ML20206K265
| ML20206K265 | |
| Person / Time | |
|---|---|
| Site: | 07201008 |
| Issue date: | 05/10/1999 |
| From: | Bland D SOUTHERN NUCLEAR OPERATING CO. |
| To: | Hoyle J NRC OFFICE OF THE SECRETARY (SECY) |
| References | |
| FRN-64FR1542, RULE-PR-72 64FR1542-00010, 64FR1542-10, TAC-L22019, NUDOCS 9905130112 | |
| Download: ML20206K265 (148) | |
Text
,
/0 Southern Nuclect o
Operating Company,Inc.
40 invemess Center Parkway 00C r,,... 0
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Post Off ce Box 1295
[j$l *,s C Birmingham. Alabama 35201 99 MY 11 P3 :12 g
SOUTHERN L ox COMPANY S
Energy to Serve %r World' add i
BY OVERNIGIIT MAIL May 10,1999 DOCKET NUMBER PROPOSED RULE N 7,2.
Mr. John C. Hoyle Secretary of the Commission (7,yggjgg")
U. S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Attention: Rulemaking and Adjudications StatT
Subject:
Proposed Rulemaking to 10 CFR 72.214, List of Approved Spent Fuel Storage Casks (Federal Register Vol. 64, No. 6 - January 11,1999),
Holtec Users' Group Public Comment Letter No. 5030-2.
References:
- 1. Docket No. 72-1008, TAC L22019
- 2. Holtec International Report No. HI-951184, TopicalSafety Analysis Report for the Holtec International Storage Transport And Repository Cask System (Ill-STAR 100 Cask System, Revision 9).
- 3. Preliminary Safety Evaluation Report and Proposed Certificate of Compliance for the Holtec Hi-STAR 100 Cask System, dated December 15,1999.
- 4. HUG comment letter dated March 24,1999, Proposed Rulemaking to 10 CFR 72.214 regarding HI-STAR 100 inclusion.
/
Dear Mr. Hoyle,
130002 Though the deadline for public comments has passed, the group of utilities comprising the Holtec Users' Group (HUG) have continued to perform a detailed review of the proposed Technical Specifications contained within the above-referenced rulemaking for the HI STAR 100 System. Moreover, we have attempted to consider how the NRC Staff might resolve the comments contained in Reference 4, made during the public comment period, to allow for a recognition of the more important near-term items that were g51g112990510 l
72 64FR1542 PDR 35\\Q
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addressed..It is to that end that we submit the following for NRC consideration during j
1the resolution period.
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1 Attachment A, which follows, includes a hand marked-up copy of the proposed Technical f
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- Specifications as published in' Reference 3. Modification of the Technical Specifications, as indicated, would only ensure that the requirements can be implemented by the users.
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- These changes would not resolve all of the comments submitted in the original public j
- comment period. In some cases, the changes have been so significant that a mark-up of
.-the existing Specification would likely have been difficult to follow. In those cases,
- clean, newly typed pages have been included for clarity.
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Attachment B, also included, describes the previous public comment being addressed and a short de~ cription of the method of resolution.
s Please contact me at (205) 992-6697 if you have any questions or require additional
)
information.
i Sincerely,
/
~ David W. Bland Chairman, Holtec Users' Group Attachments L Cc:
M. Delligatti,'USNRC (w/ attachments)'
J. Shea, USNRC (w/ attachments)
. D. Harrison, NYPA (w/ attachments).
J. Reiss, Commonwealth Edison (w/ attachments)
' M. DeLong, PFS (w/ attachments)
? S. Miller, Yankee Atomic (w/ attachments)
D. Larkin, WPPSS (w/ attachments).
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ATTACHMENT r
Hl-STAR 100 SYSTEM TSAR f
TECHNICAL SPECIFICATION AND BASES
' FOR THE HOLTEC Hl-STAR 100 SPENT FUEL STORAGE CASK SYSTEM j.
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-TABLE OF CONTENTS m.
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~ 1.1 Definitions -
1.1-1 i
,1.0 USE AND APPLICATION-1.1-1 1.2 Logical Connectors 1.2-1 1.3 Completion Times.
1.3-1 1.4 Frequency.
1.4-1
- 2.0 :
. FUNCTIONAL AND OPERATIONAL LIMITS-2.0-1
. 2.1 Functional and Operating Limits 2.0-1
.2.2
. Functional and Operational Limits Violations
'2.0-2 3.0 LIMITING CONDITION FOR OPERATION (LCO)
APPLICABILITY 3.0-1
. SURVEILLANCE REQUIREMENT (SR)
APPLICABILITY 3.0-2 3.1 SFCS Integrityg,gyme den /Mce (mPc) 3.1.1-1 3.1.1 YPO 0;V,t, Vm,uu n vrying Fivwdwe 3.1.1-1 3.1.2 OVERPACK.^=
- V;cuum Oryir.;; Pr;;es,e 3.1.2-1
- ? 12 :
upc vem e;;i;r;;l 36u,,iy 3,;,3-1 11'
?!E ?.^C. Annulu; M;."U.-, CodT,;; i;;;u o
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3.4.5 Mr0 ll..uin Lean Rate 3.1.3-1
?M Ouggoa.cie :;;;;;m L;;3 rs;;;
-e4 3.1.T3 SFSC Lifting Requirements 3.1.7-1 3.1.g8/
Fuel Cool-Down 3.1.8 3.2 SFSC Radiation Protection 3.2.1-1
- 3.2 1 OVERPACK Average Surface Dose Rates 3.2.1-1 3.2.2 -
SFSC Surface Contamination 3.2.2-1 a
Table 3-1 1 MPC Model-Dependent Limits 3.3-1 4.0 Design Features' 4.0-1 4.1 Site 4.0-1 l
- 4.2
_ Storage Features 4.0-1 4.3.
Codes and Standards 4.0-1 4.4 Site Specific Parameters and Analyses 4.0-7 4.5.
Design Specifications 4.0-8
- 4.6.
Training Module 4.0-9 4.7 Pre-Operational Testing and Training Exerci.,
4.0-10 4.8 Special Requirements for Fiv4 3ystem in Place 4.0-11
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Dsfinitions 1.1 b
1.0 USE AND APPLICATION 4
1.1 Definitions NOTE The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term Definition j
. ACTIONS ~
ACTIONS shall be that part of a Specification that 1
prescribes Required Actions to be taken under i
designated Conditions within specified Completion j
Times.
DAMAGED FUEL-DAMAGED FUEL ASSEMBLIES are fuel assemblies
- ASSEMBLY.
with known or suspected cladding defects greater than
. pinhole leaks or hairline cracks, missing fuel rods that are not replaced with dummy fuel rods, or those that cannot be handled bynormal means. Fuel assemblies which cannot be handlad by normal means due to fuel cladding damage are considered to be FUEL DEBRIS.
. DAMAGED FUEL DFCs are specially designed enclosures for CONTAINER DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS which permit gaseous and liquid media to escape while minimizing dispersal of gross particulates.
- FUEL DEBRIS FUEL DEBRIS is fuel with known or suspected defects, such as ruptured fuel rods, severed rods, or loose fuel pellets. Fuel assemblies which cannot be handled by normal means due to fuel cladding damage are considered to be FUEL DEBRIS.
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Datinitions l
1.1 1.1 Definitions q.Q)
INDEPENDENT SPENT FUEL The facility within the perimeter fence licensed STORAGE INSTALLATION for storage of spent fuel within SFSCs. (see also (ISFSI) 10 CFR 72.3)
INTACT FUEL ASSEMBLY INTACT FUEL ASSEMBLIES are fuel assemblies without known or suspected cladding defects greater than pinhole leaks or hairline cracks and which can be handled by normal means. Partial fuel assemblies, that is fuel assemblies from which fuel rods are missing, shall not be classified as INTACT FUEL ASSEMBLIES unless dummy fuel 1
rods are used to displace an amount of wategpqual to that displaced by the original fuel rod (s).
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LOADING OPERATIONS LOADING OPERATIONS include all licensed activities on an SFSC while it is being loaded with fuel assemblies. LOADING OPERATIONS begin 3
when the first fuel assembly is placed in the SFSC and and when the SFSC is suspended from or secured on the transporter.
MULTI-PURPOSE CANISTER MPCs are the sealed spent nuclear fuel canisters (MPC) which consist of a honeycombed fuel basket 4
c'ontained in a cylindrical canister shell which is welded to a baseplate, lid with welded port cover plates, and closure ring. The MPC provides the confinement boundary for the contained radioactive materials.
OVERPACK OVERPACKs are the casks which receive and
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contain the sealed MPCs. They provide the helium retention boundary, gamma and neutron shielding, and a set each of lifting and pocket trunnions for handling.
PLANAR-AVERAGE -
PLANAR AVERAGE INITIAL ENRICHMENT is the
' INITIAL ENRICHMENT average of the distributed fuel rod initial enrichments within a given axial plane of the assembly lattice.
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1.1-2 l
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D2finitions 1.1
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.1.1 Def;nitions SFSCs are storage containers approved for SPENT FUEL STORAGE CASKS (SFSCs)-
casks of spent fuel assemblies at the ISFSI. The HI-STAR 100 SFSC System consists of the OVERPACK and its integral MPC.
- STORAGE OPERATIONS STORAGE OPERATIONS include all licensed activities that are performed at the ISFSI while an SFS.C containing spent fuel is sitting on a storage pad within the ISFSI perimeter.
TRANSPORT OPERATIONS TRANSPORT OPERATIONS include all licensed -
i TRANSPORT OPERATIONS begin when the SFSC l
is first suspended from or secured on the transporter and end when the SFSC is at its
~ destination and no longer suspended from the transporter.
UNLOADING OPERATIONS UNLOADING OPERATIONS include alllicensed activities on an SFSC to be unloaded of the contained fuel assemblies. UNLOADING OPERATIONS begin when the SFSC is no longer
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suspended from or secured on the transporter and end when the last fuel assembly is removed from the SFSC.
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1.1-3
Logical Connectors 1.2 21.01USE AND APPLICATION
- 44. --
11.2 Logical Connectors
- PURPOSE:
The purpose of this section is to explain the meaning of logical -
connectors.
Logical connectors are used in Technical Specifications (TS) to ~
~ discriminate between, and yet connect, discrete Conditions, -
' Required Actions, Completion Times, Surveillances, and o
Frequencies. The only logical connectors that appear in TS are AND and QB. The physical arrangement of these connectors constitutes logical conventions with specific meanings.
' BACKGROUND' Severallevels of logic may be used to state Required Actions.
These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justifieci with
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the number of the Required Action). The successive levels oflogic -
are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.
When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of -
the Condition, Completion Time, Surveillance, or Frequency.
EXAMPLES The following examples illustrate the use of logical connectors.
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n Logical Connectors 1.2
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1.2. Logical Connectors.
EXAMPLES-
. EXAMPLE 1.2-1 (continued)
^ ACTIONS.
CONDITION.
REQUIRED ACTION COMPLETION TIME A. LCO not met.-~
A.1 Verify...
AND A.2 Restore '..
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1 ie in this example the logical connector AND is used to indicate that 3,
when in Condition A, both Required Actions A.1 and A.2 must be
- completed.
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E Logical Connsciors
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1.2
-1.2 LogicalConnectors EXAMPLES
' EXAMPLE 1.2-2
- (continued)
ACTIONS.
CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met.
A.1 Stop...
OB A.2.1 Verify.
ANQ A.2.2.1 Reduce.,.
QB i
A.2.2.2 Perform.
DB A.3 Remove..
This example represents a more complicated use of logical connectors. Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector QB and the left justified placement.
Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector ANR. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector
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- L 1.2-3
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Logical Conn:ctors 12
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- 1.2 ' Logical Connectors ~
EXAMPLES EXAMPLE 1.2-2 (continued) l
.QB indicates that A.2.2.1 and A.2.2.2 are alternative choices, only.
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one of which must be performed.
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Completion Tim:s y
1.3
.g g] p 1.0 USE AND APPLICATION g
1.3 CompletionTimes PURPOSE-The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.
i BACKGROUND Limiting Conditions for Operation (LCOs) specify the lowest functional capability or performance levels cf equipment required for safe operation of the SFSC.. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action (s) and Completion Times (s).
DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, provided that the SFCS is in a specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. - An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the SFSC is not within the LCO
. Applicability.
Once a Condition has been entered, subsequent subsystems, components, or variables expressed in the Condition, discovered to be not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.
d' 1.3-1
r-Compistion Times 1,3 1.3 Completion Times (continued)
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EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
EXAMPLE 1.3-1 ACTIONS
. CONDITION
- REQUIRED ACTION COMPLETION TIME '
B. Required B.1 Perform Action B.1 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action and '-
associated M
Completion Time not met.
B.2 Perform Action B.2 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
)
Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.
The Required Actions of Condition B are to complete action B.1 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> M complete action B.2 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. A total of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is allowed for completing action B.1 and a total of
-36 hours (not 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) is allowed for completing action B.2 from the time.that Condition B was entered. If action B.1 is completed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, the time allowed for completing action B.2 is the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> because the total time allowed for completing action B.2 is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
1.3-2
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U@mpletion times 1.3 t
.1.3 Completion Times Sh EXAMPLES EXAMPLE 1.3-2
. (continued)
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One system A.1 Restore system to 7 days not within-within limit.
limit.
B. Required B.1 Complete action 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Action and B.1.
associated Completion AblD Time not met.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> B.2 Complete action B.2.
When a system is determined not to meet the'LCO, Condition A is entered if the' system is not restored within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If.the system is restored after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.
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1.3-3
Complction Times 1.3, 1.3 Completion Times
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I EXAMPLES EXAMPLE 1.3 3 (continued)
ACTIONS -
NOTE Separate Condition entry is allowed for each component.
CONDITION REQUIRED ACTION -
COMPLETION TIME A. LCO not met.
A.1 Restore 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> compliance with LCO.
B. Required B.1 Complete action 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Action and B.1, associated AND j
Completion Time not met.
B.2 Complete action 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B.2 The~ Note above~the ACTIONS table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.
The Note allows Condition A to be entered separately for each
- component, and Completion Times tracked on a per component basis. When a component is determined to not meet the LCO, Condition A is entered and its Completion Time starts. If subsequent components are determined to not meet the LCO, Condition A is entered for each component and
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1.3-4
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Complation Times 1.3
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1.3. Completion Times EXAMPLES EXAMPLE 1.3-3 -(continued) 1 separate Completion Times start and are tracked for each component.
IMMEDIATE
. When "Immediately" is used as a Completion Time, the COMPLETION Required Action should be pursued without delay and in a TIME ~
controlled manner.
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Frequsncy 1.4 M'
1.0- USE AND APPLICATION A$
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1.4 Frequency '
PURPOSE The purpose of this section is to define the proper use and applicatior, of Frequency requirements.
DESCRIPTION '
Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated
. Limiting Condition for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.
The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement i
.(SR) Applicability. The "specified Fregi'ency" consists of the requirements of the Frequency column of each SR.
Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is 3
within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e. the Surveillance or the Frequency) is stated such that it is only " required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction, k
1.4-1
Frcqu ncy 1.4 1.4 Frequency Q
EXAMPLES The following examples illustrate the various ways that Frequencies are specified.
EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify pressure within limit 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an extension of the time interval to 1.25 times the s
interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment or variables are outside specified limits, or the facility is outside'the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the facility is in a condition specified in the Applicability of the LCO, the LCO is not met in accordance with SR 3.0.1.
If the interval as specified by SR 3.0.2 is exceeded while the facility is not in a condition specified in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the specified condition. Failure to do so would result in a i
violation of SR 3.0.4
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E Frequ::ncy 1.4
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. jff) 1.4 Frequency
.:.y EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Once within -
Verify flow is within limits.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to starting activity AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter i
Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in 4
Example 1.4-1. The logical connector "ANQ" indicates that both Frequency requirements must be met. Each time the example activity is to be performed, the Surveillance must be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to starting the activity.
The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").. This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2.
'u 1.4-3
Frcquency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)
"Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If the specified activity is canceled or not performed, the measurement of both intervals stops. New intervals start upon preparing to restart the specified activity.
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1.4-4
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Functional and Oparating Limits 2.0
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' I +h 2.0 FUNCTIONAL AND OPERATING LIMITS i 2.1 Functional and Operating Limits 2.1.1 Fuel To Be Stored In The HI-STAR 100 SFSC System INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, a. --
and FUEL DEBRIS meeting the limits specified in Table 2.1-1 may be stored in the Hi-STAR 100 SFSC System.
b.
For MPCs partially loaded with stainless steel clad fuel assemblies, all remaining fuel assemblies in the MPC shall meet the maximum decay heat generation limit for the stainless steel clad fuel assemblies.
For MPCs partially loaded with DAMAGED FUEL ASSEMBLIES or c.
FUEL DEBRIS, all remaining Zircaloy clad INTACT FUEL ASSEMBLIES in the MPC shall meet the maximum decay heat generation limits for the DAMAGED FUEL ASSEMBLIES.
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. d.
For MPC-68's partially loaded with array / class 6x6A,6x68,6x6C, or 8x8A fuel assemblies, all remaining Zircaloy clad INTACT FUEL ASSEMBLIES in the MPC shall meet the maximum decay heat
. generation limits for the 6x6A, 6x6B, 6x6C, and 8x8A fuel assemblies.
' 2.1.2 P_ referential Fuel Loadina Preferential fuel loading shall be used whenever fuel assemblies with significantly different post-irradiation cooling times (zone year) are to be loaded in the same MPC. That is fuel assemblies with the longest post-irradiation cooling times shall be loaded into fuel storage locations at the
. periphery of the basket. Fuel assemblies with shorter post-irradiation cooling times shall be placed toward the center of the basket.
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,f Functional and Operating Limits 2.0 b.h a - ;
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.2.2.
Functional and Operating Limits Violations If any Functional and Operating Limits of 2.1 are violated, the following actions shall be completed:
2.2.1 The~ affected fuel assemblies shall be placed in a safe' condition.
2.2.2 Within'24' hours, notify t'he NRC Operations Center.
- 2.2.3 Within 30 days, submit a special report which describes the cause of the' violation, and actions taken to restore compliance and prevent recurrence.
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Functional and Operating Limits 2.0 Ma) kfh i
Table 2.1-1 I
Fuel Assembly Limits
- l. MPC MODEL: MPC-24.
A. Allowable Contents 1.
Uranium oxide, PWR INTACT FUEL ASSEMBLIES listed in Table 2.1-2 and meeting the following specifications:
a.
Cladding Type:
Zircaloy (Zr) or Stainless Steel (SS) as specified in Table 2.1-2 for the applicable fuel assembly array / class -
b.
Initial Enrichment:
As specified in Table 2.1-2 for the applicable fuel assembly array / class.
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Functional and Operating Limits 2.0 0
- c. ' Decay' Heat Per Assembly:
i.~ Zr Clad:
An assembly decay heat as specified in Table 2.1-4 for the applicable post-irradiation cooling time.
ii. SS Clad:
5 575 Watts d.
Post-irradiation Cooling Time and Average Burnup Per Assembly:
- i. Zr Clad:
An assembly post-irradiation cooling time and average burnup as specified in Table 2.1-5.
ii. SS Clad:
An assembly post-irradiation cooling time 2 9 years and an average burnup s 30,000 MWD /MTU.
l DE An assembly post-irradiation cooling time 215 years and an average burnup 5 40,000 MWD /MTU.
- e. Nominal Fuel Assembly 5176.8 inches Length:
f.
Nominal Fuel Assembly 5 8.54 inches Width:
- g. Fuel Assembly Weight:
51,680 lbs 2.0-4 E:
l Functional and Optrating Limits 2.0
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- 8. Quantity per MPC: Up to 24 fuel assemblies.
C. Fuel assemblies shall not contain control components.
D. DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS are not authorized for loading into the MPC-24.
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2.0-5 e
Functional and Operating Limits 2.0
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II. - MPC MODEL MPC-68 A. Allowable' Contents
~
.j
or without Zircaloy channels, and meeting the following specifications:
{
- a. Cladding Type:
Zircaloy (Zr) or Stainless Steel (SS) as specified in Table 2.1-3 for the applicable fuel assembly array / class.
1
- b. Maximum PLANAR-As specified in Table 2.1-3 for the AVERAGE INITIAL applicable fuel assembly array / class.
)
ENRICHMENT:
- c. Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment:
applicable fuel assembly array / class.
- d. Decay Heat Per j
Assembly:
- i. Zr Clad:
An assembly decay heat as specified in Table 2.1-4 for the applicable post-irradiation cooling time, except for array / class 6x6A,6x6C,and.8x8A fuel assemblies, which shall have a decay heat 5115 Watts.
ii. SS Clad:
s 95 Watts D
2.0-6 u
fi:
Functional and Operating Limits 2.0
+...h e.
Post-irradiation.
CoolingTime and
/ Average Burnup Per JAssembly:
- i. Zr. Clad:
An assembly post-irradiation cooling time -
and average burnup as specified in Table 2.1-5, except for array / class 8x6A, 6x6C,
-l and 8x8A fuel assemblies, which shall have a cooling time 218 years and an' average burnup 5 30,000 MWD /MTU.
]
ii.- SS Clad:
An assembly cooling time after discharge 210 years and an average burnup 5 22,500 MWD /MTU.
f.
Nominal Fuel Assembly _
s 17S.2 inches s
. Length:
E
- g.
Nominal Fuel' Assembly =
. s 5.85 inches Width:
- h. - Fuel Assembly Weight:
5 700 lbs, including channels e
?b 2.0-7 S
6
.x x <
r Functional and Operating Limits h1 2.0 d
2.
Uranium oxide, BWR DAMAGED FUEL ASSEMBLIES', with or without Zircaloy channels, placed in DAMAGED FUEL' CONTAINERS. BWR DAMAGED FUEL' ASSEMBLIES shall meet the criteria specified in Table
~ 2.1-3 for fuel assembly array / class 6x6A, 6x6C, 7x7A, or 8x8A, and meet the following specifications:
- a. Cladding Type:
Zircaloy (Zr)
- b. Maximum PLANAR-As specified in Table 2.1-3 for the AVERAGE INITIAL applicable fuel assembly array / class, ENRICHMENT:
- c. Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment:
applicable fuel assembly array / class.
- d. Decay Heat Per s 115 Watts Assembly:
- e. Post-irradiation An assembly post-irradiation cooling time Cooling Time and
> 18 years and an average burnup 5 Average Burnup Per 30,000 MWD /MTU.
Assembly:
- f. Nominal Fuel Assembly 5135.0 in' hes c
Length:
- g. Nominal Fuel Assembly 5 4.70 inches Width:
- h. Fuel Assembly Weight:
s 400 lbs, including channels 4
s 2.0-8 i
w
=
Functional and Operating Limits 2.0
.e 5?h 31 Mixed oxide (MOX), BWR INTACT FUEL ASSEMBLIES, with or without Zircaloy channels. MOX BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array / class 6x6B, and meet the following specifications:
a.' Cladding Type:
Zircaloy (Zr)
- b. Maximum PLANAR-As specified in Table 2.1-3 for fuel AVERAGE INITIAL assembly array / class 6x68.
ENRICHMENT:
- c. Initial Maximum Rod As specified in Table 2.1-3 for fuel Enrichment:
assembly array / class 6x68.
- d. Decay Heat Per 5115 Watts Assembly;
- e. Post-irradiation An assembly post-irradiation cooling time Cooling Time and 218 years and an average burnup s Average Burnup Per 30,000 MWD /MTlHM.
Assembly:
- f. Nominal Fuel Assembly 5135.0 inches Length:
- g. Nominal Fuel Assembly 5 4.70 inches Width:
- h. Fuel Assembly Weight:
5400 lbs, including channels 2.0-9
(%,it.
e :.
Functional and Operating Limits O) 2.0 4.
Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. MOX BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array / class 6x68, and meet the following specifications:
a.
Cladding Type:
Zircaloy (Zr) b.
Maximum PLANAR-As specified in Table 2.1-3 for I
AVERAGE INITIAL array / class 6x68.
ENRICHMENT:
c.
Initial Maximum Rod As specified in Table 2.1-3 for Enrichment:
array / class 6x68.
d.
Decay Heat Per s 115 Watts l
Assembly:
{
i
- e. Post-irradiation An assembly post-irradiation j
Cooling Time and cooling time > 18 years and an
)
{
Average Burnup Per average burnup 5 30,000 l
Assembly:
MWD /MTlHM.
.)
j
- f. Nominal Fuel Assembly 5135.0 inches Length:
)
i
- g. Nominal Fuel Assembly 5 4.70 inches Width
- h. Fuel Assembly Weight:
s 400 lbs, including channels B. Quantity per MPC: Up to 68 INTACT FUEL ASSEMBLIES or DAMAGED FUEL ASSEMBLIES in DAMAGED FUEL CONTAINERS.
C. Fuel assemblies with stainless steel channels are not authorized for loading in the MPC-68.
2.0-10 a
ir j
Functional and Operating Limits l
2.0
$kIk)
..w 111. MPC MODEL: MPC-68F
' A. Allowable Contents 1.
Uranium oxide, BWR INTACT FUEL ASSEMBLIES, with or without Zircaloy channels. BWR INTACT FUEL ASSEMBLIES shall meet the criteria in Table 2.1-3 for fuel assembly array class 6x6A,6x6C,7x7A or
]
8x8A, and meet the following specifications:
j
- a. Cladding Type:
Zircaloy (Zr) b.
Maximum PLANAR-As specified in Table 2.1-3 for the AVERAGE INITIAL applicable fuel assembly array / class.
ENRICHMENT:
j c.
Initial Maximum Rod As specified in Table 2.1-3 for the l
Enrichment:
applicable fuel assembly array / class.
{
- d. Decay Heat Per 5115 Watts.
Assembly:
l
- e. Post-irradiation An assembly post-irradiation cooling Cooling Time and time > 18 years and an average burnup Average Burnup Per s 30,000 MWD /MTU.
Assembly:
- f. Nominal Fuel Assembly
. 5176.2 inches Length:
- g. Nominal Fuel Assembly 5 5.85 inches Width:
- h. Fuel Assembly Weight:
5 700 lbs, including channels g.h 2.0-11 e
Functional and Operating Limits 2.0
Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array / class 6x6A,6x6C,7x7A, or 8x8A, and meet the following specifications;
- a. Cladding Type:
I;rcaloy (Zr)
- b. Maximum PLANAR-As specified in Table 2.1-3 for the AVERAGE INITIAL applicable fuel assembly array / class.
ENRICHMENT:
- c. Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment:
applicable fuel assembly array / class.
- d. Decay Heat Per 5115 Watts Assembly;
- e. Post-irradiation A post-irradiation cooling time after Cooling Time and discharge > 18 years and an average Average Burnup Per burnup 5 30,000 MWD /MTU.
)
Assembly:
f.
Nominal Fuel Assembly 5135.0 inches Length:
- g. Nominal Fuel Assembly 5 4.70 inches Width-1 i
- h. Fuel Assembly Weight:
5 400 lbs, including channels
)
j I
l 2.0-12 O
D1 l-1 i.
,_ v Functional and Op3 rating Limits s
2.0 i
i-
- 3. Uranium oxide, BWR FUEL DEBRIS, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the BWR FUEL DEBRIS shall meet the criteria specified in. Table 2.1-3 for fuel assembly array / class 6x6A, 6x6C, 7x7A, or 8x8A, and meet the following t
specifications:
l a.
Cladding Type:
Zircaloy (Zr) b.
Maximum PLANAR- -
As specified in Table 2.1-3 for the
' AVERAGE INITIAL applicable original fuel assembly ENRICHMENT:
array / class.
c.
Initial Maximum Rod As specified in Table 2.1-3 for the Enrichment; applicable original fuel assembly _
array / class.
d.-
Decay Heat Per s 115 Watts DFC:
i e.
Post-irradiation A post-irradiation cooling time after Cooling Time and -
discharge 218 years and an average
. Average Burnup Per bumup 5 30,000 MWD /MTU for the Assembly; original fuel assembly.
f.
. Nominal Original Fuel
< 135.0 inches Assembly Length:
g.
Nominal Original Fuel s 4.70 inches Assembly Width:
h.
Fuel Debris Weight:
5400 lbs, including channels f
4 2.0-13 j%SV I'
t
c; Functional and Operating Limits 2.0 ib,.
4..
Mixed oxide (MOX), BWR INTACT FUEL ASSEMBLIES, with or without Zircaloy channels.- MOX BWR INTACT FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for fuel assembly array / class 6x68, and meet the following specifications:
a.'
Cladding Type:
Zircaloy (Zr) b.
Maximum PLANAR-As specified in Table 2.1-3 for fuel AVERAGE INITIAL ~
assembly array / class 6x68.
ENRICHMENT: -
. c.
Initial Maximum Rod LAs specified in Table 2.1-3 for fuel Enrichment:
assembly array / class 6x6B.
~ d.
Decay Heat Per ~-
5115 Watts
. Assembly:
- e. : Post-irradiation An assembly post-irradiation cooling Cooling Time and time after discharge 218 years and an Average Burnup Per average bumup 5 30,000 Assembly:
MWD /MTlHM.-
^'
f.
Nominal Fuel Assembiy 5135.0 inches Length:
g.
Nominal Fuel Assembly 5 4.70 inches Width:
h.
Fuel Assembly Weight:
s 400 lbs, including channels 2.0-14 s!
Functional and Op3 rating Limits S
2.0 4
!h-
- 5. Mixed oxide (MOX), BWR DAMAGED FUEL ASSEMBLIES, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. MOX BWR DAMAGED FUEL ASSEMBLIES shall meet the criteria specified in Table 2.1-3 for' fuel assembly array / class 6x68, and meet the following specifications:
/
a.-
Cladding Type:
?!rcaloy (Zr) b.
. Maximum PLANAR-As specified in Table 2.1-3 for fuel AVERAGE INITIAL assembly array / class 6x6B.
ENRICHMENT:
c.
Initial Maximum Rod As specified in Table 2.1-3 for fuel-Enrichment:
assembly array / class 6x68.
d.
Decay Heat Per -
. 5115 Watts Assembly:
e.
Post-irradiation A post-irradiation cooling time after Cooling Time and discharge 218 years and an average Average Burnup Per.
burnup 5 30,000 MWD /MTlHM.
^
Assembly; f.
Nominal Fuel Assembly 5135.0 inches Length:
g.
Nominal Fuel Assembly 5 4.70 inches -
Width:
. h.
Fuel Assembly Weight:
5 400 lbs, including channels
$,J.
2.0-15
, y,n
~~
" ~ ' '
~
-[E Functional and Operating Limits 2.0 l
bi
- 6. Mixed Oxide (MOX), BWR FUEL DEBRIS, with or without Zircaloy channels, placed in DAMAGED FUEL CONTAINERS. The original fuel assemblies for the MOX BWR FUEL DEBRIS shall meet the criteria specified in Table 2.1-3
= for fuel assembly array / class 6x68, and meet the following specifications:
1 a.
Cladding Type:
Zircaloy (Zr) b.
Maximum PLANAR-As specified in Table 2.1-3 for original AVERAGE INITIAL fuel assembly array / class 6x68.
ENRICHMENT:
c.
Initial Maximum Rod As specified in Table 2.1-3 for original Enrichment:
fuel assembly array / class 6x6B.
]
d.
Decay Heat Per 5115 Watts DFC:
e.
Post-irradiation A post-irradiation cooling time after
)
Cooling Time and discharge > 18 years and an average Average Burnup Per burnup 5 30,000 MWD /MTlHM for the 3
Astembly:
original fuel assembly.
> I 1
f.
Nominal Original Fuel 5135.0 inches Assembly Length:
g.
Nominal Original Fuel 5 4.70 inches Assembly Width:
h.
Fuel Debris Weight:
5 400 lbs, including channels 2.0-16
-/
..)
a
r.
/
a; s
Functionsl and Op@ rating Limits 2.0 Q:h
'M87 B. Quantity per MPC:
}
Up to four (4) DFCs containing uranium oxide' or MOX BWR FUEL DEBRIS.
~ The remaining MPC-68F fuel storage locations may be filled with array / class 6x6A,6x6B,6x6C,7x7A, and 8x8A fuel assemblies of the following type, as applicable:
. b. MOX BWR INTACT FUEL ASSEMBLIES; j
J C. Fuel assemblies with stainless steel channels are not authorized for loading in the MPC-68F.
l I
. - * :.1
- 2.0.gg m.,
i-h
n Functional and Operating Limits, Table 2.1-2 PWR FUEL ASSEMBLY CHARACTERISTICS (note 1)
Fuel Assembly.
14x14A 14x148 14x14C 14x14D 15x15A
' Array / Class -
Clad Material Zr Zr Zr SS Zr (note 2) i Design initial U
$402 5402 5410-5400 5420 (kg/assy.)
Initial Enrichment (wt -
's 4.6 54.6 5 4.6 5 4.0 5 4.1
% 22sy)
No. of Fuel Rods 179 179 176 180 204 Clad O D. (in )
3 0.400 2 0.417 2 0.440 2 0.422 3 0.418 Clad I D. (in.)
5 0.3514 5 0.3734 5 0.3840 5 0.3890 5 0.3660 Pellet Dia. (in.)
5 0.3444 5 0.3659 5 0.3770 5 0.3835 5 0.3580 Fuel Rod Pitch (in.)
0.556 0.556 0.580 -
0.556 0.550 Active Fuel Length 5150 5150 5150 5144 5150 (in )
No, of Guide Tubes 17 17 5(note 3) 16 21
)
Guide Tube ~
t 0.017 2 0.017
. 0.040 t 0.0145 2 0.0165 Thickness (in.)
All dimensions are design nominal values. Maximum and minimum u-'"er ::: :; cified to bound variations 1.
ithin a given assembly class.
2.
Zr designates ci aterial made of Zirconium or Zirconium alloys 3.
ch guide tube replaces four fuel ro U
2.0-18
y h
T:
Functional and Opnrating Limits
.S.
2.0 k
l Table 2.1-2 (continued) l PWR FUEL ASSEMBLY CHARACTERISTICS (note 1)
Fuel Assembly 16x158 15x15C 15x15D 15x15E 15x15F Array / Class Clad Material Zr Zr -
Zr Zr Zr (note 2) 5 75 5475 4
Design initial U '
5464 5464
-5475 (kg/assy.)
L-Initial Enrichment (wt 54.1 54.1 5 4.1 54.1 54.1
% " U).
No, of Fuel Rods 204 204' 208 208 208 1 420 2 0.417 1 0.430 t 0.428 3 0.428 0
Clad O.D. (in.)
Clad I.D. (in.)
5 0.3736 5 0.3640 s 0.3800 5 0.3790 5 0.3820 Pellet Dia. (in )
5 0.3671 1 0.3570 5 0.3735 5 0.3707 5 0.3742 Fuel Rod Pitch (in.)
0.563 0.563
'O.568 0.568 0.568 Active Fuel Length 5150 5150 5150 5150 5150 (in.).
No,'of Guide Tubes 21 21 17 17 17 Guide Tube
' t 0.015
. t 0.0165 3 0.0150 1 0.0140 1 0.0140 Thickness (in )
All dimensions are design nominal values. Maximum and minimum values are specified to he=>ad W wit i assembly class.
L 2.
Z s cladding materiat ym;m M Zi-WZirconium alloys.
p
{ '.)
2.0 9
- y.
- ,r'
\\
n, Functional and Op$ rating Limits 2.c Table 2.1-2 (continued)
PWR FUEL ASSEMBLY CHARACTERISTICS (note 1)
Fuel Assembly 15x15G 16x16A 17x17A 17x178 17x17C Array / Class Clad Material -
SS Zr Zr Zr Zr (note 2)
Design initial U -
5420 5430 5450 5464 5460 (kg/assy.)
i Initial Enrichment (wt 5 4.0
$ 4.6 5 4.0
$4.0
$ 4.0
% " U)
{
No. of Fuel Rods 204 236 264 264 264 Clad O.D. (in.)
1 0.422 2 0.382 t 0.360 2 0.372
. t 0.377 Clad I.D. (in.)
5 0.3890 s0.3320 5 0.3150 5 0.3310 5 0.3330 Pellet Dia. (in.)
5 0.3825 5 0.3255 5 0.3088 5 0.3232 5 0.3252 Fuel Rod Pitch (in.)
0.563 0.506 0.496 0.496 0.502 Active Fuel Length 5144 5150 5150 5150 5150 (in.) '
No. of Guide Tubes 21 5 (note 3) 25 25 25 Guide Tube 2 0.0145 t 0.0400 2 0.016 3 0.014 2 0.020 l
Thickness (in.)
Notes:
I en are d no values. Ma m and minim value re s%d to nd riapns 2.
Zr designates cladding material made of Zirconium or Zirconium alloys.
3.
Each guide tube replaces four fuel rods.
e nmial 1
- n. lsiki aruism weiyhh and all dinstora are dw9n alun.
Ackt m ya m,.g,,,,, y y 5 p.oy, j,,p,, y,-gia d e m a a A c h ie r 5 fol<<a,u e.
M utsve anJ naim
- du men stons I
a ".s y e A d to boud na b a n deagn n. in) vaLa am*any b 4l auem hh u wib a ginn array /olou.
)
l 2.0-20 A
p Functional and Op: rating Limits 2.0 Table 2.1-3 l c9
~-IdMF BWR FUEL ASSEM3LY CHARACTERISTICS (note 1) 1 Fuel Assembly 6x6A 6x6B 6x6C 7x7A 7x7B 8x8A Array / Class Clad Material.
Zr Zr Zr Zr Zr Zr (note 2) i Design initial U
$108 5108
,5108 5100 5195 5120 l
l (kg/assy.)
Maximum PLANAR.
52.7 5 2.7 for the 52.7 5 2.7 54.2 52.7 AVERAGEINITIAL UO, rods.
ENRICHMENT-See Note 3 (wt.% 8"U) for MOX rods Initial Maximum 5 4.0 54.0 5 4.0 5 4.0 5 5.0 54.0 Rod Enrichment (wt.% 2"U)
No. of Fuel Rods 36 36 (up to 9 36 49 49 64 MOX rods)
Clad O.D. (in.)
2 0.5550 1 0.5625 t05630 2 0.4860 1 0.5630 1 0.4120 Clad I.D. (in.)
5 0.4945 50.4945 5 0.4490 5 0.4200 50.4990 5 0.3620 Pellet Dia. (in.)
5 0.4940 5 0.4820 5 0.4880 5 0.4110 5 0.4880 5 0'.3580 Fuel Rod Pitch (in.)
0.694 D.694 0.740 0.631 0.738 0.523 I
Active Fuel Length 5110 5110 5 77.5 5 79 5150 5110 l
(in.)
No. of Water Rods 0
0 0
0 0
0 Water Rod N/A N/A N/A N/A N/A N/A Thickness (in.)
5 100 0
5 060 5 0.060 5 0.120 0
ChannelThickness 5 0.060 5 0.060 (in.)
nsions are design nominal values. Maximum and ini
-.J
.. gi':d L uvunu venetions e Nee,.
1
^ " di within a given class.
- 2. Zr designates el nal maDTwooalum or Zirconium alloys.
12 wt. % 2"U and 51.578 wt. % total fissile pluten
- Pu).
l l
l i
2.0-21 4
l
n s
e Functional and Operating Limits 2.
.v b,
Table 21-3 (Continued)
BWR FUEL ASSEMBLY CHARACTERISTICS (note 1)
Fuel Assembly 8x88~
8x8C 8x8D 8x8E 9x9A 9x98 Array / Class N
Clad Material Zr Zr Zr Zr Zr Zr (note 2)
Design initial U
$185 5185 5185 5180 5173 5173 (kg/assy.)
Maximum PLANAR-5 4.2 5 4.2 5 4.2 5 4.2 5 4.2 54.2 AVERAGE INITIAL ENRICHMENT (wt.%8250) initial Maximum Rod 5 5.0 s 5.0
$ 5.0 5 5.0 5 5.0 5 5.0 Enrichment -
(wt.% 228U)
No. of Fuel Rods 63 62 60 59 74/66 72 (note /)N Clad O.D. (in.)
t 0.4840 t 0.4830 2 0.4830 2 0.4930 3 0.4400 2 0.4330 Clad I.D. (in.)
5 0.4250 5 0.4250 5 0.4190 s 0.4250 5 0.3840
,,s 0.3810 - '
)
Pellet Dia. (in.).
5 0.4160 5 0.4160 5 0.4110 5 0.4160 5 0.3760 5 0.3740 Fuel Rod Pitch (in.)
0.636 - 0.641 0.636 - 0.641 0.640 0.640 '
O.566 0.569 Design /et vs Fuel 5150
$150 5150 5150 5150 s150 Length (in.',
No. of Water Rods 1
2 1-4 5
2 (notef)b 1 (Note /)"
y' Water Rod Thickness 2 0.034
> 0.00
>0.00 3 0.034
>0.00
> 0.00 (in.)
ChannelThickness 5 0.120 5 0.120 5 0.120 5 0.100 5 0.120 5 0.120 (in.)
' L;.e.
An dimensinns are decinn nominalvalues. Maximum values are specified t und variations within a given array type.
2.
Zr designates ci g material made of Zirconium or Zi m alloys.
A inis assm.sy n=ss contains t4 miai rous, -- " " bid [i,9 h rods.
4 Adranleina aina O=t mde ddanYble.
~
ddb 2.0-22
1 Functional and Operating Limits j
2.0
(
, a.o Table 2.1-3 (continued)
N* L BWR FUEL ASSEMBLY CHARACTERISTICS (note 1) i Fuel Assembly 9x9C 9x9D 9x9E 9x9F 10x10A,
j I
ef, f Arrey/Cises Clad Material Zr '
Zr Zr Zr Zr l
Design initial U ;
5173 5170 5170 5170 5182 (kg/assy.)
Maximum PLANAR.
5 4.2 34.2 54.2 54.2 s4.2 AVERAGE INITIAL" ENRICHMENT -
(wt.% "U) initial Maximum Rod
$ 5.0 55.0 55.0 55.0-S 5.0 Enrichment (wt.% "U)
No. of Fuel Rods -
80.~
79
' 76
.76 g 92/78 )-
7 Clad O.D; (in'.) '
$0.4230-
-t0.4240 1 0.4170 3 0.4430 g 0.4040 Clad 1.0. (in.) -
5 0 3640 5 0.3640
$0.3590 5 0.3810 5 0.3520 Pellet Dia. (in.).
5 0.3565 5 0.3565 5 0.3525 5 0.3745 5 0.3455 Fuel Rod Pitch (in.)
0.572
' O.572 0.572 0.572 0.510 s
Design Active Fuel -
5150 5150 5150 5150 5150 I
W,-Oi (in.)
No. of Water Rods 1
2 5
5
'2 Water Rod Thickness 0 020 '
t 0.0305 t 0.0305 3 0.0305 t 0.0300 (in.) -
Channel Thickness (in.)
5 0.100 s 0.100 5 0.100 5 0.100 5 0.120
. Notes:
All dimensions are d nominal values. Maximum values are to bound variations '
agiven l,
type.
f
- 2. LZr d::'
_ cladding material made of Zirconiu irconium alloys.
c-a:
3.'
is aswmbly class ins 92 total s; 78 fulllength r
' nd 14 length rods.
L
(
i w
.g.
2.0-23 fd.
'n 8
l:
l
g Functional and Opsrating Limits 2.c Table 2.1-3 (Continued)
O BWR FUEL ASSEMBLY CHARACTERISTICS (note 1)
=b; Fuel Assembly Array / Class 10x10B 10x10C 10x10D 10x10E Clad Matenal(note 2)
Zr Zr SS SS Design initial U (kg/assy.)
5182' 5180 5125 5125 Maximum PLANAR-AVERAGE 5 4.2 5 4.2 54.0 5 4.0 INITIAL ENRICHMENT (wt.% :ssU) initial Maximum Rod 5 5.0 5 5.0 5 5.0 5 5.0 Enrichment (wt.% assU) j 1
No. of Fuel Rods 91/83 (note /) h 96 100 96 Clad O.D. (in.)
2 0.3957 1 0.3790 2 0.3960 1 0.3940 Clad i D. (in.)
5 0.3480 5 0.3294 5 0.3560 5 0.3500 i
Pellet Dia. (in.)
5 0.3420 5 0.3224 5 0.3500 5 0.3430 Fuel Rod Pitch (in.)
0.510 0.488 0.565 0.557
{
Design Active Fuel Length (in.)
5150 5150
$ 83 5 83 No. of Water Rods 1 (Note [) [
5 (Note /)
0 4
Water Rod Thickness (in.)
> 0.00 1 0.034 N/A E 0.022 Channel Tnickness (in.)
5 0.120 5 0.055 5 0.080 5 0.090 1.
All dimensions are desi n nominal values. Maximum values e specified to bound variations a given array type, 2.
Zr des' a adding matenal made of Zirconium or Zirconium all his assembly class con 91 total fuel rods; 83 ngth rods and 8 partial th r
- 4.. SquaAreplacing nine fuel rod 5.
One diamon d replacing the four cente ods ap ur rectangular water s dividing the a into four quadrants.
\\
db 4
2.0-24 4
g N
'1Cl6nt h,thff I
hl4 e.1 -3 (con 4.)
7 l'l f
2, CH A R ScTER IST 5 b '- Ei I
ThwR fan Assea ei Y
(
Ndrs:
1.
lo;k\\. uranium w e y k h M a )I d w a n,,,, gay,is k y w<gA6 may nomw\\ slues.
Aels\\ vantus
/. s* % Aip h er, as Mih 14< asow L /w<,j klu u w.
ayeci h d k bo^o'
.nluinvm anJ ata;, sum di.aensta,a ace vacidians In dat n nominal
@lun a"03 S'I 9
\\
7 ven aers.y/c}&ss.
a.ss e nt blt<s MNis 7
a oIdd Lau/ nh d %'** I"**
Ze deslymfa at/sp.y su a.
- e Zis eentun
- 3. & o.411 wf. fo' *"20 onJ h 1. s y JA ro fos) /}pi/,
plu/ensus, (**% g.nyg
'f. 7Als ass <m bly class es,b,,,,;>yg;,J'.yggpg
\\
)
t' ds and 8 p,./;,) p y,
,,y,,
Guara, <<jdaci9 nine he) cads, 6~.
c.
vac air i
7.
Tats auembi class on/am, 92 Md Ael rods; 79 A ll g
legH
<sds and tr' pcfal /<yM n ds.
Bs MI co k,os et ut Ad cods; 9
A assem% ekss n
N rods.
}<ng/h uds and S pelial /<79 ac a,a
.u,i-p,kn$ O' fue) cods and Arrrlehayuhr ws/u rods dM
\\
fourJ rads.
d assendl
%{o y
i i
I I
L l
1
- 2. 0,vla
)
~.
j.-
l l
\\
4
E 7
Functional and Operating Limits l.
i
'N) 2.0
)
is Table 2.1-4 FUEL ASSEMBLY COOLING AND DECAY HEAT GENERATION Post-irradiation MPC-24 MPC-68 Cooling Time PWR Assembly BWR Assembly (years)
Decay Heat Decay Heat (Watts)
(Watts) 5 5792 5272 i
56.
5773 5261 j
s7 5703 5238 58 5 695 5236 J
s9 5692 5234 5 10 5687 5232 i
i 5 11 5683 s231 5 12 5678 5229 5 13 5674 5228 5 14 5669 5227
> 14 5665
.s226
)
'l J
i gp::
2.0-25 y
m Functional and Operating, Limits, 2..
(['))
Table 2.1-5 FUEL ASSEMBLY COOLING AND AVERAGE BURNUP Post-irradiation MPC-24 MPC-68 Cooling Time PWR Assembly BWR Assembly (years)
Burnup Burnup (MWD /MTU)
(MWDIMTU) 25 5 28,700 5 26,000 I
26 5 32,800 5 29,100 27 5 33,300 5 29,600 28 5 35,600 5 31,400 29 5 37,000 5 32,800 20 5 38,300 5 33,800 1
> 11
< 39,300 5 34,800 2 12 5 40,200 5 35,500 2 13
.5 40,900 5 36,200 2 14 5 41,500 5 36,900 2 15 5 42,100 5 37,600
(
i 2.0-26 i
i
)
=
LCO Applicability 3.0 8
3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY 4
.LCO 3.0.1 LCOs shall be met during specified conditions in the Applicability, except as provided in LCO 3.0.2.
LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions
- of the associated Conditions shall be met, except as provided in LCO 3.0.5.
If the LCO is met or is no longer applicable prior to expiration of the ypecified Completion Time (s), completion of the Required Action (s) is not required, unless otherwise stated.
LCO 3.0.3 Not applicable to an SFSC system.
LCO 3.0.4 When an LCO is not met, entry into a specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in specified conditions in the Applicability that are required to comply with ACTIONS or that are related to the unloading of an SFSC.
LCO 3.0.5 Equipment removed from service or not in service in compliance with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate it meets the LCO or that other equipment meets the LCO. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing.
LCO 3.0,6 Not applicable to an SFSC system.
LCO 3.0.7 Not applicable to an SFSC system.
3 f h.
H 3.0-1
3.0 ilD"]
3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR. 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, inhether such failure is experienced during the performance of the Surveillance or between performances of the
' Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the spelfied Frequency shall be failure to meet the LCO except as provided in SR 3.0.3 Surveillances do not I
have to be performed on equipment or variables outside specified limits.
SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
For Frequencies specified as "once," the above interval extension does not apply.
If a Completion Time requires periodic performance on a "once per..." basis, the above Frequency extension applies to each' performance after the initial performance.
Exceptions to this Specification are stated in the individual Specifications.
SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to
. declare the LCO not met may be delayed, from the time of discovery, up.to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is less. This delay 3.0-2
)
m.
SR Applicability 3.0 SR 3.0.3.(continued).
period is permitted to allow performance of the Surveillance.
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition (s) must be entered.
When the Surveillance is performed within the delay period and the l
Surveillance is 'not met, the LCO must immediately be declared not met, and the applicable Condition (s) must be entered.
SR 3.0.4 Entry into a specified condition.in the Applicability of an LCO shall
]
- not be made unless the LCO's Surveillances have been met within j
their specified Frequency. This provision'shall not prevent entry
{
into specified conditions in the Applicability that are required to
]
comply with Actions or that are related to the unloading of an SFSC.
J q
I
- j-
.~
3.0-3
p.,
, o,...
gdiljdcasIrve18 09.
e
,.e a%, c' l s
l De 9
-k' t
,,..?
r
9
' (
~
g f
PC Cavity Vacuum Drying Pressure s.
..i g.
4 p s) 3.1.1 3.1 SFSC INTEGRITY
'EM 1.1.MPC Cavity Vacuum Dryin r
re LCO
.1.1 The MPC cavity vacuum drying pressure sffall meet the limit specified in Table 3-1 for the applicable fC model.
APPLICABI s TY:.. During LOADING OPERATIONS.
ACTIONS
-NOTE Separate Condition is allowed for each SFSC x
OM E
~ CONDITION -
REQU ED ACTION.
E A.. MPC cavity vacuu'm A.
Est lish MPC cavity -
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> drying pressure limit not a uum drying pressure met.
in limit.'
Remokall fuei assemblies 30 days'
. B.
Required Action and B.
Associated Completion from theToFSC.
\\
Time not met.
l i
' SURVEILLANCE REQU EMENTS:
[ SURVEILLANCE FREQUENCY 3
- SR L 3.1.1.1 -
erify MPC cavity vacuum drying pressure is -
dhin 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> within limit.
er completion of C draining.
N l
j;g.y 3.1.1 +
h 1
OVERPACK Annulus Vacuum Drying Pressuro_
3.1.2
"'Dg) h S K (3
's; i
- 3.1' SFSC INTEGRITY.
ng 3, f, p -
1
~
l3
~OVERPACK Annulus Vacuum Drying ressure
- LCO
.1.2 The OVERPACK annulus vacuum drying pressure sh meet the
~ limit specified in Table 3-1 for the applicable MPC del.
4 APPLICA ITY; During LOADING OPERATIONS.
. ACTIONS'
-NOTE-Separate Condition try is allowed for each SFSC.
COM E'
CONDITION' REQUIRED TlON E
.\\
L A.
OVERPACK annulus
.1 Establish VERPACK 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> vacuum drying pressure annulu acuum drying
-limit not met.
pres re within limit.
N B.1 ove all fuel assemblies 30 days j
B. ' Required Action and
~
from he SFSC.
Associated Completion-
' Time'not met.
~ SURVEILLANCE REQUI EMENTS 1
[ SURVEILLANCE. \\
FREQUENCY Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
- SR 3.1.2.1 Verify OVERPACK annulus vacuum dryin after completion
' pressure is within limit.
of OVERPACK annulus
% raining.
e xs 1
4
-,s 3.1.2-1.
L I
L ^
a i_
s
.)
F Q d' MPC Helium Backfill Density
.M
\\-
3.1.3 Yhh i3.1' SFSC INTEGRITY 3.1.3 MPC Helium Backfill' Density.
'LC 3.1.3
.The MPC helium backfill density shall meet the limit s ifed in LTable 3-1 for the applicable MPC model.
APPLI BILITY: - During LOADING OPERATIONS.
. ACTIONS i
NOTE ~
' Separate Con on entry is allowed for each SFSC.
OM ETION CONDITIO REQUIRED ON E
A.
MPC helium backfill A.1 Establish C helium 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> -
density limit not met.
backfill nsity_within limit.
~
Bi Required Action and.
B.1 Re ve all fuel assemblies 30 days
. Associated Completion fr the SFSC.
Time not ' met.
/
\\
--SURVEILLANCE REQUIRE NTS
\\
URVEILLANCE FREQUENCY
- SR 3.1.3.1 Veri MPC helium backfill density i within limit.
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after verifying MPC cavity ~
vacuum drying pressure is within limit.
i
<{N 3.1.3-1
.b ^g) 'k OVERPACK Annulus Helium Backfill Pressure
/
g,\\'
3.1.4 3.1 SFSC INT G 3A.4 OVERPACK Annuius Helium Backfill Pressure N
LCO 1.4 The OVERPACK annulus helium backfill pressure shall meet the limit.specified in Table 3-1 for the plicable MPC model.
APPLICA LITY:
During LOADING OPERATIO ACTIONS
\\
NOTE j
Separate Conditio ntry is allowed for each FSC.
CONDITION R
UlRED ACTION T ME OVERPACK annulus \\A.1 dstablish OVERPACK 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> A.
helium backfill pressure annulus helium backfill limit not met.
pressure within limit.
/
\\
B.
Required Action and
' B.1 move all fuel assemblies 30 days Associated Completion fro the SFSC.
Time not met.
i
/
SURVEILLANCE REQU)REMENTS
[ SURVEILLANCE FREQUENCY rify OVERPACK annulus helium backk Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.1.4.1 ressure is within limit.
N after verifying OVERPACK annulus vacuum yrying pressure is within limit
\\
s 4
3.1.4-1
. }
s
_hg -d 3.1.5 t.
7 i
'31 SFSC INTEGRITY Y
3 MPC Helium Leak Rate-LCO A1.5-The total helium leak rate through the MPC lid cpnfinement weld and the drain and vent port confinement weldsfhall not exceed the limit specified in Table 3-1 for the applicable C model.
c
' APPLICABILITY:
During LOADING OPERATIONS.
- ACTIONS PDTE-
- Separate Condition entry is allowed for each SFSC.
OM CONDITION REQUIR ACTION T ME A.
.1 Establi MPC helium leak 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit not met, rate hin limit.
B.
Required Action and 8.1 move all fuel assemblies 30 days Associated Completion the SFSC.
Time not met.
I i
SURVEILLANCE REQUIREM TS S
VEILLANCE FREQUENCY
. Verify PC helium leak rate is within li Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after completion L
of MPC hydrostatic
{esting.
I j
[
3r, 3.1.5-1 1
1
r Dg)k d
neJ OVERPACK Helium Leak Rate M
3.1.6 a
- n.,-
(
2
}
l 3.1 SFSC INTEGRih
\\
3.
OVERPACK Helium Leak Rate LCO
.1.6 The total helium leak rate through the following OV RPACK penetration mechanical seals shall meet the limi pecified in Table 31 for the applicable MPC model.
- a. Closure plate inner mecnanical seal; i
Vent port plug seal; and l
c.
ain port plug seal APPLICABILITY: During L' ADING OPERATIONS ACTIONS
._-N OTE Separate Condition entry is allowed ach S SC.
. g.
OM E'
CONDITION
. RE U RED ACTION E
A.
OVERPACK helium leak A.1 tablish OVE CK 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> 4
rate limit not met.
elium leak rate wi in limit.
!.1 Remove all fuel assemb B
s 30 days B.
Required Action and Associated Completion from the SFSC.
Time not met.
'N N
l r
L i
3.1.6-1 L
[-
9
FI OVERPACK Helium Leak Rate
.,, Ji 3.1.6
' 'a$9 d-SURVEILLANCE REQUIREMENTS
/
[
SURVEILLANCE FREQUENCY.
SR 3.1.6.1 herify OVERPACK helium leak rate 'adhin Within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limit.
after verifying OVERPACK N[ '
annulus helium backfill pressure
[
.N, _,.
is within limit.
/
x N r
h At
,' )
p 4
'O L
\\'
e I
l 4
1 q
,; r' : t,'
'V,-
3.1.6-2 t
l L_.
r
LCO 3.1.1 The MPC shall be dry and helium filled.
APPLICABILITY:
TRANSPORT OPERATIONS and STORAGE OPERATIONS ACTIONS
..-.....N OT E.--......
Separate Condition entry is allowed for each SFSC.
COMPLETION CONDITION REQUIRED ACTION TIME A.. MPC cavity vacuum dry A.1 Perform an engineering 7 days pressure limit not met.
evaluation to determine quantity of moisture lef1 in
. MPC.
AND 30 days A.2 Determine and complete corrective actions necessary to return MPC to analyzed condition.
B.! Perform an engineering 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
- density limit not met.
evaluation to determine impact of helium differential.
i AND-(
B.2 Determine and complete 14 days -
-]
corrective actions necessary to return MPC to analyzed condition.
]
3.1.1 1
.D
Multipurpose Canister (MPC) 3.1.1 1
COMPLETION CONDITION -
-REQUIRED ACTION C. MPC helium leak rate C.1 Perform an engineering 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limit not met.
evaluation to determine impact ofincreased helium leak rate on heat removal capability and off-site dose release effects.
AND-C.2 Determine and complete 7 days corrective actions necessary to return MPC to analyzed condition.
D. Requ' ired Actions and D.1 Remove all fuel assemblies 30 days Associated Completion from the SFSC.
Times not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify MPC cavity vacuum drying pressure is During LOADING within the limit specified in Table 3-1 for the OPERATIONS applicable MPC model.
SR 3.1.1.2 Verify MPC helium backfill density is within the During LOADING limit specified in Table 3-1 for the applicable OPERATIONS MPC mode!.
S R 3 d 1.3 Verify that the total helium leak rate through the During LOADING MPC lid confinement weld and the drain and vent OPERATIONS port confinement welds is within the limit specified in Teble 3-1 for the applicable MPC model.
1 3.1.1-2 b
C OVERPACK 3.1.2 3.1 SFSC INTEGRITY 3.1.2. OVERPACK LCO 3.1.2 The OVERPACK shall be dry and belium filled.
APPLICABILITY:
TRANSPORT OPERATIONS and STORAGE OPERATIONS ACTIONS
N OTE-----
Separate Condition entry is allowed for each SFSC.
COMPLETION CONDITION REQUIRED ACTION A._ OVERPACK annulus A.1 Perform an engineering 7 days vacuum dry pressure evaluation to determine limit not met.-
quantity of moisture left in the OVERPACK.
AND 30 days A.2 Determine and complete corrective actions necessary to return the OVERPACK to analyz'ed condition.
B. OVERPACK annulus B.1 Perform an engineering 7 days helium backfill pressure evaluation to determine limit not met.-
ima'ct of helium pressure differential.
A N D..
30 days B.2 Determine and complete corrective actions necessary to retum the OVERPACK to
{
analyzed condition.
i 3.1.2-1 I
I~
l OVERPACK 3.1.2 l
COMPLETION CONDITION REQUIRED ACTION C. OVERPACK helium C.I Perform engineering 7 days leak rate limit not met.
evaluation to determine impact ofincreased helium leak rate on heat removal capability and off-site dose release effects.
AND C.2 Determine and complete 30 days corrective actions necessary to return the OVERPACK to analyzed condition.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify OVERPACK annulus vacuum drying During LOADING pressure is within the limit specified in Table 3-1 OPERATIONS for the applicable MPC model.
SR 3.1.2.2 Verify OVERPACK annulus helium backfill During LOADING pressure is within the limit specified in Table 3-1 OPERATIONS for the applicable MPC model.
SR 3.1.2.3 Verify that the total helium leak rate through the During LOADING OVERPACK closure plate inner inechanical seal, -
OPERATIONS the OVERPACK vent port plug seal, and the OVERPACK drain port plug seal is within the limit specified in Table 3-1 for the applicable MPC model.
3.1.2-2
o SFSC Lifting Requirements 3.173 r
3.1 SFSC INTEGRITY 3.1.hSFSC Lifting Requirements LCO 3.1.]
An OVERPACK loaded with spent fuel shall be lifted in accordance J
with either of the following requirements:
]
- a.,
i A lift height s 21 inches when oriented vertically.
AND ii '
A lift height 5 72 inches when oriented horizontally.
QB b.
The OVERPACK is lifted with lifting devices designed in accordance with ANSI N14.6 and having redundant drop prevention design features.
APPLICABILITY:
puringlRAJS_P.QElLOJERA))QVllt Yhe P
e Nois:
s le 0 is o n a Itw% Wh SYSC l> \\" 4 ost/n* *suy'yoe} w ' w A cenga gknerA h a dwM w I
1
' ACTIONS NO Separate Condition entry is allowed for each SFSC.
OM E
CONDITION REQUIRED AC~flON E
A. SFSC lifting A.1 Initiate actions to meet immediately I
requirements not met.
SFSC lifting requirements.
- fC.
$lk-syteibt Grulys).s%evi)absdt-e[4,,g e ctk <.
co4;ks -to awe
.nd n g,,
a imh ceuta w,b 2ns th-sr.p a y 100 nu Ibn H.s.
5 '
~
3.1.T-1 3
G,
SFSC Lifting Requirements m) f 3.1.h
- ' ~
3 SURVEILLANCE REQUIREMENTS
.i.!)
SURVEILLANCE FREQUENCY SR 3.1./.1 Verify SFSC lifting requirements are met.
After the SFSC l
J is suspended from, or secured in the transportei and prior to the transporter beginning to 1
move the SFSC
{
to/from the ISFSI J
1 l
')
s J
.I t
1l 3.1.t-2 3
R Fuel Cool-Down
- () '
3.1 YfhIh
'3.1 SFSC INTEGRITY 3.1:
Fuel Cool-Down LCO 3.1g-The MPC exit gas temperature shall be 5 200 F;r!:r t initiatet!:n Y
e!" C ::";; ding oper;;bne Q
-NOTE The LCO is only applicable to wet UNLOADINS OPERATIONS.
APPLICABILITY:
Gweg UNLOADING OPERATIONS 7eter lo n[/ coding.
ACTIONS NOTE--
Separate Condition entry is allowed for each SFSC.
1 OM CONDITION REQUIRED ACTION T ME A.
MPC exit temperature A.1 Establish MPC exit gas Prior to initiating i
~
not within limit.
temperature.
MPC re-flooding operations l
SURVEILLANCE REQUIREMENTS -
SURVEILLANCE FREQUENCY I
SR 3.1.[Y 1
Verify exit gas temperature.
Prior to initiation of MPC re-
{
flooding 1
operations.
).
y> -
\\
bp:
3.1-.
1
t
.Overpack Averaga Surfaco Doso Ratss
,y 3.2.1 4Q) 3.2 SFSC RADIATION PROTECTIONL e./
- 3.2.1 Overpack Average Surface Dose Rates 9' js ;
y
,LCO 3.2.1 Der;;;': deee retee ehe;t 6 ineeecim: ht the lce;;;sne siivwn u
' Fi;rq2.2.i=1. The average surface dose' rates of each overpack shall not exceed:
a.-
125 mrem / hour (neutron t gamma)_on the side; b.
< 80 mrem / hour (neutron + gamma) on the top; APPLICABILITY:
D N;LO?D'MOPEP^T!ONO. To d6 PORT opera Arlo^/5 Wd S70KARG GPeRATIONS.
ACTIONS NOTE
. Separate Condition entry is allowed for each SFSC.
COMPLETION
. CONDITION REQUIRED ACTION TIME
._s A. ' Overpack average A.1 Administratively verify 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> surface dose rate limits correct fuel loading.
- not met.
i AND I
A.2 Perform analysis to verify Pd;r ;w ~ A Y b8"5 compliance with the ISFSI
'P."J40 FORT offsite radiation protection -
N requirements of 10 CFR
- Pad 20 and 10 CFR Pad 72.
B.1 -Required Action and B.1 Remove all fuel assemblies 30 days
< Associated Completion from the SFSC.
. Time not met.'
khk j
3.2.1 -1
r-A Overpack Average Surface Dose Rates 3.2.1
}
SURVEILLANCE REQUIREMENTS I
I II I I
II I 11 Ill SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify average surface dose rates of overpack Ptrb containing fuel asserpblies are within limits.
IP ^JOSFORT Over ack doss ruto skil be musured OREr *T;ON5 aFFe k %s sbcun in Flyure s. a.1 - 1.
q lu.dn3 Loaw4
)
OPBADCAS 3.2.1-2 0
' ' ~
4:
e 6
.-3
'q'{h :
TASURE !(CNG MDDL.E OF THE FLAT SECT!DNS OF TkE HI-STAR NEUTR:N SHIC.D h
.....*'.l............
. '.'; *.. :..d; :.* :.: ::c:l: ; *:.;.
s..t...
ississ/s NNN\\\\\\\\
CROSS SECTIONAL VIEV 90'
( ASURE DOSE RATES AT
'32-Inches Nominal
- TARGET POINTS SHDVN
/
0*
180 i
t r h TARGET POINT g79.
I I
.n.
! l 3
HEASURE DOSE 60-inches Nominal
- RATES AT FOUR POINTS (0, 90.
180, 270 DEGREES)
U 8'M
-i m rXH PuNE j
60-inches Nominal s i, I
N l
HI-STAR 100 Figure 3.2.1 OVERPACK Surface Dose Rate Measurement Locahons 3.2.1 -3
- m
- 74 1
u --
SFSC Surface Contamination
.A 3.2.2 9$
. 3.2 SFSC RADIATION PROTECTION 3.2.2 SFSC Surface Contamination LCO 3.2.2 Removable' contamination on the exterior surfaces of the OVERPACK and accessible portions of the MPC shall each not exceed:
a.1000 dpm/100 cm from beta and gamma sources; and
- b. 20 dpm/100 cm from alpha sources.
2 APPLICABILITY:
ni,ri"0 LOAO!NO OPERATlONO. 7RadPoa.T" 6P6dTl045 l
omd S TOR 46 opeganca.s i
ACTIONS NOTE
{
Separate Condition entry is allowed for each SFSC.
I COMPLETION
' CONDITION' REQUIRED ACTION TIME vg8 A.
SFSC removable A.1 Restore SFSC removable Drier to 7 day 5 surface contamination surface contamination to TRANSPORT limits not met.
within limits.
OPEPATlONG SURVEILLANCE REQUIREMENTS SURVEILIANCE FREQUENCY SR 3.2.2.1 Verify that the removable contamination on the PrieHer exterior surfaces of the OVERPACK and TPAMSPORT accessible portions of the MPC containing fuelis CPE?ATlONO within limits.
% rin3 L MDIN6 oyetA7/0^/5 3.2.2-1
F
.k Table 3-1 MPC Model-Dependent Limits MPC MODEL LIMITS
- 1. MPC-24
- a. MPC Cavity Vacuum Drying Pressure 5 3 torr for 2 30 min
- b. OVERPA?K Annulus Vacuum Drying Pressure s 3 torr for 2 30 min
andh*AT "lbfo
-~d. OVERPACK Annulus Helium Backfill Pressure 210 psig and 514 psig
- f. OVERPACK Helium Leak Rate s 4.3E-6 std cc/sec (He)
- 2. MPC-68
- a. MPC Cavity Vacuum Drying Pressure s 3 torr for 2 30 min
- b. -OVERPACK Annulus Vacuum Drying Pressure 5 3 torr for 2 30 min
and -10%
- f. OVERPACK Helium Leak Rate s 4.3E-6 std cc/sec (He)
- 3. MPC-68F
- a. MPC Cavity Vacuum Drying Pressure.
5 3 torr for 2 30 min b.' OVERPACK Annulus Vacuum Drying Pressure 5 3 torr for 2 30 min
~ c. MPC Helium Backfill Density' O.1218 g-moles / liter +0%
and -10%
d.- OVERPACK Annulus Helium Backfill Pressure 210 psig and 514 psig
- f. OVERPACK Helium Leak Rate s'4.3E-6 std cc/sec (He)
! Helium used for backfill of MPC shall have a purity of 2 99.995%.
'3; f"
3.3-1
c;-
e ilg s
4.0 DESIGN FEATURES 4.1 Site -
t 4.1.1 - Site Location Not applicable; 4.2 -Storage Features 4.2.1 Storace Cask
' l The HI-STAR 100 System consists of the OVERPACK and its integral multi-purpose canister (MPC).
4.2.2 Storace Caoacity The total storage capacity of the ISFSI is limited by plant-specific license conditions.
4.2. '3
_Storace Pad (s)
Not applicable.
4.3. Codes and Standards The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME
- Code),~ 1995 Edition with Addenda through 1997, is the governing Code for the Hi-STAR 100
- cask systern.
4.3.1' Exceptions to Codes, Standards, and Criteria Table 4-1 lists all approved exceptions.
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o 4.4 Site Specific Parameters and Analyses
.f,)
Site-specific parameters and analyses that will need verification by the system user, are as a minimum, as follows:
1.
The temperature of 80*F is the maximum average yearly temperature. The average daily ambient temperature shall be 100 F pr less.
{
)
2.
'The temperature extremes of 125 F with incident solar radiation and -40 F for storage of the MPC inside the cask.
3.
The horizontal and vertical seismic acceleration levels are bounded by the values listed below in Table 4-2.
{
Table 4-2 Desian-Basis Earthauake Inout on the Too Surface of an ISFSI Pad Horizontal g-level in Horizontal g-level Corresponding each of two orthogonal Vector Sum Vertical g-level directions (upward) i 0.222 g -
0.314 g 1.00 x 0.222 g = 0.222 g O.235 g 0.332 g 0.75 x 0.235 g = 0.176 g 0.24 g 0.339 g 0.667 x 0.24 g = 0.160 g f
0.25 g 0.354 g 0.500 x 0.25 g = 0.125 g 4.
The analyzed flood condition of 13 fps water velocity and a height of 656 feet of water (full submergence of the loaded cask) are not exceeded.
l S.
The potential for fire and explosion shall be addressed, based on site-specific j
considerations. This includes the condition that the on-site transporter fuel. tank will contain no more than 50 gallons of fuel.
hib 6.
In addition to the requirement of 10 CFR 72.212(b)(2)(ii), the cask storage pads j
and foundation shall include the following characteristics as applicable to the drop and tipover analyses:
I a.
Concrete thickness: 5 36 inches 1
b.
Concrete compressive strength: 5 4,200 psi
- I!
4 4.0-7
l f
i
' Rsinforcement top and bottom (Both Dirsctions);
. c; A.
I Reinforcement area and spacing determined by analysis
();
Reinforcement yield strength: s 60.000 psi 29,060
- d.
Soil effective modulus of elasticity: 56#00 psi L
. 7.
9
- In cases where engineered features (i.e., berms, shield walls) are used to ensure that the requirements of 10 CFR 72.104(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category.
4.5 Design Specifications 4.5.1 Specifications important for Criticality Control
'4.5.1.1 MPC-24 1.
Minimum flux trap size: 1.09 in 2
2.
Minimum ' B loading in the Boral neutron absorbers: 0.0267 g/cm 4.5.1.2.
MPC-68 and MPC-68F 1.
Minimum fuel cell pitch: 6.43 in 2
2.
Minimum ' B loading in the Boral neutron absorbers: 0.0372 g/cm in the MPC 68, and.01g/cm in the MPC-68F.
2 4.5.2 : Specifications important for Thermal Performance 4.5.2.1.
OVERPACK The painted surface of the HI-STAR 100 OVERPACK must have an emissivity no less than 0.85.
/vy "4Wwt w,N.h br/ eh ~& M*4
?~w/d' i+ We B
- f subw h
opuc&.1. s. deep and he u<
NWS/cA -yos (&Le
, tees) ta/d.sd/ cbaibe k k Awdace at sm-wer-e srw es.wkh.,.t Mr & saa.uw 9
, w.O ad devily nyi(t4th kY 'csu.Ada 6
5 ddsn,asdu, & Awdua nW W-M% M
.1 AdJ$$ %te'd,fd sa/ sp////Bse */ Sem, pay *Ws-k 4_a_g r
a 4.6 Training Module 3
- h Training modules shall be developed under the generallicensee's training program as required by 10 CFR 72.212(b)(6). Training modules shall require a comprehensive, program for the operation and maintenance of the Hl-STAR 100 spent fuel storage cask system and the independent spent fuel storage installation (ISFSI). The training modules shall include the following elements, at a minimum:
HI-STAR 100 Cask System Design (overview)
ISFSI Facility Design (overview)
Systems, Structures, And Components important To Safety (overview)
HI-STAR 100 Cask System Topical Safety Analysis Report (overview)
NRC Safety Evaluation Report (overview)
Certificate of Compliance conditions Hi-STAR 100 Cask System Technical Specifications and other conditions for use HI-STAR 100 Cask System Regulatory Requirements (e.g.,10.CFR Part 72, Subpart K.10 CFR Part 20,10 CFR Part 73)
Required instrumentation and Use Operating Experience Reviews HI-STAR 100 Cask System and ISFS1 procedures, including:
Procedural overview Fuel qualification and loading MPC/OVERPACK rigging and handlirig, including safe load pathways MPC welding operations OVERPACK closure Auxiliary equipment operation and maintenance (e.g., draining, vacuum drying, helium backfilling, and cooldown)
MPC/OVERPACK pre-operational and in-service inspections and tests -
Transfer and securing of the loaded OVERPACK onto the transport vehicle Transfer and offloading of the OVERPACK at the ISFSI Preparation of MPC/OVERPACK for fuel unloading Unloading fuel from the MPC/OVERPACK 44 Surveillance 4.0-g 5
e d
Radiation protection
. Maintenance f
Secunty
- 4 Off-normal and accident conditions, responses, and corrective actions 4.7 Pre-OperationalTdsting and Training Exercise A dnf run training exercise of the loading, closure, handling. unloading, and transfer of the Hi-STAR 100 system shall be conducted by the licensee prior to the first use of the system to load spent fuel assemblies. The dry run may be performed in an alternate step sequence from the actual procedures, but all steps must be performed. The dry run shall include but is not limited to the following
Moving the HI-STAR 100 MPC/OVERPACK into the spent fuel pool.
1 Preparation of the Hi-STAR 100 Cask System for fuel loading.
Selection and verification of specific fuel assemblies to ensure type conformance.
l i
Locating specific assemblies and placing assemblies into the MPC (using a dummy fuel assembly), including appropriate independent verification.
j Remote installation of the MPC lid and removal of Hi-STAR 100 MPCIOVERRPACK from the spent fuel pool.
MPC welding, NDE inspections, hydrostatic testing, draining, vacuum drying, helium I
backfilling, and leakage testing.
Hi-STAR 100 OVERPACK closure, draining, vacuum drying, helium backfilling and leakage testing.
Hi-STAR 100_OVERPACK upending /downending on the horizontal transfer trailer or other transfer device, as applicable to the site's cask handling arrangement.
L
- Piscement of the Hi-STAR 100 Cask System at the ISFSI.
l HI-STAR 100 Cask System unloading, including cooling fuel assemblies, flooding MPC cavity, removing MPC lid welds (for which a mock-up may be used).
1 1 4.0-10 l
O-
_____________1______1___
l:
s.
4.8 Special Requirements For First System In Place NN The heat transfer characteristics of the cask system will be recorded by temperature i
measurements of the first HI-STAR 100 system placed in service with a heat load equal to or greater than 10 kW.
. A letter report summarizing the results of the measurements shall be submitted to the NRC -
for each cask subsequently loaded with a higher heatload, up to the 19 kW heat load for the MPC-24 basket or 18.5 kW heat load for the MPC-68 basket. The calculation and the measured temperature data shall be reported to the NRC in accordance with 10 CFR 72.4.
The calculation and comparison need not be reported to the NRC for MPCs that are subsequently loaded with lesser loads than the latest reported case.
V8 e
.',*6
'4.0-11
v
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A PROGRAMS 5.0
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5.0 ADMINISTRATIVE CONTROLS '
5.1 Programs.
The following programs shall be established, implemented and maintained.
5.11 Technical Specification (TS) Bases Control Pronram Thisl program provides a means for. processing changes to the Bases of these Technical Specifications.
1.
Changes to' the Bases for the TS shall be made under the appropriate o
administrative controls'and reviews, 2.
Licensees may make cF *,ges to the Bases without prior NRC approval provided the changes do n ' involve either of the following:
i 1.
A change to the TS incorporated in the license; or 2.
A change to the SAR or Bases that involves an unreviewed safety -
question,' a significant increase in occupational exposure, or a significant unreviewed environmental impact as defined in 10 CFR 72.48.
3.
. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the SAR.
4.~
Proposed changes' that.. meet the criteria of Specification 5.1.1.2.1 or Specification 5.1.1.2.2 above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior
.NRC approval shall be provided to the NRC on a frequency consistent
' with 10 CFR 72.48 (b)(2).
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5 BASES TABLE OF CONTENTS Ms 3NM 2.0 FUNCTIONAL AND OP' RATIONAL LIMITS B2.0-1 E
.3.0 LIMITING CONDITION FOR OPERATION APPLICABILITY B3.0-1 1
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SFSCJ.NTEGRITY gg
, g4(g) 23.1.1-t y
- 3.1.1
...y youuun,vii...,,.._:u.-
B3.1.1-1 J
,, n 3.1.2 OVERPACK Annu;ss Vecuum O,ying Pr;;;;;;
B3.1.2-1 3.1.0
. MFC l lo,uin Saukidi Danviy
d 11 11i
. GVERFACK Annuiu ;;oll Uni Deunilii Fie==ure 53.1.4-v k
4.1.5
. MFC no;, uni Leek P:t 93.1.5 1 G.1.G OVEP.P.^CK H Sm Le.k Raie.
- 65. i.^
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3.173 SFSC Lifting Requirements B3.1 3.1 pf' Fuel Cool-Down B3.1 3.2 SFSC RADIATION PROTECTION 03.2.14 3.2.1 OVERPACK Average Surface Dose Rates
, B3.2.1-1 3.2.2 SFSC Surface Contamination B3.2.2-1 is i
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Functional and Opsrating Limits B 2.0 B 2.0 FUNCTIONAL AND OPERATING LIMITS B 2.1.1 Fuel to' be Stored in the Hi-STAR 100 System SFSC BASES BACKGROUND The SFSC design requires specifications for the spent fuel to be
' stored in each MPC model, such as the type of spent fuel,_
maximum allowable enrichment prior to irradiation, maximum
~
'bumup, minimum acceptable post-irradiation cooling time prior to storage in the SFSC, maximum decay heat, and conditions of the i
spent fuel (i.e., INTACT FUEL ASSEMBLY, DAMAGED FUEL I
ASSEMBLY, OR FUEL DEBRIS). Other important limitations are the dimensions and weight of the fuel assemblies.
I l
Requirements for fuel to be loaded into the Hi-STAR 100 SFSC
. System are specified in Sections 2.1.1 and 2.1.2.
Specific limita' tions for each MPC model are specified in Table 2.1-1 as referred to by Functional and Operating Limit 2.1.1.a. These 1
' limitations support the assumptions and inputs used in the thermal, structural, shielding, and criticality evaluations performed for the HI-STAR 100 SFSC System.
]
Actions required to respond to violations of any Functional and Operating Limits are provided in Section 2.2.
j 1
APPLICABLE
.-To ensure that the lid is not placed on an SFSC containing SAFETY an unauthorized fuel assembly, facility procedures require ANALYSES verification of the loaded fuel assemblies to ensu e that the correct fuel assemblies have been loaded in the SFSC.
FUNCTIONAL' 2M
. AND OPERATING LIMITS Functional and Operating Limit 2.1.1.a refers to Table 2.1-1 for the specific fuel assembly characteristic limits for fuel assemblies
^
authorized for loading into the HI-STAR 100 SFSC System. Table
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2.1-1 contains three major subsections, one each for the three B 2.0-1
Functional and Opsrating Limits B 2.0
]s,)
. BASES-u
. MPC modelsL the MPC-24, MPC-68, and MPC-68F. These fuel assembly characteristics include such parameters as cladding material, enrichment, decay heat generation, post-irradiation cooling time, burnup, and fuel assembly length, width, and weight.
Tables 2.1-2 and 2.1-3 are referenced from Table 2.1-1 and
~
provide additional specific fuel characteristic limits for PWR and BWR fuel assemblies, respectively, based on the fuel assembly array / class type. Tables 21-4 and 2.1-5 are also referenced from Table 2.1-1 and provide limits for decay heat generation and burnup as a function of post-irradiation cooling time, respectively.
The fuel assembly characteristic limits of Table 2.1-1 and other referenced tables must be met to ensure the thermal, structural, shielding, and criticality analyses supporting the Hi-STAR 100 SFSC System Topical Safety Analysis Report (TSAR) are preserved.
Functional and Operating Limits 2.1.1.b, c, and d provide limits on MPCs loaded with different types of fuel in the same MPC to ensure the TSAR thermal analyses remain bounding for the
.I specific loading scenario.~ The basis for these Functional and Operating Limits is that stainless steel clad fuel assemblies, DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS, and array / class 6x6A,6x6B,6x6C, and 8x8A fuel assemblies for limits 2.1.1.b, c, and d, respectively, have heat emission rates j
substantially lower than the design basis fuel assembly due to the j
relatively poor heat transfer characteristics of these fuel assembly
' types.
212
= Functional and Operating Limit 2.1.2 requires preferential loading of fuel assemblies with significantly different post-irradiation cooling times. This is required to prevent a cooler assembly from heating up due to being ' surrounded b'y less-cooled fuel assemblies generating'more decay heat. For the purposes of complying with this Functional and Operating Limit, only fuel assemblies with post-irradiation cooling times differing by one year or greater need to be loaded preferentially. This is based on the fact that the heat-up' phenomenon can on'y occur with significant differences in decay '
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l B 2.0-2
Functional and Oparating Limits B 2.0
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BASES' A
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heat emission characteristics between adjacent fuel assemblies
' having different post-irradiation cooling times.
FUNCTIONAL 22d
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AND OPERATING LIMITS If any Functional and Operating Limits of 2.1.1 or 2.1.2 are VIOLATIONS violated, the limitations on loading fuel assemblies in the SFSC have not been met. Actions must be taken to place the affected fuel assemblies in a safe condition. This safe condition may be established by returning the affected fuel assemblies to the spent fuel pool. However, it is acceptable for the affected fuel assemblies to remain in the SFSC, in a wet or dry condition, if that is determined to be a safe condition.
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B 2.0-3
m Functional and Optrating Limits B 2.0 BASES 2.2.2 & 2.2.3
- Notification of the violation of a Functional and Operating Limit to the NRC is required within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Written reporting of the violation must be accomplished within 30 days. This notification and written report are independent of any reports and notification that may be required by 10 CFR 72.216.
/0 CFR 72.75'or REFERENCES 1.
TSAR, Sections 2.1,4.4; Chapters 5 and 6 4
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B 2.0-4 l
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LC Applicability 1
.e B 3.0 3fh
.B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY j
BASES LCOS _
LCO 3.0.1,3.0.2,3.0.4, and 3.0.5 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise stated.
i I
LCO 3.0.1 LCO 3.0.1 establishes the Applicability statement within each individual Specification as the requirement for when the LCO is required to be met (i.e.,'when the facility is in th'e specified conditions of the Applicability statement of each Specification).
LCO 3.0.2 LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO are not met. This Specification establishes that:
' Completion of the Required Actions within the specified Completion Times a,
constitutes compliance with a Specification; and 4
b.
Completion of the Required Actions 'is not required when an LCO is met
.within the specified Completion Time, unless otherwise specified.
There are two basic types of Required Actions. The first type of Required Action specifies a time limit in which the LCO must be met. This time limit is the Completion Time to restore a system or component or to restore variables to within specified limits. Whether stated as a Required Action or not, correction cf the entered Condition is an action that may always be
. considered upon entering ACTIONS. The second type of Required Action i specifies the remedial measures that permit continued SFCS activities
' that are not further restricted by the Completion Time. In this case, compliance with the -Required Actions provides an acceptable level of safety for continued operation.
h.
B 3.0-1 il
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- LCO 3.0.1'(continued) i Completing the Required Actions is not required when an.LCO is met or is no longer applicable, unless otherwise stated in the individual
[
Specifications.
ii LThe Completion Times of the Required Actions are also applicable when a system or component is removed from service intentionally. The reasons
.for intentionally relying on the ACTIONS include, but are not limited to, performance of Surveillances, preventive maintenance, corrective l
maintenance, or' investigation of operational problems. Entering
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ACTIONS for these ieasons must be done in a manner that does not I
- compromise safety. Intentional entry into ACTIONS should not be made for operational convenience.
i LCO 3.0.3 This specification is not applicable to an SFSC system because it describes conditions under which a power reactor must be shut down
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when an LCO is not met and an associated ACTION is not met or provided. The placeholder is retained for consistency with the power reactor technical specifications.
LCO-3.0.4 LCO 3.0.4 establishes limitations on changes in specified conditions in the Applicability when an LCO is not met. It precludes placing the facility in a specified condition stated in that Applicability (e.g., Applicability desired to be entered) when the following exist:
q d
. SFCFC conditions are such that the requirements of the LCO would not
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- a.
be met in the Applicability desired to be entered; and
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1b!
Cer'inued noncompliance with the LCO requirements,if the Applicability ~
l
- were entered, would result in SFCS activities being required to exit the
. Applicability desired to be entered to comply with the Required Actions.
- Compliance with Required Actions that permit continued operation for an L unlimited period of time in a specified condition provides an acceptable level of safety for continued operation. This is without regard to the status 1
B 3.0-2
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1 LCO 3.0.4 (continued) of the SFSC. Therefore, in such cases, entry into a specified condition in the Applicability may be made in accordance with the provisions of the Required Actions.. The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of i
restoring systems or components before entering an associated specified condition in the Applicability.
The provisions of LCO 3.0.4 shall not prevent changes in specified conditioas in the Applicability that are' required to comply with ACTIONS.
In addition, the provisions of LCO 3.0.4 shall not prevent changes in specified conditions in the Applicability that are related to the unloading of an SSSC.
Exceptions to LCO 3.0.4 are stated in the individual Specifications.
Exceptions may apply to all the ACTIONS or to a specific Required Action of a Specification.
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LCO 3.0.5 LCO 3.0.5 establishes.the allowance for restoring equipment to service
. under administrative controls when it has been removed from service or determined to not meet the LCO to comply with the ACTIONS. The sole purpose of this Specification is to provide an exception to LCO 3.0.2 (e.g.,
to not comply with the applicable Required Action (s)) to allow the performance of testing to demonstrate:
a.
The equipment being retumed to service meets the LCO; or b.
Other equipment meets the applicable LCOS.
The administrative controls ensure the time the equipment is returned to service in conflict with the requirements of the ACTIONS is limited to the time absolutely necessary to perform the allowed testing. This Specification does not provide time to perform any other preventive or corrective maintenance.-
LCO. 3.0.6 Not Applicable.
.. LCO' 3.0.7 Not Applicable.
h B 3.0-3
r; SR Applicabilith Q/].
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B 3.0
^
B 3.0 ' SURVEILLANCE REQUIREMENT (SR) APPLICABILITY BASES-SRs SR 3.0.1 through SR 3.0.4 estabiish the general requirements applicable to all Specifications and apply at all times,- unless otherwise stated.
SR 3.0.1 SR'3'.0.1 establishes the requirement that SRs must be met during -
the specified conditions in the Applicability for which the requirements of the LCO apply, unless otherwise specified in the individual SRs. This Specification is to ensure that Surveillances are performed to verify that systems and components meet the LCO and variables are within specified limits. Failure to meet a Surveillance within the specified Frequency, in accordance with SR 3.0.2, constitutes a failure to meet an LCO.
)
Systems and components are assumed to meet the LCO when the y
associated SRs have been met. Nothing in this Specification, however, is.
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to be construed as implying that systems or components meet the associated LCO when:
The systems or components are known to not meet the LCO, a.
although still meeting the SRs; or b.
.The requirements of the Surveillance (s) are known to be not met i
between required Surveillance performances.
Surveillances do not have to be performed when the SFSC is in a specified condition for which the requirements of the associated LCO are not applicable, unless otherwise specified.
'Surveillances, including Surveillances in'voked by Required Actions, do not
, have to be perfo'rmed on equipment that has been determined to not meet the LCO because the ACTIONS define the remedial measures that apply.
Surveillances have to be met and performed in accordance with SR 3.0.2, prior to returning equipment to service. Upon completion of maintenance, i
B 3.0-4 s
uvA L
SR Applicability 1
B 3.0 BASES SR 3.0.1 (continued)_
. cppropriate post maintenance testing is required. This includes ensuring
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applicable Surveillances are not failed and their most recent performance j
is in accordance with SR 3.0.2. Post maintenance testing may not be possible in the current specified conditions in the Applicability due to the i
necessary facility parameters not having been established, in these situations, the equipment may be considered to meet the LCO provided -
testing has been satisfactorily completed to the extent possible and the -
equipment is not otherwise believed to be incapable of performing its function. This will allow operation to proceed to a specified condition where other necessary post maintenance tests can be completed.
l SR 3.0.2
- SR 3.0.2 establishes the requirements for meeting the specified Frequency for Surveillances and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per..."
interval.
This extension facilitates Surveillance scheduling and considers facility-conditions that may not be suitable for conducting the Surveillance (e.g.,
transient conditions or other ongoing Surveillance or maintenance activities).
The 25% extension does not significantly degrade the reliability that results from performing the Surveillance at its specified Frequency. This
. is based on the recognition that the most probable result of any particular j
Surveillance being performed is the verification of conformance with the i
SRs.' The exceptions to SR 3.0.2 are those Surveillances for which the 25% extension of the interval specified in the Frequency does not apply.
I These exceptions are stated in the individual Specifications as a Note in j
the Frequency stating."SR 3.0.2 is not applicable."
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As stated in SR 3.0.2, the 25% extension also does not apply to the initial portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after q
the initial performance. The initial performance of the Required Action,
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SR Applicability B 3.0 mg Q
BASES SR 3.0.2 (continued) whether it is a particular Surveillance or some other remedial action, is
- considered a single action with a single Completion Time. One reason for not allowing the 25% extension to this Completion Time is that such an action usually verifies that no loss of function has occurred by checking the status of redundant or diverse components or accomplishes the function of the affected equipment in an alternative manner.
The provisions of SR 3.0.2 are not intended to be used repeatedly mer as an. operational convenience to extend Surveillance intervals or peri Completion Time intervals beyond those specified.
SR 3.0.3 establishes the flexibility to defer declaring affected equipment SR - 3.0.3 as not meeting the LCO or an affected variable outside the specified limits
- when.a Surveillance has not been completed within the specified Frequency. A delay period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is less, applies from the point in time th it is discovered that the Surveillance has not been performed in accordance with SR 3.0.2, and not at the time that the specified Frequency was not met.
This delay period provides adequate time to complete Surveillances that have'been missed. This delay period permits the completion of a Surveillance before complying with Required Actions or other remedial measures that might preclude completion of the Surveillance.
The basis for this delay period includes consideration of facility conditions, adequate planning, availability of personnel, the time required to perform the Surveillance, the safety significance of the delay in completing the I
required Surveillance, and the recognition that the most probable res any particular Surveillance being performed is the verification of conformance with the requirements. When a Surveillance with a
. Frequency based not on time intervals, but upon specified SFCS conditions, is discovered not to have been performed when specified, SR 3.0.3 allows the full delay period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform the B 3.0-6
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1
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9 SR Applicability
- g+
B 3.0 v
BASES SR 3.0.2 (continued)L Surveillance.
SR 3.0.3 also provides a time limit for completion of Surveillances that become applicabie as a consequence of changes in the specified conditions in the Applicability impoced by the Required Actions.
Failure to comply with specified Frequencies for SRs is expected to be an infrequent occurrence. Use of the delay period established by SR 3.0.3 is a flexibility which is not intended to be used as an operational convenience to extend Surveillance intervals.
1 If a Surveillance is not completed within the allowed delay period, then the equipment is considered to not n ;eet the LCO or the variable is i
considered outside the specified^ limits and the Completion' Times of the i
Required Actions for the applicable LCO Conditions begin immediately
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upon expiration of the delay period. 'If a Surveillance is failed within the delay period, then the equipment does not meet the LCO, or the variable is outside the specified limits and the Completion Times of the Required Actions for the applicable LCO Conditions begin immediately upon the failure of the Surveillance.
= Completion of the Surveillance within the delay period allowed by this Specification, or within the Completion Time of the ACTIONS, restores compliance with SR 3.0.1.
lSR 3.0.4 SR 3.0.4 establishes the requirement that all applicable SRs must be met before~ entry into a specified condition in the Applicability.
This Specification ensures that system and component requirements and variable limits are met before entry into specified conditions in the Applicability for which these systems and components ensure safe operation of SFCS activities.-
C B 3.0-7 L
c SR Applicability BASES SR 3.0.2 (continued)
The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components before entering an associated specified condition in the Applicability, However, in certain circumstances, failing to meet an SR will not result in f
SR 3.0.4 restricting a change in specified condition. When a system, l
subsystem, division, component, device, or variable is outside its specified limits, the associated SR(s) are not required to be performed per SR 3.0.1, which states that Surveillances do not have to be performed on equipment that has been determined to not meet the LCO. When equipment does not meet the LCO, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance (s) within the specified Frequency does not resuliin an SR 3.0.4 restriction to changing specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or
' may not) apply to specified condition changes.
The provisions of SR 3.0.4 shall not prevent changes in specified
. conditions in the Applicability that are required to comply with ACTIONS.
In addition, the provisions of LCO 3.0.4 shall not prevent changes in specified conditions in the Applicability that are related to the unloading of l
an SFSC The precise requirements for performance of SRs are-specified such that exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition (s) specified in a Surveillance procedure require entry into the specified condition in the
. Applicability of the associated LCO prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after entering the LCO Applicability would have its Frequency specified such -
that it is not "due" until the specific conditions needed are met.
B 3.0-8 z...
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.q SR Applicability J-
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B 3.0
' ff,If,
. BASES SR 3.0.2 (continued)
Altemately,.the Surveillance may be stated in the form of a Note as not required (to be met or performed) until a particu'lar event, condition, or time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4, Frequency.
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B 3.0-9 i
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'MPC Cavity Vacuum Drying Pressure h.
B3.1-1
' B 3.1.
S C Integrity B 3.1.1-MP Vacuum Drying Pressure BASES-BACKGROUND n OVERPACK with an em MPC is placed in the spent f I pool and loaded with fysi assemblies meeting the
' rements of the Functibnal and Operating Limits. A lid is i
r thertplaced on the MPol The OVERPACK and MPC are raised I
to the top of the spenpfuel pool surface. The OVERPACK and q
g MPC e then moved into the cask preparation area where dose ra s are mefrs' ured and the MPC lid is welded to the MPC shell an the welps are inspected and tested. The water is drained fr m thp'MPC and MPC cavity vacuum drying is performed. Tip MPC cavity is backfilled with helium. Additional dose rates e measured and the MPC vent and drain cover
~ lates and/ sure ring are installed and welded. Inspectioris p
are perfo' e on the welds. The OVERPACK lid is installed
,s and se, red.
he annulus space between the MPC and OVEF3 PACK is rained, vacuum dried and backfilled with helium gas /The OVE PACK seals are tested for leakage.
Colitamination asurements are completed prior to moving pVERPACK and PC to the ISFSI.
MPC cavity vacuu drying is utilized to remove residual-moisture from the M C fuel cavity'after the MPC has been drained of water. An water that has not drained from the fuel cavity evaporates fro the fuel cavity due to the vacuum. This is aided by the temper ure increase due to the heat generation of the fuel.
- APPLICA 'LE-The confinement of radios ivity during the storage of safety SAFETY ANALYSIS. analysis spent fuelin the M C is ensured by the multiple confinement boundaries and stems. The barriers relied on are the fuel pellet matrix, the tallic fuel cladding tubes in
- which the fuel pellets are contai
, and the MPC in which the fuel assemblies are stored. Long erm integrity of the fuel and cladding depend on storage in an i rt atmosphere. This is Y^
B 3.1.1-1 N
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MPC Cavity Vacuum Drying Pressur 44 B3 -1 6
h 6y.
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d backfilling ccomplished by removing water from the MPC the cavity with an inert gas; The thermal ana ses of the MPC-assume that the MPC ~ cavity is filled with dry lium.
j/
-LCO-A vacuum pressure meeting the limit specified in Table 3-1 indicates that liquid water has evaporated and been removed xfrom the MPC cavity. Removing wa'ter from the MPC fuel cavity.
helps to ensure the long-term maintenance of fuel cladding int ty, APPLICABILITY--
. Cavity'v cuum drying is performed during LOADING OPERATIONS before th OVERPACK an'd integral MPC are transported to
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1 the ISFSI.
herefore, the vacuum requirements do not apply I
.after the MP is backfilled with helium and leak tested prior to TRANSPORT PEMTIONS and STORAGE OPERATIONS.
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ACTIONS A note has be'en ahed to the ACTIONS which states that, for this LCO, peparate C ndition entry is allowed for'each MPC.
j This is acceptable sin the Required Actions for each 4
Condition provide appro riate compensatory measures for each MPC not meeting the LC Subsequent MPCs that don't meet the,LCO are governed by s bsequent Condition entry and application of associated Re ired Actions.
/M If the cavity vacuum drying pressur limit cannot be met, actions must be taken to meet the LCO. Fail e to successfully complete cavity vacuum drying could h ve many causes, such as failure of the vacuum drying system, i dequate draining, ice clogging of the drain lines, orlaaking MPC elds. The
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Completion Time is sufficient to determine a correct most failure mechanisms.
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8 3.1.1-2 1
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MPC Cavity Vacuum Drying Pressure A
' B3.1-1
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If the MPC fuel cavity cannot be su.ccessfully vacuum dried, the fuel must be placed in a safe co The Completion Time is reasona,ndition in the spent fuel ble based on the time required to perform fuel cooldown ope' rations, re-flood the MPC, cut the MPC lid welds, move the SSSC into the spent fuel pool, and j
remove the MPC lid in an orderly manner and without i
hallenging personne,.
)
i N
SURVEILLANCE SR 3.1h.1 I
REQUIREMENTS The long-te integrity of the stored fuel is dependent on
)
storage in a
, inert environment. Cavity dryness is 4
demonstrated evacuating the cavity to a very low absolute j
'/ pressure and ver ing that the pressure is held over a specified
/-. period of time. A I vacuum pressure is an indication that the
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cavity is dry. The su eillance must be performed within 48 j
hours after completion f MPC draining. This allows sufficient 1
~
time to backfill the MPC vity with helium while minimizing the time the fuelis in the MPC ithout water or the assumed inert j
atmosphere in the cavity.
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.. REFERENCES 1.
TSAR Sections 7.3 and 8.1.
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}si B3.1.1-3
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.OVER acuum Drying Pressu e y
fy K.V LB 3.1 LSFSC Integrity f
9
. B 3'.1.2
'OVERPACK Annulubvitq1upgWessure BASES.
iBACKGROUND.
An OVERPACK with an empty MPC is aced in the spent ool and loaded'with fuel assemb es meeting the fuel p? aments of the Functional and Operating Limits. A lid i requi then pla'cp on the MPC. The OVyRPACK and MPC are raised to the top of the spent fuelpool surface. The.
OVERPAC nd MPC are then oved into the cask preparation ar where dose r tes are measured and the MPC lid is weld to the MP shell and the welds are inspected and tes The, water is drained from the MPC and the MPC cavi vacuum drying 'is performed. The MPC cavity is backfilled wi h6(ium. Additional dose rates are measured and the MP vent and drain cover plates and closure f.ng are inst e and welded.- Inspections are performed on the, Ids.
he OVERPACK lid is installed annulus pace between the MPC and and secured. Thy'ined, vac OVERPACK is Wa m dried and backfilled with helium gas. Tiy6 OVERPACK eals are tested for leakage.
Contaminatiorf measurements a completed prior to moving the OVERP 'CK and MPC to the FSI.
Vacuum
' ing' of the annulus betwe n the MPC and the OVERP CK is utilized to remove resi al moisture from the annulu after the annulus has been drai of water. Water that h s not drained from the annulus eva orates from the enn us due to the vacuum. This is aided the te perature increase due to the heat gener 'on of the fuel i the MPC.
APPLICABLE The confinement of radioactivity during the stora e of spent fuel in the MPC is ensured by the multiple SAFETY L
~ ANALYSIS 1 confinement boundaries and systems. The barrie relied on are the fuel pellet matrix, the metallic fuel claddin tubes '
in which the fuel' pellets are contained, and the MPC i which the fuel assemblies are stored. Long-term integrity of the fuel and cladding depend on the ability o the s
SFSC to reject heat to the environment. This is A.
.B 3.1.2-1
OVERPACK Annulus Vacuum Drying Pressure,
B 3.1.2 L
N 1p ccomplished in part by retaining helium gas in the annulus ~ ]!
4
. space between the OVERPACK and the MPC. By removing, i
Y water from the annulus space, the boiling of residual water and associated pressurization of the annulus is avoided.'
Backfilling the annulus with an inert gas optimizesjh'e ability of the SFSC to transfer heat from the MPC to th(
OVERPACK in a dry environment. In additi
, the thermal analyses of the OVERPACK assume thatt e annulus is filled with dry helium.
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/
A va'cyum pressure meeting the ifmit specified in Table 3-1 LCO j
indicatgs that allliquid water h s evaporated and been remove from the annulus.
emoving water from the annulus h Ips to prevent p,e ential deterioration of the OVERPAC structure dt;6 to corrosion. The specified time ensures a st le pressyre has been sustained.
APPLICABILITY Annulus vacuum'
.ifig is performed during LOADING OPERATIONS be e the SFSC is transported to the ISFSt.
Therefore, the v uu req'uirements do not apply after the OVERPACK arpiulus i backfilled with helium and leak i
tested prior tcyTRANSP T OPERATIONS and STORAGE OPERATIONS.
/
ACTIONS A note ha's been added to'th CTIONS which states that, for this (CO, separate Cond'itio entry is allowed for each SFS This is acceptable since he Required Actions for eac Condition provide appropria compensatory m sures for each SFSC not meet g the LCO. Subsequent SCs that don't meet the LCO are ovemed by -
subsequent Condition entry and appli tion of associated Required Actions.
AJ.
If the annulus vacuum drying pressure limit nnot be met, actions must be taken to meet the LCO. Fail e to successfully complete annulus vacuum drying uld have many causes, such as failure of the vacuum dryi
- system,
)
inadequate draining, ice clogging of the drain lines, r leaking OVERPACK seals. The Completion Time is
.. 4 B 3.1.2-2
=
OVERPACK Annulus Vacuum Drying Prcssure 3
B 3.1.2 igg sufficient to determine and correct most failure mech s/
2 ms.
,as fL1 If the OVERPACK annulus cannot be succ ssfully vacuum dried, the fuel must be placed in a safe ndition in the spent fuel pool. The Completion Time ' reasonab.e based on the time required to perform fuel ooldown opections, re-flood the MPC, cut the MPC lid we ds, move the SFSC into th'e spent fuel pool, rerlove the l6IPC lid, and remove the j
challen(uel assemblies in an derly manner and without spent gin personnel.
j SURVEILLANCE SR 3.1.2.1 REQUIREMENTS l
The long-term inte of the stored fuelis dependent on the j
ability of the SF to r et heat from the MPC to the OVERPACK. p'nnulus drgess is demonstrated by i
evacuating tpe annulus to a pressure and verifying that the pressur6 is held over a sp fied period of time. A low vacuumjdessure is an indicatio hat the annulus is dry.
The surveillance must be perform within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after com etion of OVERPACK draining. This allows sufficient ti to backfill the annulus with heliu hile minimizing the I
t' e the loaded MPC is in the OVERPA without water or he assumed inert atmosphere in the annu REFERENCES 1.
TSAR Section 8.1.6 b
e, p
W 0 4
-; g B 3.1.2.
V
\\
L B 3.1.3
%L 4-L\\
ti.
B 3.1 SFSC Integri S
.3 JMPC Helium Ba kfill ensity
/
/
B.(T
/
BAS
/-
'BACKGR ND An OVERPACK with an e pty MPC is placed in the spent i
fuel pool and loaded wit el assemblies meeting the i
i
, requirements of the Functional and Operating Limits. A lid is then placed on the MK. ~ The OVERPACK and MPC are raised to the top of tpe spent fuel pool surface. The PC are then moved into the cask VERPACK and N)here dose rates are measured a paration area yt L
p
- MPC lid is welded to the MPC shell and the welds are inspected and bsted. The water is drained from the MPC and the\\MP cavity vacuum drying is performed. The MPC lied with helium. Additional dose rates are cavity is ba _
l-measur d the MPC vent and drain cover plates and closure g'are installed and welded. Inspections are
. perfo d on\\he welds. The OVERPACK lid is installed cured. Tt e annulus space between the MPC and and PACK is d(rained, vacuum dried and backfilled with
.OV
^
h m gas. The RPACK seals are tested for leakage.
a C ntamination mea rements are completed prior to moving e OVERPACK and PC to the ISFSt.
Backfilling of the MPC fu I cavity with helium promotes heat l
transfer from the fuel and e inert atmosphere protects the j
fuel cladding. Providing a lium pressure greater than l
1 atmospheric pressure ensur that there will be no in-leakage of air over the life of e MPC, which might be j!
harmful to the fuel.
?APPLIC LE.
' The confinement of radioactivity'd ring the storage of l
SAFE spent fuel in the MPC is ensured b the multiple j
- ANALY IS
~ confinement boundaries and system The barriers relied j
on are the fuel pellet matrix, the meta 'c fuel cladding tubes
- in which the fuel pellets are contained, d the_MPC in Lwhich the fuel assemblies are stored. Lo
-term integrity of i
.the fuel and cladding depend on storage in n inert l
atmosphere and maintaining cladding temperatures below a,
i.
j B 3.1.3-1
]
=
i l
3
?[
Y MPC Helium Backfill Density '
~
B 3. 'i.3
.A k
p long-term limits. This is accomplished by removing water
/Qy 4
from the MPC and backfilling the cavity 'Nith an inertpas.'
~
The thermal analyses of the MPC assume that th AIPC cavity is filled with dry helium.
- LCO.
Backfilling the MPC fuel cavity with helium af a pressure exceeding atmospheric pressure will ens re that there will be no air-in-leakage into the cavity whi could damage the fuel cladding over the ' storage period /The helium backfill nsity specified in Table 3-1 was selected based on a mi imum helium purity of 99.995%'to ensure that the pre ure and heat transfer withip'the MPC remains within the'd ign and analysis basisp'f the MPC.
/
APPLICABILITY
. Helium b kfillis performep'during LOADING OPERATI S before thejOVERPACK and integral MPC are transported t the' ISFSI/ Therefore, the backfill density requirements dq not apply after the MPC is backfilled with helium and leak tested prior to TRANSPORT OPERATIONS and STORAGE O RATIONS.
' ACTIONS A note has' beep /addh to the ACTIONS which states that, for this LCO,/. acceptabi separate ' ondition entry is allowed for each -
MPC.- This i since the Required Actions for j
each Condition provide ap ropriate compensatory measures for each/PC not meeting t e LCO. Subsequent MPCs that don't et the LCO are gove ed by subsequent Condition entry d application of associ ted Required Actions.
the backfill density cannot be obt 'ned, actions must be.
taken to meet the LCO. The Compi ion Time is sufficient to determine and correct most failures w ich would prevent backfilling of the MPC fuel cavity with h lium.
- M-If the MPC fuel cavity cannot be backfilled with elium to the specified density, the fuel must be placed in a safe condition B 3.1.3-2 e....
MPC Hslium Backfill D si
-Q in the spent fuel pool. The Completion Time is re onable w/
ased on the time required to perform fuel cool wn opgrations, re-flood the MPC, cut the MPC lid, welds, move
)'
the SFSC into the spent fuel pool, remove t 1e MPC lid, and remove'the spent fuel assemblies in an orderly manner and without chqllenging personnel.
~
SURVEILLANCE SR 3.1.3.1
\\
/
REQUIREMENTS
/
The long-term inte of the s[ored fuelis dependent on storage in a dry, ine nvirordnent and maintenance 'of adequate heat transfe ephanisms. Filling of the MPC cavity with helium at th gpecified density in Table 3-1 ensures that there will be o air in-leakage, which could potentially damage th,e'fue This density of helium gas is sufficient to maintairy' fuel ci ding temperatures within acceptable levels./
Backfilling of the MPC must be rformed successfully on each MPC before placing it in sto ge. The surveillance l
must be pef ormed within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after verifying MPC cavity vacj.fum drying pressdres are ithin the limit. This allows syfficient time to backfill the C cavity with helium while rrpnimizing the time the fuelis in he MPC without the assu7ed inert atmosphere,
/
- REFERENCES 1.
TSAR Sections 7.3 and 8.1.5
\\
Y r
x pp\\>
g-4, 4
,9, 3
'e:
B 3.1.3-3 U
OVERPACK Annulus Halium Backfill Pressure 1
B 3.1.4 1
- g;l ^
4
(
B 3.
' SFSC INTEGRITY.
}
j}
B 3.1.
OVERPACK Annulus Helium Backfill Pre'ssure BASES i
J J
BACKGROUNE An OVERPACK with an empty MPC isylaced in th
~
fuel pool and loaded with fuel assemblies meeting the requirements of the Functional and dperating Limits. A lid is qen placed on the MPC. The OV PACK and MPC are reised to the top of the spent fuel ool surface. The j
ONRPACK and MPC are the oved into the cask prep' ration area where dose tes are measured and the MPCI is welded to the MP shell and the welds are i
inspect and tested. The ater is drained from the MPC and the C cavity vacut)m drying is performed. The MPC j
cavity is b qkfilled with helium. Additional dose rates are measured a the MPQ vent and drain cover plates and closure ring a installed and welded, inspections are performed on t we s. OVERPACK lid is installed and secured. The adou s space between the MPC and i
OVERPACK is dr fned, vacuum dried and backfilled with helium gas. ThepVERPACK seals are tested for leakage.
Contamination rpeas rements are completed prior to moving the OVERPACK and PC to the ISFSI.
/-
Backfilling o the OVER CK annulus with helium promotes heat transf r from the MP to the OVERPACK structure.
Providin a helium pressu greater than atmospheric -
pressur ensures that there ill be no in-leakage of air over the lif f the SFSC, which
' ht be harmful to the heat tran r features of the SFSC.
APPLICABLE T e confinement of radioactivity uring the storage of SAFETY pent fuelin the MPC is ensured the multiple ANALYSIS confinement boundaries and syste s. The barriers relied on are the fuel pellet matrix, the me lic fuel cladding tubes in which the fuel pellets are contained, nd the MPC in which the fuel assemblies are stored. L ng-term integrity of the fuel and cladding depend n the ability of the SFSC to remove heat from the MPC and r 'ect it to the
[,,,
j i
B 3.1.4-1
- ).
i OVERPACK Annulus Helium Backfill Pressure B 3.1.4 l
,g f environment. This is accomplished by removing water from NA s"
-k the OVERPACK annulus and backfilling thejiinnulus with an f
inert gas. The thermal analyses of the MP,C assume that L
f, the OVERPACK annulus is filled with d helium.
LCO Backfilling the OVERPACK annulus,with helium at a pressure exceeding atmospheric p,ressure will ensure that there will be no air-in-leakage into the annulus which could gdecrease the he'at transfer properties of the SI SC and result irijncreased cladding temperatures over the storage period.
l The helium backfill pressure specified in Table 3-1 was y
selected based on a mini m helium purity of 99.995% to ensure hat the heat trans'fer from the MPC to the OVERP K is maintain'ed consistent with the design and i
analysis sis.
f APPLICABILITY Heliv backhil is p'Erformed during LOADING i
OP, (TIONkbefore the OVERPACK and integral MPC are trar-.orted tof w ISFSI. Therefore, the backfill pressure f
requ. amentsydo kot apply after the OVERPACK is backfilled with helium,and leak tested prior to TRANSPORT OPERATJONS and ORAGE OPERATIONS.
A note has been added to the ACTIONS which states that,
- ACTIONS-
_ for th,is LCO, separate Cogdition entry is allowed for each j
SFSC. This is acceptable ince the Required Actions for each Condition provide app priate compensatory measures f 'r each MPC not meeting th LCO. Subsequent MPCs that i
don't meet the LCO are govern by subsequent Condition entry and application of associat d Required Actions.
l A.1 If the backfill pressure cannot be obta ed, actions must be taken to meet the LCO. The Completi Time is sufficient to determine and correct most failures whi would prevent
~ backfilling of the OVERPACK annulus wit helium.
EL1 if the OVERPACK annulus cannot be backfilled ith helium f
B 3.1.4-2 3.
I
+
' OVERPACK Annulus Hslium Backfill Pressure c
B 3.1.4 g"
to the specified pressure, the fuel must be placed in a safe condition in the spent fuel pool. The Completion Time is -
\\
- reasonable based on the time required to perform fuel M
cooldown operations, re-flood the MPC, cut the M,P,C' I
y welds, move the SFSC into the spent fuel pool move the.
\\MPC lid, and remove the spent fuel assem s in an orderly q
manner and without challenging person i
\\
l SURVElLLANCE ~ SR. 3 1.4.1 -
- REQUIREMENTS The'long-rm integrity of th stored fuelis dependent on the,
j
' ability of thefFSC to transfer heat from the enclosed MPC j
through the O ERPAQK to the environment. Filling of the 4
OVERPACK an Ip(with helium at a pressure within the i
range specified air in-leakagpw)'n" able 3-1 will ensure that there w hic ould potentially result in fuel cladding temperatures exceedihg long term limits.
Backf of the OVERP K annulus must be performed -
sucdessfully on each SFSC efore placing it in storage. The stIrveillance must be perform within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after-
~
~ /; verifying OVERPACK annulus cuum drying pressures are within the limit. This allows suffici t time to backfill the annulus with helium while minimizin the time the loaded MPC is in the OVERPACK without wa r or the assumed inert atmosphere in the annulus.-
R RENCES 1.
TSAR Sections 4.4.1 and 8.1.6
\\b S }$@ W
} y.Y b
\\
. hI B 3.1.4-3
MPC Halium Leak Rate hp B 3.1.5 A,
Mik),
B 3.1-SFSC INTEGRITY L
\\
h) N xv L
\\.
g B
1.5 ' MPC Helium Leak Rate BAS BACKGRQND An OVERPACK with an empty MPC s placed in the spent fuel pool and loaded with fuel ass blies meeting the requirements of the Functional, d Operating Limits. A lid is then placed on the MPC. ThepVERPACK and MPC are aised to the top of the spent /uel pool surface. The VERPACK and MPC are en moved into the cask preparation area where d se rates are measured and the MP lid is welded to thef PC shell and the welds are-inspe ed and tested.
he water is drained from the MPC and the yPC cavity cuum drying is performed. The MPC cavity is be. ckfilled, th helium. Additional dose rates are measured d the/MPC vent and drain cover plates and closure ring
" stalled and welded. Inspections are i
performed on welds. The OVERPACK lid is installed and secured annulus space between the MPC and OVERPAC)(is drked, vacuum dried and backfilled with helium gas.~ The OVERPACK seals are tested for leakage.
w Contamjrlation measu'rements are completed prior to moving the OVERPACK and MbC to the ISFSI.
/
Bac,Xfilling the MPC fuel ca 'ty with helium promotes heat trafisfer from the fuel to the C vessel and the inert a osphere protects the fuel dding. Prior to moving the FSC to the storage pad, the M C helium leak rate is determined to ensure that the fue is confined.
APPLICABLE The confinement of radioactivity durin the storage of
' SAFETY spent fuel in the MPC is ensured by th multiple
- ANALYSIS.
confinement boundaries and systems.
e barriers relied on are the fuel pellet matrix, the metallic I cladding tubes in which the fuel pellets are contained, and e MPC in which the fuel assemblies are stored. Long-t integrity of the fuel and cladding depend on maintaining an 'nert atmosphere and the cladding temperatures bel established long-term limits. This is accomplished y g),,
/
B 3.1.5-1
B 3.1.5 j.y r
removing water from the MPC and backfilli the cavity with
)
hehum.
f
-- LCO'
' Verifying that the MPC cavity heliunyfeak rate is'within the
" limit.specified in Table 3-1 ensureythe MPC lid is sealed.
Me' uring the helium leakage rate will also ensure that the assu ptions in the accident andlyses and radiological-
. evaluations are maintained.,,
-\\
-/
l The heliud leak rate measgrement is performed during
' APPLICABILITY.
\\
LOADING O(ERATIONybefore the OVERPACK and
. integral MPC re transp,orted to the ISFSt. TRANSPORT -
OPERATIONS ould pot commence if the MPC helium leak rate was not with t ' limit. Therefore, MPC leak rate testing is not requi d during TRANSPORT OPERATIONS or STORAGE OP RATIONS.
.\\
\\
- ACTIONS.
A note has bedn added t(the ACTIONS which states that, for this LCO, eparate Condition entry is allowed for each.
MPC. This i acceptable sin'oe the Required Actions for-each Condition provide approp% ate compensatory measures for each C not meeting the LCO.' Subsequent MPCs that don't m the LCO are govemedk subsequent Condition entry an application of associated Required Actions.
ett l
if th helium leak rate limit is not met, action must be taken to eot the LCO. The Completion Time is su ient to termine and correct most failures which could use a elium leak rate in excess of the limit.
Y
\\
V 0) Q '
S 1
B 3.1.5-2
b j
MPC Helium Leak Rate B 3.1.5 i
../ 't g
j Th If the MPC leak rate cannot be brought within
~ \\
- The Completion Time is reasonable based on the ti x
N ' ; required to perform fuel cooldown operations re-flood the MPC, cut the MPC lid welds, move the SF into the spent
~ (uel pool, remove the MPC lid, and remo the spent fuel assemblies in an orderly manner and thout challenging pe nnel.
SURVEILLANCE SR 3.\\5.1
~
REQUIREMENTS The prima design conside tion of the MPC is that it is not exceeded nd to ens /ure that off-site do sufficiently I k tight to en ure that the helium remains in the MPC during lon temystorage. Long-term integrity of the
' stored fuel is dep dent on storage in a dry, inert environment.
Measuring the' elium i k rate must be performed successfully/on each MP prior to placing it in storage. The -
1
~ surveillan must be perfor ed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after j
hydrost ic testing of the MP This allows sufficient time to perfo the Surveillance while intaining a significant f
level in the MPC cavity. Shkid the leak rate not be wat wi in the limit, the MPC cavity can a 'ckly be re-filled with ater. Discovering an unacceptable h um leak rate.at this
]
time, as opposed to after the MPC is co. letely drained,
{
' minimizes the potential time fuel is in the C without water or an inert gas environment.
-REFERENQdS.
1.
. TSAR Sections 7.3 and 8.1.5
/
fh v
\\
\\
L
\\
s), ; + s % '
plw
/
B 3.1.5-3
"~
j
OVEyPJCK Helium Leak Rato
/
\\s B 3.1.6 MA J
.B.3.1 SFSC INTEGRITY 3.1.6 - OVERPACK Helium Leak Rate
\\@
d' BA ES D
i BACK ROUND An OVERPACK with an emp'tykihpla the spent fuel pool and loaded with fuel assemblies ting the y
requirements of the Functional and Oper ting Limits. A lid is y'
then placed on the MPC. The OVERP.CK and MPC are
\\ raised to the top of the spent fuel p I surface. The OVERPACK and MPC are then ved into the cask
\\ preparation area where dose r s are measured and the -
MPC lid is welded to the MP shell and the welds are
- in'spected and tested. Th ater is drained from the MPC anch he MPC cavity va m drying is performed. The MPC cavi (s backfilled wi elium. Additional dose rates are measured and the PC vent and drain cover plates and closure r}
are i talled and welded. Inspections are perforrned th welds. The OVERPACK lid is installed and secure he annulus space between the MPC and OVERPACK is ' rained, vacuum dried and backfilled with helium /s. Th OVERPACK seals are tested for leakage.
v Conta ination ' measurements are completed prior to moving the - ERPACK an' MPC to the ISFSI.
ckfilling the OVERPA' K annulus space with helium promotes heat transfer fr the MPC to the OVERPACK to limit the maximum fuel cla ing temperature. Prior to moving the SFSC to the storage pad, he helium leak rate is determined to ensure that the lium is retained in the OVERPACK annulus region.
APPLICA LE The confinement of radioactivity duri the storage of i
SAFE spent fuelin the MPC is ensured by the ultiple ANAL IS -
confinement boundaries and systems. Th barriers relied
- on are the fuel pellet matrix, the metallic fuel adding tubes in which the fuel pellets are contained, and the PC in
~
which the fuel assemblies are stored. Long-term tegrity of the fuel and cladding depend on maintaining the cla ing temperatures below established long-term limits. This '
accomplished by maintaining a helium atmosphere in the
- .a?
s B 3.1.6-1 y
B 3.1.6 h
Q [@ b,\\ '
)
(
10\\ [v ann,utarregion surrounding the MPC.
J j
C\\
,~
vv Verifying that the OVERPACK annulus is sealed by measuring the helium leakage rate will ensure that s'ufficient LCO helium remains in the annulus to preserve the assumptions in the therma! analysis.
The OVERPACK helium leak rate measurement is APPLICABILI performed during LOADING OPERATIONS before the
\\ SFSC is transported to the ISFSI. TRANSPORT
\\ OPERATIONS would not commence if the OVE
\\ helium leak rate is not within the' limit. Therefore, the LCO is
\\ ot applicable during TRANSP' ORT OPERATIONS or TORAGE OPERATIONS./
/
\\
\\
to the ACTIONS which states that, ACTIONS A notp has been add Condition entry is allowed for each for thiALCO, separat his is acce/Itable since the Required Actions for MPC.
each C ition pr6 vide appropriate compensatory measures C ndt meeting the LCO. Subsequent MPCs that
)
don't meet {mg{.CO are governed by subsequent Con for each entry and ap#{ication of associated Required Actions.
AJ.
/
's
\\
If the, helium leak kte limit is not met, actions must be taken eet the LCO. The Completion Time is sufficient to to d ermine and correct ost failures which could cause a elium leak rate in exce of the limit.
/ EL1
/
if the OVERPACK annulus leak e cannot be brought within the limit, the fuel must be pia d in a safe condition in e is reasonable the spent fuel pool. The Completion based on the time required to perform fu cooldown welds, move operations, re-flood the MPC, cut the MPC the SFSC into the spent fuel pool, remove th qC lid, and remove the spent fuel assemblies in an orderly mbqner without challenging personnel.
\\
B 3.1.6-2
OVERPACK H51ium Leak Rata B 3.1.6
/
h SURD ILLANCE SR 3.1.6.1 REQUIR ENTS The primary design consideration of th ERPACK is that it is sufficiently leak tight to ensure t the helium remains in nnulus region.
Measuring the helium les rate must be performed successfu'lly on each'OVERPACK prior to placing it in storage. The'
'eillance must be performed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> aftery ri the OVERPACK annulus helium backfill pressure 4s satisfac in accordance with LCO 3.1.4, OVERPACK Helium B kfill pressure. This allows sufficient ti e to perform the Surve nce while minimizing the time p
fuelis in the MPC without ve ing that helium is in the annulus.
REFER ES 1.
TSAR Sections 4.4.1 and 8.1 9
v M f[9' y
6 N'
4@
,a B 3.1.6-3 L
yTf p
Multipurpose Canister (MPC)
B 3.1.1
-B 3.1
.SFSC Integrity B3.1.1.
Multipurpose Canister (MPC)
BASES-BACKGROUND
'An OVERPACK with an empty MPC is placed in the spent fuel pool and loaded with fuel ' assemblies meeting the requirements of the Functional and Operating Limits. A lid is'then placed on the MPC. The OVERPACK and MPC are raised to the top of the spent fuel pool surface.
The OVERPACK and MPC are then moved into the cask preparation area where does rates are measured and the MPC
-lid is welded to the MPC shell and the welds are inspected and tested. The water is drained from the MPC and MPC-cavity vacuum drying is performed. The MPC cavity is backfilled with helium. Additional dose rates are measured and the MPC vent and drain cover plates and closure ring are
-installed and : welded.' ' Inspections are performed on the welds.' The OVERPACK lid is installed and secured. The annulus space.between the MPC and OVERPACK is drained, vacuum dried and backfilled with helium gas.
The
~
OVERPACK seals are tested for leakage. Contamination measurements are completed prior to moving OVERPACK
MPC cavity vacuum drying is utilized to remove residual' moisture from the MPC fuel cavity after the MPC has been drained of water. Any water that has not drained from the-fuel cavity evaporates from the fuel cavity due to the vacuum. This is aided by the temperature increase due to the heat generation of the fuel.
j Backfilling of the MPC fuel cavity with helium promotes heat transfer from the fuel and the inert atmosphere protects 1
the fuel cladding. Provided a helium pressure greater than or equal to atmospheric pressure ensures that there will be no 1
in-leakage of air over the life of the MPC. In-leakage might be harmful to the fuel. Prior to moving the SFSC'to the storage pad, the MPC.. helium leak rate is determined.to ensure that the fuel is confined.
B3.1.11
.r e
w I$
Multipurpose Canister (MPC)
B 3.1.1 APPLICABLE The confinement of radioactivity during the storage of safety
. SAFETY ANALYSIS analysis spent fuel in the MPC is ensured by the multiple confinement boundaries and systems. The barriers relied on are the fuel pellet matrix, the metallic fuel cladding tubes in which the fuel pellets are contained, and the MPC in which the fuel assemblies are stored. Long-term integrity of the fuel and cladding depend on storage in an inert atmosphere and maimaining cladding temperatures below long-term
)
limits. This is accomplished by removing water from the i
MPC canister backfilling the cavity with an inert gas. The thermal analyses of the MPC assumes that the MPC cavity is filled with dry helium.
LCO A dry, helium filled and sealed MPC establishes an inert, heat removal environment necessary to ensure integrity of the multiple confinement boundaries. Moreover,it will also ensure that there will be no air-in-leakage into the cavity that could damage the fuel cladding over the storage period.
1
. APPLICABILITY The dry, sealed and inert atmosphere is required to be in place.during TRANSPORT OPERATIONS and STORAGE OPERATIONS to ensure both the confinement barriers and j
heat removal mechanisms are in place during these operating periods. These conditions are not required during LOADING l
or UNLOADING OPERATIONS as the MPC is either establishing these conditions or removing them, respectively,
. to allow other activities to be performed with the stored fuel.
' ACTIONS A note has been added to the ACTIONS which states that, for this LCO, separate Condition entry is allowed for each SFSC.
This is acceptable since the Required Actions for each Condition provide appropriate compensatory measures for each SFSC not meeting the LCO. -Subsequent SFSCs that do not meet the LCO are governed by subsequent Condition entry and application of associated Required Actions.
I A.1 If the cavity vacuum drying pressure limit has 'ocen determined not to be met while the SFSC is in a TRANSPORT OPERATIONS or STORAGE OPERATIONS 3-B 3.1.1+
h
Multipurpose Canister (MPC)
B3.1.1
]
mode, an engineering evaluation is necessary to determine the quantity of potential moisture left within the cavity. Since moisture remaining in the cavity during these modes may represent a long term degradation concern, immediate action is not necessary. The Completion Time is sufficient to complete the engineering evaluation.
I M
l 4
. Once the quantity of moisture is determined, a corrective action plan shall be determined and implemented. Since the j
quantity of moisture can range over a broad scale, different recovery strategies may be necessary. Since moisture remaining in the cavity during these modes may represent a j
long tenn degradation concem, immediate action is not necessary. The Completion Time is sufficient to complete the planning phase and implement the recovery plan.
i Bd If the helium backfill density limit has been determined not to be met 'while the SFSC is in a TRANSPORT OPERATIONS cr STORAGE OPERATIONS mode, an
)
engineering evaluatica is necessary to determine the quantity
]
of helium within the cavity. Since odditional or. reduced helium quantities existing in the cavity during these modes represents a overprecsure or - heat removal degradation-3 concern, an engineering evaluation shall be performed in a j
timely 7.nanner.
The Completion Time is sufficient to j
complete the engineering evaluation.
j E2 Once the quantity of helium is determined, a corrective action plan shall be determined and implemented. Since the quantity of helium can range over a broad scale, different recovery strategies may be necessary. Additional or reduced helium quantities existing in the MPC during these modes represents a overpressure or cooling degradation concern, corrective action shall be performed in a timely manner: The Completion Time is sufficient to complete the planning phase and implement the recovery plan.
Cl i
B 3.1.1.$
)
C M-Multipurpose Canister (MPC)
B 3.1.1
- If the helium leak rate limit for the MPC has been determined not to-be met while the SFSC is in a TRANSPORT OPERATIONS or STORAGE OPERATIONS mode, an engineering evaluation is necessary to determine the potential leak rde and quantity of helium remaining within the. cavity.
~ The significance of such a situation is somewhat mitigated by
- the existence of the OVERPACK containment boundary.
Since an increased leak rate from the MPC represents a potential increase in off-site radioactivity releases and a reduction in heat removal capability, reasonably rapid action-is required. The Completion Time is sufficient to complete the engineering evaluation.-
C2' Once the cause and consequences of elevated leak rate for the MPC is determined, a corrective action plan can be determined and implemented.
Since the recovery mechanisms can range over a broad scale, different recovery strategies may be necessary. An increased leak rate from the MPC represents. a potential threat to elevated off-site radioactivity ; releases and a reduction in heat removal capability, reasonably rapid action-is required.
The Completion Time is sufficient to complete the planning phase and implement the recovery plan.
D_d If the MPC fuel cavity cannot be successfully returned to a
. safe condition, the fuel must be placed in a safe condition in the spent fuel pool. The Completion time is reasonable based i
on the time required to perform fuel cooldown operations, re-flood the MPC, cut the MPC lid welds, move the SFSC into the spent fuel pool, and remove the MPC lid in a safe and orderly manner without challenging personnel.
SURVEILLANCE -
SR 3.1.1.1 REQUIREMENTS '
Cavity dryness is demonstrated by evacur. ting the cavity to a very low absolute pressure and verifying that the pressure is held over a specified period of time. A low vacuum pressure is an indication that the cavity is dry. The surveillance must be ' performed during LOADING OPERATIONS to ensure that the proper conditions are established for SFSC usage.
B 3.1.1- %
p.
i Multipurpose Canister (MPC)
I B 3.1.1 SR 3.1.1.2 Filling' of the MPC cavity with helium at the specified density in Table 3-1 ensures that there will be an inert environment. This density of helium gas is sufficient to maintain fuel cladding temperatures within acceptable levels.
The surveillance must be performed during LOADING OPERATIONS to ensure that the proper conditions are established for SFSC usage.
SR 3.1.1.3 The primary design consideration of the MPC is that it is sufficiently leak tight to eiuure that off-site dose limits are not exceeded and to ensure that the helium remains in the MPC during long-term storage. Confirming a total leakage from lid, drain and vent port confinement welds to be within the limit rpecified in Table 3-1 ensures that these parameters will be maintained within design limitations. Long-term integrity of the stored fuel is dependent on storage in a dry, inert environment.
- REFERENCES 1.
TSAR Sections 7.3 and 8.1.5.
(
B 3.1.1-5 '
T-
/e OVERPACK B 3.1.2
' B 3.1 -
SFSC Integrity -
B3.1.2 OVERPACK.
BASES-BACKGROUND'-
An OVERPACK with an empty MPC is placed in the spent' fuel pool and loaded: with fuel assemblies meeting the requirements of the Functional and Operating Limits. A lid is then placed on the MPC. The OVERPACK and MPC are raised to the top of the spent fuel pool surface.
The OVERPACK and MPC are then moved into the cask preparation area where does rates are measured and the MPC i
lid is welded to the MPC shell and the welds are inspected and tested. The water is drained from the MPC and MPC-cavity vacuum drying is performed. The MPC cavity.is backfilled with helium. ndditional dose rates are measured and the MPC vent and drain cover plates and closure ring are installed and welded.
Inspections are performed on the welds.' The OVERPACK lid is installed and secured. The annulus space between the MPC and OVERPACK is drained, vacuum dried and backfilled with helium gas.
The OVERPACK' seals are tested for. leakage. Contamination -
measurements are completed prior to moving OVERPACK and MPC to the ISFSI.
' Vacuum drying of the annulus between the MPC and the OVERPACK is to remove residual moisture from the annulus after the annulus has been drained of water. Water that has not drained from the anntilus evaporates from the annulus due to the vacuum. This is aided by the temperature
- increase due to the heat generation of the fuel in the MPC.
Backfilling of the OVERPACK annulus with helium promotes heat transfer' from MPC to ' the OVERPACK structure. Provided a helium pressure greater than or equal to atmospheric pressure ensures that there will be no in-leakage of air over the life of the SFSC. In leakage m'ight be harmful to tlw heat transfer features of the SFSC. Prior to moving the SFSC to the storage pad, the helium leak rate is determined to ensure that the helium is retained in the OVERPACK annulus region.
B 3.1J-l '
. 2--
m-OVERPACK B 3.1.2 APPLICABLE The confinement of radioactivity during the storage of safety SAFETY ANALYSIS analysis spent fuel in the MPC is ensured by the multiple confinement boundaries and systems. The 'aarriers relied on are the fuel pellet matrix, the metallic fuel cladding tubes in which the fuel pellets are contained, and the MPC in which the fuel assemblies are stored. No confinement credit is taken for the overpack boundary. Long-term integrity of the.
fuel and cladding depend on the ability of the SFSC to reject heat to the environment. This is accomplished in part by retaining helium gas in the annulus space between the f
OVERPACK and the MPC. By removing water from the I
annulus space, the boiling of residual water and associated pressurization of the annulus is avoided. Backfilling the annulus with an inert gas optimizes the ability of the SFSC to transfer heat from the MPC to the OVERPACK in a dry environment.
In addition, the thermal analyses of the OVERPACK assume that the annulus is filled with dry helium.
LCO A ' dry, sealed and helium filled OVERPACK annulus establishes an inert, cooling environment necessary to ensure heat rejection to the environment. Moreover, it will also ensure that ther'e will be no air-in-leakage into the annulus that couhi be exposed to the MPC over the storage period.
' APPLICABILITY _
The dry, inert and sealed atmosphere is required to be in.
place during TRANSPORT OPERATIONS and STORAGE OPERATIONS to' ensure a heat transfer mechanism is in place during these operating periods. These conditions are not required during LOADING or UNLOADING OPERATIONS as the OVER. PACK is either establishing these conditions or removing them, respectively, to allow
. other activities to be performed with the stored MPC.
ACTIONS
- A note has been added to the ACTIONS which states that, for this LCO, separate Condition entry is allowed for each SFSC.
This is acceptable'since 'the Required Actions for each
~
Condition provide appropriate compensatory measures for each SFSC not meeting _the LCO. Subsequent SFSCs that don't meet the LCO are governed by subsequent Condition entry and application of associated Required Actions.
B 3.1.1.-2
OVERPACK B 3.1.2 A.1
.If' the annulus vacuum drying pressure limit has been
. determined not to be met while the SFSC is in a TRANSPORT OPERATIONS or STORAGE OPERATIONS mode, an engineering evaluation is necessary to determine the quantity'of potential moisture left within the annulus.
Since moisture remaining in the annulus during these modes may represent a long term degradation concern, immediate action is not necessary. The Completion Time is sufficient to 1
complete the engineering evaluation.
Al Once the quantity of moisture is determined, a corrective action plan can be determined and implemented. Since the quantity of moisture can range over a broad scale, significantly different recovery strategies may be necessary.
Since moisture remaining in the annulus during these modes may represent a long term degradation concern, immediate action is not necessary. The Complete Time is sufficient to complete the planning phase and implement the recovery plan.
Bd-If the helium backfill pressure limit has be determined not to
. be met while the SFSC is in a TRANSPORT OPERATIONS or ' STORAGE OPERATIONS mode,' an - engineering.
evaluation is necessary to determine the pressure of helium within the annulus. Since abnormal quantities of helium in the annulus during these modes represents a minimal impact,'
j immediate action is not necessary. The Completion Time is sufficient to complete the engineering evaluation.
E2 Once the pressure of helium is determined, a correciive action plan can be determined and implemented. Since the pressure of helium can range over a broad scale, significantly different recovery strategies may be' necessary. Since abnormal quantities of helium in the annulus during these modes represents a minimal impact, immediate action not is necessary. The Complete Time is sufficient to complete the planning phase and implement the recovery plan.
]
B 3.113 n
.f OVERPACK B 3.1.2 g
If the helium leak rate limit for the OVERPACK has been determined not to be met while' the SFSC is in a TRANSPORT OPERATIONS or STORAGE OPERATIONS mode, an engineering evaluation is necessary to determine the potential leak rate and quantity of helium remaining within the annulus. The' significance of such a situation is somewhat mitigated however by the existence of the MPC confinement boundary. Since abnormal leak rates in the annulus during thes'e modes represents a minimal impact,-
l immediate action is not necessary. The Completion Time is
)
sufficient to complete the engineering evaluation.
l
.C_2 Once the cause and consequences of elevated leak rates for i
the OVERPACK are determined, a corrective action plan can be determined and implemented.
Since the recovery mechanisms can range over a broad scale, significantly different recovery strategies may be necessary. Since abnormal, leak rates in the annulus during these modes l
- represents a _ minimal impact, immediate action is not necessary. The Complete Time is sufficient to complete the planning phase and implement the recovery plan, SURVEILLANCE SR 3.1.2.1
' REQUIREMENTS Annulus dryness is demonstrated by evacuating the annulus to a very low absolute pressure and. verifying that the pressure is held over a specified period of time.' A low vacuum pressure is an indication that the annulus is dry. The surveillance must be performed ' during LOADING OPERATIONS to ensure that the proper conditions are established for SFSC usage.
Filling;of the OVERPACK annulus with helium at the specified density in Table 3-1 ensures that there will be an inert environment. This density of helium gas is sufficient to maintain heat rejection to the environment at acceptable levels.
The surveillance must be performed during B 3.1.2r 7 i
)
.s OVERPACK B 3.1.2 LOADING ' OPERATIONS. to ensure that the proper conditions are established for SFSC usage.
The primary design consideration of the OVERPACK is that it is sufficiently leak tight to ensure that the helium remains.
in the annulus region during long-term storage. Confirming a total leakage from closure plate inn:r mechanical seal, vent port and. drain port plug seal to be within the limit specified in Table 3-1 ensures that these parameters will be maintained within design limitations.
REFERENCES 1.
TSAR Sections 8.1.6.
B3.1% f
[
SFSC Lifting Requiramants s
A B3.1/
.3 3
8 3.1 SFSC INTEGRITY
(
B 3.1.
SFSC Lifting Requirements BASES
. BACKGROUND
- A loaded SFSC is transported between the loading facility and the ISFSI using a transporter. The SFSC may be handled in either the horizontal or vertical orientation depending on the 7
site cask handling limitations. The height to which the SFSC e
is lifted is' limited to ensure that the structuralintegrity of the SFSC is'n mp fo a h~ehthe Yo ised should the SFSC be dropped. G
/<Hm ed OVCtP4U; u_sinn dedus whid m Joe go<<u ca % iocfs. w'sv ry,ta oas, io e,=x <b rmalrtered~-
. APPLICABLE The structural analyses of the SFSCs demonstrate that
/
SAFETY the drop of an SFSC from the Technical Specification Yj*U ANALYSIS ~
height limits to a surface having the structural characteristics
' described in Design Features Section 4.4.6,will not compromise the SFSC integrity or physical damage to the contained fuel assemblies. The structural analyses evaluated SFSC tip-over event onto an ISFSI surface also
_s having structural characteristics as described in Design
/
Features Section 4.4.6.
LCO.
Limiting the SFSC lifting height during TRANSPORT.
OPERATIONS maintains the operating conditions of the SFSC within the design and analysis basis.. The maximum lifting height is a function of the SFSC design and the orientation that the SFSC is carried. The lift height -
requirements are specified in LCO 3.1/a for the vertical and horizontal orientations.
J Design Features Section 4.4.6 provides the characteristics of the' drop surface assumed in the analyses. As required by 10 CFR 72.212(b)(3), each licensee must "... determine whether or not the reactor site parameters...are eaveloped by the cask design bases..." Therefore, licensees must evaluate the site transport route to assure that it is bounded
. by Design Features Section 4.4.6 or that potential drop accidents are bounded byt he cask design basis 60 g deceleration.
.s B3.1./-1' 3
SFSC Lifting Requircment[s B 3.1 y 3
.A Alternatively, LCO 3/.1.b allows the use of lifting devices h
designed in accordance with ANSI N14.6 and having redundant drop prevention design features. If a suitably designed lifting device is.used, dropping the SFSC is not considered credible, and the lift heights of LCO 3f.1.a do APPLICABILITY
-- S C lifting height restrictions apply during T RT ggf OPE S which include movempnt-e SFSC whil suspended fro Ath~e transporter. SFSC gg handling andydnts lated to occur in the fuel loadinpacfhties are addressed in er's FSAR or PSOAR.
ACTIONS '
A note has been added to the ACTIONS which states that, for this LCO, separate Condition entry is allowed for each MPC. This is acceptable since the Required Actions for each Condition provide appropriate compensatory measures for each MPC not meeting the LCO. Subsequent MPCs that don't meet the LCO are governed by subsequent Condition entry and application of associated Required Actions.
A._j. -
If none of the SFSC lifting height requirements are met, immediate action must be initiated and completed expeditiously to comply with one of the three lifting height requirements in order to preserve the SFSC design and analysis basis.
SURVEILLANCE-SR 3.1.7.1 REQUIREMENTS The SFSC lift height requirements of LCO 3.1.7 or the site-specific lift height requirements developed under Design Featutes Section 4.4.6 must be verified to be met after the SFSC is suspended from, or secured in the transporter and prior to t' e transporter beginning to move the SFSC to the h
ISFSI. This ensures potential drop accidents during TRANSPORT OPERATIONS are bounded by the drop analyses.
Ek-(-
v B3.1/-2 4
g
~.
SFSC Lifting Requirements
$3.1.3 INSERT A SFSC Lifling Requirements LCO
- Alternatively, LC.O 3.1.3.c allows for site-specific transport conditions which are not encompassed by those of LCO 3.1.3.a or 3.1.3.b. The licensee shall evaluate the site-
- specific conditions to ensure that the drop accident loads do not exceed 60 g's. This alternative analysis shall be
~
commensurate with the analysis which forms the basis of LCO 3.1.3.a.
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~
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t 3 'd, f, 3 %
SFSC Lifling Requirements 33,1.3 INSERT B SFSC Lifting Requirements
- APPLICABILITY The APPLICABILITY is modified by a note which says the LCO is not applicable while the transporter (e.g., rail car, heavy haul trailer, or vertical crawler) is in the. FUEL BUILDING. This is acceptable based on the relatively short period of time TRANSPORT OPERATIONS take place in the FUEL BUILDING.
OVERPACK lifling require' ents apply outside the FUEL m
BUILDING during TRANSPORT OPERATIONS when the OVERPACK is being lifted or otherwise suspended above the surface below.
This includes movement of the OVERPACK while suspended from a transporter (i.e., a vertical crawler.)
This LCO does not apply if the OVERPACK is secured on a transporter such as a heavy haul-trailer or rail car since the OVERPACK is not bemg lifted
-(i.e., the cask is supported from below) and a drop accident is not credible.
Drop events also cannot occur during STORAGE OPERATIONS since the OVERPACK is not considered lifted.
m 1
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- SFSC Lifting Rtquirements B 3.1.7
. s. -
,,gc id,,
_ ~
REFERENCES 1.
l TSAR, Sections 3.4.9,8.1, and 8.3
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--B 3.1.7 <
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'i
r Fuct Cool-Down B 3.1 B 3.1.M{.SFSC INTEGRITY g~
. B 3.1f Fuel Cool-Down
. BASES BACKGROUND in the event that an MPC must be unloaded, the OVERPACK with its enclosed MPC is returned to the cask preparation area to begin the process of fuel unloading..The OVERPACK annulus gas is sampled to determine the state of MPC integrity. The annulus is depressurized and the closure plate is removed. The annulus is filled with demineralized water and the MPC closure ring, vent and drain port cover plates are removed. The MPC gas is sampled to determine the integrity of the spent fuel cladding.
The MPC is attached to the Cool-Down System. The Cool-Down System is a closed-loop forced ventilation gas cooling system that cools the fuel assemblies by cooling the surrounding helium gas.
Following fuel cool-down, the MPC is then re-flooded with
- .o -
water and the MPC lid weld'is removed leaving the MPC lid in place. The OVERPACK and MPC are placed in the spent fuel pool and the MPC lid is removed. The fuel assemblies are removed from the MPC and the MPC and OVERPACK are removed from the spent fuel pool and decontaminated.
Reducing the fuel cladding temperatures significantly reduces the temperature gradients across the cladding thus minimizing thermally-induced stresses on the cladding during MPC re-flooding. Reducing the MPC internal temperatures eliminates the risk of high MPC pressure due to sudden generation of steam during re-flooding.-
APPLICABLE The confinement 'of fission products during tne storage of SAFETY spent fuel in the MPC is ensured by the multiple ANALYSIS confinement boundaries and systems. The barriers relied on are the fuel pellet matrix, the metallic fuel cladding tubes in which the fuel pellets are contained, and the MPC in which
, f;TV I
B 3.1.8-1 o
B3.1.M 1
the fuel assemblies are stored. Long-term integrity of the fuel s
and cladding depend on minimizing thermally-induced
)-
stresses to the cladding. This is accomplished during the unloading operations by lowering the MPC internal temperatures prior to MPC re-flooding.
MPC integrity depends on maintaining the internal cavity pressures within design limits. This is accomplished by reducing the MPC internal temperatures such that there is no sudden formation of stcam during MPC re-flooding. (Ref.1).
LLCO Monitoring the circulating MPC gas exit temperature and flow rate ensures that there will be no large thermal gradient across the fuel assembly cladding during re-flooding which could be potentially harmful to the fuel assembly cladding.
The temperature and flow rate limits specified in the LCO were selected to ensure that the MPC gas exit temperature will closely match the desired fuel cladding temperature prior to re-flooding the MPC. The temperature was selected to be lower than the boiling temperature of water with an additional margin.
APPLICABILITY -
The MPC gas exit temperature and circulation rate is measured during UNLOADING OPERATIONS after the OVERPACK and integral MPC are transported from the
- ISFSI back to the fuel loading facility and are no longer j
suspended from, or secured in, the transporter. Therefore, the Fuel Cool-Down LCO does not apply during TRANSPORT OPERATIONS and STORAGE OPERATIONS.
A note has been added to the Applicability for LCO 3.1JV'/
which states that the Applicability is only applicable during wet UNLOADING OPERATIONS. This is acceptable since the intent of the LCO is to avoid uncontrolled MPC pressurization due to water flashing during re-flooding operations. This is not a concerning for dry UNLOADING OPERATIONS.
~ ACTIONS -
A note has been added to the ACTIONS which states that, for this LCO, separate Condition entry is allowed for each SFSC. This is acceptable since the Required Actions for w
e e
f
.w_-
Fuel Cool-Down
- o-B3.1pY
.fh each Condition provide appropriate compensatory measures
. for each MPC not meeting the LCO. Subsequent MPCs that don't meet the LCO are governed by subsequent Condition entry and application of associated Required Actions.
A.1 1
If the MPC gas exit temperature is not met, actions must be j
taken to restore the temperature to within the limit before re-flooding the MPC.' Fai;ure to successfully complete fuel cool-down could have several causes, such as failure of the cool-
{
down system, inadequate cool-down, or clogging of the piping lines. The Completion Time is sufficient to determine and correct most failure mechanisms. No additional actions are appropriate - since this LCO applies during UNLOADING 4
OPERATIONS which cannot proceed until the LCO is met.
I SURVEILLANCE SR 3.1.I.1 REQUIREMENTS i
The long-term integrity of the stored fuel is dependent on the h
material condition of the fuel assembly cladding. By j
minimizing thermally-induced stresses across the cladding the integrity of the fuel assembly cladding is maintained. The integrity of the MPC is dependent on controlling the internal MPC pressure. By controlling the MPC internal temperature prior to re-flooding the MPC there is no formation of steam during MPC re-flooding.
The MPC exit gas temperature limit ensures that there will be no large thermal gradients across the fuel assembly cladding during MPC re-flooding and no formation of steam which could potentially overpressurize the MPC, Fuel cool-down must be performed successfully on each SFSC before the initiation of MPC re-flooding operations to ensure the design and analysis basis are preserved.
REFERENCES 1.
TSAR, Sections 4.4.1 and 8.3.2.
i l
. [N/.I B 3.1.
3 i
L
OVERPACK Averago Surfaca Doso Rates B 3.2.1 glgg B 3.2 SFSC Radiation Protection GJ B 3.2.1 OVERPACK Average Surface Dose Rates BASES BACKGROUND The regulations governing the operation of an ISFSI set
. limits on the control of occupational radiation exposure and radiation doses to the general public (Ref.1). Occupational radiation exposure should be kept as low as reasonable achievable (ALARA and within the limits of 10 CFR Part 20).
Radiation doses to the public are limited for both normal and accident conditions APPLICABLE The OVERPACK average surface dose rates are not an SAFETY assumption in any accident analysis, but are used to ANALYSIS ensure compliance with regulatory limits on occupational dose and dose to the public.
LCO The limits on OVERPACK average surface dose rates are based on the shielding analysis of the HI-STAR 100 System 4./
(Ref. 2). The limits were selected to minimize radiation exposure to the general public and maintain occupational dose ALARA to personnel working in the vicinity of the SFSCs. The LCO requires specific locations for taking dose rate measurements to ensure the dose rates measured are indicative of the neutron shielding material's effectiveness and not the steel channel members.
APPLICABILITY The averege OVERPACK surface dose rates apply during' TMM ANI $70Eh& LOAOlNO OPERATIONS. Th;;;llm.n;;n;are thet t5 CVERPA0l' a;;;;;; ;;t:06:0 reter 6tg TC."NOPOP7 C"C"AT ONS, STO"^.OE OPERATlON37
- nd 'JNLOAO!NO OPERATlONO arc ;;nh n th; ;;tla.;;;s c^nt;:n d :n th; H -0 TAR Top lc.; Ssiciy Anaiy... Royvik Radiation doses during STORAGE OPERATIONS are
' monitored by the SFSC user in accordance with the plant-specific radiation protection program required by 10CFR72.212(b)(6).
B 3.2.1-1 l'
_____-______________._____________-_____.______m
OVERPACK Average Surfacs Dose Rates B 3.2.1
,J ACTIONS A note has been added to the ACTIONS which states that, for this LCO, separate Condition entry is allowed for each MPC. This is acceptable since the Required Actions for each Condition provide appropriate compensatory measures for each MPC not meeting the LCO. Subsequent OVERPACKS that don't meet the LCO are governed by subsequent Condition entry and application of associated Required Actions.
IL1 If the OVERPACK average surface dose rates are not within limits, it could be an indication that a fuel assembly was inadvertently loaded into the MPC that did not meet the Functional and Operating Limits in Section 2.0.
Administrative verification of the MPC fuelloading, by means such as review of video recordings and records of the loaded fuel assembly serial numbers, can establish whether a mis-loaded fuel assembly is the cause of the out of limit condition. The Completion Time is based on the time required to perform such a verification.
&2 If the OVERPACK average surface dose rates are not within limits, and it is determined that the OVERPACK was loaded with the correct fuel assemblies, an analysis may be performed. This analysis will determine if the OVERPACK, dog rde
= L; d et ;t.e l0l St, would result in the ISFSI offsite or occupational calculated doses exceeding regulatory limits in 10CFR Part 20 or 10 CFR Part 72. ' t in det:P^d thM
- = cut cf lLr.n ave ag: ='::: deem ia;;; de rivi issun la the re;d;;;ri !%it: 5:!n; ex:::d:d, TRAN5 FORT OPEPAT!ON'S mey prerrri 4
B 3.2.1-2 I
Fr OVERPACK Avsrags Surfaca Doso Ratss B 3.2.1 w;4wg-M If it is verified that the correct fuel was not loaded or that the ISFSI offsite radiation protection requirements of 10 CFR Part 20 or 10 CFR Part 72 will not be met with the SFSC average surface dose rates above the LCO limit, the fuel assernblies must be placed in a safe condition in the spent fuel pool. The Completion Time is reasonable based on the time required to perform fuel cooldown operations, re-flood the MPC, cut the MPC lid welds,' move the SFSC into the spent fuel pool, remove the MPC lid, and remove the spent
~
fuel assemblies in an rderly manneredwithout challenging personnel.
d And SURVEILLANCE SR 3.2.1.1 I
REQUIREMENTS This SR ensures that the OVERPACK average surface dose rates are within the LCO limits prior to transporting the SFSC 3
to the ISFSI.
The surface dose rates are rneasured 1
approximately at the locations indicated on Figure 3.2.1-1
.following standard industry practices for determining average
{
m surface dose rates for large containers. Measurements at
)
-approximate locations to those shown on Figure 3.2.1-1 are
)
acceptable provided the radial steel channel members are' avoided.
)
1
-REFERENCES.
1.
10 CFR Parts.20 ami 72 i
2.
TSAR Sections 5.1 and 8.1.6 j
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B 3.2.1-3
SFSC Surfaca Contamination B 3.2.2
. B 3.2-SFSC Radiation Protection
'B 3.2.2' SFSC Surface Contamination BASES.
BACKGROUND- ; An SFSC is immersed in the spent fuel pool in order to load the spent fuel assemblies. As a result, the surface of the SFSC may become contaminated with the radioactive material in the spent fuel pool water. This contamination is removed prior to moving the SFSC to the ISFSI in order to minimite the radioactive contamination to personnel or the environment. This allows the ISFSI to be entered without additional radiological controls to prevent the spread of contamination and reduces personnel dose due to the spread of loose contamination or airbome contamination.
This is consistent with ALARA practices.
APPLICABLE The radiation protection measures implemented at the
- SAFETY ISFSI are based on the assumption that the exterior ANALYSIS surfaces of the SFSCs have been decontaminated.
Failure to decontaminate the surfaces of the SFSCs could lead to higher-than-projected occupational and potential site contamination.
LCO Removable surface contamination on the SFSC exte: lor surfaces is limited to 1000 dpm/100 cm from beta and 2
gamma sources and 20 dpm/100 cm from alpha sources.
2 These limits are taken from the guidance in IE Circular 81-07 (Ref. 2) and are based on the minimum level of activity that can be routinely detected under a surface contamination control program using direct survey methods. Only loose
~
contamination is controlled, as fixed contamination will not result from the SFSC loadincj process. Experience has shown that these limits are low enough to prevent the spread of contamination to clean areas and are significantly l
less than the levels which would cause significant personnel skin dose.
1
. LCO 3.2.2 requires removable contamination to be within the specified limits for the exterior surfaces of the
- d3%
B 3.2.2-1 y
SFSC Surface Contam.ination B 3.2.2 1
OVERPACK and accessible portions of the MPC. The 7
location and number of OVERPACK surface swipes used to
/
m determine compliance with this LCO are determined based l
on standard industry practice and the user's plant-specific j
contamination measurement program for objects of this size.
l I
Accessible portions of the MPC means the upper portion of the MPC external shell wall accessible after the inflatable annulus seal is removed and before the annulus shield ring
-l is installed. The user shall determine a reasonable number and location of swipes for the accessible portion of the MPC.
The objective is to determine a removable contamination value representative of the entire upper circumference of the MPC, while implementing sound ALARA practices.
APPLICABILITY Ve.ifmabun ihe; Sc SFSC cadew vvmaminanon is isss than tb LCO ""is petmed dut;; LOAOlNG OFERATiGiG TMc cccurs before TRANSPORT OPERATIONS and -
STORAGE OPEPAT!ON3'. Measurement of the SFSC surface contamination is unnecessary during UNLOADING OPERATIONS as surface contamination would have been measured prior to moving the subject SFSC to the ISFSI.
ACTIONS' A note has been added to the ACTIONS which states that, for this LCO, separate Condition entry is allowed for each MPC. This is acceptable since the Required Actions for each Condition provide appropriate compensatory measures for ich MPC not meeting the LCO. Subsequent MPCs that don't meet the LCO are governed by subsequent Condition
- entry and application of associated Required Actions.
refvittettb5cn his LC.0 mus+ k vM DPe#kf/00 l
Avri),,,TRAN.sPotT anJ
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o B 3.2.2-2
7 SFSC Surfaco Contamination B 3.2.2
. ;h)i A.1 w
if th' removable surface contamination of an SFSC that has -
e
. been loaded with spent fuel is not within the LCO limits, action must be initiated to decontaminate the SFSC and -
. bring the removable surface contamination within limits. The Completion Time of "P;ic-to TRANOPORT CPERATlONG" 7 hys is appropriate given that the time needed to complete the decontamination b M&te.-5 te and surface contamination '
does not affect the safe storage of the spent fuel assemblies.
SURVEILLANCE SR 3.2.2.1 REQUIREMENTS This SR verifies that the removable surface contamination on the SFSC is less than the limits in the LCO. The Surveillance
- is performed using smear surveys to detect removable surface contamination.
The Frequency requires performing the verification p&r to "t! t5g TP.^MSPORT_OFERATiCNv in order to confirm that the SFSC can be moved to the ISFSI
. without spreading loose contamination.
REFERENCES 1.
TSAR Sections 8.1.5 and 8.1.6.
buk 2.
NRC IE Circular 81-07 Loep /A4 ePERkTICA.$
j i
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1 i
'f' B 3.2.2-3
ATTACHMENT B INDEX TO COMMENT RESOLUTION NOTE:
THE FOLLOWING COMMENT NUMBERS ARE FROM ORIGINAL HUG COMMENT LETTER Comment No.1 Section: -
1.1 Comment
In the definition of INTACT FUEL ASSEMBLY, change "...an amount of water equal to..." to "...an amount of water greater than or equal to.."
{
Resolution 1.1-2 Page:
j i
Note:
To allow conservative flexibility with dummy rod sizing.
i Comment No. 6 Section:
4.4.5 Comment
Add " diesel" before " fuel" at the end of the last sentence.
Resolution 4.0-7 Page:
Note:
To accurately reflect the HI-STAR 100 analysis basis.
Comment No.11 Section:
Bases 2.2.2 & 2.2.3 4
Comment:
In the last line of this Bases section, after "by", add "10 CFR 72.75 or."
Resolution ' B2.04 Page:
Note:
To remind user of other regulatory requirements.
Comment No.12 Section:
Certificate of Compliance Comment:
The Technical Specification Bases are appended to the CoC with the Technical Specifications (TS). However, changes to the 13ases should be allowed without prior NRC approval subject to evaluation under 10CFR72.48. This would be consistent with power reactor TS, which allow Bases changes under 10CFR50.59. Therefore, the TS Bases should be removed as an appendix to the CoC and changes controlled solely as TSAR changes ' (or a separately controlled document), subject to evaluation under 10CFR72,48 by licensees.
1 Resolution ' 5.0-1 l
Page:
t Note:
To allow control of Bases to be handled in the same manner as those of Part 50 licensees.
l Comment No.13 A.
Section:
1.1 Comment
Add new definition: FUEL BUILDING. The FUEL BUILDING is a site-j specific power plant facility, governed by the regulations of 10 CFR Part I
50, where the loaded OVERPACK is transferred to or from the
)
transporter.
{
Resolution 1.1-1 j
Page:
Note:-
The Fuel. Building at a general use power plant is governed by the regulations of Part 50. Lifling restrictions contained within LCO 3.1.3 should apply once the material has traversed from the Part 50 facility. The existing regulations contained within 10 CFR 72.212 require an evaluation
- of the activities under this General License impacts on the Part 30 facility.
)
Placing additional restrictions, specifically the issue of Part 72 single failure proof lifts, would not appreciably increase safety but would add potential confusion as to the qualification of single failure proof devices Stready approved in Part 50 licensing.
B.
Section:
o Comment:
Add the following note to the APPLICABILITY: "This LCO is not applicable while the transporter is in the FUEL BUILDING."
Resolution 3.1.3-1
)
' Page:
Note:
See above.
C.
Section:
Bases 3.1.3 Comment:
In the BACKGROUND section, add the following paragraph:
"For lip.ing of the loaded OVERPACK using devices which are integral to a structure govemed by 10 CFR 50 regulations,10 CFR 50 requirements 1
apply."
J Resolution B3.1.3-1 Page:
i Note:
See above.
j D.
Section:
Bases 3.1.3 Comment:
In the APPLICABILITY section, delete the existing paragraph and add the following new bases to add clarification and address the new NOTE added by Comment 13.B.
I "SEE ORIGINAL SUBMITTAL FOR DETAILS OF ADDITION."
Resolution B3.1.3-2b Page:
Note:
See above. In addition, clarification was provided as to the definition of
" lifted" to remove interpretation errors.
l Comment No.14 Section:
Tables 2.1-2 and 2.1-3 Comment:
" Revise NOTE I as follows...." Also included here is a cleanup of Note-presentation to remove duplicate numbering within the same Table (a i
simple application of the same rules utilized in Part 50 space.)
i l
I
m s
Resolution 2.0-18 through 2.0-24a Page:
Note:
To accurately reflect the analysis and more clearly define the fuel terms
. utilized in the table in the manner that they are contained within existing Part 50 facility fuel records. As previously mention, additional changes are included to provide clarity to Note usage and align format with that utilized in improved Technical Specifications of Part 50.
Comment No.15
- Section:
Table 3-1, Item 1.c Comment:
Change lower helium tolerance to-10%.
Resolution 3.3-1 Page:
Note:
To clear up usable tolerance range, t
Comment No.17 Section:
4.4.6 i
Comment:
In accordance with the errata published by the NRC November 9,1998, revise the soil effective modulun of elasticity from "s 28,000 psi." In l
- addition, add the following text under item 4.4.6.d:"
"SEE ORIGINAL FOR DETAIL OF TEXT" Resolution 4.0-8 l
Page:
j Note:
To resolve soil parameter issues and to address definition of acceptable i
measurement methodology.
i Comment No.19 s
Section:
LCO 3.1.3 and Bases 3.1.3 Comment: '
Add a third option to the LCO (or elsewhere in the TS) which allow j
general licensees to calculate site-specific lifting requirements based on the site-specific pad design and associated drop /tipover analyses.
1 e
Resolution -
3.1.3-1 and B3.L3-1 through B3.1.3-2c Page:
Note:
To allow Dexibility in implementation and to bring requirements in line with that allowed in subsequent applications.
NOTE:
THE FOLLWOWING ITEMS RESULT FROM THE GENERAL COMMENT INLUDED WITHIN THE REFERENCE 4 COVER LETTER.
Text ofComment
"... Since that time, our reviews have led us to believe that some of the specifications may not be necessary to meet the applicable regulations or reach the level ofsafety sigmficance to be included in the TS.' As such, we expectfuture d,ialogue between the NRC and industry to result in additional, perhaps larger scale changes to the TS resulting in the deletion ofone or more specifications... "
Channe No.1 Section:
Existing LCO 3.1.1 and Bases 3.1.1 I
Comment:
As written, the LCO is not usable. Specifically, LCO 3.0.4 requires all LCO conditions to be satisfied prior to entry into the APPLICABILITY mode of operation. This is not possible as written.
Resolution 3.1.1-1 and B3.1.1-1 through B3.1.1-3 Page:
Note:
Delete pages as written. This LCO actually indicates a method, or-surveillance. requirement, of a broader operability issue; namely the functionality of the MPC, As this item does not represent a tme OPERABLE item, but more appropriately defines an item in a series of steps that define the. MPC OPERABLE, it can not be defined in the traditional sense of a MODE of operation. This is a state that the canister passes through for a short duration. This item will be re-introduced as.
surveillance in the new proposed MPC OPERABILITY specification.
)
l l
~ Channe No. 2 Section:'
Existing LCO 3.1.2 and Bases 3.1.2 I
l
c Comment:
As ' written, the LCO is not usable. Specifically, LCO 3.0.4 requires all LCO conditions to be_ satisfied prior to entry into the APPLICABILITY
. mode of operation. This is not possible as written.
)
Resolution 3.1.2-1 and B3.1.21 through B3.1.2-3
]
Page:
Note:
Delete pages as written. This LCO actually indicates a method, or surveillance requirement, of a broader operability issue; namely the functionality of the OVERPACK. As this item does not represent a true l
OPERABLE item, but more appropriately defines an item in a series of steps that define the OVERPACK OPERABLE, it can not be defmed in the traditional sense of a MODE of operation. This is a state that the canister passes through for a short duration. This item will be re-introduced as a surveillance in the new proposed OVERPACK OPERABILITY specification.
Channe No. 3 1
Section:
Existing LCO 3.1.3 and Bases 3.1.3 Comment:
As written, the LCO is not usable. Specifically, LCO 3.0.4 requires all LCO conditions to be satisfied prior to entry into the APPLICABILITY mode of operation. This is not possible a written.
Resolution 3.1.3-1 and B3.1.3-1 through B3.1.3-3 Page:
Note:
Delete pages as written. This LCO actually indicates a method, or surveillance requirement, of a broader operability issue; namely the functionality of the MPC.
As this item does not represent a true OPERABLE item, but more appropriately defmes an item in a series of steps that' define the MPC OPERABLE, it can not be defined in the traditional sense of a MODE of operation. This is a state that the canister passes through for a short duration. This item will be re-introduced as surveillance in the new proposed MPC OPERABILITY specification.
Channe Noj Section:
Existing LCO 3.1.4 and Bases 3.1.4 Comment:
As written, the LCO is not usable. Specifically, LCO 3.0.4 requires all LCO conditions to be satisfied prior to entry into the APPLICABILITY mode of operation. This is not possible as written.
fr x
i Resolution.
3.1.41 and B3.1.4-1 through B3.1.4-3 Page:
9 Note:
' Delete. pages as written. This LCO actually indicates a method, or 4
surveillance requirement, of a broader operability issue; namely the
. functionali y of the OVERPACK As this item does not represt s a true t
~ OPERABLE item, but more appropriately defines an item in a series of steps that define the OVERPACK OPERABLE, it can not be defined in.
the traditional sense of a MODE of operation. This is a state that the canister passes through for a short duration. This item will be re-
' introduced as ' a surveillance in the 'new proposed OVERPACK OPERABILITY specification.
Channe No. 5 -
Section:
Existing LCO 3.1.5 and Bases 3.1.5 Comment:
Asiwritten, the LCO is not usable. Specifically, LCO 3.0.4 requbc.s all
'LCO conditions to be satisfied prior to entry into the APPLICABILITY mode of operation. This is not possible as written.
1
. Resolution 3.1.5-1 and B3.1.5-1 through B3.1.5 Page:-
-Note:
Delete _ pages - as. written.- This LCO actually indicates a method, or surveillance requirement, of a. broader aperability issue; namely the functionality of _the_ MPC.
-As' this' item does not represent a true, OPERABLE item,' *yit more appropriately defines an item in a series of
^'
steps'that define the..MPC OPERABLE, it can not be defined in the traditional sense of a MODE of operation. This is a state that the canister passes through fol a short duration. This item will be re-introduced as 1
surveillance in the new propo' ed MPC OPERABILITY specification.
j s
l
- Channe No. 6
. Section:
Existing LCO 3.1.6 and Bases 3.1.6 Comment:-. As written,- the LCO is.not usable. Specifically, LCO 3.0.4 requires all iLCO conditions to be' satisfied prior to entry into the' APPLICABILITY e
mode of operation. This is not 'possible as written.
s Resolution 3.1.6-1 and B3.1.6-1 through B3.1.6 ;Page:
v i
' _~o:
l d
' Note:
. Delete pages as written. This LCO actually indicates a method, or surveillance' requirement, of a broader operability issue; namely the functionality of the OVERPACK. As this item does not represent a true OPERABLE item, but more appropriately defines an item in a series of
~
steps that define the OVERPACK OPERABLE, it can not be defined in the traditional sense of a MODE of operation. This is a state that the canister passes through for a short duration. This item will be re-introduced.as a surveillance in the new proposed OVERPACK i
OPERABILITY specification.
I l
'Channe No. 7 -
Section:
lNew Proposed LCO 3.1.1 Comment:
The objective of the existing LCOs 3.1.1,3.1.3 and 3.1.5 is to establish an OPERABLE MPC fo do so, one must establish a dry inert environment q
within the car.a Moreover, to camply with the licensing basis, it is required to est...sh this environment over a long period; namely with limited leakage. This is more appropriately done through a single LCO on the MPC requiring OPERABILITY of the MPC in.he TRANSPORT and STORAGE OPERATIONS periods.
Resolution. New 3.1.1-1 through ? 1.1-2 and B3.1.1-1 through B3.1.1-5 Page: '
Note:
To address the OPERABILITY in the appropriate MODE of operation and to ensure that the LCO is met prior to entering the MODE of operation. In this manner, the conditions required within the canister are established and demonstrated by performance of the required SURVEILLANCES in'a
~
time period in which the TSAR indicate the activities will be performed.
It she Jd also be noted that the ACTIONS required in the MPC are found in an INOPERABLE state are significantly different that those originally proposed.'.This. is due to the fact that the IviPC can not enter TRANSPORT or STORAGE OPERATIONS until the co dition has been established.
Since this is a fact, any caused or. -identified INOPERABILITY must have occurred once the transition has taken place.
- Recovery from this condition is much harder and requires some planing and evaluation prior to action.
The activities and time periods are i
established to reflect this.
Channe No. 8 Section-
, New Proposed LCO 3.1.2'
-o 6
i Comment:
The objective of the existing LCOs 3.1.2,3.1.4 and 3.1.6 is to establish an
~
OPERABLE OVERPACK. To do so, one must establish a dry inert environment within the annulus region of the OVERPACK. Moreover, to j
comply with the licensing basis, it is required to establish this environment I
over a long period; namely with limited leakage.
This is more I
appropriately done through a single LCO on the OVERPACK requiring OPERABILITY of the OVERPACK in the TRANSPORT and STORAGE OPERATIONS periods.
Resolution New 3.1.2-1 ^ rough 3.1.2-2 and B3.1.2-1 through B3.1.2-5 Page:
Note:
To address the OPERABILITY in the appropriate MODE of operation and to ensure that the LCO is met prior to entering the MODE of operation. In this manner, the conditions required within the canister are established and demonstrated by performance of the required SURVEILLANCES in a time period in which the TSAR indicate the activities will be performed. It should also be noted that the ACTIONS required in the OVERPACK is found in an INOPERABLE state are significantly different that those originally proposed. This is due to the fact that the OVERPACK can not enter TRANSPORT or STORAGE OPERATIONS until the condition has been established.
Since this is a fact, any caused or identified INOPERABILITY must have occurred once the transition has taken place.
Recovery from this condition is much harder and requires some planing and evaluation prior to action.
The activities and time periods are established to reflect this.
Chance No. 9 Section:
Existing LCO 3.1.7 8.
Comment:
Renumber to LCO 3.1.3 Resolution Existing 3.1.7-1 Page:
Note: -
To reflect the removal of larger quantities of LCOs to accomplish same OPERABILITY as new reduced number.
' Channe No.10 Section:
Existing LCO 3.1.8
p 1
c
- Comment
Renumber to LCO 3.1.4.
Furthermore, modify the APPLICABILITY statement to require operability only prior to reflood operations within the UNLOADING OPERATIONS mode of use.
Resolution Existing 3.1.8-1 Page:
Note:
To reflect the removal oflarger quantities of LCOs to accomplish same
. OPERABILITY as new reduced number.
The adjustment of the APPLICABILITY requirement allows the user to complete tb temperature reduction prior to entering the APPICABILITY requirement, and thus not violate LCO 3.0.4.
Channe No.11 Section:
LCO 3.2.1 Comment:
.As presented,.an APPLICABILITY of "during LOADING OPERATIONS" suggests that the dose limitations do not apply during TRANSPORT or STORAGE OPERATIONS. Moreover, while the LCO can be' established prior to LOADING OPERATIONS, to do so would have no meaning. In addition,' measurement of dose rates during pool submergence is impractical.
Resolution 3.2.1-1 through 3.2.1-2 Page: -
Note:
The requirements were modified to require the dose limits to apply during TRANSPORT and STORAGE OPERATIONS. The establishment of these requirements, through performance of the required SURVEILLANCE activities is identified during LOADING OPERATIONS.
Finally, the CONDITIONS are modified to reflect that the violation of the LCO can not occur until after the APPLICABLE mode of operation is entered; namely on the pad or in. transport. Correction of this condition must be timely as it has impacts on offsite dose requirements.
' Channe No.12 Section:
LCO 3.2.2 an APPLICABILITY of "during LOADING Comment:
As' -- presented,
. OPERATIONS" suggests that the dose limitations do not apply during TRANSPORT or STORAGE OPERATIONS. Moreover, while the LCO can be established prior' to LOADING OPERATIONS, to do so would 6
n have no meaning. In addition, measurement of contamination during pool submergence and prior to decontamination efforts is impractical and certain to result in a violation of the LCO.
I Resolution 3.2.2-1
-Page:
. Note:
TThe requirements were modified to require the dose limits to apply during TRANSI' ORT and STORAGE OPERATIONS. The establishment of these requirements, through performance of the required SURVEILLANCE activities is ' identified during LOADING OPERATIONS. Finally, the CONDITIONS are modified to reflect that the violation of the LCO can not i
occur until after the APPLICABLE mode of operation is entered; namely on the pad or in transport. Correction of this condition 'must be timely as it has impacts on offsite dose requirements but may require time consuming efforts such as a re-coating of the OVERPACK to fix any loose surface contamination.
Correspondingly, the time allowed must reflect this possibility.
l
' LL