ML17299B230

Requests Review of Encl plant-specific Lists & Addition of Omitted Significant Actions to Assist in Developing long-term Program to Improve Documentation on License Implementation of Generic Requirements

ML17299B230
Person / Time
Site:	Palo Verde
Issue date:	04/30/1986
From:	Licitra E Office of Nuclear Reactor Regulation
To:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
References
NUDOCS 8605080603
Download: ML17299B230 (12)

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UNITED STATES NUCLEAR REGULATORYCOMMISSION WASHINGTON,D. C. 20555 APR 3 0 1986 Docket Nos.:

50-528, 50-529 and 50-530 Mr. E.

E.

Van Brunt, Jr.

Executive Vice President Arizona Nuclear Power Project Post Office Box 52034 Phoenix, Arizona 85072-2034

SUBJECT:

LICENSEES'MPLEMENTATION OF GENERIC REQUIREMENTS The Compt oiler General in a Report to the Congress dated September 19,

1984, stated "NRC needs better management controls to ensure implementation of generic issue solutions."

To correct this situation, the Nuclear Regulatory Commission is working on a long-tenn program which will improve its documentation on the status of power reactor licensees'mplementation of approved regulatory improvements.

To assist me in developing this information for Palo Verde Nuclear Generating Station, Unit I, 2 and 3, please review the enclosed plant-specific lists, add omitted significant actions to the lists, and provide the date that all aspects of each identified requirement were completed/implemented or expected to be completed.

For each requirement that has been completed, enter "completed" under the Status column and the date the item was completed.

For requirements that have not been completed/implemented, provide the projected date and enter "projected" under the Status column.

I do not expect or want a major effort made to obtain precise dates.

Rather, I will accept readily-known or best-estimate dates for actions that have been completely implemented.

For

example, the year only would be acceptable for completions prior to 1984; the month as well as year is needed for requirements completed after that time.

For projected completions/implementations in 1986, use month and year.

Use year only for projections thereafter.

Please provide a response in the form of a marked up listing by May 31, 1986.

In the future, NRR will need estimated dates prior to issuance of the safety evaluation so that the estimated schedule may be included in the evaluation.

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This request is covered by OMB Clearance Number 3150-0011, which expires September 30, 1986.

Sincerely,

Enclosure:

As stated cc:

See next page E. A. Licitra, Project Manager PWR Project Directorate No.

7 Division of PWR Licensing-B Distribution:

Docket File. i NRC PDR Loca'1'PDR PBD7 Reading F; Miraglia OELD E. Jordan

"B. Grimes J.

Part-low i J.

Lee E.'A. Lfc,itra ACRS (10)

H.. Smith-Steve Scott L. Kopp-PBD7 EALicit a/es 4/g)/86

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Van Brunt, Jr.

Arizona Nuclear Power Project Palo Verde CC:

Arthur C. Gehr, Esq.

Snell 8 Wilmer 3100 Valley Center Phoenix, Arizona 85073 Nr. James N. Flenner, Chief Counsel Ari'zona Corporation Commission 1200 West Washington Phoenix, Arizona 85007 Charles R. Kocher, Esq. Assistant Council James A. Boeletto, Esq.

Southern California Edison Company P. 0.

Box 800

Rosemead, California 91770 Nr. Nark Ginsberg Energy Director Office of Economic Planning and Development 1700 West Washington - 5th Floor Phoenix, Arizona 85007 Mr. Wayne Shirley Assistant Attorney General Bataan /memorial Building Santa Fe, New Mexico 87503 Kenneth Berlin, Esq.

Winston 8 Strawn Suite 500 2550 N Street, NW Washington, DC 20037 Ns.

Lynne Bernabei Government Accountability Project of the Institute for Policy Studies 1901 gue Street, NW Washington, DC 20009 Ms. Jill Morrison 522 E. Colgate Tempi, Arizona 85238 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations Combustion Engineering, Inc.

7910 Woodmont Avenue Suite 1310

Bethesda, Naryland 20814 Nr.

Ron Rayner P. 0.

Box 1509

Goodyear, AZ 85338 Nr.

Roy Zimmerman U.S. Nuclear Regulatory Commission P. 0.

Box 239 Arlington, Arizona 85322 Ns. Patricia Lee Hour ihan 6413 S. 26th Street Phoenix, Arizona 85040 Regional Administrator, Region V

U. S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, Cali fornia 94596

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R-1208731-001 REGULATORY IHFORHATI OHTRACKIHGSYSTEM FACI L ITY IMP L EHEHTATIOtl PAGE HO.

03 FACILITY: PALO VERDE 1

PLANT LOCATIOtl: 36 NI W

OF PHOEHIX, AZ DOCKET HUHBER:

050-00528 ARCH/EHGIHEER:

BECH IE ItlSPECTOR:

LICEHSED POWER:

3800 MllT DESIGH POWER:

1270 MWE HSSS VEHDOR:

COMB PROJECT MAtlAGER: E.

LICITRA BRAHCH CHIEF:

G.

KtlIGHTOH LIC.

ASSI STAtlT:

I.

L EE T

C HO HPA lt TITL LIC ACT

~COMP LOT LICEHSEE

~STATS

~OAT NO%641 H59124 A-01 10 CFR 50.55 A(G) - ISI A-20 10 CFR 50.62 OPERATIHG REACTOR REVIEWS H59971 A-21 10 CFR 50.6'IP PRESSURIZED THERMAL SHOCK RULE H59163 B-77 ITEM 2.1 - EQUIPMEttT CLASSIFICATIOH 8 VEHDOR ItlTER H59165 B-78 ITEMS 3.1.1 8 3.1

~ 2 -POST MAIHTEtlAtlCE TEST PROCEDU H59166 B-79 ITEM 3.1.3 - POST MAItlTEtlAHCE TESTIHG - CHAtlGES TO H59169 B-80 ITEM 6.1 -

REACTOR TRIP SYSTEM RELIABILITY-VEHDO N59170 H59164

'M59167 M59168 H59171 B-86 B"87 SALEM ATWS 2.2 S-R COHPOHEHTS SALEM ATWS 3.2.1 8 3.2.2 S-R COHPOtlEHTS B"88 SALEM ATWS 3.2.3 T.S.

S"R COHPOHEtlTS B-89 SALEM ATWS 6.2.3 8 6.2.6 LIFE COMPOHEtlTS B-81 ITEMS l.2.1 8 6.2.2

-PREVEtlTATIVE HAItlT PROG FOR R

H59172 B-92 SALEM ATWS 4.5.1 DIVERSE TRIP FEATURES N59173 B-93 SALEM ATWS 4.5.2 8 6.5.3 TEST ALTERHATIVES H58077 C"16 UTILITY RESPOtlSES TO STAFF RECOMHEHDATIOtlS COHCERH M59188 N59412 F-57 II,K.3.30 SB LOCA METHODS G-01 REACTOR COOlANT PUMP TRIP (D660 - II.K.3.5)

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R-1208731-001 REGULATORY I tlFORMATI OW TRACK I WG SYSTEM F ACI L I TY IMP L EHEWTAT I Otl PAGg tl FACILITY> PALO VERDE 2,

'PLANT LOCATIOtt> 36 HI H OF PHOEWIXp AZ DOCKET tlUNBER:

050-00529 ARCH/EttGItlEER ~

BECH TIE INSPECTOR>

LICEWSED POHER:

3800 HHT DESIGtl POHER:

1270 MME tlSSS VEtlDOR:

COl'1B PROJECT MAtlAGER: E.

LICITRA BRAttCM CHIEF:

G.

KttIGHTOtt LIC. ASSISTAWT:

I.

LEE lO~

~HA t TL LIC ACT

~COIIPL T

L IC Etl5 EE STATUS

~AT NO%601 N59126

.H59971 N59163 M59165

- N59166 H59169 M59170 M59164

'H59167 H59168 M59171 N59172 M59173 t15807 7 N59188 M59412 A-01 10 CFR 50.55 A(G) - ISI A"20 A"21 B-77 B"78 B"79 B-80 B-81 B-86 B-87 B-88 B"89 B"92 B-93 C-16 F"57 G-01 10 CFR 50.62 OPERATItlG REACTOR REVIEllS 10 CFR 50.61p PRESSURIZED THERMAL SHOCK RULE ITEM 2,1 - EQUIPNEttT CLASSIFICATIOtl 8 VEtlDOR ItlTER ITEMS 3.1.1 8 3.1.2

-POST HAItlTEtlAWCE TEST PROCEDU ITEN 3.1.3 -

POST MAItlTEtlAWCF TESTIWG " CHAtlGES TO ITEM CI.1 " REACTOR TRIP SYSTEM RELIABILITY-VEtlDO ITEHS 0.2.1 8 l.2.2 -PREVEtlTATIVE HAItlT PROG FOR R

SALEM ATNS 2.2 S-R COHPOWEtlTS SALEM ATI'lS 3 ~ 2

~ 1

& 3

~ 2

~ 2 S-R COHPOtlEtlTS SALEM ATI>l

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R-1208731-001 REGULATORY I tlFORMATI OHTRACKIHGSYSTEH FACI L I TY I HP L ENEllTAT I Ott PAGL tt(

FACILITY> PALO VERDE 3 PLANT LOCATIOtt> 36 HI W OF PHOEttIXi AZ DOCKET ttUHBER~

050-00530 ARCH/EttGIttEER>

BECH IE IHSPECTOR:

LICEtlSED POWER:

0 MWT DES IGll POWER:

1270 MWE ttSSS VEtlDOR:

COMB PRO J ECT l1AttAGER: E.

L I C I T Rh BRAttCH CtlIEF:

G.

KtltGHTOtt LIC. ASSISTAttT:

I, LEE Qlg MO

~PA t TITL LIC ACT

~COtlPL ET L ICEllSEE STATUS

/ATE NO%641 M59126 H59971 A-01 10 CFR 50.55 A(G) - ISI A-20 10 CFR 50,62 OPERATItlG REACTOR REVIEWS A-21 10 CFR 50.61'RESSURIZED THERMAL SHOCK RULE H59163 B"77 ITEN 2.1 -

EQUIPHEHT CLASSIFICATIOll 8 VEtlDOR IllTER H59165 B"78 ITEMS 3.1.1 8 3.1.2 "POST HAItlTEtlAllCE TEST PROCEDU N59166 B-79 ITEM 3.1

~ 3 - POST HAItlTEtlAtlCE TESTIttG - CHAttGES TO H59169 B"80 ITEM %.1 - REACTOR TRIP SYSTEH RELIABILITY VEttDO H59170 B-81 ITEHS 6.2.1 8 6.2.2

-PREVEtlTATIVE HAItlT PROG FOR R

H59160

'N59167 M59168 M59171 B-86 B-87 SALEM ATWS 2.2 S-R COHPOtlEtlTS e

SALEN ATWS 3.2.1 8 3.2.2 S"R COMPOttEttTS B-88 SALEM ATWS 3.2.3 T.S.

S-R COMPOttEWTS B-89 SALEM ATWS l.2.3 8 4.2.1 LIFE CONPOttEttTS N59172 B-92 SALEM ATWS 0

~ 5.1 DIVERSE TRIP FEATURES M59173 B-93 SALEM ATWS 4.5.2 8 l.5,3 TEST ALTERtlATIVES H58077 M59188 M59112 C-16 F-57 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5)

UTILITY RESPONSES TO STAFF RECOMNEtlDATIOtlS COttCERtt II.K.3.30 SB LOCA METHODS

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