ML20207B850

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Summary of 861209 Meeting W/Util & Eg&G Idaho in Bethesda,Md Re SPDS Testing Program Results,Tech Spec Change Requests & Unit 3 Licensing Submittals.List of Attendees & Viewgraphs Encl
ML20207B850
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 12/18/1986
From: Marlone Davis
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8612290134
Download: ML20207B850 (38)
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UNITED STATES NUCLEAR REGULATORY COMMISSION 5

l W ASHING TON, D. C. 20555

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DEC 18 9 1

Docket Nos.: 50-528, 50-529 and 50-530 LICENSEE: Arizona Public Service Company FACILITY: PALO VERDE UNITS 1, 2 AND 3 1

SUBJECT:

SUMMARY

OFMEETINGSTODISCUSSSPDSTESTINGPROGRAMRESULTS(MORNING)

AND TECHNICAL SPECIFICATIONS CHANGE REQUESTS AND PALO VERDE UNIT 3 LICENSINGSUBMITTALS(AFTERNOON)

Meetings were held on December 9,1986, in Bethesda, Maryland, with representatives of the licensee and the hRC staff. The purpose of the meetings was to discuss t

(1)NRCquestionsonPaloVerdeSafetyParameterDisplaySystem(SPDS) isolation

(

device testing raised during a site audit on November 18-19 1986(2)Scopeand schedulefurPaloVerdeUnit3licensingsubmittalsand(3),PaloVerdeUnits1 dnd 2 Technical Specifications change reouests. Attendees for the meetings are listed in Enclosure 1.

The meetings are sumarized as follows.

Meeting Sumary The licensee prepared and presented responses to the staff's concerns regarding SPDS digital isolators generated during the NRC audit of PVNGS SPDS. conducted November 18-19, 1986. The audit team had questioned the adecuacy of the PVNGS Digital SPDS isolation devices due to the results of the ANPP maximum credible f ault te. stir.g on digital isolators showino that the isolation barrier could be breachec. Slides used in their presentat{on are enclosed as Enclosure 2.

Based on the information presented on December 9, the staff has concluded that use of the digital SFDS isolation devices is acceptable. The fault would be acceptably mitigated by the large resistor in the isolation device. Also the IE SPDS contacts are used for the SPDS function only and are acceptably isolated from the other IE contacts on the devices. There would be no unacceptable influences on Class 1E circuits.

Based on the above, the staff is withdrawing the audit team recomendation to disconnect the SPDS. A letter will be prepared authorizing use of the SPDS for accident analysis, and will include appropriate recomendations resulting from the statf review and the site audit.

During the af ternoon meeting the licensee and NRC staff members discussed the status of PVNGS Unit 3 licensino action submittals as described in Enclosure 3.

It was determined that a letter'from ANPP confiming that modifications to the remote shutdown pane l required by SER SUPPLEMENT 5 pace 9 8 have been completcd e

needs to be added to the list of Enclosure 3.

l 0612290134 061210 PDR ADOCK 05000520 P

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.. The licensee committed to meeting the schedule dates for submittals as listed in Enclosure 3.

Later in the afternoon there was discussion of Units 1 and 2 Technical Specifications change requests. Suogestions for improving the quality of licensee TS change request submittals were made based upon Generic Letter 86-03 as a guideline. The licensee is prepared to utilize the guidelines to improve future submittals.

/5 Michael J. Davis, Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B

Enclosures:

As stated cc: See next page l

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MEETING

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NRC PARTICIPANTS

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4 lianny Licitra Leo Beltracchi l

George Knighton

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Mike Davis James Raleigh George Dick 4'

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Jean Lee l

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tect Applicant & Service List 1

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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 Oue 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 Hourihan 6413 S. 26th Street Phoenix, Arizona 85040 Regional Administrator, Region V l

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

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ATTENDEES FOR DECEMEER 9, 1986, MEETING PALC VERDE SPD5 ISOLATION DEVICES Bill Quinn ANPP Mike Jones ANPP Jim Rowland ANPP Joseph Provasoli ANPP Norm Helman ANPP Mark Hypse ANPP Manny Licitra NRC Leo Beltracchi NRC George Knighton NRC Mike Davis NRC James Raleigh NRC George Dick NRC Jose Cnivo NRC Arthur Nolan EG&GID ATTENDEES FOR DECEMBER 9, 1986, MEETING PALG VERDE TECH SPECS AND UNIT 3 LICENSING Bill Quinn ANPP Mike Jones ANPP Joseph Pravasoli ANPP Manny Licitra NRC George Knighton NRC Jim Raleigh NPC Jean Lee NRC Mike Davis NRC

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  1. PP/NRC EETIts SAFETY PNWETER DISPLAY SYSTEM ISOLATION DEVICE TESTING i

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PURPOSE TO RESOLVE TE NRC'S AlDIT OPEN ITEM CONCERNING TE ADEQUACY OF TE PVNGS DIGITAL SPDS ISOLATION DEVICES #0 PROVE THAT TE ISCLATION DEVICES WILL FULFILL TEIR INTEf0ED FUNCTION WEN MAXPtti GEDIBLE FAILT 00f0ITIONS ME APPLIED IN TK TRANSVERSE MODE.

R_ESULTS OF TK NRC ALDIT TW NRC ALDIT TEM CANNOT APPROVE TE USE OF TE PVNGS SPDS DUE TO TE RESULTS OF TE ANPP MAXPui GEDIBLE FALLT TESTING ON TE DIGITAL ISOLATORS.

TE AffP RESULTS SHOW THAT TE ISOLATION BARRIER CM BE BREACHED. TEEFORE, M ADEQUACY OF TE DIGITAL ISOLATORS ME IN QJESTION.

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KEY ISSUES ASSOCIATED WITH ISOLATOR OPEN ITEM 1.

Validity and possibility for additional Maximum Credible Fault (MCF) scenarios.

ANPP POSITION For the PVNGS SPDS application there are only 2 MCF's to be considered.

F1 = 120 Vac, 9.5a = Non-lE Output Signal Fault (Test conducted modeled 375 feet of signal cable - 13 ohms) i' F2 = 120Vac, 207a = Isolator Power Supply Fault 2.

Acceptance Criteria for MCF Testing.

ANPP POSITION Isolator barrier breach is acceptable as long as there is no significant impact upon the operation of a QUE circuit function to prevent it from meeting the minimum performance requirements as specified in the PVNGS design basis.

4 Consistent With:

GDC 24 R.G. 1.75, Revision 1 IEEE-279-1971 i

IEEE-384-1974 3.

Performance of additional testing resulting in maximum energy being induced on the lE side of the isolators.

ANPP POSITION Does not intend to perform additional testing beyond that required by:

(a)

NRC letter dated July 30, 1986 (b)

IEEE-279-1971 (c)

IEEE-384-1974 i

i The ANPP position is justified because the test results from:

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Open/Short Test (d)

MCF Test prove that the isolators used in the PVNGS SPDS application will prevent malfunctions that occur in the Non-1E SPDS from causing the associated lE systems from meeting the minimum performance requirements as specified in the PVNGS design basis.

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PVXGS SPDS ISOLATORS

1. Circuit Description
2. Maximum Credible Fault Determination
3. Testing Program
4. Test Results
5. Test Documentation
6. Systems Analysis
7. Conclusion l
8. Questions 1

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  • MCF Impressed on Non-l E Output Terminals
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1. Output within.S X of Sipal Range
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3. < 10 my Change of input Signal.
4. < 10 my Signal on input Terminals.
5. No visual board or axnponsat damage.

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  • Actual Maximum Voltage measured on isolator IE input terminals with MCF Voltage applied to the Non-lE Isolator terminals. (Output and Power Supply).

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_- A\\ A_YS S Purpose - To determine if Barrier Breach "Significantig" impacts the IE circuit causing " Unacceptable" influences in the IE circuit per R61.75 Rev 1.

1. Review Plant Drawings for actual circuit.
2. Determine Type ofinput signal.
3. Determine signal ranges / ratings.

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~ SYS- ? AJ_- AN A_YS S Purpose - To determine if Barrier Breach "Significantly" impacts the 1Ecircuit causing " Unacceptable" influences in the 1E circuit per RO 1.75 Rev 1.

1. Rouleau Plant Drawings for actual circuit.
  • 202 Otugs/ 347 Digital Points.
2. Determine Type ofinput signal.
3. Determine signal ranges / ratings.

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4. Determine Significant 1 E Circuit Impact.

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SYS~~Ev 2A J~ A\\ A_YS S Purpose - To determine if Barrier Breech "Significantly" impacts the 1Ecircuit caustng " Unacceptable" influences in the 1E circuit per RG 1.75 Rev 1.

1. Review Plant Drawings for actual circuit.
  • 202 Dwgs/ 347 Digital Points.
2. Determine Type ofinput signal.
  • All Digital signals are INDEPENDANT.

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3. Determine signal ranges / ratings.
4. Determine Significant 1E Circuit Impact.

19

\\ Simplified Circuit of Isolator Input 0.5 Amp Fuse (Q1E) U 48 VDC / Field ,I /Q Contact Mininum Contact .,5 y Rating 125 VAC 1 Amp 91k Ohms M Contact Normal Position Current t l Closed .322 ma Open 0 ma i ' per Isolator Circuit Maximum calculated current.522 x 160 circuits - 83.52 ma l l i 20

~ SYS- ? A _- As A_YS S Purpose - To determine if Barrier Breach "Significantly" impacts the IEcircuit causing " Unacceptable" influences in the 1E circuit per RG 1.75 Rev 1.

1. Review Plant Drawings for actual circuit.
  • 202 Dwgs/ 347 Digital Points.
2. Determine Type of input signal.
  • All Digital signals are INDEPENDANT.
3. Determine signal ranges / ratings.
  • Digital Field contact ratings enceed 120 u e 1 Amp I
4. Determine Significant I E Circuit Impact.

I l l ai

Internal Configuration of HP Optical Isolator 5 1 ghg IEINPUT V kV 2 k 4 Non-lE Output IS0t.ATION bINDAI BA MIER Common i 22

I Si'mplified Circuit of Isolator Input 0.5 Amp Fute (Q1B) O 48 VDC .) Field / Contact Q I Mi' linum contact 3V Rating 5V 125 VAC 1 Amp _. 91k Ohms W Current Contact Normal with MCF leakage Position Current = Closed .522 ma .533ma/.522 ma Open 0 ma O ma (

  • per Isolator Circuit Maximum cattulated current.522 x 160 circuits -

83.52 ma Maximum calculated current.533 x 160 circuits - 85.28 ma 1 23

Reg Guide 1.75 Revision 1 Excerpts ,l RequiredSeperation 'Seperation..maintainindependenceof circuit.so that the protective functions required any design basis event can be accomplished. Section C1 Isolation device " preventing malfunctions in one section of a circuit from causing unacceatable influences in othersectionsof othercircuits. Secuon 3.3 Barrier- % device interposed between Class 1E Equipment and a potentia 1 source of damage to limit damage to Class 1E Systems to an acceptable level. Section 3.8 Isolation Device " prevents malfunctionsin a circuit from causing unecceetable influences in other sections of other circuits. 24-

l'- IEEE 384 - 19[4 Excerpts Page A-7 Section 3 Definitions o Barrier "ADevice.interposedbetween 1EEquipment and a potential source of damage to limit damage to an acceptable level. 8 ~ IsolationDevice "aDevice whichprevents malfunctions in one section of a circuit from causing MD.B.GiWLlRbli. influences in other sections of the circuit. PG 17 Section 7.1.2 Isolation Devi - A deviceis considered to be a Power Circuit isolation device if.. the MCF voltage / current transient..will not degrade below an acceptable level the operation.. on the other side.? l l l l PG 18 Section 7.2.2.1 Isolation Device ".. isolation device..MCF voltage / current applied to..Non-1E side will not degrade the operation below an acceatable level. l 25

1 ~ IEEE 279 Excerpts Criteria Section 4.7.2-The. signals from Protection System equipment.shall be throughisolation devices 'No credible failure at the output.shall prevent the associated channel from meeting. minimum performance requirements spedfied in the design bases. Examples. Include shorts, opens, grounds and application of Maximum Credible AC or DC potential." 26

"~ SYS-- A _- A \\ A _YS S Purpose - To determine if Barrier Breach "Sigruficanuy" impacts the IEcircuit causing " Unacceptable" influences in the 1E circuit per RG 1.75 Rev 1.

1. Review Plant Drawings for actual circuit.
  • 202 Dwgs/ 347 Digital Points.
2. Determine Type of input signal.
  • All Digital signals are INDEPENDANT.

1

3. Determine signal ranges / ratings.
  • Digital Field contact ratings exceed 120 y e 1 Amp 1

i

4. Determine Significant 1E Circuit impact.

No Sl6NIFICANT impact on operation of Q1E circuit function-Degradation of component life or inadvertent operation. (IEEE-394) l l

2. 7

. - ~ _ - - - - -.

12/16/93 PVNGS UNIT 3 LICENSING STATUS LIST Enclosura 3L ITEM DUE FORCAST O TASK RE REFERENCE PRIOR TO COMPLETION

==- 1. Submit to the NRC the detailed technical description BJA

PP31864, 12/31/86

.C/31,6cr associated with relief request No. 1 of Accendi x B. This 02/05/85 Cogptrgr pg/rf/96 submittal concerns the PVNGS Unit 3 preservice examination SSER 1 program. (5.2.4.2 & 4'4Y~3$33~7 6.6.2) LCTS 034037 2. Det erm ine NRC close out status for Pressurized Thermal PGN SSER 9 01./15/87 12/31/86F Snock. PP33305. 08/30/85 3. Submit summary of ooerating experience of shift staffing. PGN SSER 9 0t/15/87 01/15/87F 4. Close out each of the following Supplement 1 to NUREG-0737 MAJ

PP23505, 0*./30/87 01/30/87F items prior to recient of Unit 3 0. L.

or submit schedular 04/14/83 (:;0 days extension requests to NRC for approval 30 days ortor to O.L. prior to Fuel Load) a) SPDS installed and ready for operation b) DCRDR HED Complet ion verification c) R. G.

1. 97 Instrumentation operability verification d) EOP's imolemented and operators trained e) ERF's complete and ready fl 5.

Submit summary of completion of pre-oo testing for RMS. JKR NRC 03/01/87 01/15/87F management (Fuel Load) {, meetinq 10/28/86 6. Submit a let ter to NRC not ing the differences between Units JKR IEIR 50-530/ 02/01/87 01/23/87F 1 and 3 for cable routing. 85-08-01 (30 days prior to Fuel Load) 7. Submit supolemental information on RCS Pressure-Temperature PGN NRC letter 12/31/86 12/31/86F T. S. 3/4.4.8 dated 11/13/86 8. Finalize and certify Unit 3 T/S JRP 03/01/87 03/01/87F (Fuel Load)

12/16/93 PVNGS UNIT 3 LICENSING STATUS LIST ITEM DUE FORCAST Q TASK RE REFERENCE PRIOR TO COMPLETION 9. Complete the following charging / auxiliary pressurizer spray BJA

PP33713, 83/01/87.

01/31/87F system modi ficat ions in accordance with the l ist ed schedule 10/15/85 (Fuel Load) for each and submit confirmatory letter to the NRC.

PP33905, 11/01/85
PP34174, 12/05/85 LCTS 834334,
035350, 035353 SSER 9,10 (Item #5) a) Modification to provide oower to valves CH-501 and CH-536 from a Class 1E MCC (IU3 fuel load).

b) Modification to provide for aut omat t e re-al i gnment of CH-501 and CH-536 on a Lo-Lo VCT level and LOP (U3 fuel load). c) Modification to enhance the VCT level instrumentation (U3 fuel load). Ij d) Lock open valves CH-532 and CH-524. In addition. remove power from valve CH-524 (U3 fuel load). I e) Modificationr to add vent piping to charging pump piping I to ensure that hydrogen will not be vented into a charging pump cubicle. (U3 fuel load). 10. Install Class 1E overvoltage protection isolation relays to BJA

PP31501, 03/01/87 01/31/87F the reia-1E control circuitry for valves CHE-PDY-239B and 12/18/84 (Fuel Load)

CHE-PDY-240B, and submit confirmatory letter to the NRC. SSER7(5.4.3) LCTS 833587 PP31832,. 12/07/84 11. Submit confirmatory letter to NRC on completion of RSP BJA SSER 5 (a) 03/01/87 01/30/87F modifications (Teold). MAJ (Fuel Load) 12. EQ differences. For PVNGS Unit 3, submit to the NRC a list BJA SSER 5 (pg 02/01/87 02/01/87F of all eq ui pment that is not ident ical to the Unit 1 B-12) '(30 days-equipment and/or is located in areas for which environmental ' prior to conditions are more severe than the demonstrated values for Fuel Load) Unit 1.

14/16/93 m PVNGS UNIT 3 LICENSING STATUS LIST ITEM DUE FORCAST C TASK RE REFERENCE PRIOR TO COMPLETION , _...F 13. Submit security p$an changes v.nich incorporate Unit 3. This DAL '91/01/87 12/19/86F submittal will be done 'in accordance with 10 CFR50.54(p). Also, NRC will perform audit once Unit 3 vital area is locked up. 14. Monitor status of possible ant i-t rust litigation oh part of JRP El Paso Electric. 15. Submit the Unit 3 initial Reactor Containment Building BJA

10CFR50, 12/12/E6 12/12/86F Interrated Leak Rate Test Summary Technical Report.

Appendix J 16. Submit letter to NRC certifying completion of PVNGS Unit 3 MAJ NRC letter iO2/13/87 02/13/87F as described in the safety analysis reports and reauest dated (2 weeks operating license as Unit 3 is now ready to load fuel. 2/24/83 . prior to ' fuel load) 17. Submit all approved FSAR changes to NRR. JKR 10CFR50.34 01/01/87 01/01/87F 18. Send letter to NRC listing all letters that submitted FSAR JKR N/A 03/01/87 02/15/87F and CESSAR changes (Letter of Letters) submitted after FSAR (Fuel Load) Amendment 16. 19. Submit to the NRC a response to the Unit 1 and 2 operational BJA EEVB verbal 12/31/86 12/31/86F concerns that were identified in the 10/28/86 meeting commitment bet ween NRR and ANPP. in 10/28/86 meeting with NRC. 23. Review T.M.I. item for Unit 3 Licensing with Region V SGB NUREG 0737 03/01/87 02/01/87F PM00186 21. Submit Construction Readiness Letter to Region V. PGN anticipated

02/01/87 02/01/87F Region V request 22.

Ensure installation of proximate pipe supports in Unit 3 SGB

PP31473, 03/01/87 01/15/87F prior to fuel load and confirm complet ton with Region V.

12/14/84}}

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