ML20038A731
| ML20038A731 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 11/12/1981 |
| From: | Bradley Jones NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Atomic Safety and Licensing Board Panel |
| References | |
| ISSUANCES-OL, NUDOCS 8111160236 | |
| Download: ML20038A731 (8) | |
Text
11/12/81
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UNITED STATES OF AMERICA
,e UOVJ 3 799fg 7 NUCLEAR REGULATORY COMillSSI0li
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BEFORE THE ATOMIC SAFETY AND LICENSI!iG BOARD C C %r In the lidtter of
)
s
)
(,,0 PACIFIC GAS AND ELECTRIC COMPANY
)
Docket Nos. 50-275 0.L.
)
50-323 0.L.
(Diablo Canyon Nuclear Power Plant )
Unit Nos. 1 and 2)
)
NRC STAFF RESP 0i4SE TO J0li4T IliTERVEr40RS' REVISED CONTENTION ON ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMEI4T If4TRODUCTIO_N On July 1,1981 a Conference of Counsel in the above proceeding was held to discuss Joint Intervenors' Statement of Clarified Contentions dated June 30, 1981.
On August 4, 1981 the Licensing Board issued a Memorandum and Order admitting Contention 1 related to emergency planning.
The Board rejected all other contentions; however, on Contention 14, which related to environnental qualification of equipnent, the Board stated the following:
The Board, however, expects that Diablo Canyon will not be permitted to operate until the safety-related electrical equipment has been qualified in accordance with the mandates of the various general design criteria, as required by regu-lation. Having said this, the Board does not see herein a liti able issue set forth. This part of the contention is 9
therefore denied.
Joint Intervenors also contend that the Staff has failed to deteruine that environmental qualification of Class 1E electrical equipaent for full-power operatic' is adequate, and that the Staff has not determined the adequacy of the radiation qualification of safety-related equipaent. Joint Intervenors are quite correct in this assertion.
The Staff has stated (SER, Supp.13, p. 7-1; SER, Supp.14, p. 3-8) that the Staff evaluation of these matters will be presented in a following SER supplement. The Board, therefore, will allow Db Joint Intervenors, if they so desire, to file a contention on
-T these matters setting forth specific areas of inadequacy in 8111160236 811112
'."Tr.;:aTED 031GIUAL PDR ADOCK 05000275 G
PDR 7"L Cartified BY_
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the Staff's evaluation to be contained in a forthcoming SER supplement.
The contention will be due fifteen days after service of the SER supplement.
1enorandun and Order at 8).
On October 2,1981, the Staff issued Suppleaent #15 to the SER.
On October 23, 1981, the Joint Intervenors filed a 1:evised Contention on Environnental yualification of safety related electrical equipment. The NRC Staff opposes the adnission of that contention.
DISCUSSION Joint Intervenors' contention suffers from several infiraities.
First, the Licensing Board specifically star.d that contentions could be filed " setting forth specific areas of inadequacy in the Staff's evaluation to be contained in a forthcoming SER supplement."
(Id.). The Staff objects, of course, to a contention which fails to identify an area of alleged non-compliance with a NRC requirenent as opposed to alleging only that the Staff review is inadequate.
In only one paragraph of Joint Intervenors' contention is a specific perceived deficiency in the Staff's SSER 415 addressed.
The only other references to SSER #15 are in the introducto;y and conclusory paragraphs which allege the SSER e15 is inadequate without specifying why the supplenent is inadequate.
Since the vast majority of the two-page contention filed by the Joint Intervenors, contrary to the Board's instructions, does not address new information contained in the Staff's evaluation in SSER #15, those portions not addressing the Staff's SSER #15 should be rejected. Those portions not within the Licensing Bu.rc's directive must satisfy the requirements
of 10 C.F.R. 5 2.714 for late filing of contentions, as well as the requiremhntsforreopeningaclosedrecord.
Pacific Gas and Electric Co.
(Diablo Canyon fluclear Plant, Units 1 and 2) CLI-81-5,13 fiRC 362 (1981).
In addition to these standards, in order to have a contention on the subject Odtter covered by SSER #15 admitted, Joint Intervenors must demonstrate that new information is contained in the supplement which was not available at the time provided by the Board for filing contentions in this proceeding.
Joint Intervenors have not even addressed, let alone met, those requirenents. Thus, those portions of the contention not addressing SSER #15 should be dismissed.
Even beyond the fact that the Licensing Board's Order does not provide for the filing of those portions of the contention addressing othe.* than the Staff's SSER #15, those portions have, in effect, already been rejected by the Board. The majority of Joint Intervenors' contention addresses deficiencies in the qualification of equipnent as previously identified by the Applicant.
Joint Intervenors' contention requests that certain actions be taken to correct or compensate for the deficiencies.
It is not evident what Joint Intervenors wish to litigate on this issue since the Licensing Board has already agreed with then on this point.
In its August 4,
(
1981 Order, the Licensing Board agreed with the Joint Intervenors that l
certain deficiencies in identified equipment did exist at that time as admitted in the June 10, 1981 submittal by PU&E to the Staff.
The Boa d stated that it expected that Diablo Canyon would not be allowed to operate I
until the regulations were complied with.
(Prehearing Conference Order at 8).
The Staff position is that the Applicant must either correct the deficiencies or provide a justification for operating with the deficiencies prior to full power operation. This is consistent with the Commission's directions that the environmental qualification of equipment need not be completed until June 30, 1982 and that the Staff should deteruine in the interim whether to allow operation where equipment had not been documented as qualified.
Petition for Emergency and Remedial Action, CLI-80-21, 11 f4RC 707, 715 (1980).
[40 thing remains for Joint Intervenors to litigate on the portions of their contention addressing the deficiencies identified by Applicant.
The only portion of Joint Intervenors' contention which addresses new information contained in the suppleuent and is not late is the second paragraph on page two of the contention.
That paragraph alleges an inadequacy in the SSER #15.
Specifically, Joint Intervenors contend that the instruments and post accident monitoring equipment as described in Reg. Guide 1.97, Rev. 2, and 140 REG-0737 should be identified and qualifi-cation requirements listed and evaluated in SSER #15. To the extent that paragraph alleges non-compliance with Commission requirements it could form the basis for an admissable contention.
However, Joint Intervenors have not identified an item which is required to be considered in SSER #15.
While SSER #15 does not specifically address Reg. Guide 1.97, Rev. 2, this is appropriate.
As explained in the supplement's " Background" section, SSER #15 is in response to the Commission Memorandum and Order, CLI-80-21 (Issued on May 23,1980), which required qualification of safety related equipment as oddressed in fiUREG-0588.
(SSER #15, p. B-3).
f4UREG-0588 does not address the requireuents of Reg. Guide 1.97, Rev. 2.
Further, in the low power license issued on September 22, 1981 the
\\
Commission specifically required the Applicant to submit a proposal, including an implementation schedule, for compliance with Reg. Guide 1.97, Rev. 2 (Low Po.ver License, Section 2.C(7)).
The Applicant subnitted on October 22, 1981 a report on compliance with Reg. Guide 1.97, Rev. 2.
Tnat document identified the extent to which the variables identified in the Reg. Guide have been met or need further action to be met.
The document concludes that all equipment will be in coopliance with the Reg.
Guide by the June 1983 deadline provided in the Reg. Guide.
(This document is attached as Appendix A).
It is thus not evident why Joint Intervenors believe the specific Reg. Guide 1.97, Rev. 2, standards should be analyzed at present in SSER #15.
Based on the foregoing, the Staff believes that Joint Intervenors contention lacks sufficient specificity in that it does not clearly identify what it is they wish to litigate.
C0i1CLUSION The majority of Joint Intervenors' Revised Envircnnental Qualifica-tion Contention is inadaissible because it is beyond the scope of the area the Licensing Board provided was available for the filing of additional contentions in its August 4,1981 Menorandun and Order.
Specifically, all portions of the contention, ><ith the exception of the second paragraph on page two of the contention, should be dismissed as falling outside the scope of the August 4, 1981 Meuorandua and Order.
The second paragraph on page two of the contention is an inadmissible contention because it lacks specificity in identifing what it is the Joint Interveno,rs wish to litigate.
The Staff, therefore, urges the Licensing Board to reject all portions of the contention.
Respectfully submitted, Y
/
Bradley W. Jones Counsel for f1RC Staff Dated at Bethesda, Itaryland this 12th day of Ilovember,1981.
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APPENDIX A 1
PACI.FIC GAS AND ELECTR,IC C O M PANY 77 BE ALE $7 R EET,3157 F LC OR, S AN FR ANCISCO. C ALIFCR NI A 94* C6 P. C. B C X 74 4 2
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October 22, 1981 4
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Mr. Frank J. Eraglia, Jr., Chief, Licensing Branch No. 3 t-9 Divir; ion of Licensing (R,,
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Office of Nuclear Reactor Regulation g
U. S. Nuclear Regulatorf Cctrnission-S-
Washington, D. C.
20555 OCT2 31981> y Re: Docket No. 50-275 v.s. ena enumma Y
i Diablo Canyon Unit 1 License No. DW.-76 License Condition-Ccceliance w/ li s Iv N
with R/G 1.97
Dear Mr. Miraglia:
F;.rsuan to ::em .C(7) of the '.icense we have reviewed the design, cualificaricn and insta11aticn of inst:.:nents a: the Diablo Canycn Fcwer Plant to deter:.ine what changes are needed to cceply l
with the Regulatory Guide 1.97. Revision 2.
The Regulatcry Guide
'.ists 69 ser1 rate variables c ich need to be reviewed.
(Scce '. triables are listec rcre than once in the Regula cry Guide.)
i FGandR's review of these ite s is su:Tnarized in Tables 1 through 5 attached. Table 1 lists the 48 variables Miich cccply with i
the Regulator 7 Guide. The work required to bring 21 renaining variables into ccepliance has been categorized as follows:
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Mr.' Frank J. Miraglia, Jr. October 22, 1981 Table 2: Eleven variables which require qualification of the existing (quipnent.
Table 3: Four variables which require changing the ranges.
Table 4: One variable which requires upgrading of the indication loop.
Table 5: Five variables which rcquire new indication loops.
We will complete this work prior to the June,1983 implenentation date established in the Regulatory Guide.
Kindly acknowledge receipt of this material on the enclosed copy of this letter and return it to tre in the enclosed addressai envelope.
'ery truly yours, b /
id cc L
,e h'philipA. Crane,Jr.
EclcsL"e cc(w/ enc.): Service List e
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Page 1 of 6 a
TABII 1 VARIABI2 FUNCTICN CORPICTIVE ACTION 1)
Centrol Rod Position 1)
Reactivity Control None.
Type B, Category 3 2)
Reactivity Control None.
Concentration Type B, Category 3 3)
RCS Pressure
- 1) Core Cooling None.
Type B, Category'l
-2 ) Maintaining Reactor Coolant System Integrity Type B, Category 1
.3)
Reactor Coolant Pressure Boundary Type C, Category 1
~4)
Containment
?fpe.C, Catecory.1 4)
Core Exit Terperature 1)
Core Cooling None.
?fpe B, Category 3 2)
Fuel Cladding Type C, Category 1 5)
Coolant Level in 1)
Core Cooling None.
Reacter
?fpe 3, Catecery 1 6)
Degees cf Suheceling 1)
Cere Cccling None.
?fpe B, Category 2 7;
-*4
-=nt Su p 1)
- '_ai.taining Reac:cr Mone.
Water Level Coolant System Integrity
?ype B, Category 2 (NR)
Category 1 (WR) 2)
Reacter Coolant Pressure Boundary
?fpe C, Category 2 U,R)
Category 1(WR)
Page 2 of 6 TABLE 1 (Cent'd.)
CORPICTIVE ACTION VARIABLE FU';CTICN 8)
Centairment Pressure
- 1) Maintaining Reactor Ncne.
Coolant System Integrity
?fpe B, Category 1
- 2) Maintaining Containment Integrity Type B, Category 1 3)
Reactor Coolant Pressure Boundary
?fpe C, Categcry 1 4)
Containment Pfpe C, Category 1 9)
Contairment Isolation 11 Ma ntaining None.
Valve Position Contairment Integrity
?fpe B, Category 1 10)
Analysis of Primary
- 1) Fuel Cladding None.
Coolant ( Ga==a
?fpe C, Category 3 Spectrum) 11)
Centainnent Area 1)
Reacter Ccclant Pres-Nene.
Fadiaticn sure Ecundary Type C, Categcry 3 2)
Centain.er.t F2 dis tict.,
?fre E, Categcry 1 12)
Effluent Fadioactivity 1)
Reacter Ccelant Nene.
'::' le Gas Effluent Pressure Ecundary frcn Condenser Air
?fpe C, Categcry 3 Re= oval System Exhaust 13)
Containment Hydrogen 1)
Centairrent Nene.
Ccncentration
?fpe C, Category 1 14)
Containment Effluent
- 1) Centaircent None.
Padioactivity - Ncble Type C, Category 2 Gases from Identified Release Points e
Page 3 of 6 o
TABLE 1 (Cont'd.)
VARIABLE ITNCTICN CCPRECTIVE AC* ION 15)
Effluent
- 1) Containnent None.
Radioactivity
?ipe C, Category 2.
Neble Gases (inside buildings or areas) 16)
Accumulator Isolatien 1)
Safety Injection None.
Valve Position System Type D, Category 2 17)
Refueling Water 1)
Safety Injection None.
Storage Tank I,evel System Pipe D, Category 2 18)
Reactcr Coolant
- 1) Primary Coolant None.
Pu=p Status
- System,
?/re D, Category 3 19)
Primary System Sa'fety 1) Primary Coolant None.
Relief Valve
- System, Positioners (including
?ipe D, Category 2 PCRV and code valves) or flow through or pressure in Relief valve Lines 20)
Pressurizer Level 1)
Pri ary Coelant Nene.
- System,
? re D, Category 1
/
21)
Pressurizer Heater 1)
Pr.ary Cociant Nene.
Status
- System,
?/pe D, Catecery 2
- 2)
Quencn Tank Level 1)
Pr:rary Coolant Ncne.
Syste=,
?/pe D, Catecery 3 23)
Quench Tank Pressure 1)
Prirary Coolant Nene.
Systc=,
?fpe D, Category 3 24)
Steam Generator Level 1)
Secondary System None.
?fpe D, Category 1
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Page 4 of 6 TABLE 1 (Cont'd.)
i VARIABLE FUNCICN CORRECTIVE ACTICN 25)
Safet7/ Relief valve 1)
Secondary System Nene.
Positions on Main Type D, Category 2 Steam Flow i
26)
Main Feedwater Flow 1)
Secondary System Ncne.
Type D, Category 3 27)
Auxiliary or 1)
Auxiliary Feedwater None.
Emergency Feedwater Type D, Category 2 Flow
- 23) Condensate Storage 1)
Auxiliary Feedwater Nene.
Tank Water Level Type D, Category 1 29)
Comconent Cooling 1)
Cooling Water System Nene.
Water Terperature Type D, Category 2 l
to ESF System
- 30) Corponent Cooling Water 1) Cooling Water System None.
Flow to ESF System Type D, Category 2
- 31) High-Level Fadioactive 1)
Radwaste System Nene.
Liquid Tank Level
?fpe D, Category 3 22:
Fadicactive Oas H0ld-1)
Fadwaste System Nene.
?fpe D, Category 3 Tank Pressure
- 33) E.ergency ventilatien 1) Ventilaticn Systen Nene.
Damper F sitien
?fpe D, Catecory 2
- 34) Status of Standby
- 1) Fewer Supplies Nene.
and other Enercy
?fpe D, Categcry 2 Sourcs: : pertant
- w Safety (hydraulic, pneumatic) 35)
Fadiatien Exposure 1)
Area Radiation Nene.
Fate (inside
?fpe E, Category 2 buildings t
on areas where access is required to service ecuip=ent imoortant to safety) 36)
Neb 1q Gases and Vent 1)
Airborne Fadicactive Nene.
Flow Fate (Cc= men Materials Released Plant vent Discharging f.~:m Plants Any of AbcVe Releases
?fpe E, Category 2 if containment purge is included, v-3--,,,,-
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Page 5 of~6 TABLE 1 (Cont'd.)
CCRRECTIVE ACTICN FUNCTION VARIABLE 37)
Noble ' Cases and Vent 1)
Airberne Radioactive None.
Flow Rate (Vent Materials Released from steam from Plants Generator Safety Type E, Category 2 Relief Valves or At:espheric D=p Valves)
~
39)
Neble Gases and Vent 1)
Airborne Radioactive None. -
~
Flew Kate (All other Materials Released Identified Release from Plants Points)
Type E, Category 2 39)
Radiation Exposure
- 1) Environs Radiation None.
Meters (continuous and Radioactivity
. indication at fixed Type E locations)
- 40) Airborne Radichalo-1)
Environs Radiation Nene.
and Radioactivity gens and Particu-lates (portable
?/pe E, Category 3 sarpling with onsite analysis capability) 41)
Plant and Environs 1)
Envirens Radiation Nene.
Fadiation 'po rtable and Radicactivity ins tr=en tatien)
?fpe E, Catege rf 3 42)
Plant and Envirens 1)
Environs Radiation None.
and Radioactivity Fadicactivity (p:rtanle
?fpe E, Catecery 3 instr =entation)
Ncne.
42; Wind Oirecticn 1)
Metecrology Type E, Catecerf 3 None.
44)
Wind Speed 1)
Meteorology Sfre E, Categcry 3 None.
- 45) Estiestien of 1)
Meteorology Atmospheric Stability Type B, Categerf 3
- 46) Primary Coclant and 1)
Accident Sampling None.
Capability (Analysis Sunp capability on Site)
Type E, Category 3
=
Page 6 of 6 TABLE 1 (Cont'd. )
VARIABLE FUNC'"ICN CORRICTIVE AC* ION
~
- 47) Centa n=ent Air 1)
Accident Sanpling None.
Capability (Analysis Capability on Site)
Type E, Category 3
- 43) Particulates and 1)
Airborne Radioactive None.
Halogens (All Materials Released frc=
Identified Plant Plant Release Points.
Type E, Category 3 Sarpling with Cnsite Analysis Capability)
O 4
Page 1 ef 1 o
TABLE 2 VARIA3II FUNCTICN CORRECTIVE ACTION 1)
Neutrog Flux 1)
Reactivity Control Qualify the equipment Type B, Category 1 2)
RHR System Flow 1)
Residual Heat Removal Qualify the transmitter' Type D, Category 2 3)
EHR Heat Exchanger 1)
Residual Heat Rereval Qualify the transmitter Outlet Temerature Type D, Category 2 4)
Accu =ulator Tank Level 1)
Safety Injection Qualify the transmitter
- System, Type D, Category 2 5)
Accumulator Tank 1)
Safety Injection Qualify the transmitter Pressure
- System, Type D, Category 2 6)
Boric Acid Charging 1)
Safety Injection Qualify the transmitter Flow
- System, Type D, Category 2 7)
Flew in FPl System 1)
Safety Injection Qualify the transmitter
- System,
?ype D, Category 2 E)
Ficw in 171 Syster 1)
Safety Inj ecti:n Cualify the transritter
- System,
?ine D, Category 2 9)
.v.akeup F1:w-2 1)
Che-ical and Vcl=e Qualify the transmitter Centrol Syste:
?yte D, Category 2 1
101 Letf vn Flow-Cut 1)
Che-ical and ';;1=e Qualify the transmitter Centrol Syste:
?ype D, Category 2 j
l 11)
Volume Centrol Tank 1)
Che-ical and Volure cualify the transmitter Level Control System Type D, Category 2 i
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Page 1 of 1 TABLE 3 VARIABLE FUNCION CCRRECTIVE ACTICN 1)
RCS Cold Leg Water 1)
Reactivity Control Change the present rance -
C Terper_ature Type B, Category 3 of 00 - 700 F to 500 - 7500F.
There is no scan change.
2)
Core Cooling hTe B, Category 1 2)
RCS Het Leg Water 1)
Core Cooling Change the presee Te:= erature Type B, Category 1 range of 00- 7 0.,
0 750 F.
Taere to 50 is no span change.
3)
Cuench Tank
- 1) Prirary Coolant Change the range Temperature System from 500 - 3000F to 500- 750 F.
0 Type D, Category 3 4)
Steam Generater 1)
Secondary System Change the range Pressure Type D, Category 2 from O - 109% of safeties to 1320 psig.
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Page 1 of 1 TABLE 4
_~ -
VARIABLE FUNCTION CORRECTIVE ACTICN 1)
Containment Atmos-1)
Containment Cooling Upgrade the phere. Temperature System indication loop.
Type D, Category 2 Replace the existing loop with a new one that meets the requirement.
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Page 1 of 1 TABLE 5 VARIABLE FUNCION CCRRECTIVE ACTION 1)
Radioactivity
- 1) Fuel Cladding Add new indication loops Conceneration on Type C, Category 1 Fadiation Level in Circulating Pri ary Coolant 2)
Radiation Exposure 1)
Containment Type C, Add new indication loops Rate (inside Category 2 (Monitors at the penetration buildings or area and the Fuel areas, e. g.,
Handling Budiding) auxiliary
- building, reactor shield building annulus, fuel handling building, which are in direct contact with prirary centainment where penetrations and hatches are located) 3)
- 1) Contain=ent Add new indication loops Flew Cooling Systems
?fpe D, Categcry 2 4)
Contai. ment Sump 1)
Centain:nent Coclina Add new indication locp Water Tercerature Systems Type 0, Catercri 2 5)
Heat re cval by 1)
Containment Cccline Add new indication leeps the Containment Fan Syste.s Heat Renoval System Type 2, Catercr/ 2 e
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,<n--
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD IntheMatt([of
)
)
PACIFIC GAS AND ELECTRIC COMPANY Docket Nos. 50-275 0.L.
50-323 0.L.
fDiablo Canyon Nuclear Power Plant uit Nos. 1 and 2
)
CERTIFICATE OF SERVICE I hereby certify that copies of NRC STAFF RESPONSE TO JOINT INTERVENORS' REVISED CONTENTION ON ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class or, as indicated by an asterisk, through deposit in the Nuclear Regulatory Commission's internal mail system, this 12th day of November, 1981.
John F. Wolf, Esq., Chairman Richard E. Blankenburg Administrative Judge Co-publisher Atomic Safety and Licensing Board Wayne A. Soroycn, News Reporter U.S. Nuclear Regulatory Commission South County Publishing Company Washington, D.C.
20555
- P.O. Box 460 Arroyo Grande, California 93420 Glenn 0. Bright, Esq.
Administrative Judge Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Washington, D.C.
20555
- Dr. Jerry Kline Mr. Gordon Silver Administrative Judge Mrs. Sandra A. Silver Atomic Safety and Licensing Board 1760 Alisal Street U.S. Nuclear Regulatory Commission San Luis Obispo, California 93401 Washington, D.C.
20555
- Arthur C. Gehr, Esq.
Elizabeth Apfelberg Snell & Wilmer 1415 Cozadero 3100 Valley Center San Luis Obispo, California 93401 Phoenix, Arizona 95073 Philip A. Crane, Jr., Esq.
Paul C. Valentine, Esq.
Pacific Gas and Electric Company 321 Lytton Avenue P.O. Box 7442 Palo Alto, California 94302 San Francisco, California 94120 Bruce Norton, Esq.
Mr. Frederick Eissler 3216 North 3rd Street Scenic Shoreline Preservation Suite 202 Conference, Inc.
Phoenix, Arizona 85012 4623 More Mesa Drive Santa Barbara, California 93105 Andrew Baldwin, Esq.
124 Spear Street Mrs. Raye Fleming San Francisco, California 94105 1920 Mattie Road Shell Beach, California 93449
Atomic Safety and Licensing Appeal
- ~
Panel
'~
Joel R. Reyriolds, Esq.
U.S. Nuclear Regulatory Commission John R. Phi flips, Esq.
Washington, D.C.
20555
- Center for Law in the Public Interest Atomic Safety and Licensing Board 10951 West Pico Boulevard Panel Third Floor U.S. Nuclear Regulatory Commission Los Angeles, CA 90064 Washington, D.C.
20555
- Byron S. Georgiou Docketing and Service Section Legal Affairs Secretary U.S. Nuclear Regulatory Commission Governor's Office Washington, D.C.
20555
- State Capitol Sacramento, California 95814 Mark Gottlieb California Energy Commission David S. Fleischaker, Esq.
MS-18 P.O. Box 1178 1111 Howe Avenue Oklahoma City, Oklahoma 73101 Sacramento, California 95825 Richard B. Hubbard MHB Technical Associates 1723 Hamilton Avenue - Suite K San Jose, California 95125 John Marrs, Managing Editor San Luis Obispo County Telegram-Tribune 1321 Johnson Avenue P.O. Box 112 San Luis Obispo, California 93406 Herbert H. Brown Hill, Christopher & Phillips, P.C.
1900 M Street, N.W.
Washington, D.C.
20036 Harry M. Willis Seymour & Willis 601 California St., Suite 2100 San Francisco, California 94108 Janice E. Kerr, Esq.
Lawrence Q. Carcia, Esq.
350 McAllister Street San Francisce, California 94102 f.
Mr. James O. Schuyler Nuclear Projects Engineer Bradley W. Jones Counsel for URC Staff Pacific Gas and Electric Company 77 Beale Street San Francisco, California 94106
-