ML20054C819
| ML20054C819 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon |
| Issue date: | 11/10/1981 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Scheigert J ENVIRONMENTAL LAW CENTER OF THE PACIFIC |
| References | |
| FOIA-81-406 NUDOCS 8204210723 | |
| Download: ML20054C819 (1) | |
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NUCLEAR REGULATORY COMMISSION c
WASHINGTON, D. C. 205S5 M et @# p[,_
s November 10, 1981
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OI Mr. Jack F. Scheigert
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Environmental Law Center of the Pacific
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250 South Hotel Street, 2nd Floor Auditorium IN RESPONSE REF Honolulu, HI 76813 TO F0IA-81-406
Dear Mr. Scheigert:
This is in additional respon.se to your letter dated October 2,1981 in which you requested, pursuant to the Freedom of Information Act, information regarding the precautions taken to " earthquake proof" the Diablo Canyon Nuclear Power Plant in California.
The two documents, listed below, were recently discovered by NRC staff members.
1.
September 28, 1981 Letter to NRC Region V from Philip Grove, PG&E.
2.
September 30, 1981 Letter to NRC Region V from Philip Grove, PG&E.
A copy of these documents are enclosed.
Sin r i
l J. M. Felton, Director Division of Rules and Records Office of Administration
Enclosures:
As stated 8204210723 811110 PDR FOIA SCHEIGE81-406 PDR
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250 South Hotel Street 2nd floor Auditorium Honolulu Hawaii 96813 October 2, 1981 FOIA REQUEST IREEDOM OF INFORM Nunzio J.
Palladino, Chairman Nuclear Regulatory Commission
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[DM -[/-MCh Washington, D.C.
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Re:
FREEDOM OF INFORMATION REQUEST
Dear Chairman Palladino:
In the Honolulu Star Bulletin a recent set of articles occured and out of " coincidence" they relate and point to the grave dangers of the Diablo Canyon Power Plant in California. Please explain what kind of error in design was overlooked at the Diablo plant (see enclosure).
I would be interested in knowing what precautions have been taken to " earthquake proof" the Diablo Canyon plant, in view of the fact that it is located in an area prone to earthquakes.
I look forward to your response.
Regards t
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Schit:.tgert Jack JFS:vs Enclosure j
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IN BRIEF M AM MOTTI LAKES. Cahl.t APD -
Twe earthquakes registenng 5 a and. back couairy areas wer. being.?' Paust.No Lajuries were reported. t>ut Forest Servic SGard=*r=='d i
' 5.5 on the fttchter scale triggered l
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checked by behcopter as soon as "We'had sonie pretty bi power blackouts and rockshdes ' daybght arrived several hours after-slides la Convict Canyon."g 'roeg.
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mo Paustf But there was no darsage reported early today and knocked boules off the (trst temWor at 4:53 a.m. Some[.asaid. "Right now there is just an to.* st the Crowley La ke Dam. Paa.si supermarket shelves across a wide. res6 dents sand it jotted them awake.
cred1We' amount of dust coming out. said.
area of the lingh Sterra.. authertties
.w, "It sure rattled us,l'u ten you. la $; of canyan. A local resklens says The earthemebes were fait op f ar sa id.
a waterbed it gets you moving.". there's more dust than with se s away as Sacramente, abouL,Jac An earthquake of 5 on the Richter said Don Dupuy. owner of Crowley quakes la swarm with the largest / muss morthwest, and Maredata pped.
scale can cause consaderaWe dam. Lake Boat Rentala la Crowley take /.* measuring 6.51.... We do age la the local area and an earth t just a feus mues from the epicenter, deer hunters out there.
quake measuring 6 on the scale can
. Mamasath Lakas abeest 40 anges four mtles west of the ski resort of,7 At the Mono County aberuf"a sta. ' aarthwest of Seahop.
, n n., 6g cause severe damage.
Mammettf Lakes.
Diablo Plant Error.,, It just rattled,and made an in y.,
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WASIIINGTON iAP)- Offletals of. "There were a lot of aftershocks. but j','the Nuclear Regulatory Commis aon, was messed up here.
isA8 Laigff M0WM so far it doesn't look Iske anytlung s4 g M
I said today a deslan error affecting t'*
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the ebuity of the Diablo Canyon nu-No amp spdled.** add.ed MA-.
,h clear power plant to withstand an ' THE FIRST QUAKE reaged la
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1 I several years aM might never have size from 5.7 on the Untwarsity. of e e f **. C'MONA2GETYOURS!w' e'
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.s 53 on the equipment at the National N.
At a briefing for the commission. Earthquake Center in Golden. Colo..
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4 i early to tell whether the error would Califorma Institute of Technalogy la Pasadena put it at SA. said Caltech - n' CORDUROY Ot #**.
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- h. require estens'twe design moddica-spokesman Dennsa Meredith.
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b, it can be allowed to operate.
He sa6d an aftershock at 4:05 a.tn.- > VELVETEEN ':
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t commasion officials sand they had. May 1980 i
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Gas As Electric Co. that they would panic." said Gma Jones, y ecale of..i 70g gg D',3 4
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a clerk at g.
- , not start loading fuel untd any're-Tamarack lodge la Mammoth.
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- $4TljtS&Y quired plant modifncations are done... There were dozens of aftershocks 4 4,
The plant has been the site of two of lesser snagnitude. Meredith said..
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weeks of protesta in which I.893 ar.; T1netr sine and number were being l ' rests were made of demonstrators.1compued at Caltech.
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The company said earher 4 hts Power went off in the Mono Coun.
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et N-week that it had mistaken &y used.* ty sheriff's substation in Crowley for. MO.hMaN e.
diagrams of the sister Unst 2 reactor a bout an hour and briefly in the
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' t' la earthquake.prooftng Unit 1.
That error means that tutra, Crowley Lake area and Mammoth strength supports for pipes and
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Lakes strport. but no problems were k'
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cases put in the wrong places be.
" Broken bottles that were fathng
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i cause the equipment is not accated la off shcIves. Safeway had a few cana ggg"*"
the same aren in both plants.
and botues coming down." said U.S.
leURAY let WHILg SUPPLY LASTp' **
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g September 28, 1981
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Mr. R. H. Engelken, Director Of fice of Inspection and Enforcement Region V U. S. Nuclear Regulatory Conmission 1990 N. California Boulevard l
Walnut Creek Plaza, Suite 202 Walnut Creek, CA 94596
Dear Mr. Engelken:
This will confirm our telephone notification of your office on September 28, of piping systems contained in the annulus area of the containm building.
This report is in conformance with technical specification section 6.9.1.12.1.
A review is in progress to determine the ability of dato used for seismic analysis in the annulus area. accept-i results of this review should be available in 7 to 10 days and correc-The tive actions,.if required, will then be determined.
be delayed until a resolution of those items necessary for fuel loading.
Fuel loading will are completed and concurrence is obtained from the NRC.
informed of progress during the revi We will keep you ew.
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Tel. 341-3930 (R e.ns, 791-4211 (After 3 go. ors., MWLeords an FOR IMMEDIATE RELEASE
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Septernber 28, 1981 bacitic Can and Electric Company today informed the Nuclear Regulatory Comnission thtt it had discovered a dincrepancy in one of the diagrarme used in the streus analysis of piping hangez systems in t.he containment structurec Diablo Canyon Nuclear Power Plant.
at The problem was identifled Sunday af ternoon as the result of a design review' Dcoause of this, fuel loading will be delayed while the problem is being reviewed.
The discrepancy involves the loontion on the drawing of reference points used in annlyzing pipo supports in the area betwcon the o t u er wall of the containment at.ructure and an inner wall which tupports the overhead crano.
The Company will review the previous stress analytic to confirm the adsquacy of the piping systemc in the area to moet design criteria.
The extent to which fuel Innding will be delayed by this development m'as not yet been determined.
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September 30, 1981 Mr. R. H. Engelken, Director cc
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Dear Mr. Engelken:
This supplements our September 28, 1981 letter on a discovery of an error found in the analyses of systems contained in the annulus area of the Unit I containment building.
This letter is intended to provide background information and the present status of our review. As a result of this discovery we are reviewing the seismic design of plant components located in the annulus area to verify compliance with seismic design criteria. We have not yet determined that changes in the physical plant are reovired.
However, in our September 28, 1981 letter, PGandE conunitted to delay fuel loading until items necessary for fuel loading are resolved and concurrence is obtained from the NRC.
Because of the collective conservative assumptions and methodology used by PGandE and its consultants during the design of the plant, PGandE is optimistic that most existing installations should be adequate for changed, and in some cases increased, spectra requirements, and that only minor modification may be required.
As indicated in our September 28, 1981 letter, the principal probicm is associated with the vertical seismic floor response (VSFR) spectra used to design piping systems in the annulus area of the containment.
PGandE has determined that the diagram used to locate the
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i Mr. R. H. Engelken September 30, 1981 VSFR spectra in the Unit I containment annulus area above the base slab through the operating deck at Elevation 140 was in error. The diagram used to locate the spectra was applicable to Unit 2, but was identified for use in the Unit i seismic design.
Since the arrangement of Units 1 and 2 are opposite hand to each other and the V5FR spectra are dependent on circumferential location, certain piping was analyzed utilizing inappropriate spectra.
PGandE is currently reviewing piping analyses using the' correct diagram. Preliminary indications are that 14 of the 59 computer generated large diameter piping analyses for the annulus area may be affected. Fourteen of seventy-six large diameter pipe support designs not included in the above computer generated piping analyses may also be affected.
Small diameter piping analyses and pipe support designs are also being reviewed in a similar manner.
PGandE will reanalyze all affected analyses to verify piping stress acceptability and all affected pipe support designs will be rev iewed and reuudlif ied ur r edes igned Lu comply with the corrected loads.
Investigations are also undcrway to determine what.effect this discrepancy has on other systems in the annulus area.
So far we have determined that in addition to the error in the orientation of the dia-gram, the final VSFR spectra was not used in the design of electrical conduit and cable tray supports.
We have underway a comprehensive review of the capability of these supports to accommodate the proper VSFR spectra.
Comparable reviews are underway for other components and systems.
ine pe uviem was uiscovereo oy tampany engineers assigneo piping analysis responsibilities.
Their work required utilization of the dia-gram which we now have determined to be incorrect.
Since the VSFR spectra varied considerably with azimuth location and the spectra loca-tions were not spaced with constant degrees of separation, a cuestion was raised.
Subsecuent investigation by ComnanY Cnd Consultant engineers confirmed the problem.
This error was identified as poten-tially affecting piping analysis and pipe support design late on Friday, September 25, 1981.
Over the weekend this situation was determined to be reportable.
On Monday, September 28, 1981, PGandE notified I&E Region V of this matter.
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Mr. R. H. Engelken September *:0,1981 At the present time, information and analyses are being compiltd to determine the significance of this problem.
While PGandE is still reviewing the cause of the problem, preliminary investigations indicate the cause of this error affects only analysis of containment antaulus systems and has no impact on overall seismic design adequacy.
This conclusion is made since no deficiencio have been identificd with analysis methods or plant configuration drawings.
We plan to present additional information regarding the above concerns at the meeting with the tiRC staff set for October 5,1981 at 9:00 a.m. In Bethesda, Maryland.
Very truly yours,
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