ML16341C096

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Board Notification 84-035:updates Allegation Listed in Sser 21 & Board Notification 84-003.Public Allegations Not Previously Forwarded & Characterizations of Allegations from Confidential Sources Encl
ML16341C096
Person / Time
Site: Diablo Canyon  Pacific Gas & Electric icon.png
Issue date: 03/02/1984
From: Eisenhut D
Office of Nuclear Reactor Regulation
To: Gilinsky, Palladino, Roberts
NRC COMMISSION (OCM)
References
TASK-AS, TASK-BN84-035, TASK-BN84-35 BN-84-035, BN-84-35, NUDOCS 8402090030
Download: ML16341C096 (38)


Text

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Docket No.:

50-.275 50 323 UNITED+ATES

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N LEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 I lEt l0f+NDUi~l FOR:

Chairman Palladjno.

Commissioner Gil ensky Commissloner Rober-ts Commissioner Asselstine Commissioner Bernthal FROM:

SUBJECT:

Darrell G. Eisenhut, Director Division of Licensing DIABLO CANYON ALLEGATIONS (BOARD NOTIFICATION NO.84-035)

The purpose of this Diablo Canyon notification is to update the Diablo Canyon allegation listing found in Supplement 21 of the Safety Evaluation Reoort and the subject of BN-84-003.

Enclosure 1 is the updated listing of Diablo Canyon allegations through February 24, 1984.

In addition, Enclosure 2 provides copies of the actual allegations for those public allegations which have not already been sent to you in previ'ous board notifications.

Enclosure 3 provides characterizations of allegations from confidential sources.

For your convenience, the listing in Enclosure 1

has a column whi'ch identifies the BN transmittal information for each allegation.

Please note that a few of the allegations are currently being investigated or have been investigated by OI and are so noted in enclosure 1 of this board notification.

By copy of this memorandum, we are also informing the Atomic Safety and Licensing Board and the Atomic Safety and Licensing Appeal

Board,

,Or1ginal s1gnod by ggarrell Q Zisonhut 8'402090030 ~

Enclosures; Aq Stated Darrell G. Eisenhut, Director Division of Licensing See Next Page for cc

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SECY (2)

OPE E00 OGC J.

F. Wolf, ASLB G. 0. Bright, ASLB J. Kline, ASLB T.

S. t'loore, ASLAB

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R. Johnson, ASLAB J.

H. Buck, ASLAB Parties to the Proceeding

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DISTRIBUTION LIST FOR BOARD NOTIFICATION Diablo Canyon Units 152 Docket Nos. 50-275/323 OL Ms. Elizabeth Apfelberg Maurice Axelrad, Esq.

Mr. Richard E. Blankenburg Mr. Glenn 0. Bright Dr. John H. Buck Philip A. Crane, Jr.,

Esq.

Mr. Frederick Eissler David S. Fleischaker, Esq.

Mrs.

Raye Fleming Arthur C. Gehr, Esq.

Mr. Mark Gottlieb Mr. Lee M. Gustafson Mr. Thomas H. Harris Mr. Richard B. Hubbard Dr.

W.

Reed Johnson Janice E. Kerr, Esq.

Dr. Jerry Kline Mr. John Marrs Thomas S. Moore, Esq.

Bruce Norton, Esq.

Joel'.

Reynolds, Esq.

Mr. James

0. Schuyler Lewis Shollenberger, Esq.

Mr. Gordon Silver Michael J.

Strumwasser, Esq.

Paul C. Valentine, Esq.

Harry M. Willis John F. Wolf, Esq ACRS Members Dr. Robert C. Axtmann Mr. Myer Bender Dr. Max W. Carbon Mr. Jesse C. Ebersole Mr. Harold Etherington Dr. William Kerr Dr. Harold W. Lewis Dr. J.

Carson Mark Mr. William M. Mathis Dr.

Dade W. Moeller Dr. David Okrent

'Dr. Milton S. Plesset Mr. Jeremiah J.

Ray Dr. Paul C.

Shewmon Dr. Chester P. Siess Mr. David A. Ward Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Appeal Panel Malcolm H. Furbush RBsident Inspector/Diablo Canyon NPS Dr. William E.

Cooper Mr.

W.

C. Gangloff Mr. Lee M. Gustafson Dr. Jose Roesset Mr. Malcolm H. Furbush

REGULATO INFORMATION DISTRIBUTION TEM (RIOS)

ACCESSION NBR 8402090030 DOC ~ DATE 84/03/02 NOTARIZED:

NO FACIl:50-275 Diablo Canyon Nuclear Power Planti Unit li Pacific Ga 50 323 Diablo Canyon Nuclear Power Plantg Unit 2i Pacific Ga AUTH ~ NAME,.

AUTHOR AFFILIATION EISENHUT~D.G.

Divisi.on of licensing

'ECIP ~ NAME RECIPIENT AFFILIATION PALLADINO Commissioners GIlINSKY Commissioners ROBERTS Commissioners DOCKET 05000275 05000323 SUBJECT; Board Notification 84 035:updates allegation listed in SSER 21 8 Board Notification 84-003,Public allegations not-pr eviously forwarded L characterizations of allegations from confidential sources encl.

DISTRIBUTION CODE:

NQQSS COPIES RECEIYED:LTR, ENCL SIZE ~, Il+fg TITLE: Board Notification NOTES:J Hanchett 1cy PDR Documents' Hanchett 1cy PDR Documents'~

~S~i Cepo~4 RECIPIENT COPIES ID CODE/NAmE LTTR ENCl NRR LB3 BC 2

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1 RECIPIENT ID CODE/NAME NRR LB3 LA COPIES LTTR ENCL 1

1 05000275 05000323 INTERNAL: EDO ELD CHRISTANBRY IE DIR IE/OGASIP DIR NRR DEPY NRR/DE/DIR NRh/DL OEPY NRR/DL TA NRR/DL/LB1 NRR/DL/LB3 NRR/DL/SSPB NRR/DST EXTERNAL: LPOR NSIC NOTES' 0

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1 1

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TOTAL NUMBER OF COPIES REQUIRED:

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Docket No.:

50-275 50-323 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 MAR p ig~

4I iREI40RANDUi~l FOR:

Chairman Palladi'no Commissioner Gi linsky Commissioner Roberts Commissioner Asselstine Commissioner Bernthal FROi~1:

SUBJECT:

Darrell G. Eisenhut, Director Division of Licensing DIABLO CANYON ALLEGATIONS (BOARD NOTIFICATION NO.84-035)

Tne ourpose of this Diablo Canyon notification is to update the Diablo Canyon allegation listing found in Supplement 21 of the Safety Evaluation Reoort and the subject of BN-84-003.

Enclosure 1 is the updated listing of Diablo Canyon allegations through February 24, 1984.

In addition, Enclosure 2 provides copies of the actual allegations for those public al~l gations which have not already been sent to you in previ'ous board not'i'fications..

Enclosure 3 provides characterizations of allegations from confidential sources.

For your convenience, the listing in Enclosure 1

has a column which identifies the BN transmittal information for each allegation.

Please note that a few of the allegations are currently being investigated or have been investigated by OI and are so noted in enclosure 1 of this board notification.

By copy of this memorandum, we are also informing the Atomic Safety and Licensing Board and the Atomi'c Safety and Licensing Appeal Board.

q-'

( L A,A"gj,,J i<~,

Darrell G. Ei'senhu(,

'Director Division of Licensing

Enclosures:

As Stated See Next Page for cc

'8402090030

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SECY (2)

OPE EDO OGC J.

F. >lolf, ASLB G. 0. Bright, ASLB J. Kline, ASLB T.

S.

Moore, ASLAB Il.

R. Johnson, ASLAB J.

H. Buck, ASLAB Parties to the Proceeding

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DISTRIBUTION LIST FOR BOARD NOTIFICATION Diab1 o Canyon Units 1&2 Docket Nos. 50-275/323 OL ACRS Members Ms. Elizabeth Apfelberg Maurice Axelrad, Esq.

Mr. Richard E. Blankenburg Mr. Glenn 0. Bright Dr. John H. Buck Philip A. Crane, Jr.,

Esq.

Mr. Frederick Eissler David S. Fleischaker, Esq.

Mrs.

Raye Fleming Arthur C. Gehr, Esq.

'r. Mark Gottlieb Mr. Lee M. Gustafson Mr. Thomas H. Harris Mr. Richard B. Hubbard Or.

W.

Reed Johnson Janice E. Kerr, Esq.

Dr. Jerry Kline

'r. John Marrs Thomas S. Moore, Esq.

Bruce Norton, Esq.

Joel'.

Reynolds, Esq.

Mr. James

0. Schuyler Lewis Shollenberger, Esq.

Mr. Gordon Silver Michael J.

Strumwasser, Esq.

Paul C. Valentine, Esq.

Harry M. Willis John F. Wolf, Esq Dr. Robert C. Axtmann Mr. Myer Bender Or.

Max W. Carbon Mr. Jesse C. Ebersole Mr. Harold Etherington Dr. William Kerr Dr. Harold W. Lewis Dr. J.

Carson Mark Mr. William M. Mathis Or.

Dade W. Moeller Dr. David Okrent

'Dr. Milton S. Plesset Mr. Jeremiah J.

Ray Or. Paul C.

Shewmon Or. Chester P. Siess Mr. David A. Ward Atomic Safety and Licensing Board Panel Atomic Safety and Licensing Appeal Panel Malcolm H. Furbush Resident Inspector/Diablo Canyon NPS Or. William E.

Cooper Mr.

W.

C. Gangloff Mr. Lee M. Gustafson Or. Jose Roesset Mr. Malcolm H. Furbush

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ENCLOSURE 1

LIST OF ALLEGATIONS Allegation Location of Al 1 e ati on 1.

2.

3.

5.

6.

6a.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

23.

24.

25.

26.

27.

28.

29.

30.

31.

32.

33.

34.

35.

36.

37.

38.

39

'0.

41.

42.

43.

44.

45.

46.

47.

48, 49.

50.

Passing of contraband Anti-Nuclear Demonstration Seismic qualification CCW Single Failure Capability CCE Heat removal capability CCW I8C Design Classification Feedwater Isolation Classification Seismic Category I/Category II Interface Seismic Design of Diesel Gen.

I 5 Exh.

USI-17 Systems Interaction Generic Seismic Tilting of Containment Classification of Platform (Category I/Category II)

HELBA did not meet

FSAR, RG 1.46 Inadequate seismic systems Loads on Annulus Structural Steel not calculated properly Inadequate Tornado Load Analysis of Turbine Building High energy pipe break restraint inadequate NSSS SSE Load Inadequate gA/gC Allegations Guard gualification Health Physics personnel do not meet ANSI requirements ALARA Program - Paper Tiger Radiation t",onitors lack sensitivity gC Inspector Concerns HP Foley NCR's rejected without good cause Deficiency in use of "Red Head" anchors for raceway support Foley didn't document NCR's issued fy field inspectors Melding and gA deficiency in "Super Strut" Annulus Structure Reverification Pipe restraints design inadequate Inadequate Documentation of Safety Related 'Equipment gA procedures for Struct. Analysis Seismic analysis containment Turbine Building (Class
2) Contains Class 1 systems 8 components Incomplete as-built drawings Lack of support calcs for fluorescent light fixtures Resolution of fluorescent light fixture interaction Solid state protection system relays PGSE ignoring spurious closure of mot. valve No control room annunciation of closed RHR suction valve RHR hot leg suction not single failure Drawings inadequate Licensee management unresponsive to problems Licensee reporting failure Licensee improper assessment of Design Change Notice Design inconsistency in FSAR RHR valves HPFoley gA procedures voiding NCR's incorrect Plant P.

A. System SI'tudy and associated t<ods Emergency Sirens not seismic qualified Plant security should h'ave been retained OI Withheld OI Withheld Enclosure 3

II BN-83-017 BN-83-48 5 83-61

. OI Withheld BN-84-003 Enclosure 2

OI Withheld OI Withheld Enclosure 2

OI Withheld BN-84-003 BN-83-161 II II II II II II BN-83-168 BN-83-168 BN-83-169 II BN-83-164 Enclosure 3

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Alleqation Location Enclosure 3

Il OI Withheld BN-83-170 51.

52.

53.

Risk of job action against allegers Construction 5 hearings in progress after load inappropriate Welder gualification 54.

Wire traceability not evident for work by PGE and Foley BN-83-171 Enclosure 2

'Enclosure 3

ass tests rior OI Withheld Enclosure 3

Enclosure 2

nclosure 2

I Withheld BN-84-003 BN-8 <-003 BN-84-003 BN-83-194 II II II II ways Enclosure 2

BN-83-.194 If oblems a pipe II diheral 55.

Bechtel approved analysis of small bore pipe by altering failed analysis 56.

Pitting of main steam and feedwater piping 57.

Foley used uncertified and unqualified g.C. insoectors prior to 1983 58.

Foley allows "Red Head" anchors studs reported improperly installed 59.

Foley lost cable traceability 60.

Foley purchased material through unapproved vendors 61.

Lack of document control 6la.

H.

P.

Foley used unapproved drawing 62.

'Foley lacks adequate sampling of cable pull activities 63.

Foley has lost material tracability through upgrade of non-cl 1 to Class 1

64.

Grout test sampling based on special tests rather than field 65.

Foley documents prior to 1980 questioned NO review required p

to 9/1981 license issuance date 66.

Defective weld reports rejected by Foley 67.

Negligence by PGRE flooding at 55 ft. elevation pipe tunnel 68.

NSC Pullman-Kellog audit 69.

Revision of Draft Case Study "C" 70.

Inadequate of response to NRC notice of Violation 71.

Use and sale of drugs 72.

Audits of PG8E (PAC/EDS) 73.

Selling of drugs 74.

Defective piping support 75.

Discharge piping too close to accumulater 76.

U-Bolts have failed 77.

Flange bent on I-beam 78.

Bracket Bolted to wall with only bolt 79.

Engineers are calculating stresses in piping in a variety of 80.

Concerns about the emergency response plan 81.

Individual fired for whistle blowing 82.

Minimal Orientation for New Wngrs. at the site 83.

NRC was not effective in identifying problems 84.

Lack of resoonsiveness by management to identified problems relating to design 85.

U-bolt design 86.

"Code-break" design 87.

Calc. related to "code break" design destroyed 88.

Undocumented modifications were made because of code break pr 89.

I'nterference of pipe supports (attempted use of uni-.strut as a pipe) 89.

Interference of pipe supports (attempted use of uni-strut as support) 90.

Defective concrete in intake structure 91.

Alleged cover-up of defective material use 92.

Flare bevel welds are undersized and do not comply with code angle

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94.

95.

96.

97.

98.

99.

100.

101.

102.

103.

104.

105.

106.

107.

108.

109.

110.

111.

112.

113.

114.

1.1 5.

116.

117.

118.

119.

120.

121.

122.

123.

124.

125.

126.

127.

128.

129.

130.

Inaccurate depiction of welds on drawings (symbolic)

Pullman used pipe welding procedures to make structural support welds Angles of pioe support member are out of specification Improper anchor bolt spacing ("Hilti"and "Red Head" )

Site design engineers have been required to use uncontrolled documents resulting in different assumptions, etc.

Possible non-adherence of pentration seal orocedure Falsification of Welding guality Control Records No quality control program for coatings gualification of welders and procedures Improper references on 'DCN Welding and welding program concerns Pullman welding procedure specification are not sufficient Pullman weld joints not prequalified for AWS and don't meet ASt1I IX Pullman welded materials are not listed as approved for AWS/ASNE welding Pullman weld technique sheets used in lieu of welding procedure specifications Pullman used gA vice engineering to write a welding technique sh Pullman used ASME welders to weld AWS welds Pullman used weld procedure specifications which were not tested for notch toughness as required Pullman procedure WPS 88/89 used GTAW for weld contrary to AWS D

Pullman welder no.

N elide not maintained activity during August-December 1982 Deficiencies in Pullman pipe rupture restraint welding, caused serious weld cracking problems Pullman used square groove welds for supports and restraints contrary to requirements Pullman made square groove welds without a qualified welding procedure Pullman used generic qualifications for WPS's Pullman used copper chill bars for plug welds of improperly divilled holes PGSE may not have reviewed deviation from Pullman spec 8333XR Pullman welded threaded bolts and studs to liner without a qualified WPS Pullman Possible intimidation of personnel Pullman inadequacies in valve wall thickness measurement acti vities Pullman inadequacies in nondestructive testing activities and audits Improper acceptance of welder qualification tests Responses to audits were not timely Pipe rupture restraint welds not tested per specification PGE has not implemented a consistent set of weld symbols for engineers and contractors Preheat requirements not followed for certain welds Pullman did not properly accept problem reports Improper activities related to Pullman welding Pullman possible intimidation of personnel BN-83-194 Enclosure 3

OI Withheld BN-83-003 Enclosure 3

Enclosure 3

BN-84-009 eet II 1

)

II BN-84-014 Enalosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

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~ Alle ations Location 131.

132.

133.

134.

135.

136.

137.

138.

139.

140.

141.

142.

143.

144.

145.

146.

147.

148.

149.

150.

151.

152.

153.

154.

155.

156.

157.

158.

159.

160.

161.

Pullman welded bolts and studs to containment liner without a qualified MPS Pullman welded plate to CCW piping while piping contained water Foley did not properly accept/document properly reports Foley did not invoke Part 21 on. vendor contracts Foley audits were not performed for an extended period Foley audit findings i<ere not properly handled Foley did not audit procedure adequacy Foley lost wire tracability for incore thermocouple circuits Foley improperly performed tubing fabrication (socket welding a'nd bending)

Foley used material purchased from one contract to another Foley performed transverse welding across beams (installation of unistrut)

Foley inadequately installed and checked anchor bolts Foley did not torque beam claps at installation Foley installs P1100 conduit clamps to close to channel edges-may slip out Foley did not specify raceway materials in details-improper bolt heads may have been used:.

Foley does not keeo raceways free of damaging debris Foley installs different nitalities of systems on a single suppor Foley gC identifying unsat.

work in progress were told to wait until completion, then reject Foley did not submit HVAC as-built information during 1981/82-as-built may not be checked against design Foley production may have falsified structural steel and tubing heat number records Foley installs to many conduits or supports; inspection reject ra is too high for supports Concerns with installation of P1331 conduit clamps (torque achiev ment, relocation, excess)

Foley specifies 1/8" welds or 3/32" clamp material Foley does not specify adequate inspection criteria for anchor bolts

!lelding on embed plates causes distortion may damage plate or anchors'oley-'possible intimidation of, personnel Pullman possible intimidation of personnel Unit 2 annulus design-inadequate seismic load comginations Unit 2 annulus design-steel members may be over stressed due to additions Unit 2 annulus design-bracings carry axial loads and supports Unit 2 annulus design-too many assumptions of Class II and small bore loads Enclosure 3

See.24

& 128 duplicate Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

Enclosure 3

e-.

II Enclosure 3

Enclosure 3

Enclosure 2

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V Alle ations Location Enclosure 3

162. Unit 2 annulus design-calculations changed by reviewers without consultation with originator/checker Enclosure 2

163. Unit 2 annulus design-improper assumptions related to thermal expansion 164. Unit 2 annulus design-beams not checked for tearing failure mode 165. Unit 2 annulus design-computer code check did not annount for torsional stresses 166.

Foley allows correction to quality documents by gC with inadequate guidelines Enclosure 3

167.

Foley is not reviewing all records in preparation for turnover-only post 9/81 records 168.

Foley did not properly grout base plate anchor bolts Enclosure 3

169.

Pullman failed to conduct support welds as required by procedures Enclosure 3

170.

Pullman lost pipe traceability due to inadequate training of fab shop inspectors Enclosure 3,

171.

Inadequate planning and routing of cables within the plant giving rise to a potential for inadequate separation of redundant safety-related cables and loss of traceability Enclosure 3

172. Transfer of cable to alternate reels - short sections of cable were frequently transferred from their original reel to other reels of cable as a convenience resulting in confuston:

regarding specific documentation of cable characteristics 173.

Improper clearing of cable ways before pulling cables.

Failure to adequately clear the cable ways could have resulted in damage to cables when they were pulled through the cable ways 174.

Inadequate control of tension levels when pulling cables inade-quate control was exercised in pulling electrical cable through cable ways and could have resulted in damage to cables during installation 175.

Changes from interim "as built" drawings to final drawing--

inadequate control has been exercised over the transition from interim drawings to final drawings of the station as actually constructed 176.

Anchor bolts (torquing of "red-head" bolts) 177.

RHR pump section line valve control.

Potential damage to RHR pumps due to loss of suction as a result of a single failure 178; Boron Worth vs.

Temperature written in 1976 to 1978 may be in error 179.

Concern that Auxiliary'salt water pump flow does not meet FSAR flow rates 180.

During tests of CCW system 3

CCW heat exchanger inlet valves were broken due to water hammer.

All pressure transients not listed on test documents.

181.

Diesel Generatoi surveillance test records are inaccurate and incomplete 182. Bolts on

CVCS, RHR,
RCS, PORV's and Safety Valves did not meet ASME Code Specifications.

They were over-torqued, 183. Alleged use of hard drugs in portable toilets on site 184. Unqualified fire stop designs being used Enclosure 3

185.

No gA being practiced during fire stop installation 186. Operator doesn't know how to operate a two component silicone foam equipment 187.

Many foam seals are not good

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I Alle ations Location 188.

Hudson allegation package on gA breakdown at Pullman 189. Magnaflux Corp. weld reverification program accepted by PGSE with bad welds 190.

Pipe support base-plate installation doesn't define hearing surfaces 191.

"gC finds too many problems" attitude by PGIIE 192.

Acceptance criteria changed to decrease weld failure rates 193.

Poor gC inspector selection and training 194.

Document control rules made up as they go along 195.

Document control stamps not controlled 196.

Employee threats to supervision 197.

Employee threaten 2 gC'nsoectors 198.

>lork packages not in gC review package 199.

Too many qC items being ramrodded through to maintain schedule Enclosure 3

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tIIf/IR g 9 Distribution Document Control (50-275/323)

PRC System JLee (2)

DOCKET NO(S) 50-275/323 The Honorable Alan Simpson, Chairman Subcommittee on Nuclear Regulation Committee on Environment and Public Works United States Senate Washington, D.C.

20515

SUBJECT:

PACIFIC GAS AND ELECTRIC COllPANY, DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1

5 2

, dated The following documents concerning our review of the subject facilityare transmitted for your information.

Notice of Receipt of Application.

Draft/Final Environmental Statement, dated Notice of Availabilityof Draft/Final Environmental Statement, dated B Safety Evaluation Report, or Supplement No. 22, dated tlarch 1984 Notice of Hearing on Application for Construction Permit.

Notice of Consideration of Issuance of Facility Operating License.

Application and Safety Analysis Report, Volume Amendment No.

to ApplicationiSAR dated Construction Permit No. CPPR-

, Amendment No.

, dated Facility Operating License No.

, Amendment No.

Order Extending Construction Completion Date, dated Other (Specify)

Enclosures:

As stated cc:

Senator Gary Hart bcc:

OCA Office of Nuclear Reactor Regulation LB: L JL t

OFFICE/

SURNAME/

DATEP

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NRC FORM 318 {10/80) NRCM 0240 OFFICIAL RECORD COPY

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1a MAR 29 884 I

'I Distri tion Document Control (50-275/323)

PRO System JLee (2)

DOCKET NQ($)

50-275/323

'I The Honorab1e Richard Ottinger, Chairman Subcommittee on Energy Conservation and Power Committee-on Energy and Commerce United States House of Representatives Washington, D.C.

20515

SUBJECT:

PACIFIC GAS AND ELECTRIC COIIPANY, DIABLO CANYON NUCLEAR POMER PLANT, UNITS 1 5 2 The following documents concerning our review of the subject facilityare transmitted for your information.

Notice of Receipt of Application.

Draft/Final Environmental Statement, dated Notice of Availabilityof Draft/Final Environmental Statement, dated B Safety Evaluation Report, or Supplement No., dated March 1984 Notice of Hearing on Application for Construction Permit.

Notice of Consideration of Issuance of Facility Operating License.

Application and Safety Analysis Report, Volume Amendment No.

to ApplicationiSAR dated Construction Permit No. CPPR-

, Amendment No.

Facility Operating License No.

, Amendment No.

Order Extending Construction Completion Date, dated Other (Spec/fy)

, dated

, dated

Enclosures:

As stated cc:

Representative Car1os Moorhead j

bcc:

OCA I

Office of Nuclear Reactor Regulation

,, OFFICE)

SURNAME/

DATEP 3:

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NRC FORM 318 (10/80) NRCM 0240 OFFICIAL RECORO COPY

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MAR 2 9 1984 Distribution PRC System Document Control (50-275/323)

JLee (2)

DOCKET NO(S).

50-275/323 The Honorable Ilorris K. Udall, Chairman Subcommfttee on Energy and the Environment Committee on Interior and Insular Affairs United States House of Representatives Mashfngton, D.C.

20516

SUBJECT:

PACIFIC GAS AND ELECTRIC COMPANY, DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1

II1 2 The following documents concerning our review of the subject facilityare transmitted for your information.

Notice of Receipt of Application.

Draft/Final Environmental Statement, dated 0 Notice of Availabilityof Draft/Final Environmental Statement, dated Kj Safety Evaluation Report, or Supplement No.

22, dated Notice of Hearing on Application for Construction Permit.

Notice of Consideration of Issuance of Facility Operating License.

Application and Safety Analysis Report, Volume Amendment No.

to Application/SAR dated Construction Permit No. CPPR-

, Amendment No.

, dated

, Amendment No.

Facility Operating License No.

Order Extending Construction Completion Date, dated Other (Speci fy)

, dated

Enclosures:

As stated Office of Nuclear Reactor Regulation cc:

Representative t<anuel Lucan bcc:

OCA OFFICE/

SURNAME/

DATEtrt

DL, ft gnt/84 NRC FOAM 318 (10/00) NRCM 0240 OFFICIAL RECORD COPY

MAR P V >984 Distribution Document Control (50-275/323)

PRC System LB¹3 Reading JLee DOCKET NO(S),

50-275/323 The Honorable Vorris K. Udall, Chairman Subcommittee on Energy and the Environment Committee on Interior and Insular Affairs United States House of Repreeentatives klashington, D.C.

20515

SUBJECT:

PACIFIC GAS AND ELECTRIC COMPANY, DIABLO CANYON NUCLEAR POlJER BLANT, UNITS 1 AND 2 The following documents concerning our review of the subject facilityare transmitted for your information.

Notice of Receipt of Application.

Draft/Final Environmental Statement, dated Notice of Availabilityof Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No.~, dated Notice of Hearing on Application for Construction Permit.

Notice of Consideration of Issuance of Facility Operating License.

Application and Safety Analysis Report, Volume Amendment No.

to Applicati'on/SAR date'd Construction Permit No. CPPR-

, Amendment No.

, dated Facility Operating License No.

, Amendment No.

Order Extending Construction Completion Date, dated X

Other(Spec//y)

Exem tion for Extension of Submittal D t dated 2 12 84

, dated

Enclosures:

As stated Representative Hanuel Lucan bcc:

OCA Office of Nuclear Reactor Regulation OFFICE/

SURNAME)

DATEP L

DL

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NRC FORM 3I8 (10/80) NRCM 0240 OFFICIAL RECORD COPY

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MAR 07

)984 Distribution Document Control (50-275/323)

PRC System JLee LB¹3 Reading DOCKET NO(S).

50-275/323 The Bonorable Richard Ottinger, Chairman Subcommittee on Energy Conservation and Power Committee on Energy and Commerce United States House of Representatives Mashington, D.C.

20515 PACIFIC GAS AND ELECTRIC COMPANY, DIABLO CANYON NUCLEAR POMER PLANT, UNITS 1 AND 2 The following documents concerning our review of the subject facilityare transmitted for your information.

Notice of Receipt of Application.

Draft/Final Environmental Statement, dated Notice of Availabilityof Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No., dated F ""ar>> g84 Notice of Hearing on Application for Construction Permit.

Notice of Consideration of Issuance of Facility Operating License.

Application and Safety Analysis Report, Volume Amendment No.

to Application/SAR dated Construction Permit No. CPPR-

, Amendment No.

,dated Facility Operating License No.

, Amendment No.

Order Extending Construction Completion Date, dated Other(Spec//'y)

Exem tion for E e

dated 2/12/84 0"

, dated

Enclosures:

As stated Representative Carlos Moorhead bcc:

OCA Office of Nuclear Reactor Regulation OFFICEI SURNAME/

DATEP

DL mme m ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

NAG FOAM 318 u0/80) NACM 0240 OFFICIAl RECORO COPY

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MAR 0 7 1984.

ie Distribution Document Control (50-275/323)

PRC System LB/13 Reading JLee DOCKET NO(S).

50-275/323 The Honorable Alan Simpson, Chairman Subcommittee on Nuclear Regulation Committee on Environment and Public Works United States Senate Washington, D.C.

20515

SUBJECT:

PAC?FIC GAS AND, ELECTRIC COMPANY, DIABLO CANYON NUCLEAR POWER PLANT, UNITS 1

AND 2 The following documents concerning our review of the subject facilityare transmitted for your information.

Notice of Receipt of Application.

Draft/Final Environmental Statement, dated Notice of Availabilityof Draft/Final Environmental Statement, dated CS Safety Evaluation Report, or Supplement No. 1", dated Notice of Hearing on Application for Construction Permit.

Notice of Consideration of Issuance of Facility Operating License.

r Application and Safety Analysis Report, Volume Amendment No.

to Application/SAR dated Construction Permit No. CPPR-

, Amendment No.

, dated Facility Operating License No.

, Amendment No.

Order Extending Construction Completion Date, dated Gl Other($ pec/fy)

Exem tion for Extension o

S bm tt dated 2 12 84

, dated

Enclosures:

As stated cc:

Senator Gary Hart bcc:

OCA Office of Nuclear Reactor Regulation oFF/CSIN'URNAME/

DATKP DL

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