ML20210S965
| ML20210S965 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 10/06/1986 |
| From: | Mccall J PACIFIC GAS & ELECTRIC CO. |
| To: | Sierra Club |
| References | |
| CON-#486-0978, CON-#486-978 OLA, NUDOCS 8610080272 | |
| Download: ML20210S965 (23) | |
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. 00CMETED USHRC 1 UNITED STATES OF AMERICA -
NUCLEAR REGULATORY COMMISSION '86 BCT -6 P5 :08 2
~
3 BEFORE THE ATOMIC SAFETY AND LICENSING BOAR'D 4
) Docket Nos. 50-275 5 In the Matter of ) 50-323 - 0 0
)
6 PACIFIC GAS AND ELECTRIC COMPANY ) (Reracking of Spent Fuel Pools)
)
7 (Diablo Canyon Nuclear Power )
Plant Units 1 and 2) )
8 )
9 '
LICENSEE PACIFIC GAS AND ELECTRIC COMPANY'S 10 ANSHERS TO FIRST SET OF INTERROGATORIES OF THE SIERRA CLUB. DATED SEPTEMBER 15. 1986 11 12 13 INTERROGATORY NO. I:
14 15 Identify all records and documents relating to theoretical work 16 regarding the displacements of high density spent fuel racks at Diablo Canyon 17 resulting from hypothetical seismic excitation of the the spent fuel pools.
18 Such documents should include, but are not limited to, any reports of 19 calculations regarding:
20 21 1) the displacement of any rack toward a wall or another rack; 22 2) displacements resulting in collisions between a rack and a wall; 23 3) the nearest approach of a rack to a wall; 24 4) the presentation made by PGandE to the NRC at the meeting of 25 February 20, 1986; 26 5) the claim reported in the Safety Evaluation, Appendix A, l
8610090272 861006 j hDR ADOCK 05000275 PDR
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1 page 49, regarding rack displacements.
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3 RESPONSE TO INTERROGATORY NO. I:
4 5 Theoretical work related to displacements are contained in Documents 6 4, 7, 8, 9, 10, 11, 12, 13, 14, 16, 18, (Section 6), 19, 24, 27, 28, 29, 33, 7 35, 36, and 37, and Documents A, B, and E which are identified in Attachment I.
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10 INTERROGATORY NO. II:
11 12 Identify all records and documents relating to experimental studies 13 which serve to verify theoretical rack displacement calculations.
14 15 RESPONSE TO INTERROGATORY NO. II:
, 16 17 Experimental studies were not performed specifically to verify 18 theoretical calculations for the high density racks. However, related 19 experimental studies have been conducted which serve to verify portions of the 20 rack analysis they are contained in Documents 3, 17, and 22, and Document C i
l 21 which are identified in Attachment I.
22 23 24 INTERROGATORY NO. III:
25 l
26 Identify all records and documents relating to theoretical work l
1 regarding impact forces and/or fluid coupling forces exerted on spent fuel 2 racks as a result of interactions between racks or between a rack and a wall 3 in response to hypothetical seismic excitation of the spent fuel pools. Such 4 documents should include, but are not limited to, all reports of calculations 5 involving:
6 7 1) the forces on a rack arising from rack-rack interactions, 8 including collisions; 9 2) the forces on a rack arising from rack-wall interactions, ,
10 including collisions; 11 3) interaction forces reported or discussed by PGandE to the NRC at 12 the meeting of February 20, 1986; 13 4) the claim reported in the Safety Evaluation, Appendix A, page 49 14 regarding rack forces (" Safety Evaluation By The Office of 15 Nuclear Regulation Relating to the Reracking of the Spent Fuel 16 Pools At the Diablo Canyon Nuclear Power Plant, Units 1 and 2, 17 ..., " U.S.N.R.C., Washington, D.C., May 30, 1986.);
18 5) the claim made in the Safety Evaluation, Appendix A, page 24, 19 that the fluid. coupling method conservatively underestimates the 20 -
coupling forces.
21 22 RESPONSE TO INTERROGATORY NO. III:
23 24 Records and documents relating to theoretical work regarding impact 25 forces and/or fluid coupling forces exerted on the racks are included in 26 Documents 1, 4, 5, 6, 8, 9, 10, 13, 15, 16, 18, 20, 21, 22, 23, 24, 30, 34, i
i 1 36, and 37, and Documents A, B, D, and H (Chapter 9) which are identified in 2 Attachment I.
3 4
5 INTERROGATORY NO. IV:
6 7 Identify all records and documents relating to experimental studies 8 which serve to verify theoretical calculations regarding rack forces, 9 including impact and fluid coupling forces. .
10 11 RESPONSE TO INTERROGATORY NO. IV:
12 13 See response to Interrogatory No. II.
14 15 16 INTERROGATORY NO. V:
17 18 Identify all records and documents relating to theoretical analysis 19 of rack strength. Such documents should include, but are not limited to, 20 reports of calculations involving both impact loads and fluid coupling loads.
21 22 RESPONSE TO INTERROGATORY NO. V:
23 24 Records and documents relating to theoretical analysis or rack 25 strength are included in Documents 1, 2, 4, 5, 6, 11, 15, 18 (Part I and 26 Section 6), 20, 25, 26, 30, and 32, and Documents A, B, and E which are
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1 identified in Attachment I. ,
2 )
3 l 4 INTERROGATORY NO. VI:
5 6
Identify all records and documents relating to experimental studies 7
which serve to verify predicted rack strengths. Such documents should (
8 include, but are not limited to, reports of experiments involving both impact 9 loads and fluid coupling loads.
10 11 RESPONSE TO INTERROGATORY NO. VI:
12 13 See response to Interrogatory No. II.
14 15 16 INTERROGATORY NO. VII:
17 18 Identify all records and documents relating to the fluid coupling 19 coefficients used in.the time-history analysis, as discussed in section 6.2.3 20 of the Reracking Report.
("Reracking of Spent Fuel Pools Diablo Canyon 21 Units 1 and 2", PGandE, September,1985.) Such documents should include, but 22 are not limited to, reports of calculations involving:
23 24 1) a complete description of the fluid coupling coefficients; 25 2) the theoretical derivation of the fluid coupling coefficients; 26 3) experimental verification of the fluid coupling coefficients; 4
I 1 4) limiting values attained by the fluid coupling coefficients 2 during time-history analysis of rack behavior during seismic 3 excitation.
4 5 RESPONSE TO INTERROGATORY NO. VII:
6 7 Records and documents relating to fluid coupling coefficients are 8 included in Documents 5, 16, 18, and 37, and Documents A, B, and H which are 9 identified in Attachment I. .
10 11 12 INTERROGATORY NO. VIII:
13 14 Identify all records and documents relating to theoretical analysis 15 of the fluid coupling between racks.
16 17 RESPONSE TO INTERROGATORY NO. VIII:
18 19 Records and documents related to fluid coupling between racks are 20 included in Documents 4, 5, and 15 through 24, and cited in Document H which 1
I 21 are identified in Attachment I.
22 23 24 INTERROGATORY NO. IX:
25 26 Identify all records and documents relating to experimental studies 1
{
1 performed to verify the theoret.ical analysis of fluid coupling between racks.
2 l 3
RESPONSE TO INTERROGATORY NO. IX:
4 5
See response to Interrogatory No. II.
6 7
8 INTERROGATORY NO. X:
9 10 -
Identify all records and documents relating to theoretical analysis 11 of fluid coupling between a fuel rack and a wall of the spent fuel pool.
12 13 RESPONSE TO INTERROGATORY NO. X:
14 15 See response to Interrogatory No. VIII. Additional references are 16 provided in Documents A and B which are identified in Attachment I.
17 18 19 INTERROGATORY NO. XI:
20 21 Identify all records and documents relating to experimental studies 22 performed to verify the theoretical analysis of fluid coupling between a rack 23 and a wall.
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1 RESPONSE TO INTERROGATORY NO. XI:
2 3
See response to Interrogatory No. II.
4 5
6 INTERROGATORY NO. XII:
7 8
Identify all records and documents relating to the density of the 9
racks and/or the bouyant force on racks under water.
Such documents should -
10 include, but are not limited to, any discussion of the effect of rack bouyancy 11 on rack behavior during seismic excitation.
12 i
13 RESPONSE TO INTERROGATORY NO. XII: !
14 15 The documents used for analysis of the racks are included as 16 Documents 4, 5, and 15 through 24 which are identified in Attachment I.
17 18 19 INTERROGATORY NO. XIII:
20 21 Identify all records and documents relating to the velocity 22 dependence of the coefficient of friction between stainless steels.
23 24 RESPONSE TO INTERROGATORY NO. XIII:
25 26 Documents relating to the velocity dependence of the coefficient of
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1 friction between stainless st, eels are Document 3 and Document C which are 2
identified in Attachment I.
3 4
5 INTERROGATORY NO. XIV:
6 7
Identify all records and documents relating to the time during which 8
a rack may be in contact with another rack during a collision with another 9
rack or in contact with a wall during a rack-wall collision. Such documents -
10 should include, but are not limited to, reports of calculations involving:
11 12 1) velocity and/or displacement time-histories for racks undergoing 13 collisions; 14 2) typical or average times during which a rack is expected to be 15 in contact with another rack or with a wall during a collision.
16 17 RESPONSE TO INTERROGATORY NO. XIV:
18 19 During time history analyses, displacements are computed at each time 20 step; however, only maximum values for the entire event are stored and 21 printed. Therefore, no detailed results are included herein.
See Documents 22 15 and 20 and Document E which are identified in Attachment I.
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l 1 INTERROGATORY NO. XV: -
2 3 Identify all records and documents relating to the possibility of 4 and/or consequences of two or more racks colliding with a third rack or with a 5 wall. Such documents should include, but are not limited to, reports of 6 calculations involving:
7 8 1) the frequency of such three-body collisions; 9 2) typical velocity and/or displacement time-histories of such _
10 collisions; 11 3) maximum impact and fluid coupling loads on racks involved in 12 multiple collisions.
13 14 RESPONSE TO INTERROGATORY NO. XV:
15 16 The possibility of two or more racks colliding with a third rack or 17 with a wall is discussed in Documents 15, 22, and 37, and Document B which are 18 identified in ^ttachment I.
19 20 --
21 INTERROGATORY NO. XVI:
22 23 It appears from the Reracking Report that the time-history analyses 24 performed assume that a rack will collide with another rack "out of phase" 25 whenever it has moved a distance of 0.125 inches relative to the pool floor 26 from its equilibrium position. In other words, it appears that the
1 time-history analyses assume as a constraint that the maximum displacement of 2 a rack relative to the pool floor is 0.125 inches. Is it true that such a 3 assumption was made for the purposes of the time-history analyses?
4 5 RESPONSE TO INTERROGATORY NO. XVI:
6 7 Such an assumption was not made. The assumption is that for a rack 8 adjacent to another rack, the free movement is 0.125" before any force 9 develops in the gap element (simulating the adjacent rack). Thesubseduent .
10 compression of the gap element yields the value of the developed impact 11 force. There is no absolute constraint imposed except when contact occurs 12 with the stiff non-linear spring (gap element).
13 14 15 INTERROGATORY NO. XVII:
16 17 If the assumption in XVI was made, identify all records and documents 18 relating to the verification of the validity of this assumption. Such 19 documents should include, but are not limited to, reports of calculations 20 involving-the change in the average separation between racks during seismic 21 activity.
22 23 RESPONSE TO INTERROGATORY NO. XVII:
24 25' Not applicable based on the response to Interrogatory No. XVI.
26
1 INTERROGATORY NO. XVIII:
- 2 3 If the assumption discussed in XVI was made, identify all reports and 4 documents relating to the examination of the consequences of this assumption.
5 Such documents should'includo, but are not limited to, reports of calculations 6 involving the effect of changes in the value of 0.125 inches on rack behavior, 7 including rack velocity, maximum impact loading and maximum fluid coupling 8 loads. ,
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10 RESPONSE TO INTERROGATORY NO. XVIII:
11 12 Not applicable based on response to Interrogatory No. XVI.
13 14 15 INTERROGATORY NO. XIX:
16 17 If the assumption discussed in XVI was not made, describe when and 18 where collisions between racks are expected to occur in the time-history 19 analyses.
20 --
21 RESPONSE _TO INTERROGATORY NO. XIX:
22 23 Collisions occur at corners of racks (nearly always at top of racks l
24 where girdle bars are present). Tables in Document 18, Section 6 25 (Attachment I) , provide a listing of maximum values. Each computer output 26 presents a summary of maximum impact forces occurring on each non-linear 1
1 spring element and the time step where it occurs. Documents 15 and 20 2 (Attachment I) also contain some information dealing with impact forces.
3 4
5 INTERROGATORY NO. XX:
6 7 Identify all records and documents containing evidence that sliding
- 8 and tilting motion will be contained within suitable geometric constraints 9 such as thermal clearances, and that any impact due to the clearances is _
10 incorporated.
11 12 RESPONSE TO INTERROGATORY NO. XX:
13 14 Document 19 (computer outputs) (Attachment I) provides details of the 15 maximum displacements for all racks studied. They are presented in a summary 16 table at the end of the computer printout. Document'18 (Attachment I) also 17 contains similar data in Section 6. All adjacent structures (walls, other
, 18 racks) are simulated by impact springs (gap elements) which have gaps that 19 reflect the assumed clearances. Other reports providing information on l
20 sliding-and tilting evaluations include Documents 1, 2, 15, 18, 20, and 31, 21 and Documents B, F, and G (Attachment I).
22 23 24 INTERROGATORY NO. XXI:
4 25 26 What equations of motions were used for the time-history analyses in
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1 the eight degree of freedom model? If the equations of motion were 2 transformed before being solved, give both the original and transformed 3 equations. All parameters in these equations should be fully identified.
4 5 RESPONSE TO INTERROGATORY NO. XXI:
6 7 Documents 16 and 18 (Attachment I) contain the derivation of the 8 equations of motion. All transformations of subsequent equations (matrix 9 manipulations, etc.) are carried out within the simulation code. _.
10 11 12 INTERROGATORY NO. XXII:
13 14 What is the maximum allowable impact force on a fuel assembly?
15 Identify all records and documents related to the experimental and/or 16 theoretical derivation of this value.
17 18 RESPONSE TO INTERROGATORY NO. XXII:
19 20 -Urknown.
21 22 23 INTERROGATORY NO. XXIII:
24 25 Identify all records and documents relating to the damage sustained 26 by a fuel element if the maximum allowable impact force is exceeded.
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1 RESPONSE TO INTERROGATORY NO. XXIII:
2 3 Unknown.
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1 FIRST SET OF INTERROGATORIES PROPOUNDED TO PACIFIC GAS AND ELECTRIC COMPANY 2 BY THE SIERRA CLUB 3
4 5 I have assisted in preparing the answers to Interrogatory Nos. I 6 through XXIII. Said answers are true and correct to the best of my 7 knowledge and belief.
8 9
10 12 J6HN K. McCALL \
1.s
'14 15 16 17 18 Subscribed and sworn to 19 before me this 3rd day 20 of October, 1986 21 22 fumM 23 Tancy in and forJ.the Lemaster, City and County Notary Public{Q 24 of San Francisco, State of .
California ..
25 26 My Commission exoires April 27, 1990 emumintimntinustusmittimillfittm,kminheimiiHmt!!IlN I OFFICIAL SEAL NANCY J. LEMASTER P
d -@* ?,3'. NOTARf PU8 tlc.CAUFORN64 y .'P/ CITY & COUNTY OF SAN FRANCISCO
-tb-y My Commission Expires April 27,1M 1stian;auluulmuummr
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Attachment I i
1 List of Documents Produced Interroaatory 2
3 1. NRC Policy Paper on Study on Significant Hazards SC-III, XX, V (SECY-83-337), August 15, 1983 4
5 2. NRC Guidance Paper on Review and Acceptance of SC-XX, V Spent Fuel Storage and Handling Applications, 6 April 14, 1978 7
- 3. Report to General Electric Nuclear Energy Programs SC-XIII 8 Division, E. Rabinowicz, (G.E. P.O. 529-CC084X),
November 23, 1977' 9 ,
10 4. " Seismic Response of a Free Standing Fuel Rack SC-I, III, V, Construction to 3-D Floor Motion," K. P. Singh VIII, XII 11 and A. I. Soler, Nuclear Engineering and Design 80, 1984, 315-329, January 1984 12 13 5. " Dynamic Coupling in a Closely Spaced Two-Body SC-III, V, VII, System Vibrating in a Liquid Medium: The Case VIII, X, XII 14 of Fuel Racks," K. P. Singh and A. I. Soler, Proc. of the Third Conference on Vibration in 15 Nuclear Plant-1982, (British Nuclear Energy Society (1983) 16 17 6. Reracking Meeting Notes, PGandE, December 11, 1985 SC-III, V 18
- 7. Memo on NRC Visit to Joseph Oat Corp., Camden, NJ, SC-I 19 PGandE, February 7, 1986 20
- 8. Reracking Meeting Notes, PGandE, February 24, 1986 SC-I, III 21 22 9. Telephone Call Record, H. Schierling and D. Jeng SC-I, III (NRC) to E. Connell et al. (PGandE), June 19, 1986 23 24 10. Telephone Call Record, D. Jeng and C. Herrick (NRC) SC-I, III to E. Connell et al. (PGandE), June 20, 1986 25 ///
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Attachment I 1 List of Documents Produced Interroaatory 2
3 11. Structural Evaluation of High Density Spent Fuel SC-V Racks for Diablo Canyon - Review Coments, dated I
4 February 13, 1986
.i 5
- 12. Draft Meeting Notes: Seismic Analysis Review - SC-I 6 High Density Fuel Racks, July 3, 1985 (3 copies) 7
- 13. Memos from E. Connell/S. Johnson to J. McCall/M. Yan SC-I, III 8 dated June 10, 1985, Re: Licensing (Reracking)
Report 9
10 14. Memo from A. Ariey to R. Shah (Oat), dated August 12, SC-I 1985 (Final Version of Item 12) 11 1
12 15. Joseph Oat Corporation Responses to Comments / Questions, SC-III, V, undated VIII, XII, XIV, 13 XV, XIX, XX 14
- 16. "Information Manual for DYNAHIS (Version for 800F SC-I, III, VII 4
15 Analysis)" Oat STD-28 Rev. 4, March 1, 1986 - VIII, XII, XXI (Proprietary) Computer Code listing removed 16 17 17. " Planning Study for Experimental Measurements and SC-II, VIII, Analytical Correlations of Fluid Drag of Fuel XII 18 Assemblies in Fuel Rack Storage Locations,"
K. P. Singh and T. L. Ng, November 1982 3
19 20 18. " Seismic Analysis of High Density Fuel Racks for SC-I, III, V, j Pacific Gas and Electric for Diablo Canyon Nuclear VII, VIII, XII, Power Station," Rev. 3, September 3, 1986, 21 XIX, XX, XXI
- A. Soler, TM #779 22 ///
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Attachment I 1 List of Documents Produced Interroaatorv
. 2 3 19. Computer Outputs from DYNAHIS simulations for Diablo SC-I, III, Canyon VIII, XII, XX 4
- a. ee01 j. aa003 5 b. ee02 k. aa004
- c. ee03 1. ac13aal 6 d. 3304 m. ac33ab
- e. ee05
- n. ac13ab 7 f. aa001 o. ac33b
- g. aa002 p. ac33aa 8 h. acorn 10 q tt04
- 1. acorn 12 r. tt15 9 '
- 20. J. Oat Corp. responses to comments / questions, SC-III, V, 10 Supp1 ment 1 VIII, XIV, XII, 1
XIV, XV, XIX, 11 XX l
12 21. Chapter 16, Mechanical Desian of Heat Exchanaers and SC-VIII, XII r Pressure Vessel Comoonents, by K. P. Singh and
- 13 A. I. Soler, Arctur.us Publishing, 1984.
14
- 22. Verification Runs on DYNAHIS, A. I. Soler, SC-III, VIII, 15 January 29, 1986, Solution of Test Problem #2, XII Oat Report TM-780.
16 17 23. Joseph Oat Corporation transmittal entitled SC-III, VIII,
" Copy of Items Reported in Other Documents," XII i 18 19 24. Copy of transparencies and notes by K. P. Singh SC-I, III, from presentation to NRC in Camden, N.J., VIII, XII l 20 February 20, 1986 21 25. High Density Racks Seismic Analysis Independent SC-V l Review, M. R. Khan, PGandE, undated I
22 23 26. J. Oat Corp. Letter to PGandE, May 9, 1986 SC-V I.
. 24 l 27. PGandE Memorandum on Spent Fuel Racks - Review of SC-I
- 25 J. Oat's Submittals, November 21, 1985 26 ///
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Attachment I 1 List of Documents Produced Interroaatory 2
3 28. PGandE Heeting Agenda for July 3, 1985 SC-I 4
- 29. PGandE Memorandum, Spent Fuel Pool High Density Racks, SC-I, III 5 Units 1 and 2, January 10, 1986 6
- 30. J. Oat Corp. responses to issu'es raised in Sierra Club SC-III, V 7 March 6, 1986 letter, May 5, 1986 8
- 31. Two memoranda, J. Oat Corp. to PGandE on NRC 0.T. SC-XX 9 Position Paper, undated. _
10 -
- 32. J. Oat Corp. Memorandum to PGandE on Preliminary SC-V 11 Calculations, September 3, 1986 12
- 33. J. Oat Corp. letter to PGandE, Bridge Plates, SC-I 13 April 4, 1986 14
- 34. Impact Analysis, undated SC-III 15 16 35. Sketch from J. Oat Corp. to PGandE, June 18, 1986 SC-I 17
- 36. Telephone conversations between J. Oat Corp. and SC-I, III 18 PGandE, March 8, 1985; March 19, 1985; August 9, 1985 19
- 37. Affidavit of NRC Consultant, R. Clyde Herrick, SC-I, III, VII, 20 June ~25, 1986 XV 21 ///
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Attachment I 1 List of Reference Documents Interroaatory
~
2 (Not Produced) 3 A. PGandE Reracking Report, DCL-85-306, September 19, 1986, 4 Section 6 SC-I, III, V, VII, X 5
6 B. NRC Safety Evaluation Report, May 30, 1986 Section 4 -
SC-I, III 7 Appendix A SC-I, III, V, VII, X, XV, 8 XX 9
C. " Friction Coefficients of Hater-Lubricated Stainless SC-XIII j 10 Steels for a Spent Fuel Rack Facility," E. Rabinowicz, November 5, 1976 11 12 D. "Effect of Liquids on Dynamic Motions of Immersed SC-III 4
Solids," R. Fritz, February 1972 13 14 E. PGandE Letter DCL-86-019, January 28, 1986 SC-I, V, XIV 15 F. PGandE Letter DCL-86-067, March 11, 1986 SC-XX 16 17 G. PGandE Letter DCL-86-108, April 24, 1986 SC-XX ;
. 18 2
H. A. S. Levy and J. Hilkinson, The Comoonent Element SC-III, VII,
, 19 Method in Dynamics, McGraw Hill, 1976 VIII through
! XIII.
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a T *en pruus fr cieONDENCE 00}$c" UNITED STATES OF AMERICA *a6 (c -6 P5 :08 NUCLEAR REGULATORY COMMISSION If0CNT e. gifbf
) Docket Nos. 50-275 In the htter of ) 50-323
)
PACIFIC GAS AND ELECTRIC COMPANY ) (Reracking of Spent Fuel Pools)
)
(Diablo Canyon Nuclear Power )
Plant Units 1 and 2) )
)
CERTIFICATE OF SERVICE I hereby certify that on October 3,1986, copies of the following -
documents in the above-captioned proceeding have been served on the following by deposit in the United States mail, first class: (1) LICENSEE PACIFIC GAS AND ELECTRIC COMPANY'S ANSWERS TO FIRST SET OF INTERROGATORIES OF THE SAN LUIS OBISPO MOTHERS FOR PEACE, DATED SEPTEMBER 15, 1986; (2) LICENSEE PACIFIC GAS AND ELECTRIC COMPANY'S ANSHERS TO FIRST SET OF INTERROGATORIES OF CONSUMERS ORGANIZED FOR DEFENSE OF ENVIRONMENTAL SAFETY, DATED SEPTEMBER 16, 1986; and (3) LICENSEE PACIFIC GAS AND ELECTRIC COMPANY'S ANSHERS TO FIRST SET OF INTERROGATORIES OF THE SIERRA CLUB, DATED SEPTEMBER 15, 1986. The production of documents associated with the interrogatories have been served on only those indicated by an asterisk.
B. Paul Cotter, Jr., Chairman Docketing and Service Branch Administrative Judge Office of the Secretary Atomic Safety and Licensing U.S. Nuclear Regulatory Commission Board Panel Hashington DC 20555 U.S. Nuclear Regulatory Commission 4350 East West Highway 4th Floor Bethesda MD 20814 Glenn O. Bright Lawrence Chandler, Esq.*
Administrative Judge Henry J. McGurren, Esq.
Atomic Safety and Licensing Office of Executive Legal Director Board Panel U.S. Nuclear Regulatory Commission i U.S. Nuclear Regulatory Commission Maryland National Bank Building 4350 East West Highway 4th Floor Room 9604 Bethesda MD 20814 7735 Old Georgetown Road Bethesda MD 20814 Dr. Jerry Harbour Lewis Shollenberger
> Administrative Judge Regional Counsel Atomic Safety and Licensing U.S. Nuclear Regulatory Commission Board Panel Region V U.S. Nuclear Regulatory Commission 1450 Maria Lane, Suite 210 4350 East Hest Highway 4th Floor Halnut Creek CA 94596 Bethesda MD 20814
9 Diablo Canyon Service List Atomic Safety and Licensing Diane M. Grueneich*
Board Panel Grueneich & Lowry U.S. Nuclear Regulatory Commission 345 Franklin Street Hashington DC 20555 San Francisco CA 94102 Atomic Safety and Licensing Jacquelyn Wheeler Appeal Board Panel 2455 Leona Street U.S. Nuclear Regulatory Commission San Luis Obispo CA 93401 Washington DC 20555 ,
Mr. Lee M. Gustafson C.O.D.E.S.
Pacific Gas and Electric Company 731 Pacific Street Suite #42 1726 M Street NH Suite 1100 San Luis Obispo CA 93401 Hashington DC 20036-4502 Managing Editor Janice E. Kerr, Esq. San Luis Obisoo County Public Utilities Commission Telearam-Tribune 5246 State Building 1321 Johnson Avenue 350 McAllister Street San Luis Obispo CA 93406 San Francisco CA 94102 Richard E. Blankenburg Nancy Culver, Co-publisher 192 Luneta Street Hayne A. Soroyan, News Reporter San Luis Obispo CA 93401 South County Publishing Company P. O. Box 460 Arroyo Grande CA 93420 Dr. Richard Ferguson*
Vice-Chairman Sierra Club Rocky Canyon Star Route Creston CA 93432
/6/
Richard F. Locke Pacific Gas and Electric Company 77 Beale Street. 31st Floor San Francisco, CA 94106 Dated at San Francisco, California, this 3rd day of October,1986.
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