ML17300B363

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Forwards Insp Repts 50-528/99-11,50-529/99-11 & 50-530/99-11 on 990614-0702 with Inoffice Insp Continued Until 990901 & Suppl Onsite Insp from 990830-0902.Violations Occurred & Being Treated as NCVs
ML17300B363
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 10/02/1999
From: Powers D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Overbeck G
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
Shared Package
ML17300B365 List:
References
50-528-99-11, 50-529-99-11, 50-530-99-11, NUDOCS 9910120251
Download: ML17300B363 (14)


See also: IR 05000528/1999011

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

CESSION NBR:9910120251

DOC.DATE: 99/10/02

NOTARIZED: NO

DOCKET I

ACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi

05000528

STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi

05000529

STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi

05000530

AUTH'.NAME

AUTHOR AFFILIATION

POWERS,D.A.

Region

4 (Post

820201)

RECIP.NAME

RECIPIENT AFFILIATION

OVERBECK,G.R.

Arizona Public Service

Co.

(formerly Arizona Nuclear Power

C

SUBJECT:

Forwards insp repts 50-528/99-11,50-529/99-11

6 50-530/99-11

on 990614-0702 with inoffice insp continued until 990901

&

suppl onsite insp from 990830-0902.Violations

occurred,&

being treated

as

NCVs.

DISTRIBUTION CODE: IE01F

COPIES

RECEIVED:LTR

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SIZE:

TITLE: General

(50 Dkt)-Insp Rept/Notice of Violation Response

NOTES: STANDARDIZED PLANT

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05000528

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05000530

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ID CODE/NAME

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NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS

OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL

DESK

{DCD)

ON EXTENSION 415-2083

TOTAL NUMBER OF COPIES

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uNITED STATES

NUCLEAR REGULATORYCOMMISSION

REGION IV

611 RYANPLAZADRIVE, SuITE 400

ARLINGTON,TEXAS760114064

PCT

2

1999

Gregg R. Overbeck, Senior Vice

President, Nuclear

Arizona Public Service Company

P.O. Box 52034

Phoenix, Arizona 85072-2034

SUBJECT:

NRC 'INSPECTION REPGRT NO. 50-528/99-11; 50-529/99-11; 50-530/99-11

Dear Mr. Overbeck:

This refers to the inspection conducted on June 14 through July 2, 1999, at the Palo Verde

Nuclear Generating Station, Units 1, 2, and 3, facility. Additional review and inspection were

performed in the Region IVOffice until September

1, 1999. Supplemental onsite inspection

was also conducted August 30 through September 2, 1999. This inspection assessed

your

containment spray system, 125Vdc power system, and portions of your containment isolation

systems for conformance to applicable regulatory requirements for the Palo Verde Nuclear

Generating Station. The enclosed report presents the results of this inspection.

Atthe end of the first onsite period of the inspection, the team leader conducted an exit meeting

with you and members of your staff on July 2, 1999. Following this exit meeting, your staff

provided the inspection team with additional requested information. New information was

provided to the team in several telephonic conferences and during the supplemental onsite

inspection. This'new information changed some of the preliminary findings discussed

in the exit

meeting, necessitating a followup exit meeting that was conducted via teleconference on

September 30, 1999.

Overall, we concluded that the containment spray and 125Vdc systems conformed to their

design and licensing bases and were capable of performing their intended safety functions.

However, we identified numerous errors in design calculations, procedures, and the Updated

Safety Analysis Report. While none of these errors Individuallyconstituted operability

problems, the number of issues revealed problems in the implementation of your design control

program which, under different circumstances,

may have been more significant. Examples of

problems identified by the team included:

(1) improper assumptions,

references, and input

associated with design calculations; (2) inconsistencies among the Updated Final Safety

Analysis Report, design basis calculations, setpoints, and the installed configuration; and (3)

failure to translate changes to design basis calculations, drawings, and procedures.

Some of

these errors appeared to have been caused by a lack of a fullyeffective process for identifying

the interrelationship between calculations.

The team identified several examples in which your engineering staff failed to follow

through'ompletely

with changes to desigh basis calculations resulting from changes in the source

calculations or other inputs. One potential cause of this failure is the practice of relying on

99fOM02M 99f002

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5

Arizona Public Service Company

-2-

engineering judgement to determine whether the individual significance of a change warrants

an update to the affected calculations.

While such changes may be minor, the collective

impact, which because of your current practices may not be recognized by your staff, could

result in unintended or unacceptable degradations.

Accordingly, we stress that revising design

basis calculations to reflect changes and modifications, regardless of the impact of each

individual change, is an essential element in the maintenance of your plant's design basis.

We,

therefore, encourage you to review your policies, processes,

and practices to ensure that the .

plant's design basis and licensing basis is appropriately maintained.

Based on the results of this inspection, the NRC has determined that violations of NRC

requirements occurred, all of which are being treated as noncited violations, consistent with

Appendix C of the Enforcement Policy. The noncited violations are described in the subject

inspection report.

If you contest any of the violations or severity level of the noncited violations,

you should provide a response within 30 days of the date of this inspection report, with the

basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk,

Washington, DC 20555-0001, with copies to the Regional Administrator, Region IV; the

Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington,

DC 20555-0001; and the NRC Resident Inspector at the Palo Verde Nuclear Generating

Station.,

In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its

enclosure willbe placed in the NRC Public Document Room.

Should you have any questions concerning this inspection, we will be pleased to discuss them

with you.

Sincerely,

<U.CC ( 4g

'~r-gg. r~~~>

Dr. Dale A. Powers, Chief

Engineering and Maintenance Branch

Division of Reactor Safety

Docket Nos.:

50-528; 50-529; 50-530

License Nos.: NPF-41; NPF-51; NPF-74

Enclosure:

NRC Inspection Report No.

50-528/99-11; 50-529/99-11; 50-530/99-1 1

cc w/enclosure:

Steve Olea

Arizona Corporation Commission

1200 W. Washington Street

Phoenix, Arizona 85007

e

Arizona Public Service Company

Douglas K. Porter, Senior Counsel

Southern California Edison Company

Law Department, Generation Resources

P.O. Box 800

Rosemead,

California 91770

Chairman

Maricopa County Board of Supervisors

301 W. Jefferson, 10th Floor

Phoenix, Arizona 85003

Aubrey Y. Godwin, Director

Arizona Radiation Regulatory Agency

4814 South 40 Street

Phoenix, Arizona 85040

Angela K. Krainik, Director

Regulatory Affairs

Arizona Public Service Company

P.O. Box 52034

Phoenix, Arizona 85072-2034

John C. Horne, Yice President,

Power Generation

El Paso Electric Company

2702 N. Third Street, Suite 3040

Phoenix, Arizona 85004

Terry Bassham,

Esq.

General Counsel

El Paso Electric Company

123 W. Mills

El Paso, Texas

79901

John W. Schumann

Los Angeles Department of Water 8 Power

Southern California Public Power Authority

P.O. Box 51111, Room 1255-C

Los Angeles, California 90051-0100

David Summers

Public Service Company of New Mexico

414 Silver SW, ff1206

Albuquerque, New Mexico 87102

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Arizona Public Service Company

Jarlath Curran

Southern California Edison Company

5000 Pacific Coast Hwy..Bldg. DIN

San Clemente, California 92672

Robert Henry

Salt River Project

6504 East Thomas Road

Scottsdale, Arizona 85251

-5-

bcc to DCD (IE01)

bcc distrib. by RIV:

Regional Administrator

Palo Verde Senior Resident Inspector (2)

DRP Director

DRS Director

MIS System

Branch Chief (DRP/D)

Project Engineer (DRP/D)

Branch Chief (DRP/TSS)

RIV File

Arizona Public Service Company

. E-Mail report to T. Frye (TJF)

E-Mail report to D. Lange (DJL)

E-Mail report to NRR Event Tracking System (IPAS)

E-Mail report to Document Control Desk (DOCDESK)

E-Mail report to Richard Correia (RPC)

DOCUMENT NAME: R:5 PNPV9

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DRP Director

DRS Director

MIS System

Branch Chief (DRP/D)

Project Engineer (DRP/D)

Branch Chief (DRP/TSS)

RIV File

Arizona Public Service Company

E-Mail report to T. Frye (TJF)

E-Mail report to D. Lange (DJL)

E-Mail report to NRR Event Tracking System (IPAS)

E-Mail report to Document Control Desk (DOCDESK)

E-Mail report to Richard Correia (RPC)

DOCUMENT NAME: R:3 PNPV9

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