ML20211F379

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Board Notification 83-14A:forwards PG&E 830225 Submittal Discussing Addl Info Re Apparent Deficiencies in Midland- Ross Superstrut Matl Used for Class 1E Cable Tray & Conduit Support.W/O Encl
ML20211F379
Person / Time
Site: Palo Verde, Diablo Canyon, 05000000
Issue date: 04/06/1983
From: Eisenhut D
Office of Nuclear Reactor Regulation
To: Ahearne, Gilinsky, Palladino
NRC COMMISSION (OCM)
Shared Package
ML20209B094 List: ... further results
References
TASK-AS, TASK-BN83-014, TASK-BN83-14 BN-83-014, BN-83-14, NUDOCS 8702250071
Download: ML20211F379 (1)


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NUCLEAM REGULATORY COMMIS$10N LICENSING IS u ms3:TATas RECEIVED 5

mas. avo.a.c.a AFA 6 33 APR 211983

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Docket Nos.: 50-275. 50-528 and 50-529. 50-530. 50-323 MEMORANDUM FOR: Chairman Palladino Comissioner Gilinsky Comissioner Ahearne Comissioner Roberts

  • Comissioner Asselstine

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Darrell G. Eisenhut. Director Division of Licensing Office of Nuclear Reactor Regulation e

SUBJECT:

INFORMATION ITEM - APPARENT DEFICIENCIES IN MIDLAND-ROSS

"$UPERSTRUT" MATERIAL USED FOR CLASS 1E CABLE TRAY AND CONDulT SUPPORT (Board Notification No. 83-1JA}

In accordance with present NRC procedures for Board Notifications, the enclosed information is being provided for your information. As stated in Board Notification No. 83-14 the Midland-Ross superstrut issue is limited to Diablo Canyon 1 & 2. Palo Verde 1. 2 and 3. Seabrook and WNP 1 and 4.

The enclosed Pacific Gas and Electric C3mpany's submittal dated February 25, 1983 discusses additional information on the "Superstrut" material used at the Diablo Canyon Nuclear Power plants. We will promptly notify you of anyadditionalinformationthatmaygdevelopedonthismatter.

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-Darrel G.bsenhut.D Division of Licensing Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: See next page 4-21-83:

Diablo Distribution F. A. Crane:2768:n1

Contact:

Darrell G.'Eisenhut. ONRR x27672 NPG LICENSING r

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UNITED STATES

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APR 111983 Docket No.:

50-275 MEMORANDUM FOR:

George W. Knighton, Chief Licensing Branch No. 3 Division of Licensing FROM:

Annette Vietti, Project Manager Licensing Branch No. 3 Division of Licensing

SUBJECT:

FORTHCOMING MEETING WITH PACIFIC GAS & ELECTRIC COMPANY (PG&E)-DIABLOCANYONCOMPONENTCOOLINGWATERSYSTEM DATE & TIME:

April 19,1983 9:00 am LOCATION:

Diablo Canyon Project Offices 45 Freemont

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2nd Floor, Room E San Francisco, California PURPOSE:

To discuss areas of review for the component cooling water system.

PARTICIPANTS:

NRC A. Vietti, J. Wermiel, O. Parr PG&E J. Hoch, et al.

( d, h., A Annette Vietti, Project Manager Licensing Branch No. 3 Division of Licensing cc:

See next page 1

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Diablo Canyon Philip A. Crane, Jr., Esq.

Pacific Gas & Electric Company Post Office Dox 7442 San Francisco, California 94120 Resident Inspector /Diablo Canyon NPS ce et e

al Counsel Pacific Gas & Electric Company c/o U. S. Nuclear Regulatory Commissi(-

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Ca ornia 94120 ac California 93424 Janice E. Kerr, Esq.

Ms. Raye Fleming California Public Utilities Connission 1920 Mattie Road 350 McAllister Street Shell Beach, California 93440 San Francisco, California 94102 Joel Reynolds, Esq.

Mr. Frederick Eissler, President John R. Phillips, Esq.

Scenic Shoreline Preservation Center for Law in the Public Interest Conference, Inc.

10951 West Pico Boulevard 4623 More Mesa Drive Third Floor Santa Barbara, California 93105 Los Angeles, Californi r 90064 Ms. Elizabeth Apfelberg Paul C. Valentine, Esq.

1415 Cozadero 321 Lytton Avenue San Luis Obispo, CA 93401 Palo Alto, California 94302 Mr. Gordon A. Silver Mr. Byron 5. Georgiou Ms. Sandra A. Silver.

Legal Affairs Secretary 1760 Alisal Street Governor's Office San Luis Obispo, CA 93401 State Capitol Sacramento, California 95814 Harry M. Willis, Esq.

Seymour & Willis Herbert H. Brown Esq.

601 California Street, Suite 2100 Hill, Christopher & Phillips, P.C.

San Francisco, CA 94108 1900 M Street, N.W.

Washington, D. C.

20036 Mr. Richard Hubbard MHB Technical Associates Mr. Dick Blankenburg Suite K Editor & Co-Publisher 1725 Hamilton Avenue South County Publishing Company San Jose, CA 96125 P. O. Box 460 Arroyo Grande, California 93420 Mr. John Marrs, Managing Editor San Luis Obispo County Telegram Tribune Mr. James 0. Schuyler 1321 Johnson Avenue Vice President - Nuclear Generation P. 0. Box 112 Department San Luis Obispo, CA 93406 Pacific Gas & Electric Company P. O. Box 7442 San Francisco, California 94120

y Diablo Canyon Chilio A. Crane, Jr., Esc.

  • Bruce Norton, Esq.

Suite 202

-3216 North 3rd Street Phoenix, Arizona 85012 Mr. W. C. Gangloff Westinghouse Electric Corporation P. O. Box 355 Pittsburg, Pennsylvania 15230 David F. Fleischaker Esq.

P. O. Box 1178 Oklahoma City, Oklahoma 73101 * '

Arthur C. Gehr. Esq.

Snell & Wilmer i

3100 Valley Center Phoenix, Arizona 85073 Mr. Owen H. Davis, Director Federal Agency Relations Pacific Gas and Electric Company 105017th Street, N.W.

Suite 1180 Washington, D. C.

20036 Regional Administrator - Region V U.S. Nuclear Regulatory Commission 6

1450 Maria Lane Suite 210 Walnut Creek, California 94596 Dr. Jose Roesset 3506 Ouval Road Austin, Texas 78759 m

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DISTRIBUTION Document Control 50-275 APR 101953 PRC System LB#3 Reading GKnighton docket 'to.:

50-275 i'E"0 rah 00!i F0P.:

Pat Sullivan, Chief Administrative Pranch Office of the Secretary F.W:

nons Scnierlina, Project t!anager Licensing 3ranen No. J Division of Licensing SUNCCT:

REQUEST TRANSCRIPT OF FEETING TO EE HELD APRIL 19, l'3Cf3 - DIAul0 CAtJYCli In.iccornance with a telephone reouest by Jean Lee, this is to request arrannenents for a reporter to precare a transcript of the r'eeting to be heln on April 1!.',19dJ, in San Francisco, California with Pacific Gas J Elactric Cccoany ant! Brookhaven flational Laboratory regarding Diablo Canyon riuclear Power 6'lant, Uni +.1 (see the attached neeting notice for details of the neeting). He rem the transcript within two days following the meetinq f.o tnat we can nake copies for our internal.use as'well as for the parties to this croccettino. tie anticip4te attencante of anoroxinately 20 occule. Please contact

.e (x27236) or Jean Lee (x28413) if you need acditional in+cr*vtir.n.

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IlJ!lt.'Odi'i1 hans Schierline, Project *!,enarjer Licensine Branch.40. 3 Division of Licensint:

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APR 15 E83 MEMORANDUM FOR:

Chainnan Palladino

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Coamissioner Gilinsky Consissioner Ahaarne Cosaissioner Roberts

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Consissioner Asselstine

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FROM:

William J. Dircks Executive Director for Operations

SUBJECT:

STATUS OF DIABLO CANYON DESIGN VERIFICATION EFFORT O

Per your request, enclosed is a sur: mary of the status of the Diablo Canyon design verification efforts by PG&E, the IDVP and the staff.

The PG&E analysis of the containment annulus structure and necessary modifications to the structure remain as critical elements in the schedule for fuel load authorization as evidenced by a recent slip in schedule.

In addition, the review of the PG&E corrective actions by the IDVP and the issuance of final reports could lead to additional delays.

(S!pedWitsaml.Dhtkt William ?. Dircks Executive Director for Operations

Enclosures:

As stated cc:

SECY OPE OGE e

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H. Schierling NRR xt. 27100 s

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tusvuxou Diablo Canyor Design Verification Program Status Report - March 31, 1983 I.

PG&E Effort The PG&E Phase I seismic design verification effort of safety-related structures and equipment is progressing. Submittal 10 to the PGAE Phase I Final Report was issued on March 15, 1983. The report addresses the 9

criteria and methodology used in the PGAE design verification. The results will be included in a final submittal.

The report is under review by the IOVP and by the staff.

The PG&E Semi-monthly Report of March 25,1983 provides a status of the analyses and modifications of safety-related structures and equipment with respect to the requirements for Step 1.

For most areas 80% of the analyses have been completed. The major exception is the containment annulus steel structure.

Horizontal response spectra of the structure have not been finalized and acceleration response spectra for analysis of piping and

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equipment are being generated.

The containment annulus structure was the subject of meetings by PG&E and the IDVP (Fe5FuiFy 23-24 and March 20-30) which were attended by NRC staff.

The containment annulus structure modifications are estimated to be about 10 percent completed.

.. - s Pipe support modifications are about 50 percent complete and modifications in the turbine building have not started. We estimate that the overall status of completion of all Step 1 required modifications is about 50 percent.

On March 11, 1983.PG&E submitted the Phase !! Status Report in accordance with the Step 1 requirements and schedule.

The report is under review by the staff. The PG&E, efforts include responses to E0!'s identified Qg._.

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by the IDVP (in progress), responses in five areas for additional verification (in progress - see under IDVP), audit of construction quality assurance (completed) and resolution of open items identified by PG4E.

The resoldtion of the following four items is in progress:

rating of 125 V DC Switch gear shared electrical power supply for HVAC of control room component cooling water system design

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heat loads and HVAC capacity for switch gear areas.

PG&E and the IDVP have met to discuss the Phase II E0!'s identified by the IDVP, in particular those that relate to the need for additional verification (seeunderIDVP).

II.

IDVP Effort l

The following E0I (error or open item) information for Phase I and Phase II is based on the IDVP Semi-monthly Report of March 25, 1983.

Also listed, in parentheses for comparison, is the information from our previous status report.

Construction l

Phase I Phase II QA Total 201 (194)

72 (70)"

  • 29(29)

Errors 15 (17) 7(22) l Non Errors 186(177) 65(48) 29(29)

Resolution Resolved by IDVP 101(164) 53 (3) 29(18)

Evaluation Continuing 20 (30) 19(67)

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. The total E0!'s for Phase I and Phase II increased by 7 and 2, respectively.

The decrease in E0I errors, in particular for Phase II, is due to " downgrading" as a result of further evhluation.

It is also noted that about three quarters of Phase II E0I's are new closed, compared to less than 10 percent in the previous report.

The IDVP has essentially completed its review of the initial sample and has issued Interim Technical Reports on the various subjects. A complete list of ITR's is attached.

The major effort of the IDVP with respect to Phase I is the review of the ongoing PG&E design verification effort of safety-related structures and equipment.

The IDVP has requested and received from PGAE detailed information (criteria, procedures,workpackages)whichisnowunderreview.

With respect to Phase II the IDVP review of the three initial sample systems has been completed (auxiliary feedwater system, 4160 V safety-related electrical system, and control room ventilation and pressurization system).

ITR's have been issued and are under staff review.

The following five areas have been identified for additional verification:

1.

redundancy of equipment in shared systems J

2.

selection of system design pressure and temperature 3.

environmental consequences of high energy line breaks outside containment 4.

jet impingment analysis inside containment 5.

circuit separation s

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ITR's have been issued for these subject and the resolution is being pursued by the IDVP.

Revisions to the ITR's are expected to be issued.

In the March 25 semi-monthly report the IDVP informed us that the Phase I l

and Phase II IDVP Status reports will be combined and issued on April 15 J l

instead of April 8.

In addition a major slip from April 1 to May 20 hac been projected for the issuance of the IDVP Final Reports on the Hosgri

.g and Non-Hosgri spectra.

111.

Staff Effort The staff effort at this time is focused on review and evaluation of the following documents:

Interim Technical Reports issued by the IDVP, PG&E Phase I Final Report Supplements and PG4E Phase II Status Report. The Staff has been attending meetings between PGAE and the IDVP at which the various

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issues are discussed (The Joint Interv'enors and the State of California are

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advised of such meetings and have been attending them selectively).

The staff review is preliminary because the information is subject to change ~.

The major effort toward preparation of a Safety Evaluation Report in sdpport "I

of a staff recossendation regarding fuel load authorization (Step 1) cannot be completed until the appropriate reports have been submitted in their' final fom.

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The st'idias at BNL are nearing completion.

To expedite the reporting we

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requested BNLto inform us by letter of their findings as soon as possibie and i

to prepare a more detailed report at a later date.

BNL has provided to

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Teledyne detailed infomation on their inalyses.

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'q The st'ff evaluation of the component cooling water system is continuing.

a We:are awaiting additional information from PG&E to, complete the effort.

- (This effort is in response to all allegatimis made in early January.)

7-The PG&E schedule for completion of items necessary to permit reinstatement of the suspended low power license (Step 1 and Step 2 in Phase I) and for issuance of a full power license (Step 3) has slipped. The principal

$I reasons for the delay are additional structural analyses, additional modifications in the containment annulus structure and lower than expected production rates at the plant.

The projected PG&E dates are as follows:

New Date Previous Date (PG&Eltr 03/02/83)

(PG&Eltr12/2/82)

NRC decision PG&E action NRC decision Step 1 - fuel load and cold system testing 06/30/83 06/30/83 03/31/83 Step 2 - criticality and low power

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operation 07/15/83 08/15/83 05/15/83

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Step 3 - issuance of full power license 08/15/83 09/30/83 06/30/83

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The new dates for Step 2 and Step 3 include adequate lead time for the necessaryNRCdecisionpriortothestart'oflhePG&E'a'ctionforthese j

steps.

However, PG&E advised the staff that there are only a few days, if any, between the NRC decision date for Step 1 and the PG&E readiness to commence the fuel loading.

Therefore, either an earlier NRC decision would be required or PG&E fuel loading would be delayed.

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.. i Based on our attendance at the meetings between PG&E and the'IDVP and on the status as described in the PG&E and IDVP semi-monthly reports, we

.n conclude that the following activities coul'd impact the current schedule:

(1) continuing analysis of containment annulus structure; (2) modification in the annulus, turbine building and pipe supports; (3) review by'the IDVP of the PG&E corrective actions; and.(4) issuance of the necessary reports.

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INTERD* TECH' ' CAL REPORTS (ITd) iTR -

1 Additional Verification and Additional Sampling, Rev. O, RLCA, June 6, 1982 Additional Verification and Additional Sampling, Rev. 1, RLCA, October 22, 1982 ITR - 2 Evaluation of Quality Assurance Program and Implementation Review, Rev. O, TES, June 23, 1982 ITR - 3 Tanks Rev. O, RLCA, July 16; 1982

!TR - 4 Shake Table Testing Rev. O, RLCA, July 23, 1982 ITR - 5 Design Chain Rev. O, RLCA, August 19, 1982 ITR - 6 Auxiliary Building Rev. O, RLCA, September 10, 1982 ITR - 7 Electrical Raceway Supports Rev. O, RLCA, September 17, 1982 ITR - 8 Verification Program for PG&E Corrective Action Rev. O. RLCA, October 5,1982

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ITR - 9 Development of the Service Related Contractor List For Non-Seismic Design Work Performed for DCNPP-1 Prior to June 1978 - Phase II Rev. O, R. F. Reedy, October 15, 1982

.s ITR - 10 Verification of Design Analysis Hosgri Spectra Rev. O, RLCA, October 29, 1982 ITR - 11 Pacific Gas & Electric / Westinghouse Seismic In erface Review Rev. O, TES, November 2, 1982 ITR - 12

Piping, Rev. O, RLCA, November 5,1982 ITR - 13 Soils - Intake Structure Rev. O, RLCA, November 5,1982 k

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crificati:n of the Temperature, Pi essure, Humidity and Submergence Environments Used for Safety-Rel EquipT. ant Specification Outside Containment for,ated Auxiliaty Feed. tater Systen and Control Room Ventilation and Pressuirzation System Rev.-0, SWEC,, December 6, 1982

'ITR 15 HVAC Duct and Supports Report Rev. O RLCA, December 10, 1982 1 R - 16 Soils - Outdoor Water Storage Tanks Rev. O, RLCA, December 8, 1982 ITR - 17 Piping - Additional Samples Rev. O, RLCA, December, 14, 1982 ITR - 18 Verification of the Fire Protection Provided for Auxiliary Feedwater Systems. Control Room Ventilation and Pressurization System, Safety-Related Portion of the 4160 V Electric System Rev. O, SWEC, December 13, 1982 ITR - 19 Verification of the -Post-LOCA Portion of the Radiation Environments Used For Safety Related Equipment Specification Outside Containment for Auxiliary Feedwater System and Control Room Ventilation and Pressurization System Rev. O, SWEC, December 16, 1982 ITR - 20 Verification of the Mechanical / Nuclear Design of the Cncrol Room Ventilation and Pressurization System Rev. O, SWEC5 December 16, 1982 ITR - 21 Verification of the Effects of High Energy Line Cracks and Moderate Energy Line Breaks for Auxiliary Feedwater System and Gontrol Room Ventilation and Pressurization System-Rev. 0, SWEC, December 15, 1982 ITR - 22 Verification of Mechanical / Nuclear Portion of the Auxiliary Feedwater System Rev, 0, SUEC, December 17, 1982 ITR - 23 Verification of High Energy Line Break and Internally Generated Missile Review - Outside Containment for Auxiliary Feedwater System and Control. D.oom Ventilation and Pressurization System Rev. O, SWEC, December 20, 1982

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,ITR - 24 Verification of the 4160 V Safety Related Electrical Distribution System Rev. O, SWEC, December 21, 1982 ITR - 25 Verification of the Auxiliary Feedwater System Electrical Design Rev. O, SWEC, December 21, 1932 ITR - 26 Verification of the Control Room Ventilation and Pressurization System Electrical Design Rev. O, SWEC, December 21, 1982 ITR - 27 Verification of the Instrument and Control Design of the Auxiliary Feedwater System Rev. O, SWEC, December 23, 1982 ITR - 2S Verification of the Instrument and Control Design of the Control Room Ventilation and Pressurization System Rev. O, SWEC, December 23, 1982 ITR - 29 Design Chain - Initial Sample Rev. O, SWEC, January 17, 1983 ITR - 30 small Bore Piping Report Rev. O, RLCA, January 12, 1983 ITR - 31 HVAC Components Rev. O, RLCA, January 14, 1983

.ITR - 34 Verification of Diablo Canyon Project Effo'rts by Stone & Webster Engineering Corporati.on Rev. O, SWEC, February 4, 1983 ITR - 35 Not issued

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ITR - 36 Final Report on Construction Quality Assurance Evaluation of Guy F. Atkinson Company Rev. O, SWEC, February 25, 1983.

ITR - 37 Valves Rev. O, RLCA, February 23, 1983 ITR - 38 Status Report on Construction Quality Assurance Evaluation of Wismer & Beck.er Rev. O, SWEC, tiarch 1,1983 ITR - 38 Final Repo'rt on Construction Quality Assurance Evaluation of Wismer & Becker Rev. 1, SWEC,tlarch 16, 1983

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ITR - 39 Soils - Intake Structure Bearing Capacity and Lateral Earth Pressure Rev. O, RLCA, February 25, 1983 ITR - 40 Soils Report'- Intake Structure Sliding Resistance

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Rev. 0, RLCA March 9,1983 t.

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GREEN TICKET NO. 12155 DISTRIBUTION *w/ incoming Document Control (50-275/323)*

NRC PDR*

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PRC System

  • LBf3 Reading GWKnightop glemmer D. Eisenhut/R. Purple J. L. Jordan, IE J. M. Taylor, IE Attorney, OELD T. Novak/M. Stine M. Bridgers, EDO (ED0#12155)

Correspondence Clerk, NRR (ED0#12155)

SECY (3)

OCA (3)

W. Dircks T. Rehm Stello DeYoung Engelken, Region V Cunninghan, ELD R. Mattson R. Vollmer H. Thompson Grace Snyder

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