ML17304A326

Forwards Revised Relief Requests for Plant Pump & Valve Inservice Testing Program & Revised Responses to Questions 3 & 7 Posed in EA Licitra to Ee Van Brunt

ML17304A326
Person / Time
Site:	Palo Verde
Issue date:	08/02/1988
From:	Karner D ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
161-01205-DBK-B, 161-1205-DBK-B, TAC-64953, TAC-64954, TAC-64955, NUDOCS 8808100024
Download: ML17304A326 (20)

Text

'C t.'ELECTED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8808100024 DOC.DATE: 88/08/02 NOTARIZED NO DOCKET FACIL: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 4

AUTH.NAME AUTHOR AFFILIATION EARNER,D.B.

Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

R

SUBJECT:

Provides info re revised relief requests Insrvice Testing Program.

I DISTRIBUTION CODE:

A047D COPIES RECEIVED:LTR i

ENCL 2 SIZE:

TITLE: OR Submittal: Inservice Inspection/Testing/Relief from ASME Code NOTES:Standardized plant.

Standard'ized plant.

Standardized plant.

RECIPIENT ID CODE/NAME PD5 LA LICITRA,E INTERNAL: ACRS AEOD/DSP/TPAB NRR/DEST/MEB 9H N~U'.ABSTRACT G FILE 01 EXTERNAL: EG&G ROCKHOLD,H NL 007 HEMMING NSIC NOTES:

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TOTAL NUMBER OF COPIES REQUIRED:

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Arizona Nuclear Power Project P.O. BOX 52034

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PHOENIX, ARIZONA85072-2034 Docket Nos.

STN 50-528/529/530 161-01205-DBK/BJA August 2,. 1988 Document Control Desk U.S. Nuclear Regulatory Commission Mail Station Pl-137 Washington, D.C.

20555

References:

(1) Letter from J.

G. Haynes, ANPP, to USNRC Document Control Desk, dated September 10, 1987 (161-00496)

Subject:

PVNGS Inservice Testing Program.

(2) Letter from E. A. Licitra, NRC, to E.

E. Van Brunt, Jr.,

ANPP, dated March 30, 1987.

Subject:

ASME Section XI Pump and Valve Inservice Testing Program - Palo Verde, Units 1, 2 and 3.

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2 and 3

Revised Relief Requests for PVNGS Inservice Testing Program File:

88-A-056-026 By Reference 1,

ANPP submitted relief requests for the PVNGS pump and valve inservice testing program.

This submittal was in response to several NRC questions (Reference 2) and a meeting between ANPP and NRC that was held on May 27 and 28, 1987.

Subsequent to the Reference 1 submittal, ANPP was informed by the NRC Staff of another alternative for performing inservice testing of pumps.

The purpose of this letter is to revise two of our previous relief requests to apply the new testing alternative proposed by the NRC Staff.

The revised relief requests are provided in an attachment to this letter.

Also provided are revised responses to questions 3

and 7

(pump testing section) of Reference 2.

These revised responses present a discussion o'f the test program changes.

If you have any additional questions on this

matter, please contact Mr. A. C. Rogers at (602) 371-4041.

Very truly yours, 00NU INtAA I,OOQ I(0O

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'OO OQ OC 00'OZ Ima

'%0 0-DBK/BJA/pvk Attachments cc:

G.

W. Knighton M. J. Davis T. J. Polich J.

B. Martin A. C. Gehr (all w/a)

D. B. Karner Executive Vice President Pro)ect Director

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ATTACHMENT 1 REVISED RESPONSES TO UESTIONS, 3 5 7

In the pump testing section of Reference 2,

the NRC Staff asked several questions concerning inservice testing

.of safety related pumps at PVNGS.

In particular, questions 3

and 7

dealt with flow measurement during inservice testing.

ANPP responded to both of these questions in Reference 1.

However, these responses must now be revised due to the changes to Pump Relief Requests (PRRs) 1 and 6.

The NRC questions along with the revised responses are provided below.

Concerning pump relief request No.

1;;Section XI, Paragraph IWP-3100 requires that both pump di'fferential pressure and flow rate to be measured.

ANPP Res onse For the auxiliary feedwater and safety injection pumps at PVNGS, the normal inser'vice test'ing is conducted: via the minimum'flow recirculation loops.

These minimum flow recirculation lines are,not instrumented for flow measurement.

Therefore, in our previous response to this NRC question we had stated that Controlotron flow instrumentation would be added,to the minimum; flow recirculati'on lines.

This would meet the code requirement to measure flow.

However, these devices could'nly be calibrated to

+5%

accuracy.

This would not have met the code requirement of

+2% accuracy for flow measurement.

Consequently, we submitted PRRs 81 and 86 to request relief from the accuracy requirements

'for flow measurement.

In conclusion, our previous response stated that:

i)

Flow will be measured during the minimum flow recirculation testing.

ii) Requested relief from the accuracy requirements for flow measurement.

Subsequent to our submittal of this response, the NRC Staff proposed another alternative.

Specifically, in lieu of measuring flow during the minimum flow recirculation testing, it would be acceptable to perform a full flow test in which flow was measured.

The full flow test would have to be performed at refueling intervals.

Me would like to implement this alternative proposed'y the NRC 'Staff.

Our revised inservice testing program for the auxiliary feedwater pumps at PVNGS will have the following features:

i)

The quarterly inservice test will be performed via the minimum flow recirculation loops.

Flow will'ot be measured during these tests.

ii) Full flow tests will be conducted at refueling outage intervals.

Flow will'be measured during these tests.

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Attachment 1 (Continued)

To implement this revised testing program, PRRs 1 and 6 have been revised.,

The previous PRRs were for the accuracy of the flow measurement devices.

The revised.

PRRs request relief from measuring flow during the quarterly inservice tests.

These revised PRRs are provided, in Attachment 2 of this letter.

Concerning

.pump relief request 86, lack of proper flow measurement instrumentation does not negate the code requirement that flow be measured.

See response to question 83 above.

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ATTACHMENT 2 REVISED PUMP RELIEF REQUESTS

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PROGRAM:

UNIT:

REV:

PUMP RELIEF RE UEST N0..1 SYSTEM'uxiliary Feedwater System (AF)

COMPONENTS:

AFN-P01, AFA-POl, AFB-POl P&ID & COORDINATES:

13-M-AFP-001 8 H8, D8, B8 CLASS:

3 FUNCTION'FN-P01, AFA-POl, and AFB-P01 are the nonessential Auxiliary Feedwater Pump, the steam driven Aux -Feedwater Pump and motor driven Aux Feedwater Pump, respectively, and supply make-up water to the Steam Generator during startup/shutdown conditions and subsequent to receipt of an AFAS (aux feed actuation signal).

Note AFN-POl does not receive an AFAS.

TEST RE UIREMENT:

IWP-3100 requires, that either the pump differential pressure or flow rate be set and both pump criteria (differential pressure and flow rate) be measured.

BASIS FOR RELIEF:

Pump degradation may be observed by changes in pump head and/or flowrate.

Due to the pump tests being performed at the miniflow recirculation point on the pump curve, changes in pump head're more indicative of degradation.

Pump flowrate is not varied for these tests but rather is constant as a result of the fixed resistance of the miniflow line and therefore does not need, to be measured.

ALTERNATE TESTING:

As an augmented inspection to provide additional information regarding pump performance, full, flow testing of AFA-POl and AFB-POl will be performed on refueling

basis, and flow rate will be measured.

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PROGRAM:

UNIT:

REV:

PUMP RELIEF RE UEST NO.

6 SYSTEM:

Safety Injection System (SI)

COMPONENTS:

SIA-P01, SIB-Pol SIA-P02, SIB-P02

'SIA-P03, SIB-P03 P&ID & COORDINATES:

13-M-SIP-001 8 B-ll, G-ll, A-ll,.'E-ll, C-11', H-11 CLASS:

FUNCTION:

SIA-P01 and SIB-P01 are Low Pressure Safety Injection Pumps and also serve as Shutdown Cooling Pumps.

SIA-P02 and SIB-P02 aze High Pressure Safety Injection Pumps.

SIA-P03 and SIB-P03 are Containment Spray Pumps.

These pumps provide Emergency Core Cooling functions (POl and

,P02), residual heat removal function (P01),

and containment heat removal function (P03).

TEST RE UIREMENTS:

IWP-3100 requires that either the pump differential pressure or flow rate be set and that both pump, criteria (differential pressure and flow rate) be measured.

BASIS FOR RELIEF:

Pump degradation may be observed by changes in pump head and/or flowrate.

Due to the.pump tests being performed at the miniflow recirculation point on the pump curve, changes in pump head are more indicative of degradation.

Pump flowrate is not varied for these tests but rather is constant as a result of the fixed resistance of the miniflow line and therefore does not need to be measured.

ALTERNATE TESTING:

As an augmented'nspection to provide additional information regarding pump performance, full flow testing of these pumps will be performed on a refueling basis.

Pump flowrate will be measured for the full flow test with an accuracy of +/- 5t full scale.

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July 22, 1988 DISTRIBUTION Docket-File.

PDR LPDR PD 5 Rdg JLee DOCKET NO(S)

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STH 50-528/529/530 Hr Donald B Karner Executive Vice President Arizona Nuclear Power Pro)ect P

0 Box 52034 Phoenix, Arizona 85072-3999

SUBJECT:

ARIZONA PUBLIC SERVICE COMPANY'T AL PALO VERDE NUCLEAR GENERATING STATIONS UHITS l, 2 6 3 The following documents concerning. our review of the subject facility are transmitted for your informati on.

Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availabi li,ty of Draft/final Environmental Statement, dated Safety Evaluation Report, or Supplement No.

dated Environmental Asse'ssment and Finding of No Significant Impact, dated Q Notice of Consideration of Issuance of Facility Operating License or Amendment to-Facil ity Operating

License, dated

+ Hi-Weekly Notice; Applications and Amendments to Operating Licenses Involving No B if' d

C id i,d d~f Ill Exemption, dated Construction.Permit No.

CPPR-

, Amendment No.

dated Facility Operating License No.

, Amendment No.

dated-Order Extending Construction Completion Date, dated Monthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-transmitted by.letter dated Encl osures:

As stated Office of Nuclear Reactor Regulation n

See next page OffICED SURNAME)

DATK)

D

/PD5 7/2 /88

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NRC FORM 3IS IIO/801 NRCM 0240 OFFtctAL RECORD COPY

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UNITED STATES'UCLEAR.

REGULATORY COMMISSlu WASHINGTON, D.

C.'0555'uly 22, 1988 DOCKET'NO(S).

STN 50-528/529/530 Mr. Donald B. Karner Executive Vice President Arizona Nuclear Power Project P. 0. Box 52034 Phoenix, Arizona 85072-3999 ARIZONA PUBLIC SERVICE COMPANY, ET AL PALO VERDE NUCLEAR GENERATING: STATION, UNITS l, 2

& 3 The following documents concerning.our review of the subject facility are transmitted for your information.

Notice of Receipt of Application, dated Draft/Final'nvironmental'tatement,,

dated Notice of Avai.lability of Draft/Final 'Environmental Statement, dated Safety Evaluation Report, or Supplement No.

dated

.Environmental Assessment and Finding of No Signi;ficant Impact, dated Notice of Consideration of Issuance of Facility Operating, License or Amendment to Facility Operating License, dated Qg Hi-Weekly Notice; Applications and Amendments to Operating Licenses Involving No id i, ~f Wl Exemption, dated Construction Permit. No.

CPPR-

, Amendment No.

dated

+ Facility Operating License No.

, Amendment No.

dated

,Order Extending Construction Completion Date, dated monthly Operating Report for transmitted by letter dated Annual/Semi-Annual Report-transmitted by letter dated

Enclosures:

As stated Office of Nuclear Reactor Regulation CC:

See next page

0>

ii

Mr. Donald B. Karner Arizona Nuclear Power Project Executive Vice President Post Office Box 52034 Phoenix, Arizona 85072-.2034 Palo Verde CC:

Arthur C. Gehr, Esq.

Snell 5 Wilmer 3100 Valley Center Phoenix, Arizona 85073 Mr. James M. Flenner, Chief Counsel Arizona Corporation Commission 1200 West Washington Phoenix, Arizona 85007 Charles.

R. Kocher, Esq. Assistant Council James A. Boeletto,. Esq.

Southern California Edison Company P.

O.

Box 800

Rosemead, Ca.l.i fornia 91770 Mr. Mark Ginsberg Energy Director Office of Economic 'Planning and Development 1700 West Washington - 5th Floor Phoenix, Arizona 85007's.

Lynn Bernabei Government Accountability Project of the Institute for Policy Studies 1901 gue Street, NW Washington,

.DC 20009 Mr. Charles B. Brinkman, Manager Washington Nuclear 'Operations Combustion Engineering,,'Inc.

7910 Woodmont Avenue Suite 1310

Bethesda, Maryland 20814 Mr. Wayne Shirley Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Mr. Tim Polich U.S.. Nuclear Regulatory Commission P. 0.

Box 97 - Palo Verde Tonopah,, Arizona 85354'-0097 Regional Administrator, Region V

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

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