ML17083B799
| ML17083B799 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 09/18/1986 |
| From: | Schierling H Office of Nuclear Reactor Regulation |
| To: | Harold Denton, Lyons J, Vollmer R NRC |
| Shared Package | |
| ML16341D906 | List: |
| References | |
| NUDOCS 8609220284 | |
| Download: ML17083B799 (22) | |
Text
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NUCLEAR REGULATORY COMMISSION '-'-
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'". Docket'os'.'0-275 and 50-323",l;;
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'.-. MEMORANDUM FOR:.,',
H, Denton>>:...,":.'..W.:.Houston F,. Rosa'-'.....;.
R. Vollmer>> '..", D;: Crutchfield V;"
Benaroya.-'.
Lyons*
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Clayton'.'hompson>>
v.'; Lainas
'..L. Rubenstein*
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- ..'..'-.",,::, ';, Miraglia>>'.x:.p.T.. Speis,.;:..
'.. G.. Lear
-;.~. ~'".,"i...'.;<:... :;:;.".R. Bernero~";.'-'.. W, Russell.".-...:
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oungblood
'-:" ':".,"":~"'r'-'"'"'. Holahan>>'""J.'ilhoan'"
S.'arga '
T..Novak ','.:'. Ballard" V. Noonan F. Schroeder C, Berlinger
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THRU Steven A
Varga" Director
': Project Directo'rate f3 Division of. PMR Licensing- ~
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')'OSURE 2
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Hans E. Schierling, Project Manager.'..:
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Division of PWR Licensing-A
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'UBJECT:
DAILY HIGHLIGHT - MEETING WITH PACIFIC GAS AND ELECTRIC COMPANY ON SPENT FUEL POOL Diablo Can on Nuclear'ower Plant':-'-'i"':.'
'"'..'?:: A"meeting will be'eld t'omorrow, Friday, September 19,: l986 with Pacific
'as and Electric Compa'ny to discu'ss in further detail the reinstallation of
...;the original racks into, the Unit.l spent fuel pool
- The meeting will begin at 9:00 a.m.r in Room P-422 and will.continue on Saturday; if necessary.
H. McGurren (OGC) was advised of the meeting in order to inform the parties of the rerack is'sue.
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THESE COPIES MUST BE HANDCARRIED
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ENCLOSURE 3
LIST OF MEETING ITEMS FROM TELEPHONE CALL ON SEPTEMBER 18, 1986
SEPTEMBER l8, I 986 CONFERENCE CALL ITEMS FOR MEETING Information Needed for Meetin I.
Provide a list of FSAR commitments and other corresponding documents (SSERs, PGBZ -
NRC correspondence, etc.)
related to racks in chronological order.
2.
Provide a description in chronological order of the types of seismic analysis and/or design basis for the rocks (e.g., DE, DDE, and Hosgri).
3.
Provide weld codes and welding procedures for welding related to the changes and the installation.
Identify specific aspects and provide the documents for staff review.
4.
Describe the seismic input used in the current analysis and spectra.
5.
What is the basis for the 4 kip uplift load?
Is it related to vertical accelerations?
6.
Provide weld attributes inspected and occeptonce criteria.
7.
Describe how as-built configurations were made and documented and how this infarmation was foctored into the calculations.
8.
Did any of the bearing plate welds overlap the embed plug weld orea?
If so, what is the effect on the embed or the weldment?
e y
9.
Describe those cells that did not pass 50 lb. drog fest.
What was done fo the cell such that it later passed?
IO.
Did PGandE consider localized buckling potential, overall t stability, C
localized high stresses?
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Discuss the quanlification of the embed for eccentric loading.
- Also, consider the case of two anchorage brockets on, the same embed.
l2.
Provide a stress table for all key rock elements.
Compare with FSAR criteria and provide ratios between criteria and actual values.
l3.
What was PGandE's response to NRC's 8/l3/73 letters item 9. I l4.
What was PGandE's response to NRC's I/4/74 question 9.4.
ENCLOSURE 4
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PGKE FSAR AMENDMENT 3 February 15, 1974 (pages 9.1-1 through 9.1-4)
(Items 1 and 3)
UNITED STATES OF AMERICA ATOMIC ENERGY COMMISSION Xn the Hatter of PACIFIC GAS AND ELECTRIC COMPANY
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Units 1 and 2 - Diablo Canyon Site
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Docket No. 50-275~L Docket Ho< 50-323-OL EHDIENT Pacific Gas and Electric Company hereby submits Amendment No.
3 to its application for an operating license for Units 1 and 2 at its Diablo Canyon Site.
This amendment responds in part to the requests for additional information transmitted to Pacific Gas and Electric Company in letters dated December 28, 1973 and Janu-ary 4, 1974, and includes other miscellaneous changes and correc-tions to the Final Safety Analysis Rcport.
Subscribed in San Francisco, California, this 15th day of February, 1974.
Respectfully submitted, PACIFIC,GAS AND ELECTRIC COMPANY By J ~ D. WORTHINGTON J. D. Worthington Senior Vice President FREDERICK T SRAIKS JOHN C HORRZSSEY PHILIP A CRANE, JR.
DENNIS C SULLIVAN By PHILIP Ae CRANE> JR+
Philip A. Crane, Jr.
Subscribed and sworn to before me this 15th day of February, 1974 TSEODORA COOKE s~)
Theodoza Cooke, Notary public in and for the City and County of San Francisco'tate of California Ny Ccganission expires January 28.
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9.0 AUXILIARYSYSTEMS 9.1 FUEL STORAGE AND HANDLING'.-
t The fuel storage and handling systems provide safe and effective means of storing, transporting, and handling new and irradiated nuclear fuel.
These systems mainly are located in the fuel handling areas of the Auxiliary Build-ing, ad)acent to the east valls of the containment structures.
Separate facilities are provided for each unit.
The Auxiliary Building is a Design Class I structure and Xs described in Chapter 3.
9.1.1 NEW FUEL STORAGE New fuel vill be stored in racks in vaults in the Auxiliary Building, located as shown in Figure 1.2-4 for Unit 1 and in Figure 1.2-10 for Unit 2.
The racks are designed to store, protect and prevent criticality of new fuel assemblies until used within the reactor.
Desi n Bases New fuel assemblies and RCC assemblies for each unit are stored in separate areas located to facilitate the unloading of new fuel assemblies and RCC assemblies from trucks.
The storage vaults are designed to hold new fuel assemblies in specially constructed racks and are utilized primarily for the P
storage of the one-third replacement cores.
The assemblies vhich make up the remainder of the first core are stored in the spent fuel pools vhich are avail-able for this use until the first refueling.
The design bases for the new fuel storage racks are as follows:
(1) Two racks provided for each unit villhold approximately one-third of a reactor core.
'2)
Racks are designed so that the fuel vill remain subcritical (k ff of less than 0.90) vith the vault flooded vith unborated vater.
(3) The racks are capable of maintaining horizontal center to center spacing of the fuel ele-ments under mLximum seismic shock (Double Design Earthquake),
and of support-ing the element vertically under maximum seismic shock.
9.1-1
S stem Desi There are tvo racks for,each unit.,
Each rack holds thirty-five assemblies, h rack is approximately nine feet six inches vide, thirteen feet long-and thirteen feet six inches high (excluding centering cones)
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Xt is built from type 304 stainless steel.
The ossemblies are in seven rows, five 'deep, and are spaced to have a center to center distance of twenty-two inches plus or ainus one thirty-second of an inch.
They are of 304 stainless steel and have a 'cone shaped top entrance 'to facilitate loading of fuel elements.
They are shaped in a nine inch square (cross section) hollow beam configuration, stan'ding upright.
They have e one inch thick "plastic" bearing plate et the base.
The nev fue1 storage racks are Design Class II, but are designed to Design Class I criteria in accordance vith Table 3.2-4.
Accordingly, the racks and the anchorage of racks to,the floor are designed for the DDE loading condition vith the racks filled vith fuel assemblies.
The seismic loads are determined from the time history, aodel superposition analysis of the Auxiliary Building.
The racks are designed to vithstand a vertical (uplift) force of 4000 lb.
in the unlikely event that an assembly vould bind in the reck vhile being lifted by the Spent Puel Bridge Crane.
The racks are located in the fuel handling area of the Auxiliary Building at e1evation 125.
Assembly access is from elevation 140.
One third of a core can be stored for each unit.
Before the first fueling, the other two-thirds vill be stored in the spent fuel racks.
Saf e Evaluation The storage racks ere designed in accordance vith the American Institute of Steel Construction, specifications for the Design, Fabrication, and Erection of Structural Steel for Buildings.
Amendment 3
9.1-2
{February 1974)
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Center-to center assembly spacing is held to one thirty-second, of an inch to assure a k f of less than 0.90, even, when. the vault is flooded with eff unborated.water.
After the racks.are installed, a dummy fuel. element 'is inserted jn each location and critical measurements taken toi assure proper arrangement and support.
A metal cap covers the top of the rack.
The holes in the cap line up with the guidance cones.
If a fuel assembly is acciden-tally dropped, it vi11 only be able to drop into a holder and could not drop into the space between fuel assemblies.
An accident analysis vill be found in Chapter 15.
9.1.2 SPENT HJEL STORAGE The spent fuel storage pool, shown in Figure 9.1-2, is the storage space for irradiated spent fuel from the reactor.
- This figure shows the spent fuel storage racks arrangement.
This pool is not required for any plant safety-related function.
Two pools are provided, one for each unit.
Desi n Bases The spent fuel pools are designed to accommodate fuel assemblies in a subcri-tical array such that a k ff < 0.9 is maintained.
They are constructed of reinforced concrete as part of the Auxiliary Building structure.
The design is described in Subsection 3.8.1.
The entire structure and the spent fuel racks have been designed in accordance with Design Class I seismic requirements.
Criteria set by Safety Guide 13 have been followed.
Gaseous radioactivity about the spent fuel storage pool is maintained below the 10 CFR 20 limits.
The spent fuel racks are designed to prevent insertion of a spent fuel assembly in other than a prescribed location.
S stem Desi The spent fuel storage pool is a reinforced concrete structure vith seam-welded stainless steel plate liner.
The pool volume is approximately 59,100 cubic feet.
Borated water is used to fill the pool at a concentration of approximately 2,000 ppm boron.
(February 1974) 9.1-3 Amendment 3
Racks for a total of 374 spent fuel assemblies can eventually be accommodated; initially, racks for 270 will be installed.
This allows for the concurrent. storage of a full core of irradiated fuel assemblies, and the normal quantity of spent fuel assemblies from the reactor during h refueling operation.
The spent fuel assemblies are stored in stainless steel storage racks in parallel rows having a center-to-center distance of 21 inches in both horizontal directions.
Rod cluster control assemblies and burnable poison rods requiring removal from the reactor are stored in the spent fuel assemblies.
The racks and the anchorage of racks to the floor are designed for the DDE loading condition with the racks filled with fuel assemblies.
The seismic loads are determined from the time history, modal superposition analysis of the Auxiliary Building.
The racks are designed to withstand a vertical (uplift) force of 4000 lbs.
in the unlikely event that an assembly would bind in the rack while being lifted by the Spent Fuel Bridge Crane.
Adjacent to the spent fuel storage pool is the stainless steel lined fuel transfer canal which is connected to the refueling cavity (inside. the containment).
A leaktight door is provided between the pool and the fuel transfer canal.
All components (handling tools, new fuel elevator, etc.) in contact with the spent fuel pool water are constructed of stainless steel.
Since all materials which are used in the construction of the spent fuel pool or are in contact with the pool water are stainless steel, material compatability is insured.
The borated water level in the pool is maintained to provide at least 10 ft of water above the tope of the active portion of a spent fuel assembly.
This water barrier serves as a radiation shield, limiting the gamma dose rate at the pool surface.
Amendment 3
9.1-4 (February 1974)
ENCLOSURE 5
NRC LETTER TO PG&E August 13, 1973 (Item 13)
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