ML17299B058

Summary of 860206 Meeting W/Util & C-E in Bethesda,Md Re Natural Circulation Cooldown Test Procedure.Attendee List & Viewgraphs Encl

ML17299B058
Person / Time
Site:	Palo Verde
Issue date:	02/13/1986
From:	Licitra E Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-56647, NUDOCS 8603040082
Download: ML17299B058 (37)

Text

Docket No.:

50-528 tg88 LICENSEE:

Airzona Public Service Company FACILITY:

Palo Verde Unit 1

SUBJECT:

Summary of Meeting Regarding Natural Circulation Cooldown Test Procedure A meeting was held on February 6, 1986 in Bethesda, Maryland with representatives of the licensee.

The purpose of the meeting was to discuss the revisions made to the procedure for the natural circulation cooldown test performed at Palo Verde Unit 1 on January 24-25, 1986.

Attendees for the meeting are listed in Enclosure 1 and the viewgraphs presented are included as Enclosure 2.

The meeting is summarized as follows:

~Summar The licensee discussed the sequence for the natural circulation cooldown test performed on Palo Verde Unit 1.

The licensee also identified the following four changes made to the version of the procedure described in its August 29, 1985 letter.

(1) test initiation -

RCS pump trips preceeded by turbine trip (2) partial use of third charging pump during natural circulation cooldown (3) use of letdown during depressurization (4) use of A and B trains for venting The licensee then discussed the reasons for the changes and indicated that an evaluation of the changes showed no effect on the test objectives.

The staff requested the licensee to submit a discussion of this evaluation with additional details in response to staff questions during the meeting.

The licensee agreed to do so and will respond by February 21, 1986.

8603040082 860213 PDR ADOCK 05000528 P

PDR

Enclosures:

(1)

Meeting Attendees (2)

Viewgraphs

/5 E. A. Licitra, Project Manager PWR Project Directorate No.

7 Division of PWR Licensing-B PBD7 EALicitra/es 2j/$86 2

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Mr. E.

E.

Van Brunt, Jr.

Arizona Nuclear Power Project Palo Verde CC:

Arthur C. Gehr, Esq.

Snell Wilmer'100 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. 0.

Box 800

Rosemead, California 91770 Mr. Hark 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 Mr. Rov Zimmerman U.S.. Nuclear Regulatory Commission P. 0.

Box 239 Arlington, Arizona 85322 Ms. Patricia Lee Hourihan 6413 S. ?6th Street Phoenix,'Arizona 85040 Regional Administrator, Reoion V

U. S. Nuclear Regulatnry Commission 1450 Maria Lane Suite 210 Walnut Creek, Cali fornia 94596 Kenneth Berlin, Esq.

Winston

& Strawn Suite 500 2550 M Street, NW Washington, DC 20037 Hs.

Lynne Rernabei Government Accountability Project of the Institute for Policv Studies 1901 gue Street, NW Washington, OC 20009 Ms. Jill Morrison 522 E. Colgate Tempi, Arizona 85238 Hr. Charles B. Brinkman, Manaqer Washington Nuclear Operations Combustion Engineerinq, Inc.

7910 Woodmont Avenue Suite 1310

Bethesda, Maryland 20814 Mr. Ron Rayner P. 0.

Box 1509

Goodyear, AZ 85338

Enclosure 1

MEETING ON NATURAL CIRCULATION COOLDOWN TEST PROCEDURE FOR PALO VERDE 1

February 6, 1986 Attendees Manny Licitra George Knighton Brad Albert Terry Juan Nark Hulet Chu-Yu Liang Matt Reid Cecil Thomas Tim Collier Mel Wolpert Gerald Sower Kelly Mcguoid Ed Branagan Norm Lauben Affiliation NRC/PWR-B/PBD-7 NRC/PWR-B/PBD-7 ANPP - Licensing ANPP - Licensing ANPP - Reactor Engr.

NRC/PWR-B/RSB ANPP - Safety Analysis NRC/PWR-B/RSB C-E C-E ANPP - Safety Analysis C-E NRC/PWR-B/RSB NRC/PWR-B/RSB

Enclosure 2

I.

INTRODUCTION PURPOSE OF MEETING BACKGROUND

SUMMARY

TEST OBJECTIVES II.

REVIEW OF TEST SEQUENCE

SUMMARY

OF SIGNIFICANT EVENTS DIFFERENCES FROM THE REVIEWED TEST PROCEDURE III.

DISCUSSION OF DIFFERENCES EFFECT OF DIFFERENCES ON THE TEST OBJECTIVES IV.

CONCLUSIONS

PURPOSE OF MEETING IDENTIFY DIFFERENCES FROM PREVIOUSLY REVIEWED TEST PROCEDURE DISCUSS THE EFFECTS OF PROCEDURE DIFFERENCES ON THE TEST OBZECTIVES

l

NRC STAFF REVIEW BASED UPON TWO SUBMITTALS:

1)

ANPP-31829 (1/31/85) - REVISION B

OF TEST PROCEDURE (72PA-iRX03) 2)

ANPP-33282 (8/29/85)

ADDITIONAL TEST PROCEDURE CHANGES DISCUSSED IN LETTER REASONS FOR ANPP CHANGES TO PREVIOUSLY REVIEWED PROCEDURE REDUCTION IN THE NUMBER OF REACTOR TRIPS REDUCTION IN THE CHALLENGES TO PLANT SAFETY SYSTENS

I.

GATHER DATA TO SUPPORT POST-TEST ANALYSIS FOR BTP RSB 5-i.

A.

REGULATORY GUIDE i.68, REV.

0 MEASURE THE POWER TO FLOW RATIO UNDER NATURAL CIRCULATION CONDITIONS B.

BRANCH TECHNICAL POSITION RSB 5-i REQUIREMENTS.:

I)

PERFORM BORON MIXING DEMONSTRATION zz)

NATURAL CIRCULATION COOLDOWN AND DEPRESSURIZATION II.

MEASURE PLANT RESPONSE TO A TOTAL LOSS OF FORCED RCS FLOW III.

USE NATURAL CIRCULATION TEST DATA TO UPDATE AND VERIFY THE PVNGS SIMULATOR MODEL IV.

DEMONSTRATE ACCEPTABLE AUXILIARY PRESSURIZER SPRAY PERFORMANCE WITH THE INTERNALS OF CHECK VALVE RCV-2R'I REMOVED

1130.00 1130. 13 1139. 00 1226 1929 1621 TURBINE TRIP INITIATED REACTOR TRIP ON HIGH PRESSURIZER PRESSURE MANUALLY TRIP RCP's (PLANT STABLIZATION IN HOT STANDBY CONDITIONS )

DETERMINE POWER TO FLOW RATIO BEGIN BORON MIXING DEMONSTATION END BORON MIXING DEMONSTATION 1808 2230 BEGIN NATURAL CIRCULATION COOLDOWN END NATURAL CIRCULATION COOLDOWN AT THOT = 399'F 2298 2257 2323 0031 0053 0119 0139 0195 BEGIN DEPRESSURIZATION WITH APSS CLOSED MAIN SPRAY VALVES TO VERIFY NO BACKFLOW STOPPED DEPRESSURIZATION AT 50X PRESSURIZER LEVEL (ADJUSTED PRESSURIZER LEVEL TO PREPARE FOR VOID FORMATION)

RE-STARTED DEPRESSURIZATION INDICATIONS OF VOID FORMATION IN UPPER HEAD STOPPED DEPRESSURIZATION BEGIN VOID COLLAPSE (OPENED HEAD VENT VALVES)

VOID COLLAPSE COMPLETE 0220 SHUTDOWN COOLING ENTRY CONDITIONS ACHIEVED 0712 ~

TEST CONCLUSXON AT 250'

V

600 PERMDAS January 2425, 1986 P PEL I Y I NARY 500 I

450 ~

400 ~

550 ~

500 250 1 1:00 1 4-29 17 58 21:27 00:58 04:29 (one minute scans)

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2.1 PERMDAS January 2425, 1986 P P,EL I 4~I 55RY 1.9 1.8 1.7 1.6 1.5 1.4 1.3 1.2 1.1 1

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I 1 1:00 14:29 17:58 21:27 00 58 04:29 (one minute scans)

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CHANGES MADE PRIOR TO TEST PERFORMANCE INITIATE NATURAL CIRCULATION FROM HOT STANDBY (MODE 3)

USE OF AN A-TRAIN AND 8-TRAIN VENT VALVE 'TO COMPLETE REACTOR VESSEL HEAD VENT PATH II.

DEVIATIONS FROM TEST PROCEDURE DURING THE TEST USE OF THE 3RD CHARGING PUMP DURING THE TEST USE OF LETDOWN DURING THE DEPRESSURIZATION PORTION OF THE TEST

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I.

PURPOSE:

TO ADDRESS THE DIFFERENCES BETWEEN THE REVIEWED TEST PROCEDURE AND THE ACTUAL TEST II.

MAZOR DIFFERENCES BETWEEN REVIEWED PROCEDURE AND ACTUAL TEST TEST INITIATION USE OF 3 CHARGING PUNPS USE OF LETDOWN DURING DEPRESSURIZATION USE OF A 6 8 TRAIN VENT VALVES

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i) STEADY STATE, POWER )80X

2) TRIP ALL 9 RCPs 3)

REACTOR TRIP ON LOW DNBR 1)

STEADY STATE POWER - iOOK 2)

TURBINE TRIP 3)

REACTOR TRIP ON MIGH PRESSURE l) TURBINE TRIP 5)

EVALUATE NATURAL CIRCULATION 9)

TRIP ALL 0 RCPs 5)

EVALUATE NATURAL CIRCULATION

620 ~

P ERMDAS January 24, 1986 600 I

I' E. L l H I li P, R Y 590

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580 ~

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1,

I, DISCUSSION OF DIFFERENT TEST INITIATION METHOD o DURING NATURAL CIRCULATION UPPER HEAD TEMPERATURES ARE A FUNCTION OF LOOP TEMPERATURES AND HEAD COOLING ONLY o

HOT LEG TEMPERATURE IS A FUNCTION OF INLET TEMPERATURE AND DECAY HEAT I I, CONCLUSIONS o OPERATION OF RCPs FOR 9-MINUTES FOLLOWING REACTOR TRIP HAD NO LONG-TERM EFFECT ON HEAD TEMPERATURES o

EFFECTS OF CEDM COOLERS WILL BE ADDRESSED IN ANALYSIS o

CPC

RESPONSE

TO LOSS OF FORCED FLOW VERIFIED BY EARLIER TEST

I.

USE OF 3

CHARGING PUMPS CHARGING PUMP WAS USED TO COMPENSATE FOR LETDOWN AND SEAL INZECTION LETDOWN WAS USED TO OBTAIN LOOP BORON CONCENTRATION DATA THROUGH THE BORONMETER II.

CONCLUSION NET CHARGING FLOW (CHARGING-LETDOWN)

WAS LESS THAN OR EQUAL TO 2

CHARGING PUMPS AT ALL TIMES DURING TEST

150 140 1>O -j 120 -I 110 100 ~

90 PERMDAS January 2425, 1986 P RELlLLHARY

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CHG PUMP LETDN

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PRIOR TO VOID FORMATION, PRESSURIZER LEVEL WAS REDUCED IN ORDER TO ACCOMMODATE THE MAXIMUM EXPECTED VOID (i000 FT~)

IN ACCORDANCE WITH THE

RESPONSE

TO QUESTION 5A.22 OF THE PVNGS FSAR PVNGS HAS CAPABILITY TO ESTABLISH VENT PATH USING ONLY A OR B TRAIN VENT VALVES

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MEETING

SUMMARY

DISTRIBUTION

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Attorney, OELD Project Manager E. A. Licitra A

NRC PARTICIPANTS H. A. Licitra G.

W. Knighton Chu-Yu Liang Cecil Thomas Ed Branagan IJorm Lauben bcc:

Applicant

& Service List

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