ML20147G205
| ML20147G205 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 03/01/1988 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20147G209 | List: |
| References | |
| NUDOCS 8803080161 | |
| Download: ML20147G205 (10) | |
Text
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UNITED STATES
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8' NUCLEAR REGULATORY COMMISSION g
5 eE WASHING TCN, D. C. 20555
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CONSUMERS POWER COMPANY PALISADES PLANT DOCKET NO. 50-255 AMENOMENT TO PROVISIONAL OPERATING LICENSE Amendment No.111 License No. OPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated September 1, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized i
by this amendment can be conducted without endangering the health j
and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the pubilc; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.8. of Provisional Operating License No. OPR-20 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.111, are hereby incorporated i
in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8803080161 880301 PDR ADOCK 05000255 P
2-3.
This license amendment is effective as of the date of its issuance, t
FOR THE NUCLEAR REGULATORY COMMISSION Martin irgilio, Director Project Directorate III-1 Division of Reactor Projects - III, IV, V
& Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: March 1, 1988 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 111 PROVISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT I
ii ii 3-69 3-69 3-92 3-92 3-93 3-93 3-94 3-94 3-95 3-95 5-4a 5-4a I
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L PALISADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION' PAGE N0 3.0 LIMITING CONDITIONS FOR OPERATION (Continued) 3.10 CONTROL R0D AND POWER DISTRIBUTION LIMITS 3-58 3.10.1 Shutdown Margin Requirements 3-58 3.10.2.
Individual Rod Worth 3-58 3.10.3 Part-Length Control Rods 3-58 3.10.4 Misaligned or Inoperable Control Rod or Part-Length Rod 3-60 3.10.5 Regulating Group Insertion Limits 3-60 3.10.6 Shutdown Rod Limits 3-61 3.10.7 Low Power Physics Testing 3-61 3.10.8 Center Control Rod Misalignment 3-61 Figure 3-6 Control Rod Insertion Limits 3-62 3.11 POWER DISTRIBUTION INSTRUMENTATION 3-65 3.11.1 Incore Detectors 3-65 3.11.2 Excore Power Distribution Monitoring System 3-66a Figure 3.11-1 Axial Variation Bounding Condition 3-66d 3.12 MODERATOR TEMPERATURE COEFFICIENT OF REACTIVITY 3-67 3.13 (Deleted) 3-69 /
3.14 CONTROL ROOM VENTILATION 3-70 3.15 REACTOR PRIMARY SHIELD COOLING SYSTEM 3-70 3.16 ENGINEERED SAFETY FEATURES SYSTEM INITIATION INSTRUMENTATION SETTINGS 3-71 1
Table 3.16.1 Engineered Safety Features System Initiation Instrument Setting Limits 3-75 3.17 INSTRUMENTATION AND CONTROL SYSTEMS 3-76 Table 3.17.1 Instrumentation Operating Requirements for Reactor Protective System 3-78 Table 3.17.2 Instrumentation Operating Reguirements for Engineered Safety Feature Systems 3-79 Table 3.17.3 Instrument Operating Conditions for Isolation Functions 3-80 Table 3.17.4 Instrumentation Operating Reguirements for Other Safety Feature Functions 3-81 3.18 (Deleted) 3-82 3.19 IODINE REMOVAL SYSTEM 3-84 3.20 SHOCK SUPPRESSORS (SNUBBERS) 3-88 3.21 MOVEMENT OF HEAVY LOADS 3-92 /
3.22 FIRE PROTECTION SYSTEM 3-96 3.22.1 Fire Detection Instrumentation 3-96 Table 3.22.1 Fire Detection Instrumentation - Minimum Instruments Operable 3-97 11 Amendment No. 37, 53, $$, SJ, 55, 198, JJp, 111
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i 3.13 (Deleted)
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3-69 Amendment No. gy,111
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- s 3.21 MOVEMdgf 0F HEAVY LGADS
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Applicability
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Applies to limitations in the movement of heavy loads over the
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649' level of the auxiliary: building and inside containment. A heav
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load iss e t].oad, otherf tlan a fuel assembly, which ' weighs more thLn y
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j 1300 lbs.
' A
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Objective
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To minimize the probability of and the consequences of a heavy load
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drop.
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Specifications
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3.21.1 Inside Containment
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Heavy loads shall.not te moved over the primary coolant system if /
a.
the temperature of the coolant or the steam;in the. pressurizer
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exceeds 225*F.
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b.
Heavy loads shall not be moved unless the potential for a load
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t drop is extremely small as defined by Generic Letter 85-11 or an
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evaluation in compliance with section 5.1 of NUREG-0612 has been
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completed.
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i 3-92 Amendment No. 35, 111 W
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3.21 MOVEMENT OF HEAVY LOADS (Continued)
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3.21.2 Over the 649' Level of the Auxiliary Buildinr,
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The surface of the floor adjacent to the spent fuel pool is at the
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649' level of the auxiliary building.
The spent fuel pool is made
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up of two (2) zones.
They are the main pool zone and the north
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tilt pit zone.
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Leavy loads shall not be moved over fuel stored in the main
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a.
pool zone.
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b.
Heavy loads shall not be moved over areas of the main pool zone
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which do not contain fuel unless the fuel stored in the main
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pool cte has decayed a minimum of 30 days when the charcoal
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filter is operating, or the fuel stored in the main pool zone
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has decayed a minimur, of 90 days when the charcoal filter is not
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operating.
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Heavy loads shall not be moved over the north tilt pit zone
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c.
unless the fuel stored in the north tilt pit zone has decayed a
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minimum of 22 days when the charcoal filter is operating; or,
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the fuel in the north tilt pit zone has decayed a minimum of
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77 days when the charcoal filter is not operati g.
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d.
deavy loads shall not be moved over the 649' level of the
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auxiliary building unless:
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(1) The fuel storage building crane interJocks are operable or
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they are bypassed and the crane is under administrative
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control of a supervisor, and
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(2) No fuel handling operations are in progress.
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Loads weighing more than 25 tons shall not h moved over the
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mafn pool zone unless an evaluation in comp 11anc( with
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Section 5.1 of NUREG-0612 has been completed.
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f.
heavy loads shall not be moved unless the potential for a load
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drop is extremely small as define:! by Generic Letter 85-11 or an
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evaluation in compliance with section 5 1 of NUREG 0612 has been
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completed.
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Bases
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Reference (7) defines a heavy load as a load which weighs more than a /
fuel assembly tud its handling tool.
The lightest Palisades fuel
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assemblies vei
',proxir '.tely 1298 lbs and the heaviest weigh
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approximately
,Ibs.
% handling tool weighs 60-70 lbs.
For
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conservati".
- . h we i, u.~, (- re than 1300 lbs, except for fuel
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s assemMie',
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4 1..avy loads.
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.s
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P Heavy loa.'
r the pressurized primary coolant
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- jj system to jn
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v
.h ects which could rupture the boundary
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n of the primc
.. J a allowing loss of coolant and
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overheating ci the c..
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3-93 tunendment No. 35,111
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3.21, MOVEMENT OF HEAVY LOADS (Continued)
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Bases (Continued)
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. Prohibiting movement of heavy loads over fuel stored in'the main pool /
zone minimizes the criticality and radiological effects of a load
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drop.
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Heavy loads are allowed over the fuel stored in the north tilt pit
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i zone because the. maximum number of fuel bundles which can be stored
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a in:that zone is relatively small and'the north tilt pit lies under
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the only possible safe load path for moving heavy loads into and out
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of containment without passing over the main pool zone.
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Requiring that the spent fuel pool crane interlocks are operable
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ensures that heavy loads or,the unloaded crane wiil et drift over or :/
be inadvertently moved over fuel stored in the asin po d area.
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Specific decay times with and without the charcoal filters operating
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are necessary to ensure that heavy loads are moved within analyzed
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conditions.
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The charcoal filter is operating when at least one Fuel Handling Area /
1 exb ust fan is drawing suction through the charcoal filter and the.
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Fuel Handling Area ventilation system is in the refueling mode.
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Assuring that no fuel handling operations are in progress while heavy /
loads are being moved allows operator attention to be focused on the
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heavy load movement.
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i The objectives of the Guidelines of Section 5.1 of NUREG-0612 are to
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3 assure that (1) the potential for a load drop is extremely small, or
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(2) for each area addressed, the following evaluation criteria are
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satisfied:
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(1) Releases of radioactive material that may result from damage to
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spent fuel based on calculations involving accidental dropping
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of a postulated heavy load produce dosew that are well within.
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10 CFR Part 100 limits of 300 rem thyroid and 25 rem whole body;
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1 (2) Damage to fuel and fuel storage racks based on calculations
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involving accidental dropping of a postulated heavy load does.
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not result in a configuration of the fuel such that k,ff'is
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larger than 0.95;
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j-(3) Da.nage to the reactor vessel or the spe.t fuel pool based oc
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calculations of damage ic11owing accidental dropping of a
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3 postulated heavy load is limited so as not to result in water.
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leakage that coulo uncover the fuel, (makeup water provided to
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overcome leakage shall be from a borated source of adequate
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concentration); and
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1 3-94 Amendment No. U, 111
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'3.21 MOVEMENT OF HEAVY LOADS'(Cc:tinu2d)
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Base-(Continued)
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l (4) Damage to equipment in redundant or' dual safe shutdown paths,
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based on calculations' assuming the accidental dropping of a _
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l postulated heavy load, will be limited so as not to result in
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loss of required safe shutdown functions.
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Generic Letter 85-11 defines the potential for a heavy load drop as -
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extremely small when a heavy load is moved in compliance with the.
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Guidelines of section S.I.1 of NUREG-0612.'
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7 References
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(1) Palisades Plant Evaluation of Postulated Cask Drop Accidents by
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Bechtel Associates Professional Corporation, August 1974.-
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(2) Palisades Plant Fir.a1 Safety Analysis Report - Appendix 1 -
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Evaluation of Postulated Cask Drop Accidents, submitted to the
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1 NRC on August 9, 1974.
(Structural Analysis only)
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(3) Letter deted January 16, 1978 from D P Hoffman, CPC to Director
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NRR, entitled "Palisades Plant - Movement of Shielded Shipping
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Cask."
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(4) Letter dated November 1, 1976 from D'A Bixel, CPC, to Director
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NRR entitled "Spent Fuel Pool Modifications."
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(5) SER supporting License Amendment No. 35 dated February 8,1978.
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l (6) SER supporting License Amendment No. 81 dated May 22, 1981.
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(7) NUREG-0612 - Control of Neavy Loads in Nuclear Power Plants.
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(8) Safety Analysis Report (Rev. 1) dated October 16, 1986 attached
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I to letter dated October 16, 1986 from K W Gerry, CPC, to NRC.
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t (9) Generic Letter 73-ti dated June 28, 1985.
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j 3-95 Arnendment No. 37,111 o
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5.4.2
-Spent Fuel Storate a.
Irradiated fuel bundles will be stored, prior to off-s'ite shipment in the stainless. steel-lined spent fuel pool.
b.
(Deleted)-
c.
.The spent fuel storage pool and spate (north) tilt pit are divided into two regions identified as Region I and Region II_as illustrated,in Figure 5.4-1.
Ragion I racks are designed and shall be maintained with a nominal 10.25" center-to-center
^ distance between fuel-assemblies with the exception of the single Type E rack which has a nominal 11.25" center-to-center
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distance between fuel assemblies. The Region I spent fuel storage racks are designed such that-fuel having a maximum U-235-loading of 3.27 w/o of U-235 placed in the racks would result ia~
aK equivalent to 5 0.95 when flooded with unborated water.
The'kg of 5 0.95 includes a conservative allowance'for uncerINaties.
d.
Region II racks have a 9.17 inch center-to-center spacing.
l Because of this smaller spacing, strict controls are-employed to_
evaluate burnup of the fuel assembly prior to its placement in l
Region II cell locations. Upon determination that the fuel-assembly meets the burnup requirements of Table 5.4-1, placement in a Region II cell is authorized. These positive controls assure the fuel enrichment limits assumed in the safety analyses will not be exceeded.
J e.
After installation of the two-region high density spent fuel racks, the maximum loading for fuel assemblies in the spent fuel racks is 3.27 w/o of U-235.
f.
The minimum spent fuel pool vater boron concentration shall be l
172'J ppm.
Boron concentration shall be verified at least once monthly.
g.
The spent fuel racks are designed as a Class I structure.
h.
(Deleted)
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Storage in Region II of the spent fuel pool and spare (north) tilt pit shall be restrie.ed by burnup and enrichment limits i
specified in Table 5.4-1.
NOTE: Until needed for fuel storage, one Region II rack in the northeast corner of the spent fuel pool may be removed and-replaced with the cask anti-tipping device.
References FSAR Update chapter 5 FSAR Update Chapter 9 5-4a Amendment No..W 111 1
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