ML20236F863
| ML20236F863 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon, 05000000 |
| Issue date: | 09/26/1975 |
| From: | Carroll J, Crane P, Lindblad W PACIFIC GAS & ELECTRIC CO. |
| To: | SAN LUIS OBISPO MOTHERS FOR PEACE |
| Shared Package | |
| ML20236A877 | List:
|
| References | |
| FOIA-87-214 NUDOCS 8708040055 | |
| Download: ML20236F863 (9) | |
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INITED STATES OF AMERICA hvCLEAR REGULATORY COMMISSIL.
BEFORE THE ATOMIC SAFETY AND LICENSING BOARD l
l In the Matter of
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PACIFIC GAS AND ELECTRIC COMPANY
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Docket Nos. 50-275-OL
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50-323-OL Units 1 and 2
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Diablo Canyon Site
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1 RESPONSES OF PACIFIC GAS AND ELECTRIC COMPANY.IO INTERROGATORIES FILED BY SAN LUIS OBISPO MOTHERS i
FOR PEACE DATED SEPTEMBER 12, 1975 (SPECIAL NUCLEAR MATERIALS).
I 1.
Please update response to question no. 2 of J. J. Forster, 6-27-75 Interrogatory.
RESPONSE
A.
An identification of such documents is contained in FSAR Appendix 2.5D, submitted to the USAEC (now USNRC) on October 31, 1974 as part of Amendment 19 to the Diablo Canyon application.
Additional documents authored by Dr. John A.
Blume, Mr. Douglas H, Hamilton, Dr. Richard H.
Jahns, and Dr. Stewart W. Smith in respcnse to USNRC questions dated February 12, 1975 are contained in FSAR Appendix 2.5E submitted with Amendments 31, 32, and 34 on August 15, August 19, and September 16, 1975, respectively.
B.
Investigations are presently being conducted _ for PGandE by Dr. John A. Blume to complete the response to the USNRC question 2.21 dated February.12, 1975.
The title of this investigation is "An Evaluation of the Maximum Credible Earthquake on the Hosgri Fault Zone and Associated Site Response Spectrum Comparisons."
In addition, a study dealing with earthquake source modeling is in progress with Dr. Stewart W.
Smith as principal investigator.
CONNORB7-214 PDR
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2.
Please update response to question no. 3 of J.
J.
Forster, 6-27-75 Interrogatory.
RESPONSE
The answer to this question dated July 18, 1975 as provided in
" Responses of Pacific Gas and Electric Company to Interrogatories i
Filed by Gordon A. Silver, Presumably on Behalf of John J.
- Forster, dated May 13, 1975" is unchanged.
3.
Please updata response to question no, 11 of J.
J.
Forster, 6-27-75 l
l Interrogatory.s
RESPONSE
Our previous response, dated June 27, 1975, is still accurate.
4.
Please update response to question no. 13 of J. J.
Forster, 6-27-75 Interrogatory.
RESPONSE
Unit 1 Unit 2 A.
Shipping of first fuel assembly 11/1/75 6/1/76 B.
Arrival on site of first fuel assembly 11/4/75 6/4/76 C.
Arrival on site of last fuel assembly 1/18/76 10/18/76 D.
Beginning of fuel loading 2/12/76 2/14/77 i
E.
Completion of fuel loading 2/28/76 3/1/77 F.
Criticality
' 1/76 3/2/77 G.
Synchronized and on line 8/76 8/77 (commercial operation)
The dates shown for Unit 1, items A, B,
and C, are those dates which could be met if a license in accordance with 10 CFR Part 70 is issued by the USNRC prior to 11/1/75.
Actual dates are dependent on receipt of this license.
5.
Identify with as much precision as possible, the route to be followed by trucks carrying Diablo-bound fresh fuel assemblies within Los Angeles County.
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RESPONSE
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The route has not yet been selected and we do not know whether the trucks will pass through Los Angeles County.
In any event the contention accepted for purposes of discovery is limited to local routes of transportation peculiar to the Diablo Canyon facility and widely used commercial routes are excluded.
(ASLB order dated July 23, 1974)
If the trucks do pass through Los Angeles County, it is anticipated that they will use one of the interstate highways.
6.
Please identify with specificity the type of defects and discrepancies that will possibly show up in the newly-arrived fresh fuel assemblies.
RESPONSE
On-site inspection of new fuel is intended to check for shipping I
or handling damage, to verify proper dimensions and cleanliness, and to verify that control rods will function properly with the.
I fuel assemblies.
7.
Do you know of any incident involving uranium fuel pellets in a cylindrical rod (inside a reactor or pile, or outside) involving l
commercial, military, naval, developmental, experimental, govern-mental, U.
S.
or foreign, etc. contexts, where some or all of the i
pellets spilled out of the rod or rods?
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A.
If yes, please identify situation and provide location and date.
l B.
For each such situation l
1.
Give U-235 enrichment 2.
Indicate if there was a criticality l
3.
If there was a criticality, please provide j
details, e.g.:
nature of moderator, if any, boron concentration, etc.
RESPONSE
A.
PGandE is not aware of any such incident which involved new unirradiated fuel.
B.
Not applicable.
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8.
Please answer Interrogatory 24, MFP, 7-18-75 or provide a relevant and acceptable objection.
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RESPONSE
PGandE objects to this interrogatory on the grounds it calls for information not relevant to this proceeding.
The contracts have i
no significance with respect to the health and safety of the public l
l arising out of receipt of nuclear fuel at the site.
9.
Please update PG&E response to Interrogatory 29 of MFP Interroga-tories dated June 19, 1975.
RESPONSE
There is no change in the answer to Interrogatory 29 except that arrangements have been made to store the fuel with Westinghouse through November 1975 rather than October 15, 1975.
The change should be made in the response to Interrogatory 28 as well.
I 10.
Please update PG&E response to Interrogatory 30 of MFP Interroga-tories dated June 19, 1975.
RESPONSE
Our response, dated July 18, 1975, is still accurate.
The trucking company has not yet been selected.
11.
Reference PG&E response to MFP June 19, 1975 Interrogatory 37.
Please identify PG&E personnel who reviewed cited document.
RESPONSE
This document was originally reviewed by Messrs. Barton W.
Shackelford, Gordon V.
- Richards, R. V.
Bettinger and W.
J.
Lindblad, during the construction permit application phase of the project.
It was subsequently reviewed by additional PGandE personnel involved in analysis and design of the facility.
12.
Reference PG&E response to MFP June 19, 1975 Interrogatory 39.
Please identify PG&E personnel who reviewed cited document.
RESPONSE
See response to Interrogatory 11.
13.
Reference PG&E response to MPP June 19, 1975 Interrogatory 43.'
Please answer this question as posed or provide legitimate objection.
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RESPONSE
The fresh and spent fuel racks were designed by Mr. Igor Sokoloff and the design was reviewed by Messrs. Arie B..Schuurman and Otto W.
Steinhardt.
The design and review of this design was accomplished under the supervision of R. V.
Bettinger, PGandE's Chief Civil Engineer.
The current address of the aforementioned individuals J
is 77 Beale Street, San Francisco, California 94106.
l 14.
Reference PG&E response to MFP June 19, 1975 Interrogatory 49.
Please answer Interrogatory 49 for the case of three fresh fuel l
assemblies of l
l A.
3.5% enrichment J
4 l
B.
3.1% enrichment
RESPONSE
for the most reactive geometry would be ThevalueofKgf 1
A.
e greater than 1 B.
The value of Keff for the most reactive geometry would be f
0.999.
15.
If the fresh fuel pellets were to spill out of several rods into a pile in a fresh water-filled pool would an effective multiplication factor greater than 1.0 obtain?
Assume 3.1%
RESPONSE
No.
16.
Reference Philip A.
Crane, Jr. letter to L.
C.
Rouse dated Aug-15, 1975.
Cited letter and attached Safety Evaluation makes no mention whatsoever of the consequences of an accident involving failure of several fresh fuel rods with attendant release of fuel pellets.
They could fall into a small container of unborated water.
A.
Is criticality categorically impossible?
l B.
Please provide basis for answer C.
Is criticality categorically impossible if they fall into a small container of water containing 4450 ppm boron?
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RESPONSE
A.
Yes.
A pile of 3.1% enriched uranium pellets submerged in water B.
will be under-moderated.
A critical assembly of pellets in j
water would require pellet-to-pellet spacing substantially the same as that which exists in a fuel assembly.
C.
Yes.
17.
Will the spent fuel pool per se (not the building above it) lose any of its functions if subjected to extended ground accelerations of A.
0.4g B.
0.5g
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0.6g D.
If yes to any of above, indicate which functions.
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RESPONSE
l A.
No.
B.
No.
C.
No.
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D.
Not applicable.
18.
Indicate the maximum sustained ground acceleration the spent fuel pool, filled with water, racks, and. full initial load of fresh fuel assemblies, can withstand without developing a water leak.
RESPONSE
The spent fuel pool, in the postulated configuration,.can with-stiind strong ground motion of 20 seconds duration with an associated peak ground acceleration in excess of 0.6g without sufficient water loss due to leaking and/or overtopping to result in an unacceptable storage condition.
19.
Reference Interrogatory 27B of MFP, June 19, 1975.
Please pro'ide v
answer to interrogatory.
Stated objection is not reasonable 6
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RESPONSE
The fuel for the two units would be dimensionally identical and would be interchangeable when new.
However, as explained.in the previous answer to Interrogatory 27, Unit 1 is scheduled to be loaded and in operation before the ' Unit 2 fuel is manufactured.
Thus, the fuel would no longer be interchangeable.due to enrichment changes in the Unit 1 fuel from use in the' reactor.
We declare under penalty of perjury. that the foregoing Responses To Interrogatories are true and correct to the best of our knowledge, information, and belief.
} Wil W Q; indblad g
James C. Carroll smu Project Engineer Supervising Steam Generation Units 1 and 2 Engineer Diablo Canyon Site Pacific Gas and Electric Company Respectfully submitted, JOHN C. MORRISSEY PHILIP A. CRANE, JR.
DENNIS C.
SULLIVAN BRUCE R. WORTHINGTON h
By Phili[1C Crane, Ur. -
Attorneys for Pacific Gas and Electric Company 77 Beale Street.
San Francisco, California 94106 415-781-4211 Dated:
September 26, 1975 7
I UNITED STATES OF AMERICA
. CLEAR REGUL7tTORY COMMISSI,.
i In the Matter of
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j
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PACIFIC GAS AND ELECTRIC COMPANY
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Docket Mos. 50-275-OL
)
50-323-OL Units 1 and 2
)
)
Diablo Canyon Site
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)
l CERTIFICATE OF SERVICE The foregoing document (s) of Pacific Gas and Electric Company hm (have) been served today on the following by deposit in the United l
States mail, properly stamped and addressed:
J l
l Mrs. Elizabeth E. Apfelberg Mr. John J.
Forster 1415 Cazadero C/o Mr. Gordon Silver l
San Luis Obispo, California 93401 5055 Radford Avenue
)
l North Hollywood, California 91607 James R. Tourtellotte, Esq.
Office of Executive Legal Director Director BETH 042 Division of Reactor Licensing U.
S.
Nuclear Regulatory Commission U.
S. Nuclear Regulatory Commission Washington, D. C. 20555 Washington, D.
C. 20555 l
l Elizabeth S.
Bowers, Esq.
Nathaniel H. Goodrich, Esq.
i l
Chairman Chairman l
Atomic Safety and Licensing Board Atomic Safety and Licensing U.
S.
Nuclear Regulatory Commission Board Panel l
Landow Building - Room 1209 U.
S.
Nuclear Regulatory Commission l
Washington, D.
C.
20555 Landow Building - Room 1209 Washington, D C.
20555 Mr. Glenn O.
Bright Atomic Safety and Licensing Board Dr. William E.
Martin l
U.
S.
Nuclear Regulatory Commission Atomic Safety and Licensing Board Landow Building - Room 1209 Senior Ecologist Washington, D. C.
20555 Battelle Memorial Institute Columbus, Ohio 43201 Mr. William P. Cornwell P. O.
Box 453 Alan S.
Rosenthal, Esq.
Morro Bay, California 93442 Chairman Atomic Safety and Licensing Mr. Frederich Eissler Appeal Panel Scenic Shoreline Preservation U.
S. Nuclear Regulatory Commission l
Conference, Inc.
Landow Building - Room 1209 l
4623 More Mesa Drive Washington, D.
C. 20555 l
Santa Barbara, California 93110 l
Secretary l
Ms. Raye Fleming U.
S. Nuclear Regulatory Commission l
1746 Chorro Street Washington, D. C. 20555 l
San Luis Obispo, California 93401 Attn.:
Docketing and Service Section
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Mrs. Sandra A.
Silver 5055 Rad ford Avenue North Hollywood, California 91607 Andrew Skaff, Esq.
1 Counsel Public Utilities Commission of the State of California l
5066 State Building San Francisco, California 94102 1
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ff Theodora Cooke Pacific Gas and Electric Company I
l Dated:
September 26, 1975 l
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