 84-15; Fee paid.

DISTRIBUTION CODE: AOOID COPIES RECEIVED: LTR i ENCL SIZE:

TITLE: OR Submittal: Qeneval Distv ibution NOTES:Standardized plant. 05000528 I

REC 1 P ENT COPIES CITRATE I REC IP ENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAl'tE LTTR ENCL, PNR-B ADTS 0 PAR-B EB 1 PNR-B PEICSB 2 2 PAR-B FQB 1 PNR-B PD7 PD 01 5 5 LI E 1 PNR-B PEICSB 1 PAR-B RSB 1 INTERNAL: ACRS 09 6 6 ADN/LFNB 1 0 ELD/HDB3 1 0 NR T/TSCB 1 1 NRR/QRAB 0 Q FIL 04 1 RQN5 1 EXTERNAL 24X 1 1 EQSG BRUSKEi S LPDR 03 1 1 NRC PDR 02 NBIC 05 1 4 )50 TOTAL NUl]BER OF CQPXEB REQUIRED: LTTR 30 ENCL 26

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Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA85072-2034 May 14, 1986 ANPP-36587-EEVB/JRP/98.05 Director of Nuclear Reactor Regulation Attention: Mr. G. W. Knighton, Project Director PWR Project Directorate II7 Division of Pressurized Water Reactor Licensing B U.S. Nuclear Regulatory Commission Washington, D.CD 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 1 Docket No. STN 50-528 (License NPF-41)

Technical Specification Amendment A. CD Sources File: 86-005-4'19.05; 86-056-026

Dear Mr. Knighton:

Attached, please find proposed, changes to the PVNGS Unit 1 Technical Specifications Section 3/4.8. 1 "A.CD Sources". The changes presented herewith were previously discussed with and agreed to by your staff during the PVNGS Unit 2 Technical Speci-.

fication review process and have been incorporated into the PVNGS Unit 2 license.

By this letter, we are requesting that the attached changes be incorporated into the Unit 1 Technical Specifications. Attachment 1 to this letter is the no signifi-cant hazards consideration for your review and approval. Attachment 2 is Techni-cal Specification 3/4. 8. 1 which is to be replaced by Attachment 3, the new section 3/4.8. 1 ~

In future correspondence, we will be requesting additional changes to the Unit 1 Technical Specifications in order for the Technical Specifications to be identical with Unit 2.

In accordance with the requirements of 10 CFR 170. 12(c), the license amendment application fee of $ 150.00 is also enclosed.

If you have any questions, please call.

Very trul yours, F.p. ck~

E. E. Van Brunt, Jr.

Executive Vice President Project Director EEVB/JRP/rw Attachments cc: Director, Region V, USNRC NRC Project Director, E. A. Licitra NRC Resident Inspector, R. P. Zimmerman F'DR 8b05200277 Bb05i4 PDR ADOCK 05000528 fed 0 Mgc.i

ATTACHMENT 1 DESCRIPTION OF AMENDMENT REQUEST:

The proposed amendment would modify Technical Specification 8.1, "A.C.

Sources"; Table 4.8-1, Diesel Generator Test Schedule; and associated pages within this section.

The proposal contains general reductions in the testing requirements for the onsite emergency diesel generators (EDG's) in the plant Technical Specifications. These changes involve both routine surveillance testing and special testing and would reduce the severity of each EDG test start and reduce the number of test starts. These changes follow the directions of existing regulatory guidance (RG 1.108) and are consistent with the guidance in Generic Letter 84-15.

BASIS FOR NO SIGNIFICANT HAZARDS DETERMINATION:

The proposed changes do not involve a significant hazards consideration because operation of Palo Verde Nuclear Generating Station Unit 1 in accordance with this change would not:

(1) Involve a significant increase in the probability or consequences of an accident previously evaluated.

The proposed changes include that the EDG tests be conducted with loading rates recommended by the, EDG manufacturer, and at a lower 'indi.cated full-load value. The primary basis for this'action is that, in addition to the belief that cold fast test starts are generally detrimental, significant engine failures have occurred at various facilities and testing requirements may have aggravated the cause of these failures.

Therefore, this proposed change would not increase the probability or consequences of an accident.

(2) Create the possibility of a new or different kind of accident from any previously analyzed.

It has been determined that a new or different kind of accident will not be possible due to this change. By eliminating unnecessary diesel generator testing, expected that the overall reliability of the EDGs will be it is improved.

'V ATTACHMENT (Continued) l (3) Involve a sign1ficant reduction in a margin of safety.

Based on industry data it can be concluded that there will be no reduction in the marg1n of safety because of the increased reliability of the EDG's and that this increase in reliability is an adequate basis for reducing the testing requirements.

(B) The Commission has provided guidance concerning the application of the standards for determ1ning whether a sign1ficant hazards consideration exists.

The proposed change is similar to example (VII), a change to make a license conform to changes in the regulations, where the license change results in very minor changes to facility operations clearly in keep1ng with the regulations.

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