ML20053B884

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Reply to Governor Brown Motion Re Board Notification Transmitting PNO-V-82-09 & IE Info Notice 82-11.When Util Investigation Into Errors Identified in PNO Complete,Rept Will Be Included in Bimonthly Rept.W/Certificate of Svc
ML20053B884
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 05/25/1982
From: Crane P
PACIFIC GAS & ELECTRIC CO.
To:
References
NUDOCS 8206010314
Download: ML20053B884 (4)


Text

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 2

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In the Matter of

)

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PACIFIC GAS AND ELECTRIC COMPANY

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Docket Nos. 50-275

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50-323 (Diablo Canyon Nuclear Power Plant, )

Units 1 and 2)

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(Full Power Proceeding)

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REPLY OF PACIFIC GAS AND ELECTRIC COMPANY TO GCVERNOR BROWN'S MOTION RE BOARD NOTIFICATION PNO-5-82-09 AND I&E INFORMATION NOTICE 82-11 PGandE answers the above-captioned motion as follows:

1.

That portion of the motion concerning Board Notification PNO-5-82-09 is essentially a repeat of an earlier motion by Governor Brown dated March 18, 1982.

The Board ruling on that motion, which is equally applicable to the instant motion, was as follows:

"No final judgment will be taken in this matter until such time as a thorough evaluation can be made of any newly discovered, relevant information."

(Order dated April 2, 1982.)

PGandE's investigation into the errors identified in Board Notification PNO-5-82-09 is not yet complete.

When it is complete the results will be included in the next regular bi-monthly report submitted to the Commission and all parties as a part of the independent design verification program.

The second part of Governor Brown's motion refers to I&E Bulletin 82-11, a copy of which is enclosed as Attachment A.

The DO 82,060$ MC

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bulletin concerns potential inaccuracies in wide range pressure instruments used in Westinghouse designed plants.

At Diablo Canyon these instruments are located outside containmente and therefore are not subject to the environmental conditions which lead to the inaccuracies noted in the bulletin.

(See Attachment B.)

Respectfully submitted, MALCOLM H. FURBUSH PHILIP A. CRANE, JR.

RICHARD F. LOCKE Pacific Gas and Electric Company Post Office Box 7442 San Francisco, CA 94120 (415) 781-4211 ARTHUR C.

GEHR Snell & Wilmer 3100 Valley Center Phoenix, Arizona 85073 (602) 257-7288 BRUCE NORTON Norton, Burke, Berry & French, P.C.

3216 N. Third Street Suite 300 Phoenix, Arizona 85012 (602) 264-0033 Attorneys for Pac

  • Gas and E ctr'c Company

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Philip f. Crane J r'.

DATED:

May 25, 1982 1

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D SSINS No.:

6835 IN 82-11 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.

20555 April 9, 1982 IE INFORMATION NOTICE NO. 82-11:

POTENTIAL INACCURACIES IN WIDE RANGE PRESSURE INSTRUMENTS USED IN WESTINGHOUSE DESIGNED PLANTS Addressees:

All nuclear power reactor facilities holding an operating license or a construction permit.

(This information was transmitted by facsimile on April

9. 1982 to Westinghouse designed nuclear ~ power plants holding an operating license.)

Purpose:

This Information Notice is provided as an early notification of a potentially significant problem pertaining to wide range pressure instruments used in Westinghouse nuclear power plants.

It is expected that recipients will review the information for applicability to their facilities.

No specific action or response is required at this time.

Description of Circumstances:

By telephone calls on April 7 and 8, 1982, Westinghouse notified the NRC of information it had conveyed to its customers regarding the results of recent qualification tests in post-accident high energy line break environment on the wide range pressure instruments supplied by Westinghouse.

Westinghouse stated that when combining transmitter, signal conditioning and indicator allowances for errors due to calibration uncertainty, drift and environmental effects that the qualification tests indicated that the RCS wide range pressure channels exhibited ambiguities in their accuracy which could potentially result in inappropriate operator actions.

Westinghouse stated that post-accident accuracy ambiguities for RCS wide range pressure instruments under certain plant accident conditions have the potential for maximum accumulated inaccuracies of 2 363 psig actuation and 1 390 psig indication.

Accordingly, the inaccuracy of RCS wide range pressure measurements could lead to pressurizer power operated relief valves being lif ted prior to the termination of safety injection (SI) and to a greater number of valve challenges, thereby increasing the probability of a small break loss-of-coolant accident due to a valve failing to close.

Likewise, the inaccuracy of the wide range pressure instruments could lead to the i

termination of SI without adequate reactor coolant subcooling.

In addition, the inaccuracies could lead to premature or late tripping of the RCS pumps during the course of a small break loss-of-coolant accident.

s&2M64W ATTACHMENT A j.

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{y IN 82-11 April 9, 1982 Page 2 of 2 1

Westinghouse further stated that it is reviewing the design and operational bases for the wide range pressure instrumentation, that it will advise its customers of appropriate actions, and that continued safe plant operation has been demonstrated by prior analyses.

If you have any questions regarding this matter, please contact the Regional Administrator of the appropriate NRC Regional Office, or this office.

Sincerely, r

ordan, i rector ~

Divis of Engineering and Qua ity Assurance Office of Inspection and Enforcement

Attachment:

Recently Issued IE Information Notices t

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MECHANICAL AND NUCLEAR ENGINEERING FILE No.

140.110 RC LETTtm or gucatcr Potential Unreviewed Safety Question Ta Division or o.panment M&NE FILES April 7, 1982 MEMORANDUM TO FILE:

Mr. Lonnie Benson of Westinghouse called at 1:30 p.m.,

today.

Present in my office were Bob Streich of M&NE and Harry Isakari of Nuclear Projects.

Lonnie stated that the Westinghouse Safety Review Group had met and determined that a generic potential unreviewed safety question exists for plants with reactor coolant system wide range pressure transmitters located inside containment during a loss of coolant accident.

Upon investigating, we found that these transmitters at Diablo Canyon (PT-403 and PT-405) are located outside containment (PG&E Drawing 102036, Sheet 29G) and that the generic problem did f

not exist.

I called Bryant Giffin of Nuclear Plant Operations to relay this message at 2:00 p.m.

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ATTACHMENT B

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of

)

)

PACIFIC GAS AND ELECTRIC COMPANY

)

Docket No. 50-275

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Docket No. 50-323 Diablo Canyon Nuclear Power Plant,

)

Units 1 and 2

)

)

CERTIFICATE OF SERVICE The foregoing document (s) of Pacific Gas and Electric Company have been served today on the following by deposit in the United States mail, properly stamped and addressed:

Judge John F. Wolf Mrs. Sandra A.

Silver Chairman 1760 Alisal Street Atomic Safety and Licensing Board San Luis Obispo, CA 93401 U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Gordon Silver 1760 Alisal Street Judge Glenn O.

Bright San Luis Obispo, CA 93401 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission John Phillips, Esq.

Washington, DC 20555 Joel Reynolds, Esq.

Center for Law in the Public Interest Judge Jerry R.

Kline 10951 W.

Pico Boulevard - Suite 300 Atomic Safety and Licensing Board Los Angeles, CA 90064 U.

S. Nuclear Regulatory Commission Washington, DC 20555 David F. Fleischaker, Esq.

P. O. Box 1178 Mrs. Elizabeth Apfelberg Oklahoma City c/o Nancy Culver Oklahoma 73101 192 Luneta Drive San Luis Obispo, CA 93401 Arthur C. Gehr, Esq.

Snell & Wilmer Janice E.

Kerr, Esq.

3100 Valley Bank Center Public Utilities Commission Phoenix, AZ 85073 State of California 5246 State Building Bruce Norton, Esq.

350 McAllister Street Norton, Burke, Berry & French, P.C.

San Francisco, CA 94102 3216 N. Third Street Suite 300 Mrs. Raye Fleming Phoenix, AZ 85012-2699 1920 Mattie Road Shell Beach, CA 93449 Chairman Atomic Safety and Licensing Mr. Frederick Eissler Board Panel Scenic Shoreline Preservation U.

S. Nuclear Regulatory Commission Conference, Inc.

Washington, DC 20555 4623 More Mesa Drive Santa Monica, CA 93105

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Chairman Judge Thomas S. Moore Atomic Safety and Licensing Chairman Appeal Panel Atomic Safety and Licensing U. S. Nuclear Regulatory Commission Appeal Board Wnshington, DC 20555 U.

S. Nuclear Regulatory Commission Washington, DC 20555 Secretary U.

S. Nuclear Regulatory Commission Judge W. Reed Johnson Washington, DC 20555 Atomic Safety and Licensing Appeal Board Attn:

Docketing and Service Section U.

S. Nuclear Regulatory Commission Washington, DC 20555 Bradley W. Jones, Esq.

Office of Executive Legal Director Judge John H.

Buck BETH 042 Atomic Safety and Licensing U. S.

Nuclear Regulatory Commission Appeal Board Washington, DC 20555 U.

S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Richard B. Hubbard MHB Technical Associates 1723 Hamilton Avenue, Suite K San Jose, California 95125 Mr. Carl Neiberger Telegram Tribune P.

O.

Box 112 San Luis Obispo, California 93402 Herbert H.

Brown, Esq.

Lawrence Coe Lanpher, Esq.

Christopher B.

Hanback, Esq.

Kirkpatrick, Lockhart, Hill, Christopher & Phillips 1900 M Street N. W.

Washington, DC 20036 Byron S. Georgiou, Esq.

Legal Affairs Secretary Governor's Office State Capitol Sacramento, California 95814 i

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' ' Phi'If A. Crarfe, Jr.

Date:

May 25, 1982

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