ML20148C374

Summarizes 781020 Meeting Re Seismic Qualification of Electrical Equipment.Open Items Include,Instrumentation & Control Sys.Branch Review of NSSS Scope of Equipment in Westinghouse Qualification Program Encl

ML20148C374
Person / Time
Site:	Diablo Canyon
Issue date:	10/25/1978
From:	Allison D Office of Nuclear Reactor Regulation
To:	Morrissey J PACIFIC GAS & ELECTRIC CO.
References
NUDOCS 7811020029
Download: ML20148C374 (9)

Text

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[pa rtogb o UNITED STATES

!vjp'" ' ,% NUCLEAn REGULATORY COMMisslON

. WASHINGTON, D. C. 20555 KRC kb

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• [/ OCT 2 51973 Docket Nos: 50-275 & 50-323 APPLICANT: Pacific Gas & Electric Company (PG&E)

FACILITY: Diablo Canyon Nuclear Power Station, Units 1 & 2 (Diablo Canyon) '

SUMMARY

OF MEETING HELD ON OCTOBER 20, 1978 TO DISCUSS SEISMIC QUALIFICATION DIABLO CANYON 0F ELECTRICAL EQUIPMENT ,

He met with the applicant on October 20, 1978 in Bethesda Maryland to discuss seismic qualification of electrical equipment. A list of attendees is provided in Enclosure No.1.

PG&E was performing a seismic reevaluation of the Diablo Canyon plant to determine what modifications were necessary to upgrade the plant's seismic resistance. As part of this program, numerous items of balance-of-plant scope electrical equipment had been retested at Wyle Laboratories to simulate the newer and more severe seismic design basis.

The purpose of this meeting was to discuss our review of the test results for this equipment. The discussions concerned our review of l electrical aspects of the testing - how the equipment performance was nonitored during the testing to demonstrate that the reauired safety functions would be accomplished. Our review of the mechanical aspects of the testing, which involves primarily the type and severity of shaking, was not discussed.

The results of the discussions are summari::ed in Enclosure No. 2. Of the 23 items discussed,15 were resolved or the specific actions to obtain resolution were identified. The others remained to be resolved.

In addition to the discussion of balance-of-plant scope equipment we provided several questions regarding equipment within the scope of the nuclear steam supply system. These questions are described in Enclosure No. 3.

We also discussed a proposal to remove electrical power from certain valves.

PG&E had proposed, in a letter dated October 10, 1978, to remove electrical power from two residual heat removal system suction line valves. These 7 8 1 1 0 2 0 0 fl 9

Mr. Joh'n C. Morrissey .

were valves 8701 and 8702 in the residual heat removal system suction line from the reactor coolant system. Electrical power would be removed by opening manual circuit breakers. -

The proposal had arisen from the fire protection review and its purpose was to preclude the possibility that a fire in the area of the valve's electrical cables could cause both valves to open, overpressurizing the .

residual heat removal system with full reactor coolant system pressure.

We indicated that removing the power in this manner would be acceptable. ,

However, redundant indication of both valves positions would be required to be available in the control room after removing the power. PG&E indicated that it would install such indication or, alternately, provide an acceptable fire protection provisions to preclude the possibility of a fire opening the valves. If acceptable fire protection provisions were made, removal of power would not be necessary.

$b Igrm D. P. Allison, Project Manager Light Water Reactors Branch No. 1 Division of Project Management

Enclosures:

As stated cc:

See next page *

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Mr. John C. Morrissey OCT 2 51978 Mr. John C. Morrissey Mr. John Marrs Vice President & General Counsel Managing Editor Pacific Gas & Electric Company San Luis Obisoo County 77 Beale Street Telegram - Tribune San Francisco, California 94106 1321 Johnson Avenue P. O. Box 112 cc: Philip A. Crane, Jr. , Esq. San Luis Obispo, California 93406 Pacific Gas & Electric Company 77 Beale Street Elizabeth S. Bowers, Esq.,

San Francisco, California 94106 Chairman Atomic Safety & Licensing Janice E. Kerr, Esq. Board California Public Utilities Commission U. S. Nuclear Regulatory 350 McAllister Street Conmission San Francisco, California 94102 Washington, D. C. 20555 Mr. Frederick Eissler, President Mr. Glenn 0. Bright Scenic Shoreline Preservation Atomic Safety & Licensing Conference, Inc. Board 4623 More Mesa Drive U. S. Nuclear Regulatory Santa Barbara, California 93105 Commission Washington, D. C. 20555 Ms. Elizabeth E. Apfelberg 1415 Cazadero Tolbert Young San Luis Obispo, California 93401 P. O. Box 219 Avila Beach, California 93424 Ms. Sandra A. Silver 1792 Conejo Avenue Richard S. Salzman, Esq.,

San Luis Obispo, California 93401 Chairman Atomic Safety & Licensing Mr. Gordon A. Silver Appeal Board 1792 Conejo Avenue U. S. Nuclear Regulatory San Luis Obispo, California 93401 Commission Washington, D. C. 20555 Paul C. Valentine, Esq.

321 Lytton Avenue Dr. W. Reed Johnson Palo Alto, California 94302 Atomic Safety & Licensing Appeal Board Yale 1. Jones, Esq. U. S. Nuclear Regulatory 19th Floor Commission 100 Van Ness Avenue Washington, D. C. 20555 San Francisco, California 94102 Alan S. Rosenthal, Esq.

Mr. Richard Hubbard Atomic Safety & Licensing MHB Technical Associates Appeal Board 366 California Avenue U. S. Nuclear Regulatory Palo Alto, California 94306 Commission Washington, D. C. 20555

Mr. John C. Morrissey OCT 2 51978 cc: Ms. Raye Fleming 1746 Chorro Street San Luis Obispo, California 93401 Brent Rushforth, Esq.

Center for Law in the Public Interest .

10203 Santa Monica Boulevard Los Angeles, California 90067 Arthur C. Gehr, Esq. ."

Snell & Wilmer 3100 Valley' Center Phoenix, Ar; zona 85073 Mr. James 0. Schuyler, Project '

. Engineer Pacific Gas & Electric Company  ;

77 Beale Street -

San Francisco, California 94106

• Bruce Norton, Esq.

3216 North 3rd Street Suite 202 Phoenix, Arizona 85012 Mr. W. C. Gangloff Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230 t r

Michael R. Klein, Esq.

Wilmer, Cutler & Pickering 1666 K Street, N. W.

Washington, D. C. 20006

' David F. Fleischaker, Esq.

1025 15th Street, N. W.

5th Floor Washington, D. C. 20005 Dr. William E. Martin Senior Ecologist Battelle Memorial Institute Coluatus, Ohio 43201

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l ENCLOSURE NO. 1 LIST OF ATTENDEES J MEETING WITH PG&E ON OCTOBER 20, 1978 NRC STAFF l J. F. Stolz F. Rosa ,

J. Knox i D. P. Allison P_G&E t J. Hoch

• J. Herbst t

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ENCLOSURE NO. 2 RESULTS OF DISCUSSION OF BALANCE OF PLANT EOUIPMENT DIABLO CANYON MEETING OCTOBER 20, 1978 The items below pe 1e Power Systems Branch review of equip-ment that was rete- av Laboratories.

The first 15 items - -

specific options to obtain '

resolution were id. .iing items were not resolved.

1. Battery - Accepta: . satisfactory performance on discharge capacity test. Th vo be performed after returning the battery

' cells to the ple . to document that voltage was monitored during testing.

2. Battery Charger - Acceptaole subject te enother retest with monitoring of charger voltage and charging current during shaking.

3. 125 Volt DC Distribution Panel - Acceptable subject to: .

(1) Retest of molded case circuit breakers to confirm that they do not chatter during shaking (2) confirmation that the white indicating ' light was monitored during shaking indicating no loss of power

4. 125/250 Volt Motor Control Centers - Acceptable subject to another -

retest of a starting resistance contactor and a main line contactor to confirm that they do not chatter during shaking

5. Local Starters - Acceptable subject to:

(1) For the two speed fan starter on page 283 of the Wiley test report:

(a) Confirmation that the auxiliary contacts were monitored end did not chatter during shaking, or (b) Submittal of an acceptable justification that the main contacts could not have chattered during shaking, or (c) Submittal of the results of an analysis demonstrating that contact chatter would have no effect on the performance of the starter or the function of other safety loads, or l

l (d) Antoher retest demonstrating that contact chatter does not occur during shaking.

(2) Revision of the text of the FSAR description and the Wiley test' report to eliminate conflicts.

6. Main Control Board Components - Acceptable subject to confirmation that Westinghouse VX252 indicator was within specification on cali-bration test after shaking.

7. Ventilation Control Logic Acceptable, PG&E to revise description of safety function during shaking.

8. Ventilation Relay Panel - Acceptable. PG&E to revise description of safety function during shaking

9. Annunciator - Acceptable t

10. Big Beam Lights - Acceptable

11. Namco Limit Svitches - Acceptable  ;

12. Fischer Controllers - Acceptable

13. Steam Dump Valve Controller - PG&E will rely upon qualified switches and qualified solenoid valves rather than controller. Acceptable

14. 4KV Switchgear Potential Transformer - Reviewed and acceptable unless rereveiw during SER preparation discloses an unknown problem.

15. Diesel Generator Excitation Cubicle - Acceptable. PG&E to document monitoring of exciter output current. PG&E to document that chattering Westinghouse SG relay has no safety function. PG&E to modify door latch to prevent door from flying open.  !

16. Diesel Generator Control Cabinet Door and Subpanel - PG&E to evaluate I and verify that the devices monitored represent all safety functions. >;

Also, PG&E to retest relays to verify they can change state during shaking.

17. 4KV Switchgear - Rationalefor monitoring auxiliary contacts rather than main contacts of large circuit breakers acceptable. Additional information provided for review in response to previous question . l

18. Safeguard Relay Board - PG&E providec' list of devices monitored during testing for review.

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19. -Vital Load Center, Reversing Starters - Some confusion as to what ,

was monitored and what to; results were. PG&E to clarify later.

- Also, PG&E provided further information on relay panel for review

20. Fan Cooler Motor Controllers - PG&E to address chatter in SAR description.

21. Vital Auxiliary Relay Panel - PG&E to address chatter in FSAR description , ,

22. Fire Pump Controller - Not yet reviewed. PG&E has provided revised description by telecopy within past week, .

23. Valve Actuators With Gear Mounted Limit Switches - PG&E to submit FSAR description (as has been done previously.for actuators with stem mounted limit switches) ,

With regard to motor starters PG&E discussed a proposed rationale to '

eliminate the requirement for monitoring main contacts for some starters.

We agreed to consider it when specifics such as contactor types involved +

are identified by PG&E and the rationale is submitted.

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ENCLOSURE NO. 3 1 QUESTIONS ABOUT NSSS SCOPE EQUIPMENT DIABLO CANYON MEETING l l

OCTOBER 20, 1978 i

The items below pertain to the Instrumentation and Control Systems Branch review of NSSS scope equipment within the Westinghouse generic requalifica-tion program.

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1. From Amendments 68 and 69 (a) .Pages 10-27, 10-28,10-288, and 10-29 discuss equipment but do not identify model numbers or specific test reports (b) For Rosemont transmitters the exact type was not established to be identical to the equipment used for North Anna Unit 1.

The test results do not appear to have been submitted on the Diablo Canyon docket. Additional testing similar to that done by VEPC0 for North Anna Unit 1 (which is beyond the generic testing) would be required. This information could probably be acquired from VEPC0 or, perhaps, handled by reference to the North Anna docket.

2. From responses to 10 draft questions (a) Information promised in response to Q5A has not yet been provided (b) The staff has not received qualification information for Sostman 11901B resistance temperature detectors.  ;

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