ML20214H581
| ML20214H581 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/19/1986 |
| From: | Marlone Davis Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8611260468 | |
| Download: ML20214H581 (35) | |
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y Ig a UNITED STATES gg 'g NUCLEAR REGULATORY COMMISSION
- i j [ WASHING TON, D. C. 20555 NOV 101986
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Docket Nos.: 50-528, 50-529 and 50-530 APPLICAhT: Arizona Public Service Company FACILITY: Palo Verde, Units 1, 2 and 3
SUBJECT:
SUMMARY
OF TRIP TO PH0ENIX, ARIZONA, OCTOBER 27-31, 1986
- 1. Management Meeting A management meeting was held on October 28, 1986, in the licensee's office in Phoenix, Arizona, with reoresentatives of the licensee and NRC representatives from the Offices of NRR, Region V, I&E, and AE00. The purpose of the meeting wa:, to discuss NRC concerns generated during assessment of the operating performance of Palo Verde Units 1 and 2 in consideration of the pending licensing decision for Unit 3, and to identify needed licensee actions for improvement prior to the licensing decision.
The rieeting agenda and list of attendees are enciesed as Enclosures 1 and 2 respet:tively.
- The licensee prepared and presented responses to the concerns identified by the NRC in the prooosed agenda provided in their letter dated October 10, 1986 ta Mr. E. Van Brunt. Slides used in their presentation are enclosed as Enclosure 3. The licensee's briefing made it clear that the licensee was or is aware of the staff concerns. In some cases such as root cause analysis, operating experience at the corporate level, contacts with other plants concerning experiences on similar systems,, single failure vulnerabilities in plant design, and I&C problems the licensee has taken actions he believes will resolve the concerns.
In the area of personnel errors and technical specifications surveillance violations, the licensee believes he now has programs in place to reduce the number of occurrences. He believes that experience to date has shown recognizable reductions already. However, recognizing the staff's concerns, he will monitor future performance and take further actions to resolve the problem, if necessary.
In light of the number of current staff concerns with two unit operation, the staff stated that the licensing of Unit three may deserve a reevaluation of corporate level operating experience.
There was a discussion of a number of items resulting frcm the licensing and operation of Units 1 and 2 that need to be resolved (Enclosure 4). It was agreed that documentation of the steps taken or planned to resolved staff concerns and schedule fcr resolution of the open items in Enclosure 4 will be submitted to the staff,by January 1, 1987.
8611260468 DR 061119 ADOCK 05000528 PDR
2-The NRC staff appreciated the presentation and will watch for evidence of success of the corrective actions in improving performance trends.
- 2. Emergency Exercise On October 29, 1986, Messer, Knighton, Licitra, and Davis observed licensee performance during the Palo Verde annual Emergency Exercise. Operations were observed in the simulator, the Technical Support Center, and the Emergency Operations Facility.
- 3. Unit 3 Readiness Meeting On'0ctober 30, 1986, a Unit 3 readiness meeting was held at the Palo Verde site with representatives of the licensee and the NRC staff. Following the l meeting the staff members toured Unit 3. The purpose of the meeting and tour was to describe the status of construction on Unit 3 and the anticipated schedule for fuel' load. The licenste expects to be ready for fuel load in early March, 1987, which is consistent with the current Eevill Schedule, and appears to the staff to be reasonable.
Enclosed as Enclosures 5 and 6 are a list of meeting attendees and a copy of the licensee's handout, Palo Verde Unit 3 Project Schedule October 28, 1986.
l5 Michael J. Davis, Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Enclosures:
As stated cc: See next page PD7 Old(
MDavis/yt h7hton GW&n 11/l4/86 11// /86
t
, .g Mr. E. E. Van Brunt, Jr.
Arizona Nuclear Power Project Palo Verde cc:
Arthur C. Gehr, Esq. Kenneth Berlin, Esq.
Snell & Wilmer Winston & Strawn 3100 Valley Center Suite 500 Phoenix, Arizona 85073 2550 M Street, NW Washington, DC 20037 Mr. James M. Flenner, Chief Counsel Arizona Corporation Commission Ms. Lynne Bernabei 1200 West Washington Government Accountability Project Phoenix, Arizona 85007 of the Institute for Policy Studies 1901 Que Street, NW Charles R. Kocher, Esq. Assistant Washington, DC 20009 Council James A. Boeletto, Esq.
Southern California Edison Company Mr. Ron Rayner P. O. Box 800 P. O. Box 1509 Rosemead, California 91770 Goodyear, AZ 85338 Mr. Mark Ginsberg Mr. Charles B. Brinkman, Manager Energy Director Washington Nuclear Operations Office of Economic Planning Combustion Engineering, Inc.
and Development 7910 Woodmont Avenue Suite 1310 1700 West Washington - 5th Floor Bethesda, Maryland 20814 Phoenix, Arizona 85007 Mr. Wayne Shirley Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Mr. Roy Zimmerman U.S. Nuclear Regulatory Commission P. O. Box 239 Arlington, Arizona 85322 Ms. Patricia Lee Houritan 6413 S. 26th Street Phoenix, Arizona 85040 Regional Administrator, Region V U. S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596
NOV is $86 FEETING
SUMMARY
DISTRIBUTION DocketNo(s)::'50-528/529/530- -
NRC POR' Local PDR PBD-7 F.eading JParticw BGrimes ACRS(10)
EJordan Attorney, OELD GWKnighton M. Davis Project Manager ELicitra NRC PARTICIPANTS G. Knighton E. Licitra M. Davis M. Harper S. Richards A. Chaffee '
R. Zimmerman L. Miller F. J. Miraglia J. G. Partlow M. H. Williams Y. Togo J. B. Martin l
bec: Applicant & Service List l
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s s Enclosure 1 PALO VERDE MANAGEMENT MEETING October 28, 1986 AGENDA I. Introduction A. NRC B. ANPP E. E. Van Brunt II. ANPP Presentation A. Overall Plant Performance J. R. Bynum B. Assessing / Improving Plant P?rformance 0. J. Zeringue/R. M. Butler C. Management Resources J. G. Haynes D. Conclusion J. G. Ilaynes III'. Closing Remarks NRC
s s Enclosure 2 MEETING ATTENDEES FOR PALO VERDE NAME AFFILIATION Manny Licitra NRC/NRR/PD7 Marc Harper NRC/AEOD/PTB Stuart Richards NRC/ Region V Al Chaffee NRC/ Region V D. J. Zerangue ANPP/PVNGS Roy Zimerman NRC/ Region V Lew Miller NRC/ Region V Joe Bynum ANPP/PVNGS Plant Manager Bob Butler ANPP/ Director Tech. Services E. E. Van Brunt ANPP/ Exec. VP J. G. Haynes ANPP/VP J. B. Martin Region V Administrator F. J. Miraglia NRR/PWR-B J. G. Partlow NRC/Div. of Insp. Program, IE Mark H. Williams NRC/AE0D G. W. Knighton NRC/ Project Directorate Dan Andrews ANPP Michael J. Davis NRC/NRR Yoichi Togo NRC/AE0D Allan Mitchell Arizona Corp. Com.
Duke Railback Arizona Corp. Com.
Ken Rotta Arizona Corp. Com.
Nowell Rush Ernst & Whinney Christopher Kempley ACC George H. Lycrs Snell & Wilmer Terry Quan ANPP/Prudency Audit Dept.
John Driscoll ANPP/AVP Bill Quinn ANPP/ Manager Licensing Tim Shriver ANPP/hnager Compliance Charles N. Russo ANPP/ Manager Nuclear Safety Arthur Gehr ANPP/Snell A Wilmer Richard Bernier ANPP/ Lead Licensing Engineer Peggy Nelson ANPP/ Licensing Engineer l
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. . Enclosure 3 DISCUSSION LIST FROM ANPP/NRC 11/04/86 MANAGEMENT MEETING ON 10/28/86
. DNBR trip. When a fast bus transfer occurs, a 7 RPM dip in RCP speed is
- sufficient to cause a flow projected DNBR trip to occur. This appears to be a problem of insufficient margin.
- 2. The Steam Bypass Control System (SBCS) responds as expected when actuated from power levels above 70".. However, when power level is below 70%, the system has a tendency to over respond. This appears to be a fine tuning problem, and Combustion Engineering is involved in providing a solution.
- 3. Reactor Coolant Pump (RCP) coastdown is quicker than indicated 'in the safety analysis. A re-analysis was completed indicating that the existing flow conditions are within the bounds of the current safety analysis.
~4. During a partial loss of non-class lE power, the motor operated isolation valve in the main steam supply to the moisture separator reheater
- remained open, due to the loss of power. Simultaneously, the high level dump valve on the reheater drain tank opened to the condenser, creating a path for steam flow from the main steam system to the condenser. This in turn caused the pressure in the cteam generator to decrease sufficiently to actuate the Main Steam Isolation Valves. Design changes will be ,
implemented to correct the problem.
-s
- S. The BOP ESFAS/RMS equipment have caused numerous actuations of the ESF '
systems. The problems have been varied and have included inadequate ventilation in cabinets, bad connections, and inadequate grounding.
- 6. Several problems have occurred with the charging pumps. Cas binding has occurred due to low VCT level and a ruptured diaphragm in a pulsation dampener. Additionally, a crack was discovered in a 4arging pump block. The changing pumps impact the operability of tne auxiliary
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pressurizer spray.
- 7. The issue of the masonry walls at elevati n 76' is being addressed in separate correspondence with the NRC. _
j 8. During the event on 7-12-86, the co'ntrol room supervisor first diagnosed
._.; ..the event as a small break LOCA when in reality it was an execesive steam
'~
demand event. During the event there was also a partial loss of
' non-class 1E power which' energizes certain main control board indicators needed to complete the diagnosis. The NRC has transmiteed their concerns j in a letter, and ANPP is evaluating them and the emergency procedure.
- 9. The NRC noted that the low pressurizer pressure trip and the safety i- injection actuation setpoints were the same. The question was raised as l
to whether it was desirable or not to have them the saue.
i
- 10. ANPP has taken exception to provisions in R.G. 1.68.2 which would require
, a test to prove remote shutdown capability in each unit. The NRC has -
determined that the test should be done in each unit. ANPP will respond to the NRC by 11-10-86.
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- 11. Problems were expe rienced with unwanted actuation of breakers in the switchyard. The breaker operations which caused actuations of the Reactor Protection System were caused by malfunctions in the plant multiplexer system (PMUX). Switchyard breaker control circuits have been hardwired, bypassing the PMUX for this function.
9
- 12. Numerous computer failures in the security system have been a problem.
- 13. PVNGS has demonstrated vulnerabilities to single failures as demonstrated by charging pump pulsation dampener failures, actuation of SBCS by a computer card, startup transformer current transformer connections, and a loose wire on H07-536.
- 14. Numerous annunciators remain lighted on the main control boards. ,
- 15. ANPP should develop more formal and regular communication with "other plants, particularly the other CPC plants.
- 16. The NRC expressed concern about whether or not formal procedures existed to insure the transfer of information and data from one unit to another.
- 17. Concern was expressed by the NRC concerning load shedding causing valve inoperability. They wanted to know if we were looking at the problem.
- 18. The NRC noted that we must insure that all information for the Sholly process is included in licensing submittals. In addition, consideration .
must be given to changes which could be affected by the Diablo Canyon -
decision in the Ninth Circuit Court which opened hearings for certain .s 4
kinds of changes. Change requests should look at more than just the ,
small scope of the change, and the time when the changes are needed must be considered.
- 19. Does the Post Trip Review Procedure adequately cover what must be done and what must be monitored when the plant is restarted when the cause of the trip has not been fully determined?
^
- 20. Does the SPDS" computer havs suffi21ent capadity to' perford in a timely manner if the third unit is added to the system?
- 21. There have been control problems at low power levels in the feedwater l control system.
~'
and relatively little debris to enter the water boxes. Condenser tube performance should be better.
- 23. PVNGS has had personnel errors / Tech. Spec. violations. Describe actions taken by management to reduce these occurrences.
Enclosure 4 PALB VERDE UNIT 3 PRB]ECT SCHEDULE DATE: 10-28-86' i
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4 1986 1987 -
JAN l FEB l MAR l APR l MAY l JUN l JUL l AUG l SEP l OCT l NOV l OEC JAN l FEB l mad l APR - l Mt.Y l JUN l JUL l AUG
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( A) 07-27-86 ,
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1 (A) 09-11-86 VACUUM kNNNSI (S) 06-28-86 ( A) 04-01-86 (ACT) (SCHED)
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LEGEND ; ;;"'t',,,t l:c ARIZONA NUCLEAR POWER PROJECT guig;; ' " ' '
s.1' STATUS l l AS OF: PALO VERDE NUCLEAR GENERATING STATION UNIT 3 i ea=unir M ovaario= h\\\\%\%q 10-24-86 MILESTONE
SUMMARY
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PALO VERDE NUCLEAR GENERATING STATION UNIT 3 STARTUP STATUS
SUMMARY
STATUS AS OF 10/18/86 - 10/24/86 I. SUBSYSTEM 'IRANSFERS TO STARTUP Scheduled Actual Actual Total To Dal Late This Feriod To Date Remainine 374 374 (1) 0 373 1 II. PREREQUISITE TE0 TING STATUS Total Total Actual Actual % % Diff for Discipline Tests This Period To Date Complete Reporting Period Electrical 10,198 ( 2) 81 9,961 97.7 0.6 I&C 13,147 (39) 91 12,821 97.5 0.4 Mechanical 3,643 (-15) 50 3,384 92.9 1.8' TOTAL 26,988 (26) 222 26,166 97.0 0.8 OPS DTS 2,303 (37) 38 931 40.4 1.0 III. SUBSYSTEM RELEASES TO PREOPERATIONAL TESTING Schedule Actual Actual Total To Date This Period To Date Remaining-374 373 0 373 1 IV. PREO?ERATIONAL/ COMMISSIONING TESTING STATUS Total Sched. TESTS TO DATE Tests Comp. In Progress Complete Remaining Preoperational 137 123 24 88 49 Commissioning 66 59 1 63 3 Hot Functional Test 34 -
13 -
34 Total 237 182 38 151 86
- V. OPERATIONS ACCEPTANCE Scheduled Actual Actual Total To Date LATE This Period To Date Remaining Startup 374 188 ( 5) 24 210 164 Construction 142 124 ( 5) _1, 121 21 Total 516 312 (10) 25 331 185
- REFLECTS THE REV. 3 ACCEPTANCE PROFILE
.5 UPDATE-SU STATUS
SUMMARY
9
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245 TOTAL o o l 2 l lo T T3 l 353 l
4 T ET EM V P i H h IS F 1f 1I Y f Y If TY 1I UNIT 2 I . I 40.0 MGNTHS
.' -5 6 e5.5 7 2 65 DTS % : 30 := T 2 > si > .00 PE/CM o l 0 2a is l22 So i.T = 221 TOTAL LEGEND:
T F4RST TRANSFER ET ENERG12E XFMR EM ENERG12E MCC P PRIM A RY HYDRO FT V VACUUM T EM V P Hf JG F V Y V V/ V 8 a i UNIT 3 I n not runCrioNAL TEST 34 o MONTHS R FUEL RECEtPT l ,
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PE/CM o n so as (59) = 203 TOTAL iI FOREC'5' 075 DISCIPLINE TEST SCHEDULE CM COMMIS$1oNING TESTS PE PRE-OP TESTS
Enclosure 5 Readiness Meeting Attendees October 30, 1986 J. Haynes ANFP/VP D. Bernier ANPP/ Lead Licensing Engineer J. Ball NRC/ Resident Inspector D. Gouge ANPP/ Unit 3 Superintendent W. Jump ANPP/ Unit 3 Startup Manager J. Kirby ANPP/ Transition Manager G. Knighton NRC/NRR E. Licitra NRC/NRR M. Davis NRC/NRR i
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- 1. CONTACTED OTHER PLANT TO EVALUATE EXISTING PROCESS.
- 2. IDENTIFIED AREAS OF IMPROVEMENT
- 3. DEFINED FORMAL ROOT CAUSE/ ENGR. EVAL. PROCESS.
- 4. QUARANTINE COMP 0NENTS UNTIL ROOT'CAUSE/ EVALUATION COMPLETE
- 5. PLANT TRANSIENT RESPONSE /0PERATOR RESPONSE EVALUATION
- 6. DEFINED RESTART CRITERIA
- 7. UNIT UNIQUE EVALUATIONS WITH SHARED RESULT
- 8. AB0VE APPLIED TO OTHER SYSTEM, COMPONENT, & PERSONNEL PERFORMANCE EVALUATIONS I
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